ML20082K758
| ML20082K758 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/27/1991 |
| From: | Chrzanowski D COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20082K763 | List: |
| References | |
| NUDOCS 9109030001 | |
| Download: ML20082K758 (3) | |
Text
__ _______ - _ _____ _ _ _ _ _ _ _ _
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- CN/ Production Commonwealth Edison l
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fv Training Center 36400 South Essen Road Wilmington, lHinois 00481 j
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! Aut;us t 27, 1991 i
Dr. Thomas E. Murley. Director l Office Of Nuclear Reactor Regulation l U. S. Nuclear Regulatory Commission l Washington, D.C. 20555 l Attn: Document Control Desk
Subject:
Byron Units 1 and 2
" Byron Simulator Facility" Certification of Simulator Facility - 10CFR 55.45
- g. Docket Nos. 50-454 and 50-455 Gentlement The purpose of this letter is to submit information pursuant to 10CFR 55.45.b.5 in order to attain certification of the Byron Simulation Facility.
l This submittal for certification addresses both operating units at Byron Station with Byron Unit I serving as the reference plant. In the section titled " Reg.
Guide 1.149 Requirements" of our certification report, the requirements for dual plant simulation facilities are evaluated and the results demonstrate that the Byron Simulator's performance compares favorably with each unit. In addition.
steady state testing per ANS1/ANb-3.5, 1985 Appendix B was performed in 1991.
These testa compared the Byron simulator performance to Byron Unit 1 performance with favorabic results.
The attachment to this letter contains two NRC Form 474's, ie. one for each docket number; two copies of the Initial Certification Report, dated August 27, 1991. These documents certify the Byron Simulation Facility meets the Nucicar Reguintory Commission's regulations. It is therefore Commonwealth Edison's intent to utilize this facility to conduct operating tests for Byron operators at this facility. Byron operators were previously tested on the Braidwood simulator which is certified to Byron Units 1 and 2.
Please direct any questions that you may have to the Nuclear Licensing Department, 708-515-7292.
Sincerely.
l p.. a David J. Chrzanowski Nuclear Licensing Administrator Attachment cca A. Bert Davis - hlII W. Kropp - Resident inspector. Byron l
l A. Hsia - NRR Project Manager. Byron viovv30uvi vng2 f0 l PDR P
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BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER,1991 0 . . .
9 Submitted: ___ 6Cm A' A'd:p ,
Simulator Fide 11ty/ Certification Coordinator-Reviewed: 4_ "
Byron Simulator Training Supervisor Reviewed:- / -c mm[k Direc' tor of Operations Program
- -1 Reviewed; e- %'
SiglatorReviewBoardChairman Approved: '
M 4447 O eredectien iraieie, sana er gren88a :assgr
BYRON SlHULA10R ANSI /ANS-3.5-1985 CERT!f! CATION REPORT INITIAL REPORT, SEPTEMBER, 1991 TABLE Of CONTENTS SECHON IUl.E EAGE A.1. Simulator Information 4 A.1.1 General 4 A.1.2.1 Control Room Physical Arrangement 5 A.I.2.2 Panels / Equipment 6 A.I.2.3 Systems 13 A.I.2.4 Simulator Contiol Room Environment 14 A.I.3 Instructor Interface 15 A.1.3.1 Initial Conditions 15 A.I.3.2 Halfunctions 15 A.1.3.3 Controls Provided for items Outside of Control Room 18 A.I.3.4 Additional Special Instructor / 19 Training Features Available .
A.I.4 Operating Procedures for Reference Plant 21 p A.I.5 Changes Since Inttial Delivery 22 V A.2 Simulator Design Data Base 23-A3 Simulator Tests -
24 A.3.1 Lomputer Real Time Test 24 A.3.2 Steady State & Normal Operations Tests 25 A.3.3 Transient Tests 2b A.3.4 Halfunction Tests 29 A.4 Simulator Discrepancy Resolution and Upgrading Program 32 APPENDIX 1 List of Initial Conditions 33 APPENDIX 2 List of Remote functions 37 APPENDIX 3 List of Acronyms / Abbreviations 38 APPENDIX 4- Byron Simulator Transient Test Review Board Qualificatioiis 42 APPENDIX 5 ANSI /ANS-3.5-1985-Certification Report Cross 45 Reference Matrix APPENDIX 6 Simulator Test Procedure and Halfunction Testing Schedule 48 O
(BYRONSIM 113/2 08/22/91) .
BYRON SJHULATOR ANSI /ANS-3.5-1985 CERT!fICATION REPORT INITIAL REPORT. SEPTEMBER, 1991 TABLE OF CONTENTS SECHON 1111.1 PAGE ATTACHMENT I Reg. Guide 1.149 Requirements for Dual Plant 49 Simulation Fact 11ty ATTACHMENT 2 Steady State / Normal Operations /Real Tirs/ 54 Transient Test Abstracts ATTACHH <,T 3 Simulator Related Hork Request Procedure 69 ATTACHMENT 4 Simulator Review Board Pree,edure 70 ATTACHMENT 5 Simulator and Control Room Layouts 71 ATTACHMENT 6 Halfunction Cause and Effects 72 O
i O .
l (BYRONSIM 113/3 08/22/91) i
i BYRON $1 HULA 10R ANS!/ANS-3.5-1985 CERT!flCA110N REPORT IN111AL REPORT. SEPTEMBER, 1991 l A.1 Simulator Information A.1.1 General 1
This report is being submitted as the initial certification report as prescribed in Reg Guide 1.149. The Commonwealth Edison owned Westinghouse PHR 4-loop, 3411 MH power plant simulator is used for training the Byron plant operators. Because of the near exact duplication between the two units, it is considered a plant specific simulator for both Byron Units 1 and 2. hereafter referred to as the Byron Simulator. The Byron Simulator is modeled after Byron Unit 1, with Byron Unit I being considered the reference plant. The simulator was constructed by Simulation Systems and Services Technologies (53 Technologies), between November, 1988 and April, 1991 and duciared " Ready for Training" in Jene, 1991.
Appendix 5 of this report lists a cross reference of sections that satisfy ANSI /ANS-3.5-1985 requirements.
I O
(BYRONSIM 113/4 08/22/91)
I BYRON S!HULATOR AN51/ANS-3.5-1985 CERTIFICA110N REPORT INITIAL REPORT SFPTEMBER, 1991 A.I.2.1 Control Room Physic 61 Artangement The physical arrangement of the simulator's control room dupilcates Byron Station with the following exceptions:
- a. Instruttors station 1$ raised 27" off of the floor (13 1/2" higher than center desk) and occ'iples the space that would be center desk in the reference plant.
- b. 1PH11J (back panel) right edge is aligned 2 1/2 feet right of IPH07? right edge (reference plant right edges align).
- c. M03J, OPH01J (front panels) left edge is 6 inches to the left of 409J 1 eft edge to enhance instructor's view of the IPH01J panel.
(reference plant left edges align),
- d. Location of doors and equipment outside of the "at the controls area" (behind the control panels) are different from the reference ,
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.
O (BYRONSIM 113/5 08/22/91) l l - _ _ -
BYRON S!HOLATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITI Al. REPORT, SEPTEMBER,1991 A.1.2.2 Panels / Equipment l
The Dyron 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 6 is the control room layouts of Byron Units 1/2 and the simulator. The following panels are simulated:
- a. IPH01J Auxiliary Power
- 1. IPH093 Fire Protection
- b. IPH02J Hain Turbine *j. IPH11J Containment
- c. IPH03] Condensate Isolation
- d. IPH04J Feedwater k. OPH01J General Services
- e. IPH05J Reactor /CVCS 1. OPH02J Ventilation k f. IPH063 Safeguard Systems m. OPH03J Switchyard
+ g. IPH07J Excore Nuclear Detectors **n. IPH14J RM-11/ESD/SER
- h. IPH08J Incore Nuclear Detectors "o. ICX05J Plant Computer
- Most 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 lights for Unit 2 components are lit. The Unit 2 Service Air Compressor and Aux Steam Valves are fully simulated.
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 A Staff Engineer).
()
(BYRONS1H 113/6 08/22/91)
_j
BYRON $1HULATOR ANSI /ANS-3.5-1965 CER11fICAT!ON REPORT INITIAL REPORT, SEPTEMBER, 1991 .
I V A.I.2.2 Panels / Equipment (Cont.) [
1he Byron Simulator is partially modeled for IPM12J and OPH05J. The l following components are modeled: l l
IPM12J l
- a. Lift Coll Disconnect Switch Box f
- b. Containment Drains (sump) Flow Recorder
- c. RIL vs. Bank Position (B-pen) Chart Recorder
- d. Boric Acid Storage Tank Level Recorder .
t
- e. RC (loop) IA & 10 Pressure Recorder ;
RC (loop) IB L IC-Pressure Recorder !
- f. .
I
- g. SJAE/GS Condenser Flow and Dew Point Recorder
- h. (N41 and'N43) Overpower Recorder j
- 1. (N42 and N44) Overpower Recorder I t
OPM05J Center Desk
{
a.- GSEP Phones {
- b. Plant fire and Evacuation Alarm Pushbuttons f I
The Byron Simulator does not model the following panels / equipment: f IPM10J - Radiation Monitoring and Turbine Supervisory Panel j
- a. RM23's Instrumentation not installed (functions provided on RM-11 j on IPH14J with use of a remote function). ;
'b. Main Turbine and reedwater Pump Turbine Supervisory Equipment I (instrumentation on back panel not installed - software simulated j to extent necessary to-drive front panel indications and alarms). l
- c. -Cont'tnment a Hydrogen Monitors (instrumentation on back panel not [
installed - software simulated to extent necessary to drive front [
panel indicatt'ons and alarms). l l
IPM08J Incore Nuclear Detectors Panel l
- a. DC supply to MIDS (installed not modeled). l y b. MIDS picoammeter panel-(installed not modeled). !
l l
(BYRONSIM 1113/7 08/22/91) [
t
BYRON $!110LATOR AN51/ANS-3.5-1985 CERTIf!CA110N REPORT INITI AL RCPORT, SEPTEMBER,1991 A.1.2.2 Patiels/ Equipment (Cont.)
The panels / equipment that are not modeled do not detract from training.
The tasks related to these panels / equipment are handled administratively to ensure procedural compilance is maintained. The Turbine-Generator Temperature Monitoring System and Radiation Monitors (RM-23's) are located outside the normal operating area. In addition, these non-modeled panels / equipment do not impact on the ability to peiform the normal plant evolutions in ANSI /ANS-3.5-1985 Section 3.1.1 or respond to the maifuncttons in section 3.1.2.
O 9
a f
t l
(BYRONSlH 113/8 08/22/91)~
BYRON S!HULATOR ANSI /ANS-3.5-1985 CERilflCATION R[ PORT INiilAl. REPORT, SEPi[HBER, 1991 p
b A.I.2.2 Panels /[quipment (Cont.)
Differences between the Byron Simulator and Dyron Unit 1 are:
DYROM A l SI MllM OR EXPLAM110N GSEP telephones located on GSEP telephones located on Does not impact training.
Center Desk facing OPH02J. Center Desk facing Unit 1. Center dest is not fully simulated.
Radio jacks are installed in Radio jacks are not Does not impact training.
control boards. Installed in control Radio jacks not used by boards, station operators.
Backplates for Af005 valve Dackplates for Af005 valve Does not impact training, and PZR safety valve and PZR safety valve indications installed, indications are not
(_- installed.
Color banding located on Color banding located on Does not impact training, meter cover, meter face.
Manufacturer's name is on Manufacturer's name may be Does not impact training, control board components, missing on control board Due to availability of components or M y bi components (ex. H2 different, switches have ELECTRO-SHITCH instead of HESTINGHOUSE on backplate).
Screws are used on name tags Screws are not used on Does not impact training.
and mimics. name tags and mimics.
, l' s
(BYRONSIM 113/9 08/22/91)
BYRON SlHULATOR ANSI /AN$-3.5-1985 CERT!f! CATION REPORT INITIAL REPORT, SEPTEMBER, 1991 l 3 i (V A.1.2.2 Panels / Equipment (Cont.)
Differences between the Dyron Simulator and Byron Unit I are:
DYROM.U-l SIMJLA10ft LXELAM110N Calibration stickers are Calibration stickers are Does not impact training, used on name tags, not used on name tags.
Dypass-permissive panel. Dypass-permissive panel Does not impact training.
Top aligned with rod out located ~ 1/2" too low.
light. ,
Digital Rod Position Digital Rod Position Does not impact training.
Indication panel located Indications panel located 1 1/8" above N1 meters. ~ 1/4" too low.
A U Annunciator acknowledge Annunciator acknowledge Does not impact training, keyswitch/pushbutton is ~ 1 Fgyswitch/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 Unit I switch.
CH Blowdown Tota 11zer has CH Blowdown Totalizer has Does not impact training, silver cover. black cover, CRT 1 & 2 are 25" monitors CRT 1 & 2 are 27" monitors Does not impact training, mounted in IPM05] with black mounted in IPM05] with plastic borders, black metal borders designed to provide similar front panel o appearance.
(BYRONSIM 113/10 08/22/91)
BYRON SlHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT IN111AL REPOR1 SEPTEMBER, 1991 3
(O A.1.2.2 Panels /[quipment (Cont.)
Differences between the Byron Simulator and Byron Unit I are:
DIR0tLU:1 SINUM10R EXEM m110N ITR-TS001 15 an ITR-TS001 is a Leeds & Does not impact training.
Esterline-Angus recorder Northrup recorder with E-A recorder is obsolete.
with lock and latch on front latch on side and no front panel appearance is cover. Recorder has lock. Recorder has similar. Control Room is mechanical point display, digital point display. pursuing a replacement as a Hod and Simulator will follow.
11R-TS002 is an ITR-TS002 is a Leeds & Does not impact training.
Esterline-Angus recorder Northrup recorder with E-A recorder is obsolete.
O with lock and latch on front latch on side and no front panel appearance is U cover. Recorder has lock. Recorder has slmtlar. Control Room is mechanical point display, digital point display, pursuing a replacement as a Mod and Simulator will follow.
HW recorder is a Leed & frequency Recorder is a Does not impact training.
Northrup 250. Leed & Northrup 2500 and is - 1/2" wider and taller.
frequency Recorder is a Leed frequency Recorder is a Does not impact training.
& Northrup 250. Leed & Northrup 2EM and 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 Station.
O (BYRONSIM 113/11 08/22/91)
BYRON SIHULATOR ANSI /ANS-3.5-1985 CERT!flCAi!ON REPORT INITIAL REPORT, SEPTEMBER, 1991
,y L) A.I.2.2 Panels / Equipment (Cont.)
Differences between the Byron tilmulator and Byron Unit 1 are:
BYft0tLU21 SIMULATOR EXPLMMION Aux butiding 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 Blant cover plates may be Does not impact training, ,
to cover switch and used to cover future holes indication cutouts not used. left in panels. Simulator panel cutouts that were V not required were filled and 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.
(3 U
(BYRONSIM 113/12 08/22/91)
i BYRON SIMULATOR ANSI /ANS-3.5-1985 CERT!f! CATION REPORT INITIAL REPORT SEPTEMBER, 1991 A.I.2.3 Systems The Byron. Simulator models most of the plant's control room operated systems. Systems not modeled by the simulator are: -
- a. Turbine-Generator Temperature Honitoring System (TGTHS).
- b. Radiation Honitors (RM-23).
The systems that are not modeled do not detract from training. The tasks related to these systems are handlea administratively to ensure procedural compilance is maintained. The Turbine-Generstor Temperature Monitoring System and Radiation Monitors (RM-23's) are located outside the normal operating area. In addition, these non-modeled sysf e9:. 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.
7-k-
V (BYRONS!H '113/13. 08/22/91)
BYRON SlHULATOR ANSI /ANS-3.5-1985 CERTIflCATION REPORT INITIAL REPORT SEPTEMBER, 1991 (D
V A.1.2.4 Simulator Control Room Environment The Byron Simulator 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 Ilghting was constructed to closely match the Byron Unit 1 Control Room. The $1mulator also has the same type ceiling tiles to ensure the lighting of the simulator is similar to thi 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 15 being tracked under Hork Request 08-91-000l. The estimated completion date for this work request is 7/92.
The annunciators in the simulator e.re 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 reference plant design specs. Presently the reference plant has additional harmonic background noise. The simulator and reference plant are working closely to resolve this slight discrepancy. This is being tracked by Work Request 08-91-0010. Since the resolution to this work request is dependent on a proposed plant modification, an estimated completion date will be provided when the Station determines the status of this modification.
The requirements of ANSI /ANS-3.5-1985, Section 3.2.3, Control Room Environment, have been met.
O
.(BYRONSIM 113/14 08/22/91)
BYRON S1H'JLATOR NSI/ANS-3.5-1985 CERTIf! CATION REPORT INITIAL REPORT SEPTEMBER, 1991 A,1.3 Instructor Inttrface A.I.3.1 Initial Conditions The Byron Simulator has 39 predetermined initial conditions with the 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 requirements 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 sDeets i which serve as the malfunction test abstracts can be found in Attachment 6.
O The Dyron Simulator malfunction assessment process uttilzes LER's, plant specific operating experiences (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.
O (BYRONSlH 113/15 08/22/91)
i BYRON SIHULATOR ,
ANSI /ANS-3.5-1985 CERTIflCATION REPORT INITIAL REPORT, SEPTEMBER, 1991 b
V A.I.3 Instiuttor Interface (Con't)
I The appilcable Attachment 6 malfunctions are cross-referenced to the :
ANSI /ANS-3.b l985, Section 3.1.2 required malfunctions at, follows:
Simulator Halfunctions ANSI /ANS 3.5-1985 corresponding to the ANSI Sn110lLL1,L..__. EtQUltiment (1) Loss of coolant: (1)
(a) Significant PHR S/G tube leaks (a) TH03 (b) Inside/outside primary (b) CV22, CV24, CV25, containment TH01, TH07, 1H13 ,
(c) Large/small Rx coolant (c) TWO4, TH05, TH06 !
breaks (including demonstration i of saturation condition) -
(d) Failure of safety / relief valves (d) THil, TH12 r (2) Loss of instrument air to the extent (2) IA01, IA02, IA03, IA04, that the whole system or individual 1/.05 IA06, IA07. IA08, ,
headers can lose pressure and affect the IA09 plant's static or dynamic performance. ;
V (3) Loss or degraded ciectrical power to (3) ED01 ED02, ED03, ED04, !
the station, including loss of offsite E005, ED06, ED07. E008, .
power, loss of energency power, loss of ED09. EDio, ED11, ED12, 5 emergency generators, loss of power to the ED13 ED14, ED15, ED16, plant's electrical distribution buses r.nf ED17, EG02, EG03, EG04 3
+
loss of power to the individual instru- EG06, EG07, EG08 EG09 mentation buses (AC as well as DC) that r provide power to control room indication :'
or plant control functions affecting the plant's response. ;
(4) Loss of forced core coolant flow due to (4) TH16 TH17. TH18 [
single or multiple pump failure.
(5) Loss of condenser vacuum including (5) FH36, FH37, FH38, FH39, loss of condenser level control. FW40 j p
(EYRONSIM 113/16 08/22/91)
- ?
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BYRON-SIMULATOR' ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT . SEPTEMBER, 1991
\ A .1. 3. Instructor Interface (Cont.) ,
Simulator Malfunctions ANSI /ANS-3.5-1985 corresponding to the ANSI Section_3.1_.2 re.guire;nent ;
(6) . Loss of service water or cooling to .(6) SH01, SH02, SH03, SH04.-
indiV1 dual components SH05 (7) . Loss-of; shutdown cooling (7) RH01, RH02
'(B) Loss of component cooling system (s) CC04, CC05, CC06, CC07, t or cooling to i_ndividual compeaents CC08.-CC09 (9) Loss of normal feedwater or (9) FH01, FH02, FH03, FH04, normal feedwater system failure FH05, FH06, FH07, FH08, FH09, FHIO, FH11, FH12, FHl3, FH14, FH15, FH16, FH17, FH18, FH22, FH23, FH24, FH25, FH26 FH27, FH28, FH29, FH30, FH31, FH32, FH33, FH34, FH35 (10) Loss of-ell feedwater (nv.c w (10) Fl!41, FH42, FH43, FH44,:
emergency) FH45 9
(11) Loss of protective system cnt....el (11) RP04, RP14, RX01, RX06, RX13. RX18,lRX21, RX22, RX23, RX24 L(12) Control-rod failure including stuck (12) RD02, RD03, RD04 rods, uncoupled rods, dttfting rods, rod. drops, and misaltgned' rods.
(13) Inability to driv'e control rods (13) RDOS, RD06 (14) Fuel claddir.g failure resulting in (14) TH08
-high-activity in reactor coolant or off gas and the. associated high 4 radiation alarms (15) Tur51ne_ trip- (15) TCO2
..(16) Generator _ trip. (16) EG01, EG05-(17) Failure in automatic: control system (s) (17) RD07, RD09. RD10, RD11, that. affect-reactivtty_and core heat RD12, RX17-removal-(18) Failure of reactor coolant pressurc (18) CV01, CV04, CV05, CV06, b and volume control syste.ns (PHR) CV07, CV10, CV11, CV12, CV14, CV15, CV19, CV21, CV23, CV26, CV27,.CV2B l'
(BYRONSIM 113/17 08/22/91) l-l t, , .;- __ _ . ~ . , _ . - - . . . < -
. _ - . _ . , - . , . _ - . , - _ . , , _ , . . . . . , . _ _ . _ - . , ~ . , _ _ . , . _ .
. . -- . - - . - - . - . . - -.- - - . ~ -
.. BYRON SIMULATOR
- ANSI /ANS-3;5-1985 CERTIFICATION. REPORT INITIAL REPORT, SEPTEMBER, 1991
.g N :A.I.3 Instructor-Interface (Cont.)
Simulator Malfunctions
-ANSI /ANS-3.5-1985 correspondin9 to the ANSI
$gtt1on 3.1.2 Et.QU1LestRt
~(19) Reactor trip (19) RD01-(20) Mat'n-steam line as well as main feed (20) FH19, FH20, FH21, MS07, line break (both inside and outside HS08, M509 containment)-
(21)-Nuclear instrumentation failure (s) (21) N!01, NIO2, NIO3, NIO4, 1 NIOS, NIO6, NIO7, NIO3, NIO9, nil 0, Nill, NI12 (22) Process instrumentation, alarms, and (22) AN01, AN02, CCO2, CC03, control system failures -CV08, CV09, CV16 CV17, -
CV18, CV20, RX02, RXO3,
- RXO4, RXOS, RXO7, RX08 -
RXO9, RX10,'RX11, RX12, RX14,---RX15, RX16. RX19 RX20, RX25, RX26, RX27, RX28, TH14 THIS (23) Passive malfurctions in systems, such (32) FH46,-RH06, RH07, RH08, .
as engineered safety features, emergency RH09,-RH10, RH11, SIO3, e feedw!ier systems SIO4, SIO5, SIO6, S107,
- - 5108, SIO9, SIl0, Sill 4 f24)-Failure of the automatic reactor trip (24) RP01, RP02, RP03
-system *
(25) Reactor pressure control _ system failure (25) N/A - BWR L includingjturbinebypassfailure(BHR)
- A.I.3.3 Controls Provided for Items-Outside Control Room E Appendix 21s a 11 sting of remote functions (RF) for-the simulator.
- The
, _ appropriate RF's exist for systems that are operatedioutside.of the L
l 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)
... m .. _ ._ . - _ ~ _. _ ._ . . _ _ _ - _ _ _ _ - ___ .. --
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT. SEPTEMBER, 1991 A
O A.1.3 Instructor Interface (Cont.)
A.I.3.4 Additional Special Instructor / Training features Available
- a. Backtrack As previously mentioned, the Byron Simulator has the capability 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, he 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.
O V c. Simulator Speed The Byron Simulator has the capability to vary the speed of simulation. The most useful portion of -
~
this feature 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 capability 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 v
l (BYRONSIM 113/19 08/22/91)
BYRON SIHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O. n.l.3 Instructor Interface (Cont.)
- e. Annunciator The Byron Simulator has the capability of failing any point on the sequence of event recorder (SER) either on or off causing the associated annunciator to either alarm or reset,
- f. Auxiliary The Byron Simulator has an auxiliary Instructor instructor's console which can be used when the Console instructor wishes to interact to a large degree ath the students. This console is a full scope instructor's station identical to the main instructor console,
- g. Plant The Byron Simulator also uses Plant Parameters Parameters which give the instructor the flexibility to modify' parameters which are outside the operating O staff's control. Examples include atmospheric conditions and electrical grid parameters O
(BYRONSIM 113/20 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INI11AL REPORT, SEPTEMBER, 1991 A.I.4 Operating Procedures for Reference Plant 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 simulator) temporary procedure changes are used to acconwnodate differences in the simulator and the plant operations. The simulator uses locally generated BOL, HOL and EOL axial flux difference curves since the plant's axial flux difference curves are based on the plant's core age. In addition, only one set of annunciator response procedures (Byron Unit 1) are utilized during simulator training.
O o
O (BYRONSIM 113/21 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991-
'l'h kf- A.1.5 Changes Since Last Report This is the initial certification report, therefore, this section is not applicable.
r
.f
(
(BYRONSIM 113/22' 08/22/91)
, . _ . - - , , ,y., ,,_.. -e v - - _ . , , , , ,,. . _,. .. , - - - . ,- , . - , _, , , . -
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 im kJ A.2. Simulator Dasign Data Base The simulator design database for the Byron Simulator is Byron 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, simplifications, 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 (SIH) flie, O
(v . .
Gl l
(BYRONSIM 113/23 08/22/91) l
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
-g U. A.3. Simulator Tests A,3.1 Computer Real Time Test Real time test was performed per Appendix A of ANSI /ANS-3.5-1985. The results of the test are acceptable with the test abstract being located in Attachment 2.
A U'
l v
(BYRONSIM 113/24 -08/22/91) l
BYRON SIHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 L A.3 Simulator Tests A.3.2 Steady State and 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 ANSI /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 le:ated in Attachment 2.
Core performance tests were conducted as part of the Byron Simulator Acceptance Test Procedure (Section 6, Core Physics Testing) in accordance with ANSI /ANS-3.5-1985. The test results are located in j Attachment 2.
Operator performed surveillance 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.
O (BYRONSIM 113/25 08/22/91)
E_-. . .
BYRON SIMULATOR ANS!/ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A.3.3 Transient Tests Transient tests (ATP Section 7.2) were performed per Appendix B of ANS1/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)
Os f. Main turbine trip Acceptable (Maximum power level -
which does not result in immediate reactor trip) (7.2.2)
- g. Maximum rate power . Acceptable ramp (1007, down to approximately 907. and back up to 1007.) (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 saturated condition .
using pressurizer relief or s safety valve stuck open (inhibited actuation of high head SI) (7.2.11)
(BYRONSIM 113/26 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 w 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 simulator was gathered on a twice per second interval. The difference in scan rates was taken into account during the comparison '
process.
Operator action _was permitted during the course of the Transient test when such action was required to be performed 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 appropriate trip criteria was reached. The times that these actions were performed were recorded on-the appropriate test. These actions
- also enable a more realistic' transient and aid in comparison of-actual.
d plant data.- -
During the Transient 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 determined to be.
minor and do not detract from. training nor' affect the acceptable response of the Transient test. These work' requests are as follows:
(BYRONSIM 113/27 08/22/91)
. . = . - .__ . .
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 f%
'u '
A.3 Simulator Tests (Con't)
ESTIMATED COMPLETION
_!iR#_ DESCRIP_UD11 .DAll 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 3/G HR level response on the 2/92 n simulator was incorrect on power U changes and was less than the Station'.: on RX trip.
i l
l (BYRONSIM 113/28 08/22/91)
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BYRON SIMULATOR :
ANSI /ANS-3,5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 A A.3.4 Halfunction Tests Halfunctions 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 Atta:hment 6. Approximately 257. of the
. malfunctions identified in Attachment 6 are tested annually as per the testing schedule in Appendix 6. The malfunction tests are located in General Files _under file SIH-B-9El. The malfunction test results were
-satisfactory.
In the event that a malfunction fails its test, a Work 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 3 letter Informs each instructor as to which malfunctions are currently -
-unavailable for-training.
- In order to avoid negative training which can result when the simulator ,
- progresses beyond_ design limits, the instructor system computer console displays a message.to the instructor _. This message; alerts the
. instructor.when selected parameters approach values indicative of events ,
beyond the_ implemented model or known plant behavior, The requirements Lof ANSI /ANS-3.5-1935, Section-4.3, Simulator Operating. Limits, have-been '
mets A Licensee Event Report (LER) review of Byron events is per_ formed as ~
part of the-plant malfunction assessment process, A summary of the
'1989-1990 Byron Unit 1 LER's that were-determined to effect simulation:
follow:
O
'(BYRONSIM 113/29 08/22/91)
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BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 p
V A.3.4 Malfunction Tests (con't)
LER DESCRIEIION CottiEMS89-002 Rx Trip Due to IFH530 Falling Open Tested Satisfactorily Added to MF-FH09 C & E 89-003 VC & VA ESF Actuations Due to Rad Tested Satisfactorily with Monitors & Loss of 345KV LER 89-006, LER 89-007 Added to MF-RM03 C & E 89-004 1A DG Failed to Start Tested Satisfactorily Added to MF-EG08 C & E 89-005 DG Inop Due to Deficient Tested Satisfactorily Post-Maintenance Testing No Specific MF O!
'd 89 006 ESF Actuation Due to 345KV Loss Tested Satisfactorily See U-l LER 89-003 89-007 VC Actuation Due to Voltage Transient Tested Satisfactorily from Lightening See U-l LER 89-003 89-008 AF Suct Press Switches Out of Cal - Not Tested - Setpoint Failure to Correct for Head Calculation Error - MF-FH24 for Xmitter failure Tested per MF Test
/%
()
l (BYRONSIM 113/30 08/22/91) l l .
l l
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
(
' A.3,4 Malfunction Tests (con't)
LER DESCRIP110N COWEMIS90-002 Rx OTAT RTD Failed with 1 Channel in Tested Satisfactorily Test Added to MF-RX18 C L E 90-.005 Auto Start of OA FHB Booster Fan Tested Satisfactorily During Calibration Added to MF-RM01 C & E 90-006 Rx Trip on Low-2 S/G Level During DEH Tested Satisfactorily Trouble Shooting Added to MF-TC01 CLE 90-008 Plant S/D Due to Excessive Cnmt Temp Tested Sati:, factor 11y No Specific MF 90-010 AF PP Auto Start Due to AMS Failure Tested Satisfactorily
(]
ks No Specific MF 90-011 Rx-Negative Flux Rate - Rod Cabinet Tested Satisfactorily Power Loss from Lightening Added to MF-N!09 C & E 00-013 Both SX M/V PPs Inoperable Due to Tested Satisfactorily Personnel Error No Specific MF 90-014 FWI During Safeguards Testing Tested Satisfactorily Added to MF-RP09 C & E (BYRONSIM 113/31 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 fv k) s- A4 Simulator Discrepancy Resolution and Upgrading
- 1. Identifying, logging, correcting, and testing simulator discrepancies.
Administrative Procedure PTAO-103, Simulator Related Hork Request ,
Procedure, describes how an identified simulator discrepancy is resolved. See f.ttachment 3 for a copy of P1AO-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 f- g addition, all modifications that require simulator work are approved and E -)
s tracked by the Simulator Review Board in accordance with PTAO-104, Simulator Review Board Procedure. See Attachment 4 for a copy of PTAO-104, Simulator Review Board Procedure.
e O
(BYRONSIM 113/32 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
APPENDIX 1 LIST of INITIAL CONDITIONS G
O (BYRONSIM 113/33 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
~..
\ -
APPENDIX 1 LIST OF INITIAL CONDITIONS (IC's)
IC DESfBirUOB 1 BOC, COLD SHUTDOHN, 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 PPM, 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 2B%, PZR TEMP 430'F, BORON 1500 PPM, STARTING RCPs, (BGP 100-1, Stop 27) 4* BOC, HOT SHUTDOHN, PZR SOLID, ALL RODS IN, RCS TEMP 200*F, RCS PRESS 325-375 PSIG, BORON 1500 PPM, RCPs ON, CS PUMPS 00S, 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, 1 CCP COS, PDP OOS, AF013S CLOSED, REMOVING RH L/U, (BGP 100-1, Step 38)
(! 6 MOC, HOT STANDBY, PLANT HEATUP; ALL RODS IN, RCS TEMP 495'F, RCS PRESS 1118'PSIG, PZR LVL 281, 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 MODE", RD & EH SYSTEMS S/D, 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 MODE", MSIVs CLOSED & EQUILIZING ON BYPASS (BGP 100-2, Step 3) 9 BOC, REACTOR STARTUP, S/D BANK RODS HITHDRAHN, RCS NOT NOP, 5TH 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 HITHDRAHN, RCS NOT N0P, STM DUMPS IN
" STEAM PRESS MODE", CRITICAL BORON CONC, HI FLUX AT S/D ALRM NOT BLOCKED, (BGP 100-2, Steps 16-23) 11 EOC, REACTOR 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) 12 BOC, 3% POWER, RCS TEMP 560*F, RCS PRESS 2235 PSIG, STM DUMPS IN " STEAM
, PRESS MODE", PRIOR TO TURBINE STARTUP, (BGP 100-3, Step 3) v (BYRONSIM 113/34 08/22/91)
BYRON SIMULATOR ANSI /ANS-3,5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 n-U APPENDIX 1 LIST OF INITIAL CONDITIONS (IC's)
(continued)
IC DISCRIEll0E 13 MOC, 10% POWER, RCS TEMP 562'F, RCS PRESS 2235 PSIG, STM DUMPS IN " STEAM PRESS MODE", TURBINE SPEED 1800 RPM, XENON SLOHLY INC, HAIN GEN SYNCHRONIZATION, (BGP 100-3, Steps 14-20) 14* EOC, 15% POWER, RCS NOT NOP, XENON SLOWLY INC, HAIN GEN AT 60 MW, STM DUMPS IN " STEAM PRESS MODE", HDPs S/D, S/U FHP OPER, ROD CONTROL IN MANUAL, PLACING TDFHP IN OPER, (BGP 100-3, Steps 21-35) 15 BOC, 20% POWER, RCS NOT N0P, XENON SLOHLY INC., MAIN GEN AT 235 MH,'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% POWER, RCS NOT NOP, MAIN GEN AT 550 MH, XENON EQUILIBRIUM, STEADY STATE POWER, (BGP 100-3, Step 54) l's -
HOC, 64% POWER, 12-3-6-3 LOAD FOLLOH FOR S HOURS, XENON INCREASING 18 MOC, 77% POWER, RCS NOT NOP, STEADY STATE POWER, (BGP 100-3, Step 56) 19 BOC, 100% POWER, RCS NOT NOP, XENON INC, JUST COMPLETED POWER RAMP, (BGP 100-3, Step 59) 20 EOC, 100% POWER, Rd NOT N0P, XENON EQUILIBRIUM, JUST COMPLETED P0HER RAMP,-(BGP 100-3, Step 59) 21 BOC, 100% POWER, RCS NOT NOP, XENON EQUILIBRIUM, STEADY STATE FULL BASE LOAD, (BGP 100-3, Step 59) 22 MOC, 100% POWER, RCS NOT NOP, XENON EQUILIBRIUM, JUST COMPLETED POWER RAMP, (BGP 100-3, Step 59) 23 MOC, 30% POWER, RCS NOT NOP, XENON DEC, 3CD.CBPs OPER, SHAPPING FH TO UPPER N0ZZLES, ELECT PLANT AT POWER L/U, STEADY STATE POWER, (BGP 100-4 Steps 11-15) 24* EOC, 15% P0 lier, RCS NOT NOP, XENON INC, FH CONTROL ON FRVs, STM DUMPS IN "TAVG MODE", ROD CONTROL IN AUTO, 1 TDFHP IN OPER, DOWNP0HER FROM 100%,
SHUTTING DOWN THE TURBINE, (BGP 100-4, Steps 18-30) 25* MOC, HOT STANDBY, RCS NOT NOP, MSIVs OPEN, MAINTAINING N01 NOP 4 HOURS AFTER SHUTDOHN FROM 100% POWER 26 BOC, C00LDOWN, RCS TEMP 350*F, RCS PRESS 400 PSIG, PZR PORVs IN AUTO, PRIOR TO RH L/U, (BGP 100-5, Steps 56-57)
O V
l (BYRONSIM 113/35 08/22/91)
BYRON SIMULATOR l ANSI /ANS-3.5-198S CERTIFICATION REPORT ;
INITIAL REPORT. SEPTEMBER, 1991 '
- APPENDIX 1 LIST OF INITIAL CONDITIONS (IC's) >
(continued)
IC DISCRIEI1ON 27 BOC, C00LDOWN TO COLD SHUTDOHN, 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 NOP, XENON INC, S/D BANKS HITHDRAHN, RX STARTUP B HOURS AFTER A TRIP 29* - BOL LOOPS PARTIALLY DRAINED
-30 MOL, 50% POWER, XENON 50% EQ'JILIBRIUM
-31 BOC, 90% POWER, XENON EQUILIBRIUM 32* BOC, 100% POWER, SGTR TRANSFER FROM BEP-3, 000 GPM BREAK, (BEP-3, last step) 33* REACTOR CAVITY-EMPTY, ALL FUEL ASSEMBLIES IN PLACE, VESSEL HEAD READY.TO BE REMOVED i 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* SP.ARE 37 -BOC, 23% POWER, RAMP FROM 100% XENON INCREASING (BGP 100-4, step 17)
- 38 MOC, 100% POWER, 12-3-6-3 LOAD FOLLON AFTER RAMP UP, XENON-DEC 39 MOC RX STARTUP INCORRECT ECC BANK C @'100 STEPS CRITICALITY
--Thesel Initial Conditions currently not-authortred for-use. These IC's are scheduled-to be. ready for training.no later than July, 1, 1992.
D (6YRONSIM 113/36 08/22/91)
BYRON SIMULATOR ANSI /ANS-3,5-1985 CERTIFICATION REPORT I- INIT)Al REPORT, SEPTEMBER, 1991 0
J APPENDIX 2 REMOTE FUNCTION LISTINGS (LIST OF IN-PLANT LOCAL OPERATOR ACTIONS) l .
(BYRONSIM 113/37 08/22/91)
BYRON SIMULATOR 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 1CC9493T, (0-100%)
50% - 176 gpm CC05 RCP C UP BRNG CLR 1CC9493C (0-100%)
50% - 176 gpm CC06 RCP D UP BRNG CLR 1CC9493D (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 1CC9466A (0-100%)
100%
g JC10 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 DRH 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 (Oh/OFF)
ON CC20 PW M/U AOV POS 1CC182 ( 0~10 0't) 0%
CC21 CC HX 1 INLET 1CC9470B (0-200%)
100%
O 1
1
BYRON SIMULATOR-ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 i3-
-I 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 ICC9504B (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
(~g 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 HX 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 LTDN HX B INLET 1CC9452C (0-100%)
0%.
CC40 LTDN HX A DISCH 1CC9452B (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 O
(O 2
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 I i
(_ / APPENDIX 2 REMOTE FUNCTION LISTINGS 4
CC43 LTDN HX B CC DISCH ICC9452D (0-100%)
100%
CC44 RCP A THERM DARR 1CC9496A (0-100%)
50% - 40 gpm CC45 RCP B THERM BARR 1CC9496B (0-100%)
50% - 40 gpm CC46 RCP C THERM Bt,RR 1CC9496C (0-100%)
< 50% - 40 gpm CC47 RCP 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%
3
BYRON SIMULATOR
-ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O(~'N APPENDIX 2 REMOTE FUNCTION LISTINGS Chol H2 ANALYZF1 PS-343 STATUS (OFF/ LOW /HIGH)
OFF CH02 H2 RECOMB 1 ..,t CONTROL (OFF/ON)
OFF CH03 RX CAVITY DRP V RE9152A-& RE152B (CLOSE/OPEN)
CLOSE
'CH04 EMERG HATCH (CNMT INTEGRITY) (0-100%)
0%
CHOS REACTOR HEAD . (REINSTALL / REMOVE)
REINSTALL CH0f H2 ANNALYZER PS-344 STATUS (OFF/ LOW /HIGH)
OFF CH07 XFER CANAL GATE VALVE (CLOSE/OPEN)
CLOSE CH03 FUEL BUNDLE IN REFUELING MACHINE (OUT/IN)
OUT CH09 CNMT CHIL 1A CONDENSER PS RESET (RESET /HI)_
RESET
{q-
"} C.H10 CNMT CHIL IB CONDENSER PS RESET RESET (RESET /HI) l
'l O .
4
? - . .
.. . _~ -. .
BYRON SIMULATOR
, ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIA L REPORT, SEPTEMBER, 1991 APPENDIX 2 '
REMOTE FUNCTION LISTINGS CRO1 QUADRANT 1 REFUELING (NO CHG/DE-FUEL /RE-FUEL) .
NO CHG
. CR02 . QUADRANT 2 REFUELINC (NO CilG/DE-FUEL /RL-FUEL)
NO CllG CR03 QUADRANT 3 REFUELING -(No CilG/DE-FUEL /RE-FUEL)
NO CHG CR04 ' QUADRANT 4 REFUELING (NO CHG/DE-FUEL /RE-FUEL)
NO CHG CRO5 = FUEL ASSEMBLY G-15 REFUELING (OUT/IN)
OUT CR06 FUEL ASSEMBLY J-03 P.EFUELING (OUT/IN)
OUT g CR07 FUEL ASSEMBLY H-03 RFFUELING (OUT/IE) r -OUT CROS- FUEL' ASSEMBLY G-03 REFUELING (OUT/IN)-
Orrr CR09 FUEL ASSEMBLY J-02 REFUELING (OUT/IN) s OJ'i
,g CR10 FUEL ASSEMBLY H-02 REFUELING (OUT/IN)
- .g OUT CR11- FUEL ASSEMBLY Ga02 REFUELING (OUT/IN)
OUT -
CR12 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-J F
5
BYRON SIMULATOR AN31/ANS-3.5-198S CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 RT: MOTE FUNCTION LISTINGS i
(
CS01 1CS022 SPRAY ADD TK DRN (0-100%)
0%
CSC2 1CSO40B SAT TO EDUC TRN B (0-100%)
100%
CS03 1CC040A SAT TO EDUC TRN A (0-100%)
100%
O l
i O
I 6
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
\_/ APPENDIX 2 REMOTE FUNCTION LISTINGS I
CV01 CV8408A PCV-CV131 ISOL (0-100%)
100t CV02 CV8409 PCV-CV131 BYPASS (0-100%)
0%
CV03 CV8421 RC FILTER BYPAGS (0-100%)
0%
qJ CV04 CV0107A LD RH EX BYPASS ISOL (0-100%)
100%
CV05_ CV8108 LD RH EX MAN BYPASS (0-100%)
0%
, CV06 CV8387A 1A CV PP DISCH BYP (0-100%)
0%
CV07 CV8387B 1B CV PP DISCH BYP (0-100%)
1 0%
CV00 CV8322A REGEN HX LTDWN (0-100%)
100%
CV09 -CV8322B REGEN HX LTDWN (0-100%)
100%
? -
CV10 CV8402B CV182 MAN ISOL (0-100%)
j- 6, 100%
- - ' CV11' CV8403 CV182 BYPASS ISOL (0-100%)
0% ,
CV12 CV8439 MAN EMER BvR ISOL (0-100%)
0%
, CV13 CVB441 PW TO AB FLUSH ISOL (0-100%)
j- 0%
CV14 CVP479A 1A CV PP RECIRC (0-100%) {
100%
CV15 CV8479B 1B CV PP RECIRC (0-100%)
100%
CV16 CV8346 LP FILL CV184 ISOL (0-100%)
, 0%
CV17 CVB100 SL PTN ISOL POS (0-100%)
0%
CV1B CV8396A SL WTR FILTER ISOL (0-100%)
100%
CV19 CV8398A SL HX INLET ISOL (0-100%)
100% ,
CV20 -CVA398B SL HX OUTLET ISOL (0-100%)
100%
-p a
7 u_-__- --
l BYRON SIMULATod AllSI / Alls-3. 5-19 8 5 CERTIFICATIOli REPORT I!11TIAL REPORT, SEPTEMBER, 1991 APPEllDIX 2 REMOTE FUllCTIOli LISTIllGS CV21 CV8399 SL FILTER BYPASS (0-100%)
0%
CV22 CV8400 SL RT!! IlX BYPASS (0-100%)
0%
CV23 CV8376 N2 SUPPLY REG STPT (0-50 PSIG) 15 PSIG CV24 CVB 410 112 SUPPLY REGULATOR STPT (0-50 PSIG)
O PSIG CV25 CV8419 VCT DRAlli (0-100%)
0%
CV26 CV8482 SL RTii-VCT IllLET (0-100%)
0%
CV27 CV8484 SL RTil-VCT OUTLET (0-100%)
100%
CV28 AB8461 BA TA14K SUCT ISOL (0-100%)
100%
CV29 AB8459 BAT PP RECIRC (0-100%)
100%
CV30 AB8478 AB RECIRC ORIFI BYP (0-100%)
O CV31 0%
AB8457 AB RECIRC ORIFI ISO (0-100%) ,
100%
CV32 AP,465 BAT 2 ISOL (0-100%)
0%
CV33 AB8460 BAT PP 1 DIScil (0-100%)
100%
CV34 AB845E 'B FILT BYPASS (0-100%)
05 CV35 AB8469 BAT E O DISCli (0-100%)
0%
CV36 AB8468 U2 MIli FLOW ISOL (0-100%)
0%
CV37 AB8476 BATCll TK TO PP SUCT (0-100%)
0%
CV38 ABB494 MAKEUP TO BATCll TK (0-100%)
0%
CV39 BAT PUMP 0/1 CONNECTED (PMP1/PMPO)
PHP 1 CV40 CV8104 EMER BOR POS (0-100%)
0%
CV41 CVB384A 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
,a CV42 CVB384B SL INJ FILT B ISOL (0/100%)
0%
CV43 1CV012 SL INJ FILT BYP (0/1004) 0%
CV44 CV8369A SL INJ ISOL 1A (0/1004) 10% - 10 gpm CV45 CV8369S SL INJ ISOL 1B (0/100%)
10% - 10 gpm 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%)
0%
O1 CV52 CV8542 BTRS BYPASS (0/100%)
. 100%
CV53 BTRS DEMIN A STATUS (NORM /BOR/UNDOR)
UNDOR CV54 BTRS DEMIN B STATUS (NORM /BOR/UNBOR)
UNBOR CV55 BTRS DEMIN C STATUS (NORM /BOR/UNDOR)
UNDOR CV56 BTRS DEMIN D STATUS (NORM / DOR /UNBOR)
UNDOR CV57- BTRS DEMIN E STATUS (NORM / DOR /UNBOR)
UNBOR CV58 CilILLER PP 0/1 CONNECTED (PUMP 1/PUMPO)
PUMP 1 CV59 AB8465 BAT PP O SUCTION (0-100%)
0%
CV60 AB8468 BAT PP 0 DISCl! (0-100%)
Os CV61 CV8455 PW TO CV M/U (0-100%)
0%
CV62 CV8464A PW ORIFI TO CV M/U (0-100%)
100%
9,
BYRON SIMULATolt ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBElt, 1991 ,
APPENDIX 2 REMOTE FUNCTIOl4 LISTINGS CV63 CV846*,.\ LTDN llX 1A OUTLET (0-100%) 4 100%
CV64 CV8467B LTDN llX 1B OUTLET (0-100%)
100%
CV65 CV8432 MAKEUP TO RWST (0-100%)
04 CV66 CV8350 LP DRN llDR TO RCDT (0-1004) 0%
CV67 CV8486A SL INJ FILT 1A DRN (0-100%)
0%
CV68 CV8486B SL INJ FILT 1B DRN (0-100%)
0%
CV69 RAD MONITOR BYPASS 1FI132 (0-100%)
30% - 3 gpm CV70 CV112B CV PP VCT SUCT POS ("-100%)
100%
CV71 CV112C CV PP VCT SUCT POS (0-100%)
100%
q CV72 CV112D CV PP VCT SUCT POS (0-100%)
0%
CV73 CV112E CV PP VCT SUCT POS (0-100%)
0% '
CV74 '
CV8804A CV PP Ril SUCT POS (0-100%)
0%
CV75 1A CV PP AUX L.O. PP (OFF/0N) 0FF CV76 1B CV PP AUX L.O. PP (OFF/0N) 0FF CV77 CV8321A/8392A REGEN llX CilG (CLOSE/0 PEN)
OPEN CV78 CV8321B/8392B REGEN HX CilG (CLOSE/0 PEN)
OPEN CV79 BORON CONC MASTER RESET (0-2100 PPM) 2000 PPM CV80 OPWO2PA PUMP CONTACT 3-4 ON MUX 4 LOW (NORMAL /0 PEN)
VCT LEVEL NORMAL CV81 1CV8355A/D VALVE MANUAL OPERATIod (0-100%)
(CONTROLS ALL 4 VALVES) 0%
CV82 1AB03P PUMP CONTACT 3-4 ON MUX 5 LOW (NORMAL /0 PEN)
NORMAL O
10
BYR0!i SIMULATOR !
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 0 APPENDIX 2 REMOTE FUllCTION LISTINGS i
CWO1 CW M/U PPS RECIRC CNTRL (0-100%) >
20%
O 4
e 11
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT,-SEPTEMBER, 1991 APPENDIX 2 RLMOTE FUNCTION LISTINGS ED001 0621-LINE DISCONNECT (CLOSE/OPEN)
C14SE ED002- 15501 LINE DISCONNECT (CLOSE/OPEN)
CLOSE
-ED003 U-1 MAIN XFMR DISCONNECT (CLOSE/OPEN)
OPEN ED004 U-2 MAIN XFMR D13 CONNECT (CLOSE/0 PEN)
CLOSE ED005 UNIT 1 SAT DISCONNECT (CLOS'4/OPEN)
CLOSE ED006' BUS 241 AVAIL TO BUS-141' (CLOSE/OPEN)
OPEN ED007 BUS 242' AVAIL TO-BUS 142 (CLOSE/OPEN) '
OPEN ED008 BUS 133U1 FEED BREAKER (CLOSE/OPEN)
CLOSE ED009 BUS 13401 FEED BREAKER (CLOSE/OPEN) ,
CLOSE
( ED010 U-1 FEED TO BUS 033Z1 (CLOSE/OPEN)
CLOSE ED011 U-2 FEED TO BUS 033Z1 (CLOSE/OPEN)
OPEN-ED012 U-2 FEED TO BUS 033W (CLOSE/OPEN)_ i OPEN-ED013. U-2 FEED TO BUS 034W (CLOSE/OPEN).
OPEN ED014 CHARGER 123 FROM BUS 134Z (CLOSE/OPEN)
CLOSE' ED015 DC BUS 123 FEED BREAKER (CLOSE/OPEN)
CIASE ED016 IC BUS 111A FEED BREAKER _(NORM /OPEN/ RESERVE)
NORM-ED017 =IC BUS 112A FEED BREAKER (NORM /0 PEN / RESERVE)
!> NORM ED018 IC BUS 113A FEED BREAKER (NORM /OPEN/ RESERVE)
NORM ,
e -ED019 IC BUS 114A FEED BREAKER (NORM /OPEN/ RESERVE) ;
NORM _ _
ED020 CHARGER 111 FEED-BREAKER (CLOSE/OPEN)
CLOSE t
- O a I
12
.-..-..-. _ .,._. _ ._ _ _ _..-_ _ .. _ ..._...._ _,.._ ..._., ,_. _ .-_, . _ _ . u.
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 ,
APPENDIX 2 REMOTE FUNCTION LISTINGS ED021 CHARGER 112 FEED DREAKER (CLOSE/OPEN)
CLOSE ED022 DC BUS 113 b'IPPLY FUSE (INSTALLED /REMJVED)
INSTALLED ED023 DC BUS 114 SUPI.LY FUSE (INSTALLED / REMOVED)
INSTALLE0 ED024 DC BUS 111 TO INV 111 (CLOSE/0 PEN)
CLOSE ED025 DC BUS 111 TO INV 11a (CLOSE/OPEN)
CLOSE ED026 DC BUS 112 TO IRV 112 (CLOSE/OPEN)
CLOSE ED027 DC BUS 112 TO INV 114 (CLOSE/0 PEN)
CLOSE ED028 BUS 156 LOCKOUT RELAYS (NORM / RESET)
NORM ED029 BUS 157 LOCKOUT RELAYS (NORM / RESET)
NORM ED030 BUS 158 LOCKOUT RELAYS (NORM / RESET)
( NORM ED031 BUS 159 LOCKOUT RELAYS (NORM / RESET)
NORM ,
ED032 BUS 141 LOCKOUT RLLAYS (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 BUS 111A:02:1PA09J (CLOSE/OPEN)
CLOSE ED03GC 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 V
13
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT 4
INITIAL REPORT, SEPTEMhER, 1991
. APPENDIX 2 REMOTE FUNCTION LISTINGS i
ED036G AC BUD 111At08 1PA10J (CLOSE/OPEN)
CLOSE ED036H AC BUS 111A 09:1PA13J (CLOSE/7 PEN)
CLOSE ED0361 AC BUS 111At10:1PM06J (CLOSE/OPEN)
CLOSE ED036J AC BUS 111At11:1PA453 (CLOSE/OPEN)
CLOSE j ED036K AC BUS 111A112:1PA09J (CLOSE/OPEN)
CLOSE ED036L AC BUS 111At16 1PA05J (CLOSE/OPEN)
CLOSE ED036M AC BUS 111A 1811PM06J (CLOSE/OPEN)
CLOSE ED037A AC BUS 112At01:1PM07J (CLOSE/OPEN)
CLOSE ED037B AC BUS 112A102: IPA 09J (CLOSE/OPEN)
CLOSE ED037C AC BUS 112At03:1PA02J (CLOSE/OPEN) i CLOSE ED037D AC BUS 112At06:1PA16J (CLOSE/OPEN) ,
CLOSE ED037E AC BUS 112A 07:IPM07J (CLOSE/OPEN) '
CLOSE ED037F AC BUS 112At08:1PM10J (CLOSE/OPEN) -
CLOSE ED037G AC BUS 112A 11:1PA4SJ (CLOSE/OPEN)
CLOSE ED037H AC BUS 112Ai16: IPA 06J (CLOSE/OPEN)
CLOSE ED037I AC BUS 112At18:1PM06J (CLOSE/OPEN)
CLOSE ED038A AC BUS 113At013.1PM07J (CLOSE/OPEN)
CLOSE ED038B AC BUS 113At02:1PA09J (CLOSE/OPEN)
> CLOSE ED038C AC BUS 113A 03 1PA03J -(CLOSE/OPEN)
CLOSE ED038D AC BUS 113Ai06 1PA15J (CLOSE/OPEN)
CLOSE ED038E AC BUS 113At07:1PM07J (CLOSE/OPEN)
CLOSE ,
3
, (V 14
-- - . - - ._ . -- -= . - . _ - - . _ - - - .- --
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 m
APPENDIX 2 REMOTE FUNCTION LISTINGS ED038F AC BUS 113At08:1PA10J (CLOSE/OPEN)
CLOSE ED038G AC BUS 113At16:1PA07J (CLOSE/OPEN)
CLOSE ED038H AC BUS 113At18:1PM05J (CLOSE/OPEN)
CLOSE ED039A AC BUS 114At01:1PM07J (CLOSE/OPEN)
CLOSE ED039B AC BUS 114At02:1PA09J (CLOSE/OPEN)
CLOSE ED039C AC BUS 114At03:1PA04J (CLOSE/OPEN)
CLOSE ED039D AC BUS 114At05:1PA28J (CLOSE/OPEN)
CLOSE ED039E AC BUS 114At06:1PA12J (CLOSE/OPEN)
CLOSE ED039F AC BUS 114At07:1PM07J (CLOSE/OPEN)
CLOSE p) ED039G AC BUS 114At08:1PA10J '
(CLOSE/OPEN)
( CLOSE ED039H AC BUS 114At09:1PA14J (CLOSE/OPEN)
. CLOSE ED039I AC BUS 114At10:1PM06J (CLOSE/OPEN)
CLOSE ED039J AC BUS 114At11:1PA34J (CICSE/OPEN)
CLOSE ED039K AC BUS 114At12:1PA10J (CLOSE/OPEN)
CLOSE ED039L AC BUS 114At16:1PA08J (CLOSE/OPEN)
CLOSE ED039M AC BUS 114At18 1PM05J (CLOSE/OPEN)
CLOSE ED040A DC MCC 123tCG1:1WG046 (CLOSE/OPEN)
CLOSE ED040B DC MCC 123 DG2:1CXOBJ (CLOSE/OPEN)
CLOSE ED041A DC BUS 111 BF1-01:11P05E (CLOSE/OPEN)
CLOSE ED041B DC BUS 111tBF1-12:1RD05E (CLOSE/OPEN)
CLOSE ED041C DC BUS 111 BF1-14:1PM11J (CLOSE/OPEN)
CLOSE Os v
15 l
l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT )
INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED041D DC BOS 111tBF1-16:1PLO7J (CLOSE/OPEN)
CLOSE ED041E DC BUS 111tBR1-01:1IP07E (CLOSE/OPEN)
CLOSE ED041F DC BUS 111tBR1-05:1DC10J (CLOSE/OPEN)
CLOSE ED041G DC BUS 111tBR1-11:1PLO7J (CLOSE/OPEN)
CLOSE ED041H DC BUS 111tBR1-12:1AF004A (CLOSE/OPEN)
CLOSE ED041I DC BUS 111tBR1-13:1PA27J (CLOSE/OPEN)
CLOSE ED041J DC BUS 111tBR1-14:1PA13J (CLOSE/OPEN)
CLOSE ED041X DC BUS 111tBR1-15:1PM02J (CLOSE/OPEN)
CLOSE ED041L DC BUS 111 BR1-17:1PLO7J (CLOSE/OPEN)
CLOSE l g-- ED041M DC BUS 111tBR1-18:1PA31J (CLOS E/OPEN)_
CLOSE ED042A DC BUS 112 BF1-01:1IP06E (CLOSE/OPEN)
CLOSE .
ED042B DC BUS 112tBF1-13:1RD05E (CLOSE/OPEN)
CLOSE ED042C DC BUS 112tBF1-14t1PM11J (CLOSE/OPEN)
CLOSE ED042D DC BUS 112tBF1-16:1PLOBJ (CLOSE/OPEN)
CLOSE
.ED042E DC BUS 112tBF1-19 1PJ08J (CLOSE/OPEN)
CLOSE ED042F DC BUS 112tBR1-01:11P08E (CLOSE/OPEN)
CLOSE ED042G DC BUS 112tBR1-03:1DC11J (CLOSE/OPEN)
CLOSE ED042H DC BUS 112tBR1-13:1PLOBJ (CLOSE/OPEN)
CLOSE ED0421 DC BUS 112tBR1-14:1PA14J (CLOSE/OPEN)
CLOSE ED042J DC BUS 112tBR1-15:1PA32J (CLOSE/OPEN)
CLOSE ED042K DC BUS 112tBR1-16:0PM02J (CLOSE/OPEN)
CLOSE 16 l
i l
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LIST 1 HGS
~.
ED042L DC BUS 112tBR1-19 1AF004B (CLOSE/OPEN)
CLOSE ,
ED042M DC BUS 112tBR1~20:1PA28J (CLOSE/OPEN) !
CLOSE ED043A DC BUS 113tEF1-03:1PA31J (CLOSE/OPEN)
CLOSE ED043B DC BUS 113 EF1-10:1RD03E (CLOSE/OPEN)
CLOSE ED043C DC BUS 113tEF1-14:1PA27J (CLOSE/OPEN)
CLOSE ED043D DC BUS 113 EF1-16:1PM02J (CLOSE/OPEN)
CLOSE ED043E DC BUS 113tEF1-1711PM04J (CLOSE/OPEN)
CLOSE ED043F DC BUS 113tEP1-18:1PM01J (CLOSE/OPEN)
CLOSE ED043G DC BUS 113tER1-02:1DC12J (CLOSE/OPEN)
CLOSE ED043H DC BUS 113tER1-08:1PM02J (CLOSE/OPEN)
CLOSE Os ED043I DC BUS 113tER1-09:1PM11J (CLOSE/OPEN)
CLOSE -
ED043J DC BUS 113tER1-13:0PM03J (CLOSE/OPEN)
CLOSE ED043K DC BUS 113tER1-18:0PM02J (CLOSE/OPEN)
CLOSE ED043L DC BUS 113tER1-19:1PA26J (CLOSE/OPEN)
CLOSE ED043M DC BUS 113tER1-20:0PM01J (CLOSE/OPEN)
CLOSE ED044A DC BUS 114tEF1-05:1PA42J (CLOSE/OPEN)
CLOSE ED044B DC BUS 114tEF1-12:1RD03E (CLOSE/OPEN)
CLOSE ED044C DC BUS 114 EF1-17:1PM04J (CLOSE/OPEN)
CLOSE ED044D DC BUS 114tEF1-18:1PM02J (CLOSE/OPEN)
CLOSE ED044E DC BUS 114tEF1-20:1TG07JB (CLOSE/OPEN)
CLOSE E0044F DC BUS 114 ER1-07t.DC13J (CLOSE/OPEN)
CLOSE O-17 l
u . . _. . - - _ _ _ _ _ _ _ _ _
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 b
APPENDIX 2 REMOTE FUNCTION LISTINGS ED0440 DC BUS 114 ER1-10:1PM11J (CLOSE/OPEN)
CLOSE ED044H DC BUS 114 ER1-14:0PM03J (CLOSE/OPEN)
CLOSE ED0441 DC BUS 114 ER1-16:1PA28J (CLOSE/OPEN)
CLOSE ED044J DC BUS 114 ER1-17:0PA01J (CLOSE/OPEN)
CLOSE ED045A BUS 156:02:1RC01PB (NORM /CLOSE/OPEN)
OPEN ED045B BUS 156:03:1HD01PB (NORM /CLOSE/OPEN)
OPEN ED045C BUS 156:04:1FWO1PA (NORM /CLOSE/OPEN)
OPEN ED046A BUS 157 01:1RC01PA (NORM /CLOSE/0 PEN)
CPEN ED046B BUS 157 03:1HD01PA (NORM /CLOSE/OPEN) l OPEN '
fg ED046C BUS 157:04:RSH (NORM /CLOSE/0 PEN)
(_) CLOSE ED046D BUS 157:05:1HD03PC (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 ED048A BUS 159:02:1CD05PA (NORM /CLOSE/OPEN)
OPEN ED048B BUS 159:03:1CD05PC (NORM /CLOSE/OPEN)
OPEN ED048C BUS 159304:1FWO2P (NORM /CLOSE/OPEN)
OPEN ED048D BUS 159:05:1RC01PD (NORM /CLOSE/OPEN)
OPEN ED049A BUS 141 02:1SX01PA (NORM /CLOSE/OPEN)
CLOSE ED049B BUS 141:03:1SIO1PA (NORM /CLOSE/OPEN) l OPEN ED049C BUS 141:04:1RH01PA (NORM /CLOSE/OPEN)
CLOSE 18
l BYRoll SIMULATOR j ANSI /ANS-3.5-1985 CERTIFICATION REPORT I!41TIAL REPORT, SEPTEMBER, 1991 s
,f
(> APPEllDIX 2 REMOTE FUNCTION LISTIllGS ED049D DOS 141106tDG1A (!!ORM/CLOSE/OPEN)
OPEN ED049E BUS 141:08:1AF01PA (NORM /CLOSE/ OPE!4)
OPEli ED049F BUS 141:09:1CS01PA (NORM /CLOSE/OPEN)
OPEN ED049G BUS 141:11:1CV01PA (NORM /CLOSE/OPEN)
CLOSE ED049H BUS 141:12:1CC01PA (ilORM/CLOSE/OPEll)
CLOSE ED049I BUS 141:18:0CC01P (NORM /CLOSE/OPEN)
OPE!1 ED050A BUS 142302:1SX01PB (NORM / CLOSE/OPEll)
OPEN ED050B BUS 142803:1SIO1PB (NORM /CLOSE/OPEN)
OPEN ED050C BUS 142 04:1RH01PB (NORM /CLOSE/OPEN)
OPEN fs ED050D BUS 142:06tDG1B (flORM/CLOSE/OPEN)
OPEN ED050E BUS 142800:1CS01PB (NORM /CLOSE/OPEN)
OPEN ,
ED050F BUS 142:09:1CC01Pb (NORM /CLOSE/OPEll)
CLOSE ED050G BUS 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 ED051C BUS 143:09:1CWO1PA (NORM /CLOSE/OPEN)
OPEN ED051D BUS 143:12:1CWO1PC (NORM /CLOSE/OPEN)
OPEN ED051E BUS 143:15:0SA01C (NORM /CLOSE/OPEN)
OPEN ED052A BUS 144103 HTRB&C (!JORM/CLOSE/OPEN)
OPEN ED052B BUS 144:04:1SA01C (NORM /CLOSE/OPEN)
CLOSE l
19 I . - - . . . . --
BYROH SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPEllDIX 2 REMOTE FUNCTION LISTINGS ED052C BUS 144107:OWS01PB (NORM /CLOSE/0 PEN)
OPEN ED052D BUS 144 iltICWO1PB (NORM /CLOSE/0 PEN)
OPEN ED053A 131X11B4:ICS001A (CLOSE/OPEN)
CLOSE ED053B 131X1:C111CS009A (CLOSE/OPEN)
CLOSE ED053C 131X1:D4 1AF013A (CLOSE/0 PEN) '
CLOSE ED053D 131X11El 1AF013D (CLOSE/OPEN)
CLOSE ED053E 131X1:E2:1AF013C (CLOSE/OPEN)
CLOSE ED053F 131X1:E3 1AF013D (CLOSE/0 PEN)
CLOSE ED053G 131X1:F2 1RII610 (CLOSE/OPEN)
CLOSE
- ED053H 131X1:P311RIIB716A (CLOSE/0 PEN)
CLOSE ED053I 131X1:F4:ISI8801A (CLOSE/0 PEN) ,
CLOSE ED053J 131X12G411SI8807A. (CLOSE/OPEN)
CLOSE ED053K 131X1:H4 ISIB821A (CLOSE/OPEN) '
CLOSE ED053L 131X1 K1 1CV8106 (CLOSE/OPEN)
CLOSE ED053M 131X1:K211CS019A (CLOSE/OPEN)
CLOSE ED053N 131X1 K3:1CC9412A (CLOSE/OPEN)
CLOSE ED0530 131X1:K4: ICV 112D (CLOSE/OPEN)
CLOSE ED053P 131X1 M3 1 SIB 811A (CLOSE/OPEN)
OPEN ED054A 131X1tL208 (120)t0PM02J (CLOSE/0 PEN)
CLOSE ED054B 131X1 L216 (120) t 1PA51J (CLOSE/OPEN)
CLOSE ED054C 131X1:L218 (120):OPR31132 (CLOSE/0 PEN)
CLOSE I ,
2e l
, - .~ . . -
I BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE TUNCTION LISTINGS ED054D 131X1tL221 (120)t1PA03J (CLOSE/OPEN) i CLOSE j ED054E 131X1tL224 (120) 1PA33J (CLOSE/nogN) ,
CLOSE ED055A 131X1AtH1:1SI8920 (CLOSE, , uN)
CLOSE ED055B 131X1AtN2:1SIBB14 (CLOSE/OPEN)
CLOSE ED055C 131X1AtPillSI8802A (CLOSE/OPEN)
OPEN ED055D 131X1AtP2 1SI8809A (CLOSE/OPEN)
CLOSE ED055E 131X1AtP3:1SI8806 (CLOSE/OPEN)
OPEN ED055F 131X1AtP4:1 SIB 835 (CLOSE/OPEN)
OPEN ED055G 131X1AtQ1:1 SIB 812A (CLOSE/OPEN)
CLOSE f- ED055H 131X1At02:1 SIB 840 (CLOSE/OPEN)
('- OPEN .
ED056A 131X2tB1:1RH701A (CLOSE/OPEN)
. . CLOSE ED056B 121X2tB4 1RH8702A (CLOSE/OPEN)
OPEN ED056C 131X2tC3:1VQ001A (CLOSE/OPEN)
OPEN ED056D 131X2:C41RC800 (CLOSE/OPEN)
OPEN ED056E 131X2tC5:1RC8003?. (CLOSE/OPEN)
OPEN ED056F 131X2 F1:1VQ002A (CLOSE/OPEN)
OPEN ED056G 131X2tG1 1RC8001A (CLOSE/OPEN)
OPEN ED056H 131X2tG2:1RC8001B (CLOSE/OPEN)
OPEN ED056I 131X2tG3:1RC8001C (CLOSE/OPEN)
OPEN ED056J 131X2 G4:1RC8001D (CLOSE/OPEN)
OPEN ED057A 131X2tF220 (120) 1PA33J- (CLOSE/OPEN)
CLOSE
- 21 l
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS E0057B 131X2tP221 (120)t1PA01J (CLOSE/OPEN)
CLOSE i ED057C 131X2 F212 (120)t1PM06J (CLOSE/OPEN) l CLOSE ED058A 131X2AtA2tBI8808D (CLOSE/OPEN) .
OPEN l ED050B 131X2AIA3tSIB008A (CLOSE/OPEN) l OPEN ED058C 131X2B A5 RY8000A (CLOSE/OPEN)
CLOSE ED058D 131X2BtB1At1HS018A (CLOSE/OPEN)
CLOSP. ,
ED058E 131X2 BIB 1B 1MS0180 (CLOSE/OPEN) i CLOSE ED059A 131X3tB4:1AF006A (CLOSE/OPEN)
OPEN ED059B 131X3tB511AF017A (CLOSE/OPEN)
OPEN ED059C 131X3tD5 1CC9473A (CLOSE/OPEN) 0- ED059D 131X3tE4:1SX001A CLOSE (CLOSE/OPEN)
OPEN ED060A 131X3tC205 (120):1PA45J (CLOSE/OPEN)
CLOSE ED060B 131X3tC210 (120)t1PM01J- (CLOSE/OPEN)
CLOSE ED060C 131X3 C220 (120)t1PA31J (CLOSE/OPEN)
CLOSE ED061 .131X4; Ant 1CV8100 (CLOSE/OPEN)
CLOSE ED062A 17.1X5tA4:1CS007A (CLOSE/OPEN)
CLOSE ED062B 131X5 A5:1CV112B (CLOSE/OPEN)
CLOSE ED062C 131X5tC4:1SX016A (CLOSE/OPEN)
CLOSE E0062D 131X5tC5:1SX027A (CLOSE/OPEN)
CLOSE ED063A 132X1tCit1SX001B (CLOSE/OPEN)
.OPEN ED063B 132X1tC211 SIB 924 (CLOSE/OPEN)
CLOSE O
22
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT -
INITIAL REPORT, SEPTEMDER, 1991 APPENDIX 2 i REMOTE FUNCTION LISTINGS ED063C 132X1 C4 1Ril611 (CLOSE/0 PEN)
CLOSE ED063D 132X1 D411CC9412B (CLOSE/0 PEN)
CLOSE
-ED063E 132X11DS:ICC9473B (CLOSE/0 PEN)
CLOSE ED063F 132X1tE4Bt1MS010B (CLOSE/0 PEN)
CLOSE ED063G 132X11G1:ICS009B (CLOSE/0 PEN)
CLOSE ED06311 132X1 G2:ICS009B (CLOSE/OPEN)
CLOSE ED0631 132X1tG3:1SI8807B (CLOSE/OPEN)
CLOSE ED064A 132X11J209 (120) : IPA 32J (CLOSE/0 PEN)
CLOSE ED064B 132X1 J211 (120)11AR021 (CLOSE/OPEN) 4 CLOSE
( ED064C 132X1 J219 (120): IPA 04J (CLOSE/OPEN)
CLOSE ED064D 132X1tJ221 (12 0) t 1PA34J (CLOSE/0 PEN)
CLOSE -
ED065A 132X2 B1 1Ril8702B (CLOSE/0 PEN)
CLOSE ED065B 132X2:B3 1Ril8701B (CLOSE/0 PEN)
OPEN ED065C 132X2:B4 1CV8112 (CLOSE/0 PEN)
CLOSE ED065D 132X2:C411RY8000B (CLOSE/0 PEN)
CLOSE EP')65E 132X2 :D4 1RC8003B (CLOSE/0 PEN)
OPEN ED065F 132X2:D5 1RC8003C (CLOSE/OPEN)
OPEN ED065G 132X2tG1:1RC8002A (CLOSE/OPEN)
OPEN ED06511 132X2:G2:1RC8002B (CLOSE/0 PEN)
OPEN ED065I 132X2:G3 1RC8002C (CLOSE/0 PEN)
OPEN E0065J 132X2:G4 1RC8002D (CLOSE/0 PEN)
OPEN O
23
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 ;
APPEllDIX 2 REMOTE TUNCTION LISTINGS ED066A 132X2tF214 (120)t1PM09J (CLOSE/OPEN) ,
CLOSE ED066B 132X2tP216 (120)t0/1AR056/12 (CLOSE/OPEN)
CLOSE ED066C 132X2tF219 (120):1PA02J (CLOSE/0 PEN)
CLOSE ED066D 132X2tF208 (120) 1PM06J (CLOSE/OPEN)
CLOSE ED067A 132X2AIA2:1SI8808C (CLOSE/OPEN)
OPEN ED067B 132X2AtA3:1SI8808B (CLOSE/OPEN)
OPEN ED068A 132X3tA4:1AF000B (CLOSE/OPEN)
OPEN ED068B 132X3tA5:1AF017B (CLOSE/OPEN) i OPEN ED069A 132X3tB207 (120 #1):1PM01J (CLOSE/0 PEN)
CLOSE ED069B 132X3tB220 (120 #1)t0PM02J (CLOSE/0 PEN)
O CLOSE ED070A 132X3tF209 (120 /2)t0PR033J (CLOSE/OPEN) l CLOSE ED070B 132X3tF211 (120 #2)t0PR34J (CLOSE/OPEN)
CLOSE ED071A 132X4IA1:1SX016B (CLOSE/OPEN)
CLOSE ED071B 132X4tA2:1SXO27B (CLOSE/OPEN)
CLOSE ED071C 132X4tA3:1CS5001B (CLOSE/0 PEN)
CLOSE ED071D 132X4tA4:1RJ18716B (CLOSE/OPEN)
CLOSE ED071E 132X4tB1:1AF013F (CLOSE/0 PEN)
CLOSE ED071F 132X4tB2:1AF013E (CLOSE/OPEN)
CLOSE ED071G 132X4tB3:1CS007B (CLOSE/OPEN)
CLOSE ED071H 132X4tB4:1AF013H (CLOSE/0 PEN)
CLOSE ED071I 132X4tC1:1AFO'3G (CLOSE/OPEN)
CLOSE l
O p 24
BYRoll SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O.
ks s APPENDIX 2 REMOTE FUliCTIOli LISTINGS ED071J 132X4 C2:1CV112E (CLOSE/OPEN)
CLOSE ED071K 132X4tC3:1CV8105 (CLOSE/OPEN)
CLOSE ED071L 132X4tD4:1CC685 (CLOSE/OPEN)
CLOSE ED071M 132X4tFit1SI8821B (CLOSE/OPEN)
CLOSE ED071N 132X4 H1:1SI8811B (CLOSE/OPEN)
OPEli ED0710 132X4 H3:1VQ001B (CLOSE/OPEN)
OPEN ED071P 132X4tH4:1VQOO2B (CLOSE/OPEN)
OPEN ED072A 132X4AtL2:1SI8802B (CLOSE/OPEN)
OPEli ED072B 132X4AtL3:1 SIB 813 (CLOSE/OPEN)
OPEN
-s ED072C 132X4AtM1:1SI8809B (CLOSE/OPEN) qj CLOSE ED072D 132X4 AIM 2:1SIBB12B (CLOSE/OPEN)
CLOSE ,
ED073A 132X5tA4 1 SIB 801B (CLOSE/OPEN)
CLOSE ED073B 132X5 B1 CV8104 (CLOSE/OPEN)
CLOSE ED073C 132X5tC2Bt1MS018C (CLOSE/OPEN)
CLOSE ED073D 132X5tC4:1CV112C (CLOSE/OPEN)
CLOSE ED074 133Yt3C 1RD01E (CLOSE/OPEN)
CLOSE ED075A 133U1tB1:1CWO1JA (CLOSE/OPEN)
CLOSE ED075B 133U1tC3:1CW001C (CLOSE/OPEN)
CLOSE ED075C 133U1 C4:1CW001A (CLOSE/OPEN)
CLOSE ED075D 133U2*E3:1CWO1JC (CLOSE/OPEN)
CLOSE O
25
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION PEPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED076 13301.0203 (12 0) t 0TT-CWO4 0 (CLOSE/0 PEN)
CLOSE ED077A 133V ::B202 (120) : 1PA27J (CLOSE/0 PEN)
CLOSE ED077B 133V2tB204 (120) 1PA26J (CLOSE/0 PEN)
CLOSE ED077C 133V2 t B205 (120) 1PA22J (CLOSE/0 PEN)
CLOSE ED077D 133V2tB206 (120):1PA24J (CLOSE/0 PEN)
CLOSE ED077E 133V2tB208 (120) : 1PM05J (CLOSE/0 PEN)
CLOSE ED077F 133V2tB215 (120)t1PA31J (CLOSE/OPEN)
CLOSE ED077G 133V2tB216 (120) 1PA38J (CLOSE/OPEN)
CLOSE ED077H 133V2tB218 (120)t1PA19J (CLOSE/OPEN)
CLOSE ED077I 133V2tB224 (120)t0PM02J (CLOSE/0 PEN) '
( CLOSE ED070A 133V3tC5:1CWO18 (CLOSE/0P:1) ,
CLOSE ED078B 133V3tF2A10PR05J (CLCSE/0 PEN)
CLOSE ED079A 133V4tA1At1PR09J (CLOSE/0 PEN)
CLOSE ED079B 133V4tA2At0PR09J (CLOSE/0 PEN)
CLOSE ED079C 133V4tE2:1FWO1PB-A (CLOSE/0 PEN)
CLOSE ED079D 133V4tE4:1FWO59 (CLOSE/0 PEN)
CLOSE ED080A 133V4tC203 (120):1PA35J (CLOSE/0 PEN)
CLOSE ED080B-133V4tC207 (120):1MS01JC (CLOSE/OPEN)
CLOSE ED080C 133V4tC212 (120):1CB039A-M (CLOSE/0 PEN)
CLOSE ED081A 133X1AtC204 (120):1TS-00671A (CLOSE/OPEN)
CLOSE l
26
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED081B 133X1AIC206 (120) : 1PR11J (>)U$$Y.:6Ysx(
CLOSE ED001C 133X1AIC208 (120)t1 TIS-CV129 (dGdht '194p CLOSE ,
ED081D 133X1AtC224 (120)t1PA05J (CLOSE/OPEN)
CLOSE ED082A 133X1BtB201 (120)t1PA36J (CLOSE/OPEN)
CLOSE-ED002B 133X1BtB203 (120)t1PA37J (CLOSE/OPEN)
CLOSE ED082C 133X1BtB204 (120):1PM120 (CLOSE/OPEN)
CLOSE ED082D 133X1BtB219 (120):1PA20JA (CLOSE/OPEN)
CLOSE ED002E 133X1BtB220 (120):1PA50J (CLOSE/OPEN)
CLOSE ED082F.133X1BtB221 (120):1PA20JB (CLOSE/OPEN) i CLOSE ED082G 133X1 BIB 222 (120) :1PA075 (CLOSE/OPEN)
O ED082H 133X1 BIB 223 (120) 1PA20JC CLOSE (CLOSE/OPEN)
. . CLOSE ED083 133X1BIC1Bt1PIO3EA (CLOSE/OPEN)
CLOSE ED084A 133X3tA1Bt1CV06J (CLOSE/OPEN)
CLOSE ED084B 133X3tE4At1PR02J (CLOSE/OPEN)
CLOSE ED085A 133X3tC202 (120 #1) :1CV06J (CLOSE/OPEN)
CLOSE ED085B 133X3tC'03 (120 #1):1PM04J (CLOSE/OPEN)
CLOSE ED085C 133X3tC205-(120 #1):1PM04J (CLOSE/OPEN)-
CLOSE ED005D 133X3tC207 (120 #1):1PM03J (CLOSE/OPEN)
CLOSE ED085E 333X3tC209 (120 #1):1PM02J (CLOSE/OPEN)
CLOSE ED085F 133X3 C211-(120 #1):1PM02J (CLOSE/OPEN)
CLOSE ED085G 133X3tC213 (120 #1)t0PM03J (CLOSE/OPEN)
CLOSE L C) 27 1
y-. - , -. , . -,e - e m,-- ,, e-..y-, . , ,
,,,-m- . . , , , , . - .,,,...,r,.... _
BYRON SIMULATOR ANSI / Alls-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 (O
v' APPEllDIX 2 REMOTE FUllCTION LISTINGS ED085H 133X3tC215 (120 #1):1PM01J (CLOSE/0 PEN)
CLOSE ED086A 133X3tG204 (120 #2):1PA17J (CLOSE/0 PEN)
CLOSE j ED086B 133X3tG212 PR21/28)XS1PA17J (CLOSE/OPEll)
CLO30 l I
ED086C 133XOtG224 (130 #2):1PR28J (CLOSE/0 PEN) chvec ED087A 133X4 J209 {1?O)tiPA21J (CLOSE/OPEll)
CLhSV ED087B 133X4tJ209 (atO) 1PM06J (CLOSE/0 PEN)
CLOSE ED088A 133Y11 A4:1CB02 PC-A (CLOSE/0 PEN)
CLOSE ED088B 133Y18A$t1CB01PA-A (CLOSE/0 PEN)
CLOSE EDOBBC 133Y1tA6:1CD05PA-B (CLOSE/0 PEN)
CLOSE ED088D 133Y1tB1:3CD05PC-B (CLOSE/0 PEN)
O ED088E 133Y1tE4:1CWOO2A CLOSE (CLOSE/0 PEN)
CLOSE -
ED088F 133Y1tE5:1CWOO3A (CLOSE/OPEN)
OLOSE ED088G 133YitG4:1CWOO2D (CLOSE/0 PEN)
CLOSE ED088H 133Y1tG5:1CWOO3D (CLOSE/0 PEN)
CLOSE ED089A 133Y1tD203 (120):1CD05PC-B (CLOSE/0 PEN)
CLOSE ED0898 133Y1tDP05 (120):1CD05PA-B (CLOSE/0 PEN)
CLOSE ED089C-133Y1tD221 (120)tCD210/211 (CLOSE/OPEN)
CLOSE ED090A 133Z2tC202 (120):1PM11/12J (CLOSE/OPEN)
CLOSE ED090B 133Z2tC205 (120):1FWO1PC-J (CLOSE/0 PEN)
CLOSE ED090C 133Z2tC208 (120):MSRVLVS -(CLOSE/0 PEN)
CLOSE ED091A 133Z2tD3 1FWOO5 (CLOSE/0 PEN)
CLOSE O
28 l
i BYRON SI!!ULATOR A11SI/ANS-3.5-1985 CERTIFICATIO!! REPORT IllITI AL REPORT, SEPTEMBER, 1991 APPEllDIX 2 RE!40TE FUllCTIOli LISTIllGS ED091B 133Z2tE4:1FWO4A (CLOSE/ OPEli)
CLOSE ED091C 133Z2tG3tirWOO2A (CLOSE/OPEll)
CLOSE ED0910 133Z2tG411FWO2P-B (CLOSE/ OPE!1)
CLOSE ED091E 133Z2til2:1T008PA (CLOSE/OPEll)
CLOSE ED091T 133Z2til3:1T008PB (CLOSE/OPEll)
CLOSE ED091G 133Z2til4:1T000PC (CLOSE/OPEli)
CLOSE ED09111 13 3 Z21115 1rWOO2 C (CLOSE/OPEN)
CLOSE ED092 134Yt2At1RD02E (CLOSE/OPEN)
CLOSE ED093A 134UltB3:1CWO1JB (CLOSE/OPEli)
CLOSE ED093B 134UltB4:1CWOO1B (CLOSE/OPEll)
O ED094 CLOSE 134V1tA1A 1PIO3EB (CLOSE/OPEN)
CLOSE
- ED095A 134VitC202 (120)t1CC9415 (CLOSE/OPEN)
CLOSE ED095B 134VitC204 (120) 1 TIS-CC672 'CLOSE/OPEN)
CLOSE ED095C 134VitC207 (120):1PM12J (CIOSE/OPEN)
CLOSE ED095D 134VitC208 (120)t1PA38J (CLOSE/OPEN)
CLOSE ED095E 134VitC210 (120):1PA43J (CLOSE/OPEN)
CLOSE ED095F 134Vit0211 (120)t1PA35J (CLOSE/OPEN)
CLOSE ED095G 134VitC212 (120)t1PA22J (CLOSE/OPEN)
CLOSE ED09511 134VitC214 (120)t1PA36J (CLOSE/OPEN)
CLOSE ED0951 134V12C216 (120) : 1PA37J (CLOSE/OPEN)
CLOSE ED095J 134VitC218 (120)t1PA50J (CLOSE/OPEN)
CLOSE 4
O 29 ll a. ______________ ___ ___ ___ _ . . . .,
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMDER, 1991 APPENDIX 2 !
REMOTE FUNCTION LISTINGS ED095K 134VI C219 (120) t 1PA20JA (CLOSE/OPEN)
CLOSE ED09DL 134VitC220 (120)t1PM10J (CLOSE/OPEN)
CLOSE ED095M 134VitC221 (120) t 1PA20JB (CLOSE/OPEN)
CLOSE ED095N 134VitC223 (120)t1PA20JC (CLOSE/OPEN)
CLOSE ED096A 134V2tF201 (120) t 0PA01J (CLOSE/OPEN)
CLOSE ED096B 134V21F217 (120)t1PA08J (CLOSE/OPEN)
CLOSE ED097 134V3tA1At1PR03J (CLOSE/OPEN)
CLOSE ED098 134V3tC208 (120)tTIS-684/6 (CLOSE/OPEN) 1 CLOSE ED099A 134V4tD202 (120) 1PA28J (CLOSE/OPEN)
CLOSE ED099B 134V4tD204 (120) t 1PA35J (CLOSE/OPEN)
O' ED099C 134V4tD206 (120)t1PM03J CLOSE (CLOSE/OPEN)
CLOSE ED099D 134V4tD207 (120)t1PM01J (CLOSE/OPEN)
CLOSE ED099E 134V4tD209 (120) 1PM04J (CLOSE/OPEN)
CLOSE ED099F 134V4tD210 (120):1PM02J (CLOSE/OPEN)
CLOSE ED099G 134V4tD211 (120) 1PM04J (CLOSE/OPEN)
CLOSE ED099H 134V4tD212 (120)t0PH01J (CLOSE/OPEN)
CLOSE ED0991 134V4tD218 (120) :1PM08J (CLOSE/OPEN)
CLOSE ED099J 134V4tD220 (120) 1PA30/32J (CLOSE/OPEN)
CLOSE ED099K 134V4 D222 (120) 1PA06J (CLOSE/OPEN)
CLOSE ED099L 134V4 t D223 - (120) 1PA42J (CLOSE/OPEN)
CLOSE ED099M 134V4tD224 (120) :1PM08J (CLOSE/OPEN)
CLOSE O
30
BYRON SIMULATOR
- ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS ED100 134V6 C210 (120) : 1FWO1PB-J (CLOSE/OPEN)
CLOSE ED101A 134X5 J202 (120)t1PA44J (OLOSE/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 134Y1 B1:1CD05PD-B (CLOSE/OPEN)
CLOSE ED103A 134Y2:A4:1CWOO2B (CLOSE/OPEN)-
CLOSE
.s ED103B 134Y2 A5:1CWOO3B CLOSE (CLOSE/OPEN)
ED103C 134Y2 D4:1CWOO2C (CLOSE/OPEN)
CLOSE ,
ED103D 134Y2:D5:1CWOO3C (CLOSE/OPEN)
CLOSE ED104A 134Y2:C203 (120):1CD05PB-B (CLOSE/OPEN)
CLOSE ED104B 134Y2:C205 (120):1CD05PD-B (CLOSE/OPEN)
CLOSE ED105 134Y3:E1:1FWO1PD-B (CLOSE/OPEN)
CLOSE '
ED106A 134Z2:D3:1T007P (CLOSE/OPEN)
CLOSE ED106B 134Z2:E3:1FWOO2B (CLOSE/OPEN)
CLOSE ED106C 134Z2 F1:1FWO1PA-B (CLOSE/OPEN)
CLOSE ED106D 134Z2:G1:1FWO1PC-B (CLOSE/OPEN)
CLOSE ED107A 134Z4:C1:1T008PD (CLOSE/OPEN)
CLOSE ED107B 134Z4 C2:1T008PE (CLOSE/OPEN)
CLOSE O
31
BYRON SIMULATOR
- ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 1
APPENDIX 2 REMOTE FUNCTION LISTINGS 1
1 1
ED107C 134Z4 C3 1T000PP (CLOSE/CPEN) cLOSE
- ED100 SAT LOCKOUT RESET (NORM / RESET)
NORM 4 ED109 SYSTEM VOLTAGE (300-370 KV) 345 XV ED110 CROSS-TIE DUSES 35-1/35-2 (CLOSE/OPEN) 1 OPEN ED111 CROSS-TIE UNIT 2 BKR 411 (CLOSE/OPEN) 4- OPEN ED112 CROSS-TIE UNIT 2 BKR 212 (CLOSE/0 PEN)
OPEN l ED113 JUMPER AT CONTACTS 5-6 FOR ACB 1411 (NORMAL / BYPASS)
- NORMAL ED114 JUMPER AT CONTACTS 5-6 FOR ACB 1421 (NORMAL / BYPASS)
NORMAL
- k 4
2 1
a
]
b k
O 32
, _ . _ . -_ . . . _ _ __ _ _ _ _ . . . . . ..-_-_;-. . u, .
BYRoll SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
,r~
( APPENDIX 2 REMOTE FUNCTION LISTINGS EG01 GEN LOCKOUT RELAY 86G1A (NORM / RESET)
NORM EG02 GEN LOCKOUT RELAY 06G1B (NORM / RESET)
NORM EG03 DGIA CONTROL MODE SELECT (LOCAL / REMOTE /MAINT_0)
REMOTE EG04 DGIA UNIT PARALLEL SWITCll (DROOP /ISOCil)
DROOP EG05 DG1A LOCAL START /STOP (STOP/ NORM / START)
NORM EG06 DG1A LOCAL RESET (NORM / RESET)
NORM EG07 DG1A VOLTAGE RAISE / LOWER (LOWER / NORM /RAIST)
NORM EGOB DG1A SPEED RAISE / LOWER (LOWER / NORM / RAISE)
NORM EG09 DG1B CONTROL MODE SELECT (LOCAL / REMOTE /MAINT_0) s REMOTE
.(' EG10 DG1B UNIT PARALLEL SWITCil (DROOP /ISOCH)
DROOP EG11 DG1B LOCAL START /STOP (STOP/ NORM / START)
NORM EG12 DG1B LOCAL RESET (NORM / RESET)
NORM EG13 DG1B VOLTAGE RAISE / LOWER (LOWER / NORM / RAISE)
NORM EG14 DG1B SPEED RAISE / LOWER (LOWER /NORH/ RAISE)
NORM EG15 BRXR 41M TRIP (NORM / TRIP)
NORM EG16 GEN TRIP TB TEST SW J (CLOSE/0 PEN)
CLOSE
(
33
I i
i DYROll SIMUIATOR l ANSI /ANS-3.5-1905 CERTIFICATION REPORT l INITIAL REPORT, S EPTEM11ER , 1991 )
i i l
l APPE!1 DIX 2 REMOTE FUNCTION LISTINGS EP01 RIVER WATER LEVEL (660'-600')
672' l EP02 IIIVER TEMPERATURE ( 3 2 -10 0'F) l 65'F l EP03 ATHOSPilERIC WIND SPEED (0-100 HPH) 10 MPil EPO4 ATHOSPilERIC WIND DIRECTION ( 0-3 60')
270' EPOS ATHOSPHEllE WET BULB TEMPERATURE ( 0-100*F) 63'F EP06 ATHOSPilERIC DRY BULB TEMPERATURE (-2 0-+ 10 0*F) )
7 5'r i EP07 AThsSPilERIC PRESSURE (12-17 PSIA) )
j 14.7 PSIA j
, EP08 EXTERNAL GRID FREQUENCY (58-62 112) !
! 60 Hz )
l EP09 EXTERNAL GRID VOLTAGE (300-370 KV) !
! 345 KV i
! EP10 EXTERNAL GRID EQUIVALENT REACTANCE (0-100%) l 50%
i l
l l
t i
t 34 t
BYRON SIMULATOR ANSI /A!1S*3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FP01 MPT 1E FP DELUGE RESET (NORMAL / RESET)
NORMAL FP02 MPT IW FP DELUGE RESET (NORMAL / tlESET)
NORMAL FP03 UAT 141-1 FP DELUGE RESET (NORMAL / RESET)
NORMAL FPO4 UAT 141-2 FP DELUGE RESET (NORMAL / RESET)
NORMAL FP05 SAT 142-1 l'P DELUGE RESET (NORMAL / RESET)
NORMAI.
FP06 SAT 142-2 FP DELUGE R7.)ET (NOFMAL/ RESET)
NORMAL FP07 FP/WS CROSSTIE FP5055 (SAC) VLV POS (0-100%)
Ot FPOB FP/WS CROSSTIE FP507 VLV POS (0-100t)
Ot FP09 MOTOR DRIVEN FP LOCAL CONTROL (STOP/AUT0/ START)
AUTO-OFF FP10 DIESEL DRIVEN FP LOCAL CONTROL (STOP/ AUTO / START)
O AUTO-OFF 4
O 35
l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FWOO1 STM DUMP SPRAY ISO 1CB038A (0-100%)
100%
FWOO2 STM DUMP SPRAY ISO 1CB038B (0-100%)
100%
FWOO3 STM DUMP SPRAY ISO 1CB038C (0-100%)
100%
FWOO4 STM DUMP SPRAY ISO 1CB038D (0-100%)
100%
EH005 STM DUMP SPRAY ISO ICB038E (0-100%)
100%
FWOO6 STM DUMP SPRAY ISO 1CB038F (0-100%)
100%
FWOO7 STM DUMP SPRAY ISO 1CB038G (0-100%)
100%
FWOOB STM DUMP SPRAY ISO 1CB038H (0-100%)
100%
FWOO9 STM DUMP SPRAY ISO 1CB03BJ (0-100%)
300%
FWO10 STM DUMP SPRAY ISO 1CB038K (0-100%)
(g--) 100%
STM DUMP SPRAY ISO 1CB038L FWO1 ?. (0-100%)
100%
FWO12 STM DUMP SPRAY ISO 1CB038M (0-100%)
100%
FWO13 CD PP RECIRC BYP 1CD159 (0-100%)
100t FWO14 CD PP 1A DIS ISO 1CD041A (0-100%)
100%
FWO15 CD PP 1B DIS ISO 1CD041B (0-100%)
100%
FW0l6 CD PP 1C DIS ISO 1CD041C (0-100%)
100% l FWO17 CD PP 1D DIS ISO 1CD0410 (0-100%)
100%
FWO18 CP DEMIN ISO VLV 1CD189 (0-100%)
0%
FWO19 CP DEMIN ISO VLV 1CD190 (0-100%)
100%
FWO20 CB PP A DIS VLV 1CB002A (0-100%)
100%
FWO21 CB PP B DIS VLV 1CB002B (0-100%)
100%
36 l
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
[v> -
APPENDIX 2 REMOTE FUNCTION LISTINGS FWO22 CB PP C DIS VLV ICB002C (0-100%)
100%
FWO23 CB PP D DIS VLV 1CB002D (0-100%)
100%
FWO24 FW PP A SUCT ISO 1CB005A (0-100%)
100%
FWO25 FW PP B SUCT ISO 1CB005B (0-100%)
100%
FWO26 FW PP C SUCT ISO 1CB005C (0-in0%)
100%
FWO27 FW PP A RCRC ISO 1FWO27A (0-100%)
100%
FWO28 FW PP B RCRC ISO 3FWO27B (0-100%)
100%
FWO29 FW PP C RCRC ISO 1FWO27C (0-100%)
100%
FWO30 S/U FW PUMP RECIRC 1FWO98 (0-100%)
100%
g- FWO31 TEMPER ISOL VLV 1FWO33A (0-100%)
(S f
FWO32 100%
TEMPER ISOL VLV IFWO33B (0-100%)
100% ,
FWO33 TEMPER ISOL VLV AFWO33C (0-100%)
100%
FWO34 TEMPER ISOL VLV 1FWO33D (0-100%)
100%
FWO35 FW PREHTR BYP 1FWO41A (0-100%)
100%
FWO36 FW PREHTR BYP 1FWO41B (0-100%)
100%
FWO37 FW PREHTR BYP 1FWO41C (0-100%)
100%
FWO38 FW PREHTR B7P 1FWO41D (0-100%)
100%
FWO39 FW ISOL BYP LFWO44A (0-100%)
100%
FWO40 FW.ISOL BYP 1FWO44B (0-100%)
100%
FWO41 FW ISOL BYP 1FWO44C (0-100%)
100%
FWO42 FW ISOL BYP 1FWO44D (0-100%)
100%
(D
%/
37
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FWO43 AF PP 3A SUCT ISO 1AF002A (0-100%)
100%
FWO44 AF PP 1B SUCT ISO 1AF002B (0-100%)
100%
FWO45 AF PP 1A DIS ISOL 1AF004A (0-100%)
100%
FWO46 AF PP IB DIS ISOL 1AF004B (0-100%)
100%
FWO47 DEMIN M/U TO CST OWM423A (0-100%)
0%
FWO48 CND NORM OVRFLW BYP 1CD146 (0-100%)
0%
FWO49 CND EMERG OVRFLW 1CD140 (0-100%)
0%
FWO50 CND NORM OVRFLW 1CD143 (0-100%)
0%
FWo51 CND NORM M/U BYP 1CD035 (0-100%)
0%
r~s FWOS2 CND EMRG M/U 1CD028 (0-100%)
Q FWO53 0%
CND NORM M/U 1CD031 (0-100%) .
0%
FWOS4 SJAE STM ISOL VLV 1MS107A (0-100%)
On FWO55 SJAE STM ISOL VLV 1MS107B (0-100%)
0%
FWOS6 SJAE OFF GAS ISOL 10G042A (0-100%)
0%
FWO57 SJAE OFF GAS ISOL 10G042B (0-100%)
0%
FWO58 17A NORM DRN 1HD008A IA (OUT/IN)
IN FWO59 17A NORM DRN 1HD008A PSN (0-100%)
0%
FWO60 17A EMRG DRN 1HD038 A I A (OUT/IN)
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%
-gy
\,)
38
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FWO64 17B EMRG DRN 1HD038B IA (OUT/IN)
IN FWO65 17B EMRG DRN 1HD038B PSN (0-100%)
100%
FWO66 16A NORM DRN 1HD011A IA (OUT/IN)
IN FWO67 16A NORM DRN 1HD011A PSN (0-100%)
0%
FWO68 16A EMRG DRN 1HD041A IA (OUT/IN)
IN FWO69 16A EMRG DRN 1HD041A PSN (0-100%)
100%
FWO70 16B NORM DRN 1HD011B IA (OUT/IN)
IN FWO71 16B NORM DRN 1HD011B PSN (0-100%)
0%
FWO72 16B EMRG DRN 1HD041B IA (OUT/IN)
IN FWO73 16B EMRG DRN 1HD041B PSN (0-100%)
- O FWO74 15A DRN CLR OUTLT 1HD014A 100%
(0-100%)
. . 100%
FWO75 ISB DRN CLR OUTLT 1HD014B (0-100%)
100%
FWO76 15A EMRG DRN 1HD062A IA (OUT/IN)
IN FWO77 15A EMRG DRN 1HD062A PSN (0-100%)
100%
FWO78 ISB EMRG DRN 1HD062B IA (OUT/IN)
IN FWO79 ISB EMRG DRN 1HD062B PSN (0-100%)
100%
FWO80 14A NORM DRN 1HD020A IA (OUT/IN)
IN FWO81 14A NORM DRN 1HD020A PSN (0-100%)
0%
FWO82 14A EMRG DRN 1HD048A IA (OUT/IN)
IN FWO83 14A EMRG DRN 1HD048A PSN (0-100%)
100%
FWO84 14B NORM DRN 1HD020B IA (OUT/IN)
IN 39
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS l
FWO85 14B NORM DRN lilD020B PSN (0-100%)
0%
FWO86 14B EMRG DRN lilD048B IA (OUT/IN)
IN l
FWOB7 14B EMRG DRN 1HD048B PSN (0-100%)
100%
2 FWO88 14C NORM DRN 1HD020C IA (OUI'/IN)
IN FWO89 14C NORM DRN 1HD020C PSN (0-100%)
0%
FWO90 14C EMRG DRN 1HD048C IA (OUT/IN)
IN FWO91 14C EMRG DRN 1HD048C PSN (0-100%)
100%
FWO92 13A NORM DRN 1HD023A IA (OUT/IN)
IN FWO93 13A NORM DRN 1HD023A PSN (0-100%)
0%
FWO94 13A EMRG DRN 1HD051A IA (OUT/IN)
IN O3 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%
FW104 12A NORM DRN 1HD026A IA (OUT/IN)
IN FW105 12A NORM DRN lilD026A PSN (0-100%)
0%
O 40
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FW106 12A EMRG DRN 1HD054A IA (OUT/IN)
Ib FW107 12A EMRG DRN 1HD054A PSN (0-100%)
100%
FW108 12B NORM DRN 1HD026B IA (OUT/IN)
IN FW109 12B NORM DRN 1HD026B PSN (0-100%)
0%
FW110 12B EMRG DRN 1HD054 B I A (OUT/IN)
IN FW111 12B EMRG DRN 1HD054B PSN (0-100%)
100t FW112 12C NORM DRN 1HD026C IA (OUT/IN)
IN FW113 12C NORM DRN 1HD026C PSN (0-100%)
0%
FW114 12C EMRG DRN 1HD054C IA (OUT/IN)
IN FW115 12C EMRG DRN 1HD054C PSN (0-100%)
i 100%
FW116 11A DRN CLR DRN 1HD029A IA (OUT/IN)
IN -
FW117 11A DRN CLR DRN 1HD029A PSN (0-100%)
0%
FW118 FLSH TK 1A DRN 1HD094A 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 1HD029B PSN (0-100%)
0%
FW122 FLSH TK 1B DRN 1HD094B IA (OUT/IN)
IN FW123 FLSH TK 1B DRN 1HD094B PSN (0-1004',
100%
FW124 11C DRN CLR DRN 1HD029C IA (OUT/IN)
IN FW125 11C DRN CLR DRN 1HD029C PSN (0-100%)
0%
FW126 FLSH TK 1C DRN 1HD094C IA (OUT/IN)
IN i
41
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
As / APPENDIX 2 REMOTE FUNCTION LISTINGS FW127 FLSH TK 1C DRN 1HD094C PSN (0-100%)
100%
FW128 HTR 17 BYP ISO 1FWOO5 (0-100%)
0%
FW129 HDT VENT TO 15A ISO 1Hra" (0-100%)
100%
FW130 HDT VENT TO 15B ISO 1h -
(0-100%)
100%
FW131 UD PP CONT VLV ISO 1HD046A (0-100%)
100%
FW132 HD PP CONT VLV ISO 1HD046B (0-100%)
100%
FW133 HD PANEL HI2 RESET BUTTON (NORM / RESET)
NORM FW134 U1/U2 CST XTIE ISO OCD116 (0-100%)
0%
FW135 FW HDR CLEAN UP LOOP FWO95 (0-100%)
0%
FW136 CP RETURN ISO VLV 1CD211 (0-100%)
O FW137 CP CONTROLLER 1CD210A/B 0%
(0-100%)
0%
FW138 S/U FW PP SUCT ISO 1CB113 (0-100%)
100%
FW139 CD H/U PP 0/1 XTIE OCD113 (0-100%)
100%
FW140 CD PP 1A SUCT ISO 1CD037A (0-100%)
100%
FW141 CD PP 1B SUCT ISO 1CD037B (0-100%)
100%
FW142 CD PP 1C SUCT ISO 1CD037C (0-100%)
100%
FW143 CD PP 1D SUCT ISO 1CD0371~ (0-100%)
100%
FW144 FWP E SPEED SETTER MOTOR (0-5800 RPM) 0 RPM FW145 FWP C SPEED SETTER MOTOF (0-5800 RPM) 0 RPM FW146 AF PP A AUX L.O. PP (STOP/ START)
STOP FW147 AF PP B AUX L.O. PP (STOP/ START)
STOP O
I 42
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
(
(s)\ APPENDIX 2 REMOTE FUNCTION LISTINGS FW148 AP 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 B (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 1HD046A/B VALVE CONTACT 09-11 ON (NORMAL /OPEN) 1LY-HD009A - LOW NPSH NORMAL FW135 1CD157A VALVE CONTACT 15-16 ON PS-CB14X(NORMAL /OPEN)
ON LOW NPSH NORMAL FW156 1CD152A VALVE CONTACT 17-18 ON PS-CB14X(NORMAL /OPEN) gsI i ON LOW NPSH NORMAL FW157 1CD05PD VALVE CO',' TACT 03-04 ON PS-CB14X(NORMAL /OPEN)
ON LOW NPSH NORMAL FW158 1PS-CB04X FOR ALL CONTACTS ON CB SUCT (NORMAL /OPEN)
NORMAL FW159 1CD210A/B FOR CONTACTS ON LOW NPSH (NORMAL /OPEN)
NORMAL FW160 1AF01J LOCAL OPERATION (SS/S4/1HS/ (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 HANDWHEEL RF (0-100%)
100%
FW164 AF 1AF005H HANDWHEEL RF (0-100%)
100%
FW165 AF 1A SUCT PRESS LO-2 (53) NORM / TRIP (NORMAL / TRIP)
NORMAL O
U 43
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS FW166 AF 1B SUCT PRESS LO-2 (55) NORM / TRIP (NORMAL / TRIP)
NORMAL FW167 FW PP 1A RECIRC VLV 1FWO12A PP TRT (NORMAL / BYPASS)
BYPASS O .
e O
44
BYRON SIMULATOR i
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
,m k ,)
m APPENDIX 2 REMOTE FUNCTION LISTINGS IA01 SA TO IA ISOL ISA113 (0-100%)
100%
IA02 SA TO IA ISOL OSA113 (0-100%)
100%
-IA03 SA TO IA ISOL (0-2) 2SA113 (0-100%)
100%
SA TO IA X-TIE (1-0) OIA147 IA04 (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 DRYER 0 ISOL OIA001 (0-100%)
0%
IA08 AIR DRYER 2 ISOL 2IA001 (0-100%)
100%
IA09 AIR 1-0 INLET X-TIE OIA053 (0-100%)
100%.
s IA10 AIR 0-2 INLET X-TIE OIA054' (0-100%)
100%
\ IA11 AIR OUTLET ISOL IIA 013 (0-100%)
. 100%
IA12 AIR OUTLET ISOL OIA013 (0-100%)
100%
IA13 AIR OUTLET ISOL 2IA013 (0-100%)
100%
IA14 IA 1-0 OUTLET X-TIE OIA114 (0-100%)
100%
IA15 IA 0-2 OUTLET X-TIE OIA113 (0-100%)
100%
IA16 UNIT X-TIE DIA055 (0-100%)
100%
IA17 UNIT 1 TB TO AB OIA097A- (0-100%)
100%
IA18 UNIT 2 TB TO AB OIA097B (0-100%)
100%
.IA19 . AUX BLD HDR X-TIE OIA107 (0-100%)
100%
IA20 AUX BLD HDR X-TIE OIA101 (0-100%)
100%
IA21 STM DUMP SUP ISOL IIA 060 (0-100%)
100%
IA22 U-0 SAC TRIP BLOCK (NORM / BLOCK)
NORM
%,) IA23 U-1 SAC TRIP BLOCK (NORM / BLOCK)
NORM 45
. - ___ . . - . ~ _ - -
DYRON SIMULATOR F
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER,'1991' APPENDIX 2
) REMOTE FUNCTION LISTINGS l
1 IA24 SAC DISCH XTIE OSA277 (0-100%)
4 100%
I IA25 PORTABLE COMPRESSOR -(OFF/ON)
OFF
'~
IA26 CONTAINMENT LOADS IIA 065 (0-100%)
. 100%
3' IA27 CONTAINMENT LOADS IIA 066 (0-100%)
- 100%
IA28 AF VALVES / CONT 0IA186 (0-100%)
- - 100%
IA29 WEST MSIV'S (B &-C) IIA 107 (0-100%)
. - 100%
8~
IA30 EAST MSIV'S (A & D) IIA 124 (0-100%)
(- 100%
100%
IA32 TB MID WEST IIA 056 (0-100%)
100%
IA33 TB NORTH WEST IIA 073 (0-100%)
100%
, , IA34 /TB SE IIA 058 (0-100%)
100%.
. IA35' TB MID-EAST--1IA059 (0-100%) -
100%
IA36 TB NORTH EAST IIA 061 (0-100%)
100%
IA37 STM DUMPS A-D IIA 132 (0-100%)
? 100% 1 IA38- -STM DUMPS E-H IIA 133 ~(0-100%)
- 100%
IA39 STM DUMPS J-M-1IA134 (0-100%)_
100%
IA40- FW PP RECIRCS-IIA 136 (0-100%)
100%
IA41 N2 SUPPLY TO SAC'S. (OFF/ON)
OFF IA42 MISC SYSTEMS ISOL VLV OIA100 (0-100%) ,
100% J
-IA43 IA ISO TO IIA 065 (ON/OFF)
ON IA44 IA ISO TO IIA 066 (ON/OFF)
'ON-IA45 1SA01 CMPRSR CONTACT 1PSL-SA004 ON- (NORMAL /OPEN) 3TR RELAY
( NORMAL IA46- U-1-3CR,4CR, & 8CR LOCAL RESET (NORM / RESET) 46
BYRON SIMULATOR ,
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 i (~N
\
sm, )- APPENDIX 2
, REMOTE FUNCTION LISTINGS NORM.
IA47 U-0 3CR,4CR, & 8CR LOCAL RESET (NORM / RESET)
NORM IA48 U-2 3CR,4CR, & 8CR LOCAL RESET (NORM / RESET)
NORM IA49 SAC 2 UNLOADER VALVE (0-100%)
64.4%
I O
47
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT
, INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS
'MS01 IST MSR A 15A VENT ES100A (CLOSE/OPEN)
CLOSE MSO2 IST MSR B iSB VENT ES100B (CLOSE/OPEN)
CLOSE MS03 IST MSR A 15A VENT ES100C (CLOSE/OPEN)
CLOSE ,
MSO4 IST.MSR B 15B VENT ES100D (CLOSE/OPEN)
' CLOSE MS05 IST MSR A 17A VENT ES101A (CLOSE/OPEN)
CLOSE.
MS06 IST MSR B 17B VENT ES101B (CLOSE/OPEN)
CLOSE MS07 IST MSR A 17A' VENT ES101C (CLOSE/OPEN)
- CLOSE MS08 _1ST MSR B 17B VENT ES101D (CLOSE/OPEN)
CLOSE
-MSO9 STM DUMP-ISO VLV MS003A (0-100%)
100%'
MS10 STM DUMP ISO-VLV MS003B '
(0-100%)
O MS11 100%
STM DUMP = ISO VLV MS003C (0-100%)
100%
-MS12 STM DUMP ISO VLV MS003D (0-100%)
100%
MS13- _STM DUMP ISO VLV MS003E (0-100%) -
100%
MS14. STM DUMP-ISO VLV MS003F (0-100%)
100%.
MS15- FTM DUMP-ISO-VLV MS003G (0-100%)
100%
MS16 STM DUMP ISO VLV MS003H (0-100%)
- 100%
MS17 'STM DUMP ISO.VLV MS003J (0-100%)
100%
MS18 STM DUMP ISO.VLV MS003K (0-100%)
100%
MS19 -STM DUMP ISO-VLV MS003L (0-100%)
100%
MS20 STM DUMP ISO VLV MS003M (0-100%)
100%
MS21. 1ST ST MSR A CND VENT ES97A (CLOSE/OPEN)
OPEN g
48
'.pF * 'NT y avea-.-+y h-ewv-i -, --- y y %
9:
BYRON SIMULATOR l ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
([]) APPENDIX 2 REMOTE FUNCTION LISTINGS MS22 1ST ST MSR B CND VENT ES97B (CLOSE/OPEN)
OPEN MS23 IST ST MSR A CND VENT ES97C (CLOSE/OPEN)
OPEN MS24 iST ST MSR B 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 ST MSR B CND VENT ES99D (CLOSE/OPEN)
OPEN MS29A A MSR SHL HORM POS HD099A (0-100%)
100%
MS29B B MSR SHL NORM POS HD099B (0-100%)
100%
MS29C A MSR SHL NORM POS HD099C (0-100%)
100%
x- MS29D B MSR SHL NORM POS HD099D (0-100%)
100%
MS30A A MSR SHL NORM IA*dD099A (CLOSE/OPEN)
OPEN MS30B B MSR SHL NORM IA HD099B (CLOSE/OPEN)
OPEN MS30C A MSR SHL NORM IA HD099C (CLOSE/OPEN)
OPEN MS30D B MSR SHL NORM IA HD099D (CLOSE/OPEN)
OPEN MS31A A MSR SHL EMER POS HD087A (0-100%)
100%
MS31B B MSR SHL EMER POS HD087B (0-100%)
100%
MS31C A MSR SHL EMER POS HD087C (0-100%)
100%
MS31D B MSR SHL EMER POS HD087D (0-100%)
100%
MS32A A MSR SHL EMER IA HD087A (CLOSE/OPEN)
OPEN MS32B B MSR SHL EMER IA HD087B (CLOSE/OPEN) ;
OPEN l 49
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT- ,
INITIAL REPORT, SEPTEMBER, 1991 f APPENDIX 2-REMOTE FUNCTION LISTINGS MS32C A MSR SHL EMER %A HD087C. (CLOSE/OPEN)
OPEN MS32D. B MSR SHL EMERLIA IID087D_ (CLOSE/OPEN)
OPEN MS33A A MSR IST NORM POS IID002A (0-100%)
100%
MS33B B MSR IST NORM POS.HD002B (0-100%)
100%-
MS33C A MSR IST NORM-POS lid 002C (0-100%)
100%
.MS33D B MSR IST NORM POS HD002D (0-100%)
1100%
MS34A A MSR IST NORM IA IID00?A (CLOSE/OPEN)
OPEN MS34B_ B MSR 1ST-NORM IA ilD002B (CLOSE/OPEN)
OPEN MS34C A MSR 1ST NORM IA !!D002C (CLOSE/OPEN)
OPEN-MS34D B_MSR IST NORM IA HD002D (CLOSE/OPEN)
O OPEN MS35A tA MSR IST EMER POS llD032A (0-100%) ,
100%
MS35B B MSR-1ST EMER POS llD032B (0-100%).
100%
MS35C -- A MSR IST EMER POS IID032C - (0-100%)-
100%
MS35D B_MSR IST.EMER~POS HD032D (0-100%)
100%
MS36A A,MSR IST EMER IA IID032A (CLOSE/OPEN)-
-OPEN' MS36B- B MSR IST EMER IA HD032B (CLOSE/OPEN)-
OPEN
-MS36C: A MSR IST EMER'IA.HD032C -(CLOSE/OPEN) :
OPEN
OPEN MS37A -A MSR:2ND NORM POS HD005A (0-100%)
100%
MS37B B MSR_2ND NORM POS HD005B (0-100%)
100%-
MS37C A MSR.2ND NORM POS-HD005C' (0-100%)
100%
O 50 E.
_ , . . . . _ _ . . . ...u,._, _ . , , . . _ , . . _ . _ . - - . . . _
. . ~ - . ~ . . . - . , . . - . - .. - . - . . - . . - - - . . . -
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS MS37D B MSR 2ND NORM POS HD005D (0-100%)
100%
MS38A A MSR 2ND NORM IA=HD005A (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)
Ol 3N MS39A A MSR 2ND EMER'POS HD035A (0-100%)
100%
MS39B B MSR 2ND EMER POS HD035B (0-100%)
100%
MS39C. A~MSR 2ND EMER POS HD035C (0-100%)
-100%.
MS39D .B MSR 2ND:EMER POS HD035D (0-100%)
100%-
MS40A' A MSR 2ND EMER.IA HD035A (CLOSE/OPEN)
O MS40B
-OPEN 3 MSR 2ND EMER IA'HD035B (CLOSE/OPEN)
.. JOPEN 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%)
100%
MS45 ES TO 15A HTR ES009A (0-100%)
100%'
MS46- ES TO 15B-HTR ES009B (0-100%)
100%
, .MS47 MN STM SUPPLY TO GS MS167 (CLOSE/OPEN)
CLOSE MS48 AUX STM FD TO GS MS163 (CLOSE/OPEN).
CLOSE D
51
BYRON SIMULATOR ANSI /ANS '.5-1985 CERTIFICATION REPORT INITIAL 4'EPORT, SEPTEMBER, 1991
('N V APPENDIX 2 REMOTE FUNCTION LISTINGS MS49 PRESSURE REGULATED LOAD (0-100 PSIG) 50 PSIG MS50 BOILER DISCH VLV AS168 (0-100%)
100t MSS 1 SG 1A PORV ISOL VLV MS019A (0-100%)
100%
MS52 SG 1B PORV ISOL VLV MS019B (0-100%)
100%
MS53 SG IC PORV ISOL VLV MS019C (0-100%)
100%
MS54 SG ID PORV ISOL VLV MS019D (0-100%)
100%
MS55 SG PORV A HAND CONTROL (0-100%)
0%
MS56 SG PORV D HAND CONTROL (0-100%)
0%
MS57 SG PORV C HAND CONTROL (0-100%)
0%
,57 MS50 SG PORV D HAND CONTROL (0-100%)
\~/ MS59 AUXILIARY BOILER PRESSURE (0-200 PSIG) 180 PSIG MS60 MSIV IIYD PP IA ISOL (NORM /ISOL)
NORM MS61 MS FLASH TK DRN MS161 (CLOSE/OPEN)
CLOSE O
52
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS 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 (0-2000 INCH) 299 NIOS 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 nil 0 INCORE DET B CALIBRATE TOP' LIMIT (0-2000 INCH)
[\ 1630
\- # Nill INCORE DET C EMERG/STOR BOTTOM LIMIT (0-2000 INCH) 215 4 NI12 INCORE DET C EMERG/STOR TOP LIMIT (0-2000 INCH) 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 LET D CALIBRATE TOP LIMIT (0-2000-INCH) 3690 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 4
53
- .+
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
/~N .
sh_ APPENDIX 2 REMOTE FUNCTION LISTINGS NI22 INCORE DET E CALIBRATE TOP LIMIT (0-2000 INCL!)
1680 NI23 INCORE DET F EMERG/STOR DOTTOM LIMIT (0-2000 INCH) 215 NI24 INCORE DET F EMERG/STOR TOP LIMIT (0-2000 INCH) 365 NI25 INCORE DET F CALIBRATE BOTTOM LIMIT (0-2000 INCH) 1520 NI26 INCORE DET F CALIBRATE TOP LIMIT (0-2000 INCH) 1690
) '
NI27 COURSE GAIN ADJ. ON NI POWER RANGE (0-5 VOLTS) 1 VOLT
+
4 i
V O
54 3
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
/~'T C APPENDIX 2 REMOTE FUNCTION LISTINGS RD01 DRPI PWR TRANSFER SWITCH (SWITCH /OFF)
SWITCH RD02 PA CONVERTER CB A (0-235 STEPS) 0 RD03 PA CONVERTER CB B (0-235 STEPS) 0 RD04 PA CONVERTER CB B (0-235 STEPS) 0 RDOS PA CONVERTER CB D (0-235 STEPS) 0 RD06 MG SET BRK A (NORMAL / TRIP)
TRIP RD07 MG SET BRK B (NORMAL / TRIP)
TRIP RD08 RESET-STOP COUNTER (NOT_ STEP,STE 2_0, STEP _ CURRENT)
DURING TRAINER RESBT IC & FROZEN NOT STEP RD09A BANK OVERLAP SETPOINTS (0-500 STEPS) 116 STEPS
[
RD09B BANK OVERLAP SETPOINTS (0-500 STEPS) 231-STEPS RD09C BANK OVERLAP SETP,OINTS (0-500 STEPS) 232 STEPS RD09D BANK OVERLAP SETPOINTS (0-500 STEPS) 347 STEPS RD09E BANK OVERLAP SETPOINTS (0-500 STEPS) 348 STEPS RD09F BANK OVERLAP SETPOINTS (0-500 STEPS) 463 STEPS RD* * = ROD # DRPI SYSTEM OVR (53. RODS) (0-231 STEPS) 0 (FEEDBACK V'"JE)
O 55
4 BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS Ril01 Rif TO CV LETDOWN Ril8734A (0-100%)
- 100%
RIIO2 Ril TO CV LETDOWN Ril8734B (0-100%)
0%
i RH03 Rif RECIRC TO RWST Ril8735 (0-100%)
0%
RiiO4 TRN A Ril/RCS SUCT R118701A (0-100%)
100%
!. R1105 - TRN A Ril/RCS SUCT Ril8701B (0-100%)
100%
Ri!06 TRN B Ril/RCS SUCT R118702A (0-100%)
100%
R1107 TRN B RH/RCS SUCT RII8702D (0-100%)
100%
Ril08 TRN A RH DISCH XTIE R118716A (0-100%)
0%
- Ril09 TRN B RH DIScil XTIE RH87168 (0-100%)
0%
- - - Ril10 TRN A RH MINIFLOW RiiG10 (0-100%)
(' 100%
4 Rlill TRN B RH-MINIFLOW RII611 (0-100%) ,
100%
RII12 TRN A RECIRC SUMP SIB 811A (0-100%)
0%
R1113 TRN B RECIRC SUMP SIB 811B (0-100%)
0%
Ril14 TRN A-RWST TO Rii SI8812A. (0-100%)
0%
RH15 TRN B RWST TO Rii SI8812B (0-100%)
0%
Ril16 RH llX A FLOW CONTROL RH606 (0-100%)
Ot Ril17 RH IIX B FLOW CONTROL Rif 607 (0-100%)
0%
Ril18 RWST LO-2 930C NORM / TRIP (NORMAL / TRIP)
NORMAL Ril19 RWST LO-2 931C NORM / TRIP (NORMAL / TRIP)
NORMAL RH2O RWST LO-2 932C NORM / TRIP (NORMAL / TRIP)
NORMAL Ril21 RWST LO-2 933C NORM / TRIP (NORMAL / TRIP)
NORMAL (3
V 56
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS RM01 1 PRO 11J 111 VAC LOCKOUT (NORM / RESET)
NORM O
O 57
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
'v 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 RPO4 BYPASS BRK A (52/RTA) (NORMAL / TRIP)
NORM RP05 BYPASS BKR B (52/RTB) (NORMAL / TRIP) i NORM RP06 BYA STATUS-BKR A (NORMAL /RACKIN)
NORM RP07 BYB STATUS-BKR B (NORMAL /RACKIN)
HORM RP08 LIFTED LEADS CLEARS P-4: TRN A (NORMAL / LIFTED)
NORM RP09 LIFTED LEADS CLEARS P-4: TRN B (NORMAL / LIFTED)
NORM
^ RP10 CNMT PRESSURE HI-3 PB934A (NORMAL / BYPASS) fI NORM RP11 CNMT PRESSURE HI-1 PB934B (NORMAL / TRIP)
NORM RP12 CNMT PRESSURE HI-2 PB934C (NORMAL / TRIP)
NORM RP13 CNMT PRESS HI-3 PB935A (NORMAL / BYPASS)
NORM RP14 CNMT PRESS HI-1 PB935B (NORMAL / TRIP) l NORM RP15 CNMT PRESS HI-2 PB935C (NORMAL / 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)
CLOSE RP21 PROTECTION CABINET DOOR #2 (CLOSE/OPEN)
CLOSE O
b l
58
BYRON SIMULATOR I ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS RP22 PROTECTION CABINET DOOR #3 (CLOSE/OPEN)
CLOSE RP23 PROTECTION CABINET DOOR #4 (CLOSE/OPEN)
CLOSE RP24 BDPS TEST SW RP-3:LA (NORM / BYPASS)
NORM RP25 BDPS TEST SW RP-32A (NORM / BYPASS)
NORM RP26 SLAVE K606 PHASE A TRN A (NORMALIN/OUT)
NORM RP27 SLAVE K612 PliASE A TRN A (NORMAL /IN/OUT)
NORM RP28 SLAVE K614 PHASE A TRH A (NORMAL /IN/OUT)
NORM RP29 SLAVE K605 PHASE A TRN A (NORMAL /IN/OUT)
NORM RP30 SLAVE K607 PHASE A TRN A (NORMAL /IN/OUT)
NORM q RP31 SLAVE K613 PHASE A TRN A (NORMAL /IN/OUT)
Q. RP32 NORM SLAVE K622 CNMT VENT TRN A (NORMAL /IN/OUT)
NORM +
RP33 SLAVE K615 CNMT 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)
NORM RP36 SLAVE K644 CS ACT TRN A (NORMAL /IN/OUT)
NORM RP37 SLAVE K643 CS ACT TRH A (NORMAL /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)
NCRM RP40 SLAVE K626 PlmSE B TRN A (NORMAL /IN/OUT)
NORM RP41 SLAVE K618 PHASE B TRN A (NORMAL /IN/OUT)
NORM RP42 SLAVE K648 RWST LO-2 TRN A (NORMAL /IN/OUT)
NORM O
59
l DYRON SIMULATOR I ANSI /AN3-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
(_/ APPENDIX 2 REMOTE FUNCTION LISTINGS 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 TAVf; 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 e RPS2 SLAVE K606 PHASE A TRN D (NORFML/IH/OUT)
(s)
RP53 NORM SLAVE K612 PHASE A TRN B (WORMAL/1N/OUT)
NORM RP54 SLAVE K614 PHASE A TRN B (NORMAL /TN/OUT)
NORM RP55 SLAVE K605 PHASE A TRN B (NORMAb/IN/OUT)
NORM RP56 SLAVE K607 PHASE A TRN B (NORMAL /IN/OUT)
NORM RP57 SLAVE K613 PHASE A TRN B (NORMAL /IN/OFJT)
NORM RP58 SLAVE K622 CNMT VENT TRN B (NORMAL /IN/OUT)
NORM RP59 SLAVE K615 CNMT VENT TRN B (NORMAL /IN/OUT)
NORM RP60 SLAVE K623 MS ISOL TRN B (NORMAL /IN/OUT)
NORM RP61 SLAVE K616 MS ISOL TRN B (NORMAL /IN/OUT)
NORM RP62 SLAVE K644 CS ACT TRN B (NORMAL /IN/OUT)
NORM RP63 SLAVE K643 CS ACT TRN B (NORMAL /IN/OUT)
NORM
[v 60
I BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 4
O APPENDIX 2 EEMOTE FUNCTION LISTINGS RP64 SLAVE K633 AF PUMPS 1/4 S/G LO-2 TRN B (NORMAL /IN/OUT)
NORM RP65 SLAVE K647 SI B TRN B (NORMAL /IN/OUT)
NORM RP66 SIAVE K626 PHASE B TRN B (NORMAL /IN/OUT)
NORM RP67 SLAVE K618 PHASE D TRN B (NORMAL /IN/OUT)
NORM RP68 SLAVE K648 RWST LO-2 TRll 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 SI TRN B (NORMAL /IN/OUT)
NORM RP72 SLAVE K609 SI TRN B (NORMAL /IN/OUT)
NORM
,m RP73 SLAVE K611 SI TRN B (NORMAL /IN/OUT)
! 1 NORM RP74 SLAVE K631 LO LO TAVG TRN b (NORMAL /IN/OUT)
NORM ,
RP75 SLAVE K603 SI TRN it (NORMAL /IN/OUT)
NORM RP76 SLAVE K608 SI TRN B (NORMAL /IN/OUT)
NORM RP77 SLAVE K610 SI TRN B (NORMAL /IN/OUT)
NORM F.P7 8 FW PP/VLV TRIP FUSES TRN A (NOIUiAL/ REMOVED)
NORM RP79 FW PP/VLV TRIP FUSES TRN B (NORMAL / REMOVED)
NORM l
RP80 MULTIPLEXER TE- 5% .. , B (NORM /INHA/INHB/AB_A/AB_B)
NORM RPS1 INPb"I' ERROR I2HIBIT A, B (NORM /INHIBITA/INHIBITB)
NORM I
RP82 MSTR OUTPU7* SEc3C"OR SW A, B (HORM/ TESTA /TESTB)
N L }i h RP83 SAFEGUARD ACTUATION SARA 1-2 CONTACT (NORMAL /OPEN)
TOR 1ACV NCPFAL l
l l im U
61
l BYRON SIMULATOR I
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS RP84 SAFEGUARD ACTUATION SARB 3-4 CONTACT (NORMAL /OPEN)
FOR 1BSI NORMAL RP85 SAFEGUARD ACTUATION SARB 7-8 CONTACT (NORMAL /OPEN)
FOR 1BRH NORMAL RP86 SAFEGUARD ACTUATION SARA 9-10 CONTACT (NORMAL /OPEN)
FOR OA VC CHILLER NORMAL RPG'i SAFEGUARD ACTUATION SARB 11-12 CONTACT (NORMAL /OPEN)
FOR 1BCS NORMAL RP88 SAFEGUARD ACTUATION SARA 13-14 CONTACT (NORMAL /OPEN)
FOR 1A + 0 CC NORMAL RP89 SAFEGUARD ACTUATION SARB 15-16 CONTACT (NORMAL /OPEN)
FOR 1BSX NORMAL g RP90 SAFEGUARD ACTUATION SARA 17-18 CONTACT (NORMAL /OPEN)
FOR 1AAF NORMAL ,
RP91 TRIP ALL ATWS SG LEVEL B/S AND IMP B/S (NORMAL / TEST)
(TEST / BYPASS)
- NORMAL s -
62
BYRON SIMULATOR ANST/ANS-3 5-19b5 CERTIFICATION REPORT
( MIITIAL RL' PORT, SEPTEMBER, 1991 m
APPEND 1X 2 REMOTE FUNCTION LISTINGS RX001 RCS LO FLOW LOOP 1 FB414A (NORMAL / TRIP)
NORM RX002 RCS LO FLOW LOOP 1 FB415A (NORMAL / TRIP)
NORM RXOO3 RCS LO FLOW LOOP 1 FB416A (NORMAL / TRIP)
NORM RX004 RCS LO FLOW LOOP 2 FB424A (NORMAL / TRIP)
NORM RX005 RCS-LO FLOW LOOP 2 FB475A (NORMAL / TRIP)
NORM RXOO6 RCS LO FLOW LOOP 2 FB426A (NORMAL / TRIP)
NORM RX007 RCS LO FLOW LOOP 3 FB434A (NORMAL / TRIP)
NORM
. RX008 RCS LO FLOW LOOP 3 FB43SA (NORMAL / TRIP)
NORM RXOOD RCS LO FLOW LOOP 3 FB436A (NORMAL / TRIP)
NORM RX010 RCS LO FLOW LOOP 4 FB444A (NORMAL / TRIP)
. NORM RX012 RCS LO FLOW LOOP 4 FB446A (NORMAL / TRIP)
NORM RX013 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 RX016 LOW TAVG TB412G (NORMAL / TRIP)
NORM RX017 RCS OT DELTA T TB421C (NORMAL / TRIP)
NORM RX018 RCS OP DELTA T TB421G (NORMAL / TRIP)
NORM RX019 LO-LO TAVG TB422D (NORMAL / TRIP)
NORM RX020 LOW TAVG TB422G (NORMAL / TRIP)
NORM RXO21 RCS OT DELTA T TB431C (NORMAL / TRIP)
NORM r
63
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE PUNCTION LISTINGS RXO22 RCS OP DELTA T TB4310 (n0RMAL/7 RIP)
NORM RX023 LO-Lo TAVG TB4320 (NORMAL / TRIP)
NORM RX024 LOW TAVG TB432G (NORMAL / TRIP)
NORM RX025 RCS OT DELTA T TB441C (NORMAL / TRIP)
NOR;1 RX026 RCS OP DELTA T TB441G (NORMAL / TRIP)
NORM RX027 LO-Lo TAVG TB442D (NORMAL / TRIP)
NORM RXO28 LOW TAVG TB442G (NORMAL / TRIP)
NORM RXO29 PZR HI WATER LEVEL PB459A (NORMAL / TRIP)
NORM RXO30 PZR HI WATER LEVEL PB460A (NORMAL / TRIP)
NORM RXO31 PZR HI WATER LEVEL PB461A (NORMAL / TRIP)
O RXO32 NORM PZR HI PRESSURE PB455A (NORMAL / TRIP)
NORM -
RXO33- PZR ENABLE BLOCK SI PB455B (NORMAL / TRIP)
NORM RXO34 PZR LOW PRESS TRIP PB455C (NORMAL / TRIP)
NORM RXO35 PZR LOW PRESS SI PB455D (NORMAL / TRIP)
NCRM RXO36 PZR HI PRESSURE PB456A (NORMAL / TRIP).
NORM RXO37 PZR ENABLE BLOCK SI PB456B (NORMAL / TRIP)
NORM RXO38 PZR LOW PRESS TRIP PB456C (NORMAL / TRIP)
NORM RXO39 PZR LOW PRESS SI PB456D (NORMAL / TRIP)
NORM RX040 FZR 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
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITI AL REPollT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTIllGS RXO43 PZR LOW PRESS SI PB457D (NORMAL / TRIP)
NORM RXO44 PZR 111 PRESSURE PB458A (NORl4AL/ TRIP)
NORM RXO45 PZR LOW PRESS TRIP PB458C (110RMAL/ TRIP)
NORM RXO46 PZR LOW PRESS SI PB45BD (110RMAL/ TRIP)
Holui RXO47 SG1 III-HI LEVEL LB517A (NORMAL / TRIP)
NORM RXO48 SG1 LO-2 WATER LB517B (NORMAL / TRIP)
NORM RXO49 SG1 HI-liI LEVEL LD518 A (NORMAL / TRIP)
NORM RXO50 SG1 LO-2 WATER LVL LB518B (NORMAL / TRIP)
NORM RXO51 SG1 HI-III LEVEL LB519A (NORMAL / TRIP)
NORM RX052 SG1 LO-2 WATER LVL LB519B (NORMAL / TRIP)
NORM RX053 SG2 111-11I LEVEL LD527A (NORMA 1/ TRIP)
NORM .
RX054 SG2 LO-2 WATER LVL LB527B (NON4AL/ TRIP)
NORM RX055 SG2 111-111 LEVEL LB528A (NORMAL / TRIP)
NORM RX056 SG2 LO-2 WATER LVL LB528B (NORMAL / TRIP)
NORM RXO57 SG2 HI-ill LEVEL LB529A (h0RMAL/ TRIP)
NORM RX058 SG2 LO-2 WATER LVL LD529B (NORMAL / TRIP)
NORM RX059 SG3 HI-ill LEVEL LD537A ( '10RMAL/ TRIP)
NORM RXO60 SG3 LO-2 WATER LVL LB537B (NORMAL / TRIP)
NORM RXO61 SG3 III-III LEVEL LB538A (NORMAL / TRIP)
NORM RXO62 SG3 LO-2 WATER LVL LB538B (NORMAL / TRIP)
NORM RXO63 SG3 III-HI I EVEL LB539A (NORMAL / TRIP)
NORM O
65
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPEllDIX 2 REMOTE FUNCTION LISTINGS r
RXO64 SG3 LO-2 WATER LVL LD5398 (NORMAL / TRIP)
NORM RXO65 SG4 III-ill LEVEL LB547A (NORMAL / TRIP)
NORM RXO66 SG4 LO-2 WATER LVL LB547B (NORMAL / TRIP)
NORM RXO67 SG4 111-111 LEVEL LB548A (NCRMAL/ TRIP)
NORM RXO68 SG4 LO-2 WATER LVL LB548B (NORMAL / TRIP)
NORM RXO69 SG4 111-11I LEVEL LB549A (NORMAL / TRIP)
NORM RXO70 SG4 LO-2 WATER LVL LB549B (NORMAL / TRIP)
NORM -
RXO71 SG1 LO-2 WATER LVL LD556C (NORMAL / TRIP)
NORM RXO72 SG1 LO-2 WATER LVL LD557C (NORMAL / TRIP)
NORM e RXO73 SG1 LO-2 WATER LVL LBS58C (NORMAL / TRIP)
NORM
(' RXO74 SGI LO-2 WATER LVL LB559C (NORMAL / TRIP)
NORM RXO75 SG1 III STM RATE PB514A (NORMAL / TRIP)
NORM RX')76 SG1 LO STM PRESS PB514B (NORMAL / TRIP) liORM RXO77 SG1 HI STM RATE P PB515A (NORMAL / TRIP)
NORM-RXO78 SG1 LO STM PRESS PB515B (NORMAL / TRIP)
NORM RXO79 SG1 III STM RATE PB516C (NORMAL / TRIP)
NORM RX000 SG1 Lo STM PRESS PB516A (NORMAL / TRIP)
NORM RXOB1 EG2 HI STM RATE P PB524A (NORMAL / TRIP)
NORM RXOB2 SG2 Lo STM PRESS PB524B (NORMAL / TRIP)
NORM RXO83 SG2 llI STM RATE P PB525A (NORMAL / TRIP)
NORM RX084 SG2 LO STM PRESS PBS25B (NORMAL / TRIP)
NORM O
66 l
i BYRON SIMULATOR i j ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 i
l
( APPENDIX 2
- l. REMOTE FUNCTION LISTINGS
) RXO85 SG2 HI STM RATE P PB526C (NORMAL / TRIP) i NORM
! RX086 SG2 Lo STM PRESS PBS26A (NORMAL / TRIP) l HORM j RXO87 SG3 HI STM RATE-P PB534A (NORMAL / TRIP)
< NORM j- RXO88 SG3-LO-STM PRESS PB534B (NORMAL / TRIP) l HORM l i
RX089 SG3-HI STM RATE P PB535A (NORMAL / TRIP)
J NORM l_
~
'RXO90. SG3-LO STM PRESS FB535B (NORMAL / TRIP)
NORM -
4 RXO91 SG3 HI STM RATE P PB536D (NORMAL / TRIP) l NORM
' NORM i RXO93_- SG4 HI STM RATE P PB544A (NORMAL / TRIP) l NORM i RXO94 SG4 LO STM PRESS PB544B '
(NORMAL / TRIP)
NORM RXO95 SG4 HI STM RATE P PB545A (NORMAL / TRIP)
- -NORM 1
RXO96 SG4 LO STM PRESS,PB545B (NORMAL / TRIP)
NORM 1
- RXO97 SG4 HI STM RATE P PB546D (NORMAL / TRIP)
NORM 4
RXO98 -SG4 LO STM PRESS PB546% (NORMAL / TRIP) i NORM RXO99 -NOT ASSIGNED-RX100. SG1 WTR HAMMER PROT. PB514C (NORMAL / TRIP)
NORM
- RX101 SG2 WTR-HAMMER. PROT. PB524C (NORMAL / TRIP) ,
NORM
. .RX102- _SG3 WTR HAMMER PROT. .PB534C (NORMAL / TRIP)
NORM RX103 SG4 WTR HAMMER PROT. PB544C. (NORMAL / TRIP)
NORM RX104 SG1 WTR HAMMER PROT. PB515C (NORMAL / TRIP)
NORM-RX105 SG2 WTR HAMMER PROT. PB525C (NORMAL / TRIP)
NORM i
O 67
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS RX106 SG3 WTR 11AMMER PROT. PB535C (NORMAL / TRIP)
NORM RX107 SG4 WTR liAMMER PROT. PB545C (NORMAL / TRIP)
NORM RX108 SG1 WTR liAMMER PROT. LB517D (NORMAL / TRIP)
NORM RX109 SG1 WTR !!AMMER PROT. LB519F (NORMAL / TRIP)
NORM RX110 SG1 WTR !!AMMER PROT. LBS56A (NORMAL / TRIP)
NORM RX111 SG2 WTR llAMMER PROT. LB528D (NORMAL / TRIP)
NORM RX112 SG2 WTR llAMMER PROT. LB529F (NORMAL / TRIP)
NORM RX113 SG2 WTR IIAMMER PROT. LB557A (NORMAL / TRIP)
NORM RX114 SG3 WTR IIAMMER PROT. LB538D (NORMAL / TRIP)
NORM RX115 SG3 WTR IIAMMER PROT. LD539F (NORMAL / TRIP)
NORM RX116 SG3 WTR HAMMER PROT. LB558A (NORMAL / TRIP) .
NORM RX117 ' SG4 WTR liAMMER PROT. LB547D (NORMAL / TRIP)
NORM RX118 SG4 WTR liAMMER PROT. LB549F (NORMAL / TRIP)
NORM RX119 SG4 WTR !!AMMER PROT. LB559A (NORMAL / TRIP)
NORM RX120 SG1 WTR HAMMER PROT. PB516D (NORMAL / TRIP)
NORM RX121 SG2 WTR liAMMER PROT. PB526D (NORMAL / TRIP)
NORM RX122 SG3 WTR IIAMMER PROT. PB536C (NORMAL / TRIP)
NORM RX123 SG4 WTR HAMMER PROT. PB546C (NORMAL / TRIP)
NORM RX124 SG1 HI-HI LEVEL LD556B (NORMAL / TRIP)
NORM RX125 SG2 HI-HI LEVEL LBS57B (NORMAL / TRIP)
NORM RX126 SG3 HI-HI LEVEL LBS58B (NORMAL / TRIP)
NORM
(
v 68
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS RX127 SG4 111-11I LEVEL LB559B (NORMAL / TRIP)
NORM RX128 -NOT ASSIGNED-RX119 -NOT ASSIGNED-RX130 -NOT ASSIGNED-RX131 -NOT ASSIGNED-RX132 -NOT ASSIGNED-RX133 -NOT ASSIGNED-RX134 -NOT ADSIGNED-RX135 RC LP1 OT DELTA T C3 TB411D (NORMAL / TRIP)
NORM RX136 RC LP1 OP DELTA T C4 7841111 (NORMAL / TRIP)
O' RX137 NORM RC LP2 OT DELTA T C3 TB421D (NORMAL / TRIP)
. . NORM RX138 RC LP2 OP DELTA T C4 TB42111 (NORMAL / TRIP)
NORM RX139 RC LP3 OT DELTA T C3 TB431D (NORMAL / TRIP)
NORM RX140 RC LP3 OP DELTA T C4 TB43111 (NORMAL / TRIP)
NORM RX141 RC LP4 OT DELTA T C3 TB441D (NORMAL / TRIP)
NORM RX142 RC LP4 OP DELTA T C4 TB44111 (NORMAL / TRIP)
NORM RX143 TURBINE POWER P-13 PB505A (NORMAL / TRIP)
NORM RX144 'IURBINE POWER P-13 PB506A (NORMAL / TRIP)
NORM RX145 SG1 LO-3 LEVEL LIS 431 (NORMAL / TRIP)
NORMAL RX146 SG2 LO-3 LEVEL LIS 432 (NORMAL / TRIP)
NORMAL RX147 SG3 LO-3 LEVEL LIS 433 (NORMAL / TRIP)
NORMAL O
69
1)YRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMI!ER, 1991
' APPENDIX 2 REMOTE FUNCTION LISTINGS ]
l RX148 SG4 LO-3 LEVEL LIS 4 34 (NORMAL / TRIP)
NORMAL
-RX149 1PS-0505 AMS C-20 (NORMAL / TRIP)
NORMAL RX150 1PS-0506 AMS C-20 (NORMAL / TRIP)
NORMAL ,
O. . .
O 70
..:..-..-..-.-.-..-.-.--.-_..-_..- . ,--.a... . . - . - . . . . - .
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS l
SIO1 SI PP 1A DISCH VLV SI8921A (0-100%)
100%
SIO2 1SI PP 1B DISCH VLV S189218 (0-100%)
100% :
SIO3 SI TEST TO RWST VLV SI8963 (CLOSE/0 PEN) !
CLOSE ,
8104 1A CS.RECIRC TO RWST SIOO1A (CLOSE/0 PEN) l CLOSE >
SIO5 1B CS RECIRC TO RWST SIOO1B (CLOSE/0 PEN) !
CLOSE SIO6 SI PP RWST SUCT POS S18806- *
(0-100%) !
100%
SIO7 SI TO CL VLV POS SI8002A (0-100%) i 100%
SIO8 SI To HL A & D POS SI8835 (0-100%)
100%
'SIO9 SI TO HL B &-C POS SIB 802B (0-1004) ,
100%
O SIl0 PWR FOR SI CL TEST SI8823 OFF (OFF/ON) >
Sill PWR FOR SI HL TEST. SIB 824 .
.(OFF/0H) r OFF SI12 PWR FOR RH HL TEST SI8825 (OFF/0N) 0FF SI13 _RH DISCH TO CL POS SIB 809A (0-100%)
100%
SI14 :RH DISCH To-CL POS-SIB 809B (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 SI8871 (OFF/ON) 1 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/0N) '
OFF 4
71
, ;_;,__ .= .u_ _ u _, _.. ___u.u ._ _ _ _ _ . _ . . _ _ _ _ _ _
.__=___.._;...-___......m_.__._
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS SI21 PWR TO Ril llL TEST SI88908 (OFF/0H)
Orr SI22 PWR To SI IIL TEST SI8881 (OFF/OH) 0FF SI23 PWR TO CV HL TEST SI8843 (OFF/ON) 0FF O
9
\
V 72
BYRON SIMULATOR ;
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS SWO1 CC HX 0 OUTLET OSXOO7 (0-100%)
25% = 6000 GPM SWO2 CC HX 1 OUTLET ISXOO7 (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 SWOS SX PP 1A STNR DKN ISX150A (0-100%)
0%
SWO6 SX PP 1B STHR DRN 1SX250B (0-100%)
0%
SWO7 U-2 SX SUPPLY 2SX005 (0-100%)
0%
SWOB SX TO FP XTIE OSX174 (0-100%)
0%
SWO9 SA COMP 1 WS312 (0-100%)
0%
,f- SW10 CB PP A OIL CLR WS021A (0-100%)
( **
SW11 CB PP B OIL CLR WS021B (0-100%)
0%
SW12 CB PP C OIL CLR I.SO21C (0-100%)
04 SW13 CD PP D OIL CLR WS021D (0-100%)
0%
SW14 CD PP A OIL CLR WS023A (0-100%)
0%
SW15 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%)
0%
SW19 GEN HYD COOLER WSO44A (0-100%)
0%
SW20 GEN HYD COOLER WSO44B (0-100%)
l 0%'
SW21 GEN HYD COOLER WSO44C (0-100%)
0%
73 l
l
l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 U APPENDIX 2 REMOTE FUNCTION LISTINGS SW22 GEN llYD COOLER WSO44D (0-100%)
0%
SW23 BLOWDOWN CO!1 DENSER WS069 (0-100%)
100%
SW24 WS PP 1A DISCil VLV OWS001A (0-100%)
100%
SW25 WS PP IB DISCil VLV OWS001B (0-100%)
100%
SW26 WS PP 1C DISCll VLV OWS001C (0-100%)
100%
SW27 WW TO SX BASIN POS WWO19A (0-100%)
0%
SW2B WW TO SX BASIN POS WWO19B (0-100%)
0%
SW29 FW PP B CLR CNTL SETPT ( 0-2 00'F) 12 0*F SW30 FW PP C CLR CNTL SETPT ( 0-2 00'F) 120'F G SW31 Eli CLR TEMP CNTL SETPT ( 0-2 00'F)
Q SW32 EXCITER TEMP CllTL SETPT 110'F
( 0-100'C) ,
4 0'C SW33 GC TEMP CNTL SETPT ( 0-2 00'F )
105'F SW34 TO CLR TEMP CNTL SETPT (0 :00'F) 110'F SW35 ASSO CLR CNTL SLIPT ( 0-2 00'F) 105'F SW36 Il2SSO 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-WS000A(NORMAL /OPEN)
ON LOW NPSil NORMAL SW39 SW COOLING TOWER BLOWDOWN VLV OSX161A (0-100%)
100%
SW40 SW COOLING TOWER BLOWDOWN VLV OSX101B (0-100%)
100%
4 c) 74
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
, APPEND 1X 2 REHCTE FUNCTION LISTINGS TC01 Deli COMPUTER (RUN/IIALT)
RUN TC'2 EGC PERMISSIVE (NORM /IN}lIBIT)
NORM TCO3 REMOTE MANUAL TURDIllE TRIP (NORM / TRIP)
NORM TC04 OPC CYCLING OF IV'S (NORM /INifIBIT)
NORM TC05 EGC RAISE SIGNAL (NORM / RAISE)
NORM TC06 EGC LOWER SIGNAL (NORM / LOWER)
NORM TC07 TURB TRIP BLOCK LEVER (NORM / TEST)
NORM TCOB VACUUM TRIP TEST VALVE (CLOSE/OPEN)
CLOSE TC09 OVERSPEED TRIP TEST VALVE (CLOSE/OPEN)
CLOSE TC10 TilRUST BEAR TRIP TEST VLV (CLOSE/OPEN)
CLOSE TCIL BEARING OIL TRIP TEST VLV (CLOSE/OPEN)
CLOSE l
O 75
- . . . - _ . , _ . _ , .-y , - . , - _,
e -. - ---,a.
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 Q U APPENDIX 2 REMOTE FUNCTION LISTINGS l
Til01 RCP A OC TRIP DEFEAT (NORMAL / DEFEAT)
NORM Til02 RCP B OC TRIP DEFEAT (NORMAL / DEFEAT)
NORM Til03 RCP C OC TRIP DEFEAT (NORMAL / DEFEAT)
NORM T1104 RCP D OC TRIP DEFEAT (NORMAL / DEFEAT)
NORM Tl105 RCP A OVERCURRENT RESET (NORMAL / RESET)
NORM :
T1106 RCP B OVERCURREllT RESET (NORMAL / RESET)
NORM T1107 RCP C OVERCURRENT RESET (NORMAL / RESET)
NORM Til08 RCP D OVERCURRENT RESET (NORMAL / RESET)
NORM T1109 PRESSURIZER SPRAY ISO VLV RYO23 (0-100%)
100%
Til10 PRESSURIZER SPRAY ISO VLV RYO24 (0-100%)
100%
Tilli PRT VENT TO CNTMT 8043 (0-100%)
0%
Till2 - PRT N2 SUPPLY REG STPT (0-50 PSIG) 3 PSIG Tl!13 LOCAL TRIP OF RCP 1A (NORMAL / TRIP)
NORM Til14 LOCAL TRIP OF RCP 1B (NORMAL / TRIP)
NORM THIS LOCAL TRIP OF RCP 1C (NORMAL / TRIP)
NORM Til16 LOCAL TRIP OF RCP ID (NORMAL / TRIP)
NORM TH17 REACT. VSL LVL ISOLATION (ISO /OPEN)
OPEN Til18 LOOSE PARTS MONITORING SYS ALARM RESET (NORMAL / RESET)
NORMAL-O 76
4 BYRON SIMULATOR j ANSI /ANS-3.5-1985 CERTIFICAT10N REPORT l
INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2
. REMOTE FUNCTION LISTINCS i
TP01 H2SSOP BYPASS VLV 1T05242 (0-100%)
50%
- TP02 GEN HYD VENT VLV 111Y5024 (0-100%)
i- 0%
TP03 GC FILT INLT GC5403/GC5404 (GC5403/GCS404)
- GC5403
- TPO4 GC HX #2 OUTLT GC5405 (0-100%)
100%
i TPOSL GC HX-0UTLT GC5406/GC5407 (GC5406/GC5407)
, GC5407
! TP06 GC HX INLT GC5408/GC5409 (GC5408/GC5409) i GC5409 '
TP07 GC.DEMIN INL GC5420/GC5422 (GC5420/GC5422)
GC5420 TP08 GC DEMIN BYPASS GC5424 (0-100%)
04 TP09 GEN H2 SUPPLV REG lily 5054 (0-100 PSIG)
O PSIG O, TP10; GEN CO2 SUPPLY 1HY5005 3 PSIG (0-100 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 T05210/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-ACKNOWLisDGE (NORMAL /ACK)
NORMAL 4
O 77
BYRON SIMULATOR j ANSI /A!1S-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUl1CTIOli LISTINGS TUO1 TURNING GEAR LOCAL CONTROL SWITCll (AUTO / MANUAL)
AUTO TUO2 TURNING GEAR LOCAL PUSilBUTTOli (liORMAL/STOP/ START)
NORMAL TU03 TURNING OIL MAKEUP (CLOSE/ OPE!1)
CLOSE TUO4 TUR!1ING OIL DRAlli (CLOSE/OPEll)
CLOSE O
O 78
BYRON SIMULATOR l ANSI /ANS*3.5-1985 CERTIFICATION REPORT l INITIAL REPORT, SEPTENBER, 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%)
0%
WD04 SG D BD CV SD0054D (0-100%)
0% \
WDOS SG B BD CV SD0054E (0-100%) j 0% l WD06 SG B BD CV SD0054F (0-100%)
0% _
WD07 SG C BD CV SD0054G (0-100%)
0%
.WD08 SG C BD CV SD0054H (0-100%) -l 0% .
WD09: CST /COND SEL WX293/WX883A (CSf/ CONDENSER) i CST i WD10 RCDT CRAIN TO SUMP RE9163 (CLOSE/OPEN)
O WD11 CLOSE RCDT DISCH RE9171/AB8551 (RWST/ HUT)
HUT WD12 RELEASE TK PUMP , (OFF/ON)
OFF.
WD13 RELEASE TK DISCH VALVE (CLOSE/OPEN)
CLOSE 79
_,u _ _.:___... - _.~...__..__;._ _ , _ . _ . . . _ . . . _ - . . . _ . - - _ . . _ , _ _ . , - . . , . . . ,
SYROff SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 APPENDIX 2 REMOTE FUNCTION LISTINGS '
YR01 THE RM11 POWER SUPPLY SW (NORMAL / BACKUP)
NORMAL YR02 RM23 REMOTE / LOCAL SW (REMOTE / LOCAL)
LOCAL O .
9 I
O 80
- .~ , . _ .-. _ . - . . . . - . . . - . _ _ -.
i BYRON S!HOLA10R ANSI /ANS-3.5-1985 CERTIflCATION REPORT INITIAL REPORT, $[PTEMBER, 1991 O
V i
)
l APPENDIX 3 LISI Of ACRONYMS /ADDREVIATIONS O
O (BYRONSIH 113/38 08/22/91)
DYRON S! HULA 10R ANSI /ANS-3.5-1985 CERilflCA110N REPORT INITIAL REPORT, SEPl[HDER, 1991 APPENDIX 3 LIST Of ACRONYMS / ABBREVIATIONS ACB0EliIADDMYJA110N D15CR11'110N AF Auxiliary feedwater AN Annunciators BDPS Boron Dilution Prevention System DOL, DOC Beginning of Life (Cycle) 005 Dyron Operating Surveillance DVS Byron lech Staff Surveillance CB Control Bank CC/CCH Component Cooling Hater C/D Cooldown CLE Cause and Effects CH Containment CND Condensyr CS Containment Spray CV/CVC Chemical & Volume Control CH Circulating Hater DC Direct Current DCRDR Detailed Control Room Design Revtew O D/G DVR Diesel Generator Deviation Report ED EledricalPowerSystem EG Electrical Generators COL, EOC End of Life (Cycle)
ESD Equipment Status Display ESF Engineered Safety features FP fire Protection fH reedwater, Heater Drain, Condensate GSEP Generating Station Emergency Plan HD Heater Drains HV Ventilation HX Heat Exchanger IA Instrument Air / Service Air IC Initial Condition O
(BYRONSlH 113/39 08/22/91)
DYRON SlHOLATOR ANSI /ANS-3,5-1985 CERT!flCATION REPORT INITI AL Ri: PORT SEPTEMBER,1991 O' APPENDIX 3 LIST Of ACRONYMS /ADDREVIATIONS (continued)
ACRONYM /ADBREVIA110N DISCRIP_IJON KV Kilovolts LED Light Emitting Diode LER Licensee Event Report Hf Halfunction HIDS Hovable incore Detector System HOL, HOC Middle of Life (Cycle)
HH/HWE Pegawatt Electrical N!/NIS Nuclear Instrumentation System PA Public Address PPC Plant Process Computer PPH Parts per Hi1 lion PRS /PZR Pressurizer PS Primary Sampling PTA0 Production Training Administrative Procedure - Operations PHR Pressurized Water Reactor RCFC Reactor Containment fan Cooler ,
RCP Reactor Coolant Pump RCS Reactor Coolant System
- R0 Rod Drive RF Remote function RH/RHR. Residual Heat Removal RIL Rod Insertion Limit-RH Radiation Monitoring RP Reactor Protection RPM Revolutions per Hinute RX Reactor, Reactor Control S/D Shutdown SER Sequence of Events Recorder S/G Steam Generator 51 Safety Injection SPDS Safety Parameter Display System SS Steady State S/U Startup SW, SX Essential Service Water TC Turbine Control TH Thermohydraulics Model, Retact (RCS System)
TP Turbine Plant Auxiliaries O TR Transient Test
d TU Turbine Oil (BYRONS!H 113/40 08/22/91)
BYRON $1HULATOR ANSI /ANS-3.5-1985 CERilflCA110N REPORT INiilAL REPORT, SEPTEMBER, 1991 APPENDIX 3 LIST Of ACRONYMS / ABBREVIATIONS (continued)
ACROMMIADBREVIMION DESCRIEUON UF Under frequency UV Under Voltage VC Control Rc.om Ventilation HD Haste Drains, Gas Decay HR Hide Range /Hort Request XE Xenon YR Radiation Monitor Display O
O h
(BYRONSIM 113/41 08/22/91)
i BYRON $1 HULA 10R ANS!/ANS-3.5-1985 CERTIFICATION REPORT :
INITIAL REPORT SEPTEMBER, 1991
[
t i
APPENDIX 4 BYRON SIMULATOR TRANSIENT TEST REVIEW BOARD QUALIFICATIONS !
i i
i 5
9 L
?
t f
l t
i i O (BYRONSIH.'113/42 08/22/91)
BYRON SlHULA10R ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPOR1, SEPTEMBER, 1991 O APPENDIX 4 BYRON SIMULATOR TRANSIENT REVIEH BOARD QUAllflCATIONS The following is a list of the members and qualifications of the Byron Simulator Transient Review Board.
MEMBER QUAliflCATIONS
- 1. Dan J. Popkins Position - Byron Simulator Training 3 yrs.
Supervisor Background - SRO Certified, Byron Station 1.5 yrs
- SRO 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 M. Farr Position - Station Reactor Engineer, Byron 1.5 yrs.
Station O Baa9roumd - SRo u cease. B, rom Sten ce
- SCRE, Byron Station 3.0 yrs.
1.0 yrs.
- Technical Staff Group Leader, 2.0 yrs.
Byron Station
- Shift Technical Adv1sor, Byron I.0 yr.
Station
- Technical Staff Engineer, Byron 2.5 yrs.
Station
- 3. Hilliam f. Hochstetter Position - Simulator Instructor, Byron 1.0 yr.
Station Background - Systems Qualifted, Byron Station
- NRC SRO Certificiation, SONGS
- General Services Instructor, 1.0 yr.
Byron 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
- U.S. Navy - Mech. Operator, 8.0 yrs.
ELT, LELT, Prototype Instructor O
(BYRONSIM 113/43 08/22/91)
. _ . . - _ = _ . - - . - -.
. BYRON $1Ht'LATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPOR1, SEPTEMBER, 1991 '
APPEN0!X 4 BYRON SIMULATOR TRANSIENT REVIEH BOARD QUALIFICATIONS (continued) tilfiDEB DVAllDC&UORS ,
- 4. Hartin R,-Holfe Fosition - Simulator Instructor, Byron 2.0 yrs.
Station Background - SRO Certtification, 4.0 yrs. .
Byron /Braidwood Stations
- R0 License, Byron Station 4.0 yrs.
- Simulator Instructor, 4.0 yrs.
Byron /Braidwood
- Nuclear Station Operator, Byron 4.0 yrs.
Station .
- Equipment Operator, Byron 3.0 yrs.
Station
- fossil Stationman, Kinceld
- 5. Steven H. Pettinger Pos' "on - Sim91ator Instructor, Byron 2.5 yrs.
Station Background - SRO License Byron Station 3.0 yrs.
'V - R0 Licensc Byron Station 4.0 yrs.
- Shift Foreman, Byron Station 1.0 yr.
- Nuclear Station Operator, Byron 3.0 yrs.
Station
- Equipment Operator, Byron 1.0 yr.
Station
- Euqipment Attendant, Byron 3.0 yrs.
Station >
i r
-(BYRONSIM 113/44 08/22/91)
BYRON SlHULATOR ANSI /ANS-3.5-1985 CERTiflCATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
APPENDIX 5 ANSI /ANS-3.5-1985 - CERT 1flCATION REPORT CROSS REFERENCE MATRIX O
4 0
(BYRONSlH 113/45 08/22/91)
BYRON SlHULA10R j ANSI /ANS-3.5-1985 CERT!r! CATION REPORT INITIAt. REPORT, SEPTEMBER, 1991 APPENDIX 5 ANSI /ANS-3.5-1985-CERilrICAT10N REPORT CROSS REFERENCE MATRIX LOCATION IN CERTiflCA110N ANSI /ANS-3.5-1985 REQUIREMENT REPORT SECIION DESCRIE1108 SEC110N 3.1.1 Normal Plant Evolutions A.3.2, Attachment 2 3.1.2 Plant Malfunctions A.I.3.2, A.3.4, Attachment 6 3.2.1 Degree _of Panel Simulation A.I.2.2, Attachment 5 3.2.2 Controls on Panels A.1.2.2 3.2.3 Control Room Environment A.1.2.1, A.I.2.4 3.3.1 Control Room Systems A.1.2.3 3.3.2 System Operation Outside Control A.I.3.3, Appendix 2 Room 3.4.1 Initial Conditions A.1.3.1, Appendix 1 3.4.2 Malfunctions A.1.3.2 3.4.3 Other Control features A.1.3.4 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 Monitoring Capability Attachment 2 4
O (BYRONSIM 113/46 08/12/91)
BYRON SlHULATOR ANSI /ANS-3.5-19R5 CERTIFICA1.0N REPORT INITIAL REP 01;T, SEPTEHBER, 1991 O APPENDIX 5 ANSI /ANS-3.5-1985-CERTiflCAT10N REPOR1 CROSS REFERENCE HAIR!X LOCA110N IN CERilflCATION ANS1/ANS-3.5-1985 REQUIRDtENT REPORT SLC110!i DESCRIfl10N SIC 110H 5.1 Simulatc' Design Data A 2 Attachment 4 5.2 Simulator Update Design Data A.1.5, A.4.2, Attachment 4 5.3 Simulator Modifications /..).5, A.4.2, Attachms.it 4 5.4.1 Simulator Performance Testing A.2, Attachment 2 5.4.2 Simulator Operability Testing Attachments 2 L 6
.......................................s.......................
HQJE
- APPENDIX A GUIDE FOR DOCUMENTING SIMULATOR PERf0RP.ANCE,
- HAS UTILIZED AS THE FORMAT FOR THIS REPORT. THEREi3RE, O-
. . . . .... P E. ND...I X. . A.
.. .CRO.
. . . ........ S. s. . R. E.....
F E. R E. ..
NC.. E . MAT
.. R I X D A. T. A HI L L. .
B.2.1 Steady State Performance A.3.2, Attachment 2 B.2.2 Transient Performance A.3.2, Attachment 2 O
(BYRONSlH 113/47 08/22/91)
BYRON SIMULATOR .
ANSI /ANS-3.5-1985 CER1lf! CATION REPORT INITIAL REPORT, SEPTEMBER, 1991 ;
(2)-
i I
i APPENDIX 6 SIMULATOR TESTING FROCEDURE AND Half 0NCT10N r
TESTING SCHLDULE s
[
e f'
I t
k t
I (BYRONSIM 113/48 08/22/91)
~ . , . .
PTA0-105 Revision 0 Nove:bar, 1989
'I )
- 57,MULATOR CERTIFICATION REPORTING AND TESTING PROGRAM A. Purpose The purpose of this procedure is to 4
- 1. standardize initial and annual simulator certification report formats.
- 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.
- 5. establish an administrative procedure for performing simulator certification testing.
B. References
- 1. ANSI /ANS-3.5-1985: Nuclear Power Plant Simulators for Use in Operator Training
- 2. 10CFR 55.45: C,'erating Tes s
-)
- 3. NRC Res Guide 1.149: Nuclear Power Finnt Simulation Facilities for Use in Operator Li;ense Examinations
- 4. NRC NUREG 1258: Evaluation Procedure for Simulation Facilities Certified undct 10CTR 55
- 5. INPO TQ-504: Simulator Configuration Management System - Good Practices
- 6. PTAG-115: Review and Processing of Operating Rxperience Event Reporta
- 7. PTAG-202: Production Training Department Revision Process
- 8. Operations Policy #1: Configuration Management
- 9. Operations Policy #2 Simulator Fidelity and Appearance
- 10. PTAO-101: . Document Tracking and Review Process Procedure
- 11. PTAO-102: Tracking Training Course Changes Procedura
- 12. PTAO-103: Simulator Work Request Procedure
- 13. PTAO-104: Simulator Review Board Procedure O
1 3C5P 01/90 1
1
- -- . - .= - - -
PTAO-105 Revisicn 0 Ntvember, 1989 C. Definitions
- 1. Ecnfimuration Manmaament Contini - A system that ensures that all training programs and the , mulator appearance, performance, and environment are kept curren 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 siediator hardware and software. It is further defined as the contents of the General Files Pattern Simulator (SIM) file. Any document that is RQI in the General Files Pattern Simulator (SIM)-file is considered RQI part of the Simulator Design Database.
- 3. Environ ==atal Fidelity - The degree of similarity between the simulator and the reference plant in the environmental aspects such as lighting circuits, lighting intensity, annunciator sound levels, and carpeting / flooring of the control room.
- 4. Fidality - The combination of Environmental, . Functional, and Physical Fidelity.
- 5. Functional Fidelity - The degree of similarity between the simulator and the reference plant in the static and dynamic response of equipment and controls.
()
- 6. Parformance Testa - The tests used to verify that the dynamic behavior of the simulator adequately represent that of the reference .
plant as required by ANSI /ANS-3.5-1985 section 5.4 and NRC Reg Guide 1.149 section C.S.
7._ Phvalcal' Fidelity - The degree of similarity between the simulator and the reference plant in the physical design and location of the panels, equipment, instruments, and controla.
- 8. Rafaranca Plant - The specific nuclear power plant reactor from which the simulator control room configuration, system control arrangement, and simulator design data is derived.
- 9. 113ulater - A simulator incorporating detailed modeling of systems 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.
- 10. Work naeumat - A document that identifies and tracks deviations in simulator performance or appearance from the current Design Database; or a document that is used to justify simulator design changes that might be incorporated into the Design Database.
A Q
2 305P 01/90-
PTAO-105 Revision 0 l Nove ber, 1989 l
t
() D. Procedure
- 1. Certification Reporting
- a. Each Production Training Department Site Operations Staff preparea an initial simulator certification report to be submitted to the Simulator Review Board for approval,
- b. After the initial report, each Production Training Department Site Operation Staff prepares a annual simulator certification report which updates the initial report. The annual simulator certification report is prepared on the anniversary date of the initial report. The annual report is used for internal documentation only and approved by the Simulator Review Board.
- c. Every four years af ter the initial simulator certification report, each Production Training Department Site Operations Staff prepares a Simulator Certification Update Report to be submitted to the Simulator Review Board for approval. The Simulator Certification Update Report summarizes the activities of the previous 4 years on the simulator.
- d. The Initial, Annual, and Tour Year Update certification reports are written in the format identified in appendix A of ANSI /ANS-3.5-1985: Nuclear Power Plant Simulators for Use in p) s.
Operator Training. An azample, the Braidwood Initial Certification Report is included as Attachment T-1.
- e. For purposes of simulator certification reporting, the Production Training Department has interpreted ANSI /ANS-3.5-1985: Nuclear power Plant Simulators for Use in Operator Training, section 5.3 Simulator Modifications, to mean the following:
"Each 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 simulator."
In order tw assure the highest fidelity of the simulator and the 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 coerational dits of the reference plant modification.
O 3 305P 01/90 '
~
PTAO-105 Rsvision 0 November, 1989 4
- 2. Certification Testing - Overview 1
- a. Each Troduction 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 procedures can be found in Attachment 2.
1
- 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.- Cartification Testing Administrative Procedure
, a. A copy of the Simulater Test Cover Sheet, PTAO-105T1, shall be I attached to each simulator certification test being performed l with the test title, number, date performed, and a brief I description of ths-test written on the Simulator Test Cover !
Sheet, PTAO-105T1. ;
- b. The outcome of the test shall be indicated on the Simulator Test Cover Sheet, PTAO-10$T1 as follows:
eeeeeeeeeeeee****eeseeeee'e**eneeeeeeeeeeeeeeeeeeeeee**=e*****ene
- NOTE *
- No test can be signed as successful and complete if a t '
any simulator work request (s) were written as a result e
- of performing the test. All simulator work request (s) *
- asson.ated with a particular test must be cleared *
- prior to accepting that test as completed. *
- eneme****eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee*****eeeeeeeeeeene 1). If the test PASSES and NO afnulator work recuents were written as a result of performing this test, the test le l- considered acceptable l
a) check the appropriate space on the Simulator Test-Cover Sheet, PTA0-105T1.
- l. b) sign and date the Simulator Test Cover Sheet, j PTAO-10$T1.
(, c) file in the SIM file, b
4 305P 01/90
PTAO-105 Revision 0 Novc:bar, 1989
() 2) If the test PASSES, but some simuister work reouests were 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 Simulater Test Cover Sheet, PTAO-105T1, c) write any simulator work requests refer. acing the test by number on the work request, d) write the simulator work requests number (s) on the Simulator Test Cover Sheet, PTAO-105T1, when work request numbers have been assigned.
e) after the associated simulator work request are completed, so indicate on the Simulator Test Cover Sheet, PTA0-105T1.
f) after all simulator work requests are completed, file in the SIM file.
- 3) If the test FAILS:
)
a) check the appropriate space on the Simulator Test Cover Sheet, PTAO-105T1.
b) sign and date the Simulator Test Cover Sheet, PTA0-105T1.
c) attach Simulator Test Cover Sheet, PTAO-105T1, to the test document.
d) write any simulator work requests referencing the test by number on the work request.
e) write the simulator work requests number (s) on the Simulator Test Cover Sheet, PTAG-105T1, when work request numbers have been assigned.
f) after the simulator work requests are completed, so indicate on the Simulator Test Cover Sheet, PTAO-105T1.
g) use additional Simulator Test Cover Sheets, PTAO-105T1, for performing subsequent tests. Use the original test number on any additional sheets. The original test sheet,must remain with the test document. l O
5 305P 01/90
PTAO-105 Revision 0 November, 1989 E. Attactunents Appendix 1. Braidwood Simulator Initial Certification Report Appendix 2. Examplee of Testing Procedures PTA0-105T1 Simulator Test Cover Sheet M
Arthur it. Roberts Production Training Manager O .
\
6 305P 01/90
BYRON SIMULATOR ANSl/ANS-3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 A- SIMULATOR MALFUNCTION U TESTING SCHEDULE NUMBER IjILE IEsT CYCLE fQuaRTER YEAR)
AN01 LOSS OF ANNUNCIATOR HORN 1st 1992 AN02 LOSS OF FUSE TO THE AN CABINET RACK 1611993 CC01 - CCW PUMP FAILS TO STAR / TRIP 1st-1992 CCO2 CCW PUMP DISCH PRESS INDICATOR FAILURE 1s.1992 CC03 CCW SURGE TANK LEVEL INDICATOR FAILURE 1st 1993 CC04 ESSENTIAL CCW TO RHR HX LEAK 1st 1992 CC05 - CCW TO THE CCW HX PIPING BREAK 1st-1993 CC06 NON ESSENTIAL CCW SYSTEM LEAK 151 1994 CC07 RCP THERMAL BARRIER LEAK 1st 1995 -
CC08 CW HX TUBE LEAK ist 1995 CC09 THERMAL BARRIER CCW FLOW X-MITTER FAILURE 1st 1994 CH01 RCFC FAN FAILS TO START / TRIP, LOW SPEED 1st 1993 CH02 RCFC FAN FAILS TO START / TRIP, HIGH SPEED 1st 1994 CH03 CRDM FAN FAILS TO START / TRIP - 1st 1995 CH04 REACTOR CAVITY BOOT FAILURE 1st 1994 CS01 CONTAINMENT SPRAY PUMP FAILS TO START / TRIP 1st 1995 CS02 CONTAINMENT SPRAY PUMP SUCTION LINE BREAK 1st 1994 CV01 CHARGING PUMP FAILS TO START / TRIP 1st-1993 CV02 PRI WATER MAKE-UP PUMP FAILS TO START /TFilP 1s11992 CV03 BORIC ACID XFER PUMP 1 AB03P FAILS TO START / TRIP 1st 1995 CV04 - VCT DIVERT VALVE FAILURE (11?A) 1st 1992 CV05 PCV 131 AUTO CONTROL FAILU'nE 1st-1993 CV06 CLOGCED RCS FILTER (ICV 3CF) 1st 1992 CV07 CLOGGED SEAL INJ FILTER . 1st 1993 CV08 FAILURE OF PT 131 (LTDN PRESS) ist 1992 CV09 FAILURE OF TE 130 (LTDN HX TEMP) 1st-1993 CV10 FLOW CONTROL VALVE 1CV121 FAILURE 1st 1994 CV11 - CVCS UNBORATED MIXED BED DEMINERALIZER 1st 1992 CV12 LTDN RELIEF VALVE FAILS OPEN 1st 1992 CV13 CHARGING LINE LEAK OUTSIDE CONTAINMENT 1st 1993 CV14~ REGENEHATIVE HX TUBE LEAK 1st 1992 CV15 SEALWATER HX TUBE LEAK 1st-1993 CV16 VCT LEVEL MALFUNCTION (112) 1st 1994 CV17- VCT LEVEL MALFUNCTION (185) 1st 1995 CV18 VCT PRESS MALFUNCTION 1st 1995 CV19 -- MAKE-UP CONTROL FAILURE 1st 1993 CV20 BORIC ACID FLOW TRANSMITTER (FT 110) FAILURE 1st-1994 CV21 CHARGING HEADER HCV 182 CONTROL FAILURE 1st 1995 CV22 LTON LINE LEAK INSIDE CONTAINMENT 1st 1994 CV23 LTON HX TUBE LEAK 1st 1994 CV24 LTDN LINE LEAK OUTSIDE CONTAINMENT 1st-1995 CV25 CHARGING LINE LEAK INSIDE CONTAINMENT 1st 1995
BYRON SIMULATOR ANSl/ANS-3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 I APPENDIX 6 SIMULATOR MALFUNOTION l ('N) TESTING SCHEDULE W uter I11Lg Test cycle _mARILfLYLAlu CV26 SEAL INJ LINE LEAKS 1st t992 CV27 RCP SEAL #1 FAILURE 1st 1994 CV28 RCP SEAL #2 FAILURE 1c11995 CWO1 CIRC WATER PUMP FAILS TO START / TRIP 1st 1993 CWO2 CIRC WATER PUMP DISCHARGE VALVE FAILURE 1st 1994 CWO3 NDCT LOSS OF EFFICIENCY 1st 1995 E001 345 KV SWITCHYARD BREAKER FAILS TO TRIP 1st 1992 ED02 345 KV SWITCHYARD BREAKER TRIP 1st 1993 ED03 FAILURE OF UNIT AUX TRANSFORMER (UAT) 1st-1994 ED04 FAILURE OF SYSTEM AUX TRANSFORMER (SAT) ist 1995 EDOS LOSS OF 6.9KV BUS 1st 1992 ED06 FAILURE OF 6.9KV ABT 1st 1993 ED07 LOSS OF 4160V BUS 1st 1992 ED08 LOSS OF FEED TO 480V NON-ESF BUS OR MCC 1s1-1993 ED09 LOSS OF FEED TO 480V ESF BUS OR MCC 1st 1994 ED10 LOSS OF 120 VAC ESF CONSTANT VOLTAGE XFMR 1611992 ED11 120 VAC INSTRUMENT BUS INVERTER FAILURE 1st 1993 ED12 LOSS OF DC DISTRIBUTION BUS 1st 1995
/^\ ED13 DC CONTROL POWER FAILURE (4160V) 1st 1994 ED14 DC CONTROL POWER FAILURE (480V) 1st-1995 ED15 345 KV BUS FAULT ist 1992 ED16 LOSS OF FEED TO 120V NON.ESF PANEL 1 st-1994 ED17 LOSS OF FEED TO 120V ESF PANEL 1st 1995 EG01 MAIN GENERATOR AUTO VOLTAGE REGULATOR FAILURE 1st 1993 EG02 MAIN GENERA 1OR EXCITER FAILURE 1st 1994 EG03 MAIN GENERATOR FIELD FORCING 15t-1995 EG04 BASE FOLLOWER UNIT FAILS TO TRACK 1st-1992 EGOS MAIN POWER TRANSFORMER TRIP 1st-1993 EG06 D/G FAILURE TO FLASH GENERATOR FIELD 1st-1994 EG07 D/G ELECTRIC SPEED CONTROL FAILURE 1st-1995 EG08 D/G SE12URE 1st 1992 EG09 D/G DIFFERENTIAL OVERCURRENT TRIP 1st 1993 FP01 MANUAL FIRE SUPRESSION WATER SYSTEM 2nd-1994 FP02 AUTO FIRE SUPRESSION WATER SYSTEM ACTIVATK)N 1st-1995 FWO1 MAIN FW PUMP FAILS TO START / TRIP (MOTOR) 2nd 1992 FWO2 MAIN FW PUMP FAILS TO START / TRIP (TURBINE) 2nd 1993 FWO3 START-UP FEED PUMD FAILS TO START / TRIP 2nd-1994 FWO4 MAIN FW OlL PUMP FAILS TO START / TRIP 2nd 1995 FWO5 TURBINE DRIVEN MFP CONTROL VALVE FAILURL: 2nd-1992 b FWOG TURBINE DRIVEN FW PUMP SPEED CONTROL FAILURE 2nd 1993 FWO7 FW PUMP SPEED CONTROL OSCILLATES 2nd-1994 FWO8 LOSS OF FW PUMP SPEED CONTROL 2nd-1995
BYRON SIMULATOR ANSl/ANS 3.51985 CERIFICATION REPORT '
INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6
/~3 SIMtJLATOR MALFUNCTION I U TESTING SCHEDULE
'i m ata mLI trET CYCLE fDUARTER YEAR)
FWO9 S/G FW CONTROL VALVE FAILURE 2nd 1992 FW10 FW REGULATION BYPASS VALVE FAILURE 2nd 1993 FW11 FW TEMPERING LINE ISOLATION VALVE FAILURE 2nd 1994 FW12 FW PREHEATER BYPASS VALVE FAILURE 2nd 1995 FW13 FW ISOLATION VALVE FAILURE 2nd 1992 FW14 FEED LINE BREAK BETWEEN FWOO9 & CONTAINMENT 2nd 1993 FW15 MAIN FW PUMP SHAFT BREAK 2nd-1994 FW16 FW HEADER PRESS FAILURE 2nd 1995 I FW17 HEATER DRAIN TANK LEVEL CONTROLLER FAILURE 2nd 1992 FW18 FW HEATER TUDE 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 (1CB025) 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
' FW28 2nd 1993 FW HEATER TUBE LEAK (11)
FW2s EW HEATER TUSE 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 l FW34 FW HEATER TUBE LEAK (16) 2nd 1995 FW35 HEATER DRAIN PUMP FAILS 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 AUX 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 lA01 LOSS OF INSTRUMENT AIR 2nd-1992 IA02 LOSS OF SERVICE AIR 2nd 1993
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6
/3 SIMULATOR MALFUNCTION
\_) TESTING SCHEDULE Hygggg 1[1LE ICyg.LE IOUARTER YEAR)
IA03 1A LEAK INSIDE OF CONTAINMENT 2nd 1994 IA04 IA LEAK ON THE TURBINE BLDG HEADER 2nd 1995 IA05 SERVICE AIR COMPRESSOR FAILS TO START / TRIP 2nd 1992 lA06 MSIV ROOM HEADER LEAK 2nd 1993 1A07 STEAM DUMP HEADER LEAK 2nd-1994 IA08 AUX FEED VALVES HEADER LEAK 2nd 1995 IA09 PENETRATION AREA HEADER LEAK 2nd 1992 MS01 FAILURE OF MAIN STEAM ISOLATION VALVE (S) 2nd-1993 MS02 MSIV BYPASS VALVE FAILURE 2nd-1994 MS03 S/G SAFETY VALVE FAILURE 2nd 1995 MSO4 S/G PORV CONTROLLER FAILURE 2nd 1992 MS05 STUCK STEAM DUMP 2nd-1993 MS06 MSR FAILS TO ISOLATE 2nd-1994 MS07 STEAMLINE BREAK INSIDE CONTAINMENT 2nd 1995 MS08 STEAMLINE BREAK OUTSIDE CONTAINMENT 2nd 1992 MSO9 MAIN STEAM HEADER CROSS TIE RUPTURE 2nd 1993 MS10 HEATER 13 EXTRACTION STEAM LINE BREAK 2nd 1994 N101 SR CHANNEL FAILURE 2nd 1995 N102 NOISY SR CHANNEL 2nd 1992 N103 SR CHANNEL HIGH VOLTAGE 2nd 1993 N104 FAILURE OF SR HIGH VOLTP 35 TO DISCONNECT 2nd 1994 -
N105 SR DISCRIMINATOR FAILURE 2nd 1995 N106 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 NI11 STUCK INCORE DETECTOR 3rd 1993 NI12 LEAK INTO GUIDE TUBE FOR INCORE DETECTOR 3rd-1994 RD01 ROD DRIVE MG SET TRIP 3rd 1995 RD02 DROPPED ROD 3rd 1992 RD03 DROPPING ROD 3rd 1993 RD04 ROD EJECTION 3rd 1994 RDOS STUCK ROD 3rd-1995 RD06 RODS FAllTO MOVE 3rd-1992 RD07 UNCONTROLLED ROD MOVEMENT 3rd 1993 RD08 DRPl 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
l BYRON SIMULATOR l ANS1/ANS-3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 SIMULATOR MALFUNCTION (d' TESTING SCHEDULE gugga mg Trst evett royARTER YEAM RH01 RHR PUMP FAILS TO START / TRIP 3rd 1992 RH02 RHR HX FLOW CONTROL VALVE FAILURE 3rd 1993 RH03 RHR HX BYPASS VALVE CONTROL FAILURE 3rd 1994 RH04 RHR AUTO SWITCH-OVER MALFUNCTION 3rd 1995 RHOS RWST LEVEL TRANSMITTER MALFUNCTION 3rd 1992 RH06 RHR HX TUBE LEAK 3rd 1993 RH07 RHR HX BYPASS LINE LEAK 3rd 1994 RH08 RWST LEAK 3rd 1995 RH09 RHR PUMP SUCTION HEADER BREAK 3rd 1992 RH10 RHR PUMP DISCHARGE HEADER BREAK 3rd 1993 RH11 RELIEF VALVE FAILURE 3rd 1994 RM01 AREA RADIATION MONITOR ACTUATION 3rd 1995 RM02 INOPERABLE RADIATION MONITOR 3rd 1992 RM03 INADVERTANT AUTO RADIATION MONITOR ACTUATION 3rd 1993 RMo4 PROCESS RADIATION MONITOR ACTUATION 3rd 1994 RM05 RADIATION MONITOR INTERLOCK ACTUATION FAILURE 3rd 1995 RM06 GASEOUS AIR MONITOR FAILURE 3rd-1992 RP01 REACTOR TRIP FAILURE 3rd 1993
]
RP02 RP03 REACTOR TRIP BREAKER FAILURE REACTOR TRIP BYPASS BREAKER FAILURE 3rd 1994 3rd 1995 RPO4 FAILURE OF PHASE A CNTMNT ISOL TO ACTUATE , 3rd 1992.
RPOS FAILURE OF PHASE B CNTMNT ISOL TO ACTUATE 3rd 1993 RP06 TURBINE TRIP INTERLOCK C-8 FAILS 3rd 1994 RP07 UNDER FREQUENCY ON RCP BUSES 3rd-1995 RP08 UNDER VOLTAGE ON RCP BUS 3rd 1992 RP09 INADVERTANT FW ISOLATION 3rd 1993 RP10 INADVERTENT PHASE A CONTAINMENT ISOLATION 3rd 1994 RP11 INADVERTENT PHASE B CONIAINMENT ISOLATION 3rd 1995 RP12 INADVERTENT CONTROL ROOM VENT ISOLATION 3rd 1992 RP13 REACTOR TRIP PERMISSIVE P-4 FAILS TO 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 RP18 POWER PERMISSIVE P 8 FAILS TO ACTUATE 3rd 1994 RP19 POWER PERMISSIVE P-10 FAILS TO ACTUATE 3rd 1995 RP20 PZR PRESS LOW PERMISSIVE P-11 FAILS 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 ACTUATE 3rd-1995 RX01 STEAM PRESS DETECTOR FAILURE 3rd-1992 RX02 UNSTABLE S/G LEVEL CONTROLLER 3rd 1993
BYRON StMULATOR ANS1/ANS 3.5-1985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 O SIMULATOR MALFUNCTION V TESTING SCHEDULE NUMBER IIILE TEST CYCLE f 0UARTER YE Am RXO3 STEAM FLOW DETECTOR FAILURE 3rd 1994 RXO4 FW FLOW TRANSMMTER FAILURE 3rd 1995 RX05 STEAM LINE PRESS DETECTOR (PT 507) FAILURE 3rd-1992 RXO6 NARROW RANGE S/G LEVEL FAILURE 3rd 1993 RX07 WIDE RANGE S/G LEVEL FA! LURE 3rd 1994 RXO8 STEAM DUMP COOLDOWN VALVES CONTROL FAILURE 3rd-1995 RXO9 STEAM FLOW OSCILLATION TIME 3rd-1992 RX10 FIRST STAGE PRESS TRANSMITTER FAILURE 3rd 1993 RX11 STEAM FLOWOSCILLATION 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 RX21 PZR PRESS CHANNEL FAILURE (455 & 456) 4th 1991 RX22 PZR PRESS CHANNEL FAILURE (457 & 458) 4th-1992 RX23 OVERPOWER DELTA T SETPOINT FAILURE 4th 1993 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 S101 SAFETY INJ PUMP FAILS TO START / TRIP 4th-1991 S10 2 St ACCUMULATOR LEVEL XMITTER FAILURE 4th 1992 S103 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8818) 4th 1993 S104 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8819) 4th-1994 S105 COLD LEG INJ CHECK VALVE LEAKAGE (Sl8948) 4th-1991 Sl06 COLD LEG INJ CHECK VALVE L EAKAGE (S!8956) 4th 1992 S 10 7 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8905) 4th-1993 S10 8 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8841) 4th-1994 S10 9 HOT LEG INJ CHECK VALVE LEAKAGE (Sl8949) 4th 1991 Sl10 HIGH HEAD St LEAK INSIDE CONTAINMENT 4th-1992 Sill St ACCUMULATOR TANK RUPTURE 4th 1993 SWO1 SX PUMP FAILS TO START / TRIP 4th 1994 SWO2 SX BREAK INSIDE CONTAINMENT 4th-1991 SWO3 LOSS OF SX COOLING TO D/G 4th-1992 SWy4 SX DISCHARGE HEADER BREAK 4th-1993 SWOS WS HEADER BREAK 4th-1994
.]
BYRON SIMULATOR ANSl/ANS-3.51985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6 O SIMULATOR MALFUNCTION V TESTING SCHEDULE WERIR n1LE TEST CYCLE foUARTEM.YE AB)
-TC01 INADVERTENT TURBINE RUNBACK 4th 1991 TCO2 TURBINE TRIP ON LOW LOAD INDICATION (PDS T0071) 4th-1992 TCO3 TURBINE AUTO TRIP FAILURE 4th-1993 TC04 TURBINE AUTO RUNBACK FAILURE 4th 1994 TC05 OPC LP TURB INLET PRESS SENSOR (PT-MS003) 4th 1991 TC06 DEHC IMPULSE PRESS TRANSMITTER FAILURE 4th-1992 TC07 DEHC MW TRANSDUCER FAILURE 4th-1993 TC08 DEHC GV/TV OSCILLATON TIME 4th 1994 TC09 DEHC GV/TV OSCILLATION MAGNITUDE 4th 1991 TC10 LOSS OF DEHC SPEED CONTROL CHANNEL (S) 4th 1992 TC11 LOSS OF DEHC SUPERVISORY SPEED CHANNEL 4th-1993 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 TH01 PZR STEAM SPACE LEAK 4th 1992 TH02 PZR RELIEF TANK LEAK 4th 1993
(]
V 4th-1994 TH03 S/G TUBE LEAK TH04 RCS LEAK, HOT LEG (HIGH) 4th 1991 i'i!05 RCS LEAK, HOT LEG (MEDIUM) 4th-1992 TH06 RCS LEAK, COLD LEG 4th 1993 TH07 REACTOR VESSEL FLANGE LEAK 4th 1994 TH08 RCS FUEL ELEMENT FA! LURE 4th 1991 TH09 RTD MANIFOLD FAULTY FLOW CONDITONS 4th-1992 TH10 PZR SPRAY VALVE FAILURE 4th-1993 TH11 PZR POWER OPERATSD RELIEF VALVE FAILURE 4th-1994 TH12 PZR SAFETY VALVF. FAILURE 4th 1991 TH13 PZR LEVEL DETECTOR REFNARIABLE LEG LEAK 4th 1992 TH14 PZR RELIEF LINE RTD FAILURE 4th 1993 THIS RCS WIDE RANGE RTD f AtLURE 4th-1994 TH16 RCP FAILS TO START / TRIP 4th-1991 TH17 RCP DEGRADED PERFORMANCEA.OCKED ROTOR 4th-1992 TH18 RCP SHAFT BREAK 4th 1993 TP01 STATOR COOLING WATER PUMP FAILS TO START / TRIP 4th 1994 TP02 STATOR COOLING WATER HIGH CONDUCTIVITY 4th-1991 TP03 SEAL OIL SYSTEM PDMP FAILS TO START / TRIP 4th-1992 TUO1 TURBINE VlBRATON 4th 1993
( ) TUO2 TURBtNE BEARING OIL PUMP FAILS TO START / TRIP 4th 1994 TUO3 TURBINE HP TEAL OIL B/U PUMP FAILS TO START / TRIP 4th-1991 TUO4 TURBINE DC EMER Olt PUMP FAILS TO START / TRIP 4th-1993
BYRON SIMULATOR ANSI /ANS 3.5-1985 CERIFICATION REPORT INITIAL REPORT, SEPTEMBER,1991 APPENDIX 6
/ SIMULATOR MALFUNCTION
\ TESTING SCHEDULE RU.MAER lilLE ILST CYCLE t00 ART E R.YE A Q}
TU0S TURBlNE OIL SYSTEM LEAK 4th 1992 TUOO BEARING LIFT PUMP SUCTION STRAINER CLOG 4th 1991 WD01 GAS DECAY TANK RUPTURE 4th-1992 YR01 LOSS OF RM 11 COMMUNICATION LOOP 4th 1994 3
(V C
e w.)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
ATTACHMENT 1 REG. GUIDE 1.149 REQUIREMENTS FOR DUAL PLANT SIMULATION FACILITY Comparison of the Byron Simulator to Byron Unit 2.
O O ,
'BYRONSIM 113/49 08/22/91)
l BYRON SfMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, 'TPTEMBER,1991 Attachment i shall demonstrate that the Byron Simulator meets the requ;rements and O
guidance of ANSI /ANS-3.5-1985 for Byron Unit 2.
The simulator design data base is maintained from Byron Unit 1 data. No data base is maintained for Byron Unit 2, however all, LER's and modifications are reviewed by the Byron Simulator Staff. A summary of the 1989-1990 Byron Unit 2 LER's that were determined to effect simulation follow: .
LER DESCRIPl10tl C0tEENIS89-001 2B D/G Sequence Test Failure and SI Tested Satisfactorily No Specific Malfunction 89-003 2AR12.1 Inoperable and Actuation Due Not Tested to Chech Source Failure Check Source Failure Not Modeled ,Several Other MF's Exist to Cause Inadvertent Actuations89-004 ESF Actuation Due to 345KV Loss Cancelled - See U-l LER 89-003 89-005 FWI from P-4 Signal Hhen Racking in Not Tested Rx Trip Breaker Inadvertent FWI Tested During MF-FH9 Testing i
9 (BYRONSIM 113/50 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT IN111AL REPORT, SEPTEMBER, 1991 O LER DESCRIEll0N COMMENIS90-001 MS Line Isoit tion /SI on S/G Pressure Tested Satisfactorily Channel Spiking w/1 in Test Added to HF-RX01 C & E 90-002 FHI from TRN B Rx Trip Breaker Not Tested Unknown Cause, Inadvertent FHI Tested During HF-FH9 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 HS Line Leak Manual RX & MS Line Tested Satisfactorily Isolation Added to MF-HS08 C & E O
l (BYRONSIM 113/51 08/22/91)
g . ._ . - _ _ _ . _ _ _ _ _ _ _ - _ _ _ _ _ . . _ -
BYRON SIHVLATOR- i ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 Major system differences between the simulator and Byron Unit 2 that affect
, simulator training are:-
RYAQlLSIMILAIDB BIR0lLUMIL2
- 1) Electrical distribution system 1) Electrical distribution system and and unit components are labeled unit components are labeled as Unit 2.
Unit-1.
2)1 The simulator has annunciators 2) Unit 2 has no annunciators associated with loss of-power to associated with these common
'Radwaste_and Turbine _ Building systems.
electrical loads, and Scent Fuel Pit Level and Temperature.
-3) S/G's are a D-4 S/G model. 3) S/G's are a 0-5 S/G model.
a)' Rx-trip / Auxiliary Feedwater Pump
- a) Rxtrip/AuxiliaryFeedwaterPumpg
- auto-start _setpoint is 40.8%. auto-start-setpoint-is 17.0%.
b) _ P-14'setpoint is-81.4%. b) P-14 setpoint is 78.1%. '
c) Smaller shrink / swell c) Larger-shrink / swell-characteristics-than the characteristics than the D-4 D-5 S/G model. S/G model.
d) l Normal operating' level, high/ low d) Normal operating level, high/ low alarm setpoints are 66%, 77% alarm setpoints are 50%, 74%,
and 45.8%. and 22%.
He consider that only difference #3 has a significant impact on simulator
- trai ni ng .' - Presently _ Byron Station is planning a modification-(M6-2-89-033) that will relocate the'D-5 level taps to provide similar response and setpoints-to that of_ the D-4_ This mod is scheduled to start on February 29,.1992.
O
.(BYRONSIM -113/52 08/22/91)
i BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION 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-evaulatulon 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-S S/G alarm setpoints, ESF actuation setpoints and the normal operating S/G 1evel.
The operational characteristics of Byron Unit 2 compared to the simulator are considered equivalent. Above 30%, Byron station feedback has reported that Unit 1 and Unit 2 respond in a similar manner.
Since Unit 1 and Unit 2 are almost identical, except for the staam generator model, adequate Unit 2 training is conducted by covering low-power operations (i.e., startups, shutdowns) and setpoints in the classroom.
J 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 procedures are not maintained in the simulator since the Unit 1 abnormal and emergency procedures are utilized for Unit 2 abnormal operctions and casualty training. The Unit 2 abnormal and emergency-procedures are developed from unit 1 i abnormal and emergency pcacedures and are almost identical. In addition, Byron !
Units 1 and 2 emergency procedures are validated on the simulator.
V
~(BYRONSIM 113/53 08/22/91)
BYRON SIMULATOR t.NSI/ANS-3,5-1985 CERTIflCATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O
ATTACHMENT 2 STEADY STATE / NORMAL OPERAT10NS/
REAL TI!1E/TRAN.;IENT TEST RESULTS O
O (BYRONSIM 113/54 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991
- ~
k-- BYRON SIMULATOR 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 1001 power. These power levels were chosen due to availability of Byron Unit 1 plant data.
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 tht values from the simulator computed variables, list (d these under the column heading " Actual", and (3,)
/
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 Roo 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 P0HER program. Boron Concentratiens for all tests were collected and compared to plant values resulting in deviations of ~ 7% to 20%. 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, l) t_
(BYRONSIM 113/55 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 BYRON SIMULATOR STEADY STATE TEST 30% P0HER TEST The 30% Power Steady State Heat Balance Test was performed from a beginning of life, 30%
power Initial Condition (IC23).
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.
Adattionally, the critical and non-critical parameters values on the Simulator do not detract from training.
O .
O (BYRONSIM 113/56 08/22/91)
07/31/91 05:10:51 TASK t 1C000107 LOAD .GOULD C.S.D. CPX-32 CECO BYRON TRAINER BALANCE PERFORMANCE -
3 0 %. c27T: cat P.f R Mi fi 2 L SYM80L Sh04T DESCRIPTION UNIT ACTUAL DATA % ERROR CRAN NORMALIZED CORE POWER DMLS .31 . 31 s .03 0049 21090 PWR #NG CH 41 (3UAD PC 30.80 31.193 -1.26 0050 21090 PWR RNG CH 42 (90AD PC 31 . 00 31 39a -1.21 0051 21090 PWR RNG CH 43 (QUAD PC 30.79 31.09a .95 0052 21090 PWR RNG CH 44 (QUAD PC 30.92 31.083 .52 0406 06825 PC LOOP 1A JR COLD DEGF 554.18 554.33a .03 0426 06870 RC LOOP 19 WR COLD DEGF 5f4.13 555.03a .15 0440 06950 RC LOOP 1C WR COLD DEGF 554.18 553.643 .10 0466 07040 RC LOOP 10 WR COLD DEGF 554.19 554.13a .01
_0617 06830 RC LOOP 1 A WR HOT L DEGF 572.53 575.46a .51 0439 06910 RC LOOP 13 WR HOT L DEGF 572.53 575.44a .50 0459 06990 RC LOOP 1C WR HOT L DEGF 572.53 579.66a -1.23 0479 07080 RC LOOP 10 WR HOT L DEGF 572.59 577.843 . 91 0499 07120 AUCTIONEERED HIGH T DEGF $63.34 563.553 .04 I 0480 06720 PRESSURIZER PRESS PSIG 2231.74 2235.4sa .17 0450- 06550 PRES $URIZER LEVEL L PC , 36.66 36.14a 1.45 0480 91245 PRESSURIZER WTR T DEGF 652.14 649.703 .13 0400 06350 S/G 1 A N AR RNG LEVE PC 62.78 61.80s 1.55 0420 06400 S/G 18 NAR RNG LEVE PC 62.79 62.794 .01 0443 06480 S/G 1C N AR ANG LEVE PC 62. 81 64.883 -3.19 0460 06500 S/G 10 NAR RNG LEVE PC 62.81 62. 60s .33 0400 00590 S/G 1 A STMLINE PRES PSIG' 1004.62 1024.163 -1.91
' 0 0422 06640 S/G 13 STMLINE PRES PSIS 1004.63 1002.514 . 21 0442 06670 S/G 1C STMLINE PRES PSIG 1004.63 978.000 2.72 0460 0 6680 *S/G 10 STMLINE PRES PSIG 1004.65 1000.233 44 0418 34540 STM GEN 1A FEEDWATE DEGF 327.40 332.924 -1.66 0438 34550 STM GEN 18 FEEDWATE DEGF 327.40 333.123 -1.72 0453 34800 STM SEN 1$ FEEDWATE DEGF 327.40 332.923 -1.66 0453 36860 579~ GEN 1C FEEDWATE DEGF 327.40 333.21d -1.74 2239 34240 S/G 1 A- FW TEMPERING GPM 97.13 101.003- -3.$4 2240 54250 S/G 19 FW TEMPERING GPM 97.1S 99.999 -2.51 2241 34260 S/G 1C FW TEMPERING GPM 99.53 99.004 .53
- 2242 34270 S/G 10 Fu TEMPERING GPM 101.43 102.00s .56 0403 06040 S/G-FW F F T-510 K9H 1017.92 1055.47a -3.56 0424 06130 S/G 1a FW F FT-521 K3M 1017.96 1033.E08 -1.53 0443 06200 S/G 1C FW F FT-530 KSH 1016.91 1049.43d -3.10 0406 Oo340 S/G 10 FW F FT-541 KBH 1017.62 1021. 07a .34 2$00 17070 GEN MW MW 309.92 318.70a' -2.75 0407 07040 S/G 1 A LOWER 90 LIN GPM 71.06 70.06a 1.42 0427 07050 S/G 13 LOWER 30 LIN GPM 71 . 06 70.062 1.42 0447 -07060 S/3 1C LOWER BD LIN GPM 71.06- 70.06a ,
1.43 0467 -07070 S/3 10 LOWER 80 LIN G'M 71 .06 70.06d 1.42 DATA VALUE 3ASED ON 31.02 % CORE POWER O
1
. . - - . .- .-- -- .~- -~-.- - -- -. . . - i w.- -
-07/31/91 05: 42:40 TASK *-20000124 -LOAD GOULD C.S.D. QPX-32 CECOL8YRON -TRAINER SALANCE PERFORMANC:
~
3 b 'c/ Ai rM ~ ctzT:c A t PAgysf7sEb
, : SfM80L SdORT ? '. $ C R I
- T I O N UNIT ACTUAL- DATA % ERRoa j _CRhN _ NOkMALIIED CORE POWE1 DMLS .31 .315 .01 L -0400- 36010 RC LOOP 1AF FT-414 PC 99.73 99.204 .5% >
j- - 0420 -06090 RC LOOP i S- F FT-424 PC 99.75 97.233 2.59
- 04401 06170 RC LOOP 1C F FT-434 PC 99.78 99.693 .00 j 0460 16250 RC' LOOP 10 F-FT-444 PC 99.76 100.75a -1.00 4
. 1000 090SOLCONTAIN4ENT PRESS PSI 3 .59 .503 6.07
- 0403 06323RC-LOOP 14 DELT A PC 32.90 34.253 -3.94
[ , 0&23 l06800 RC LOOP 18 DELTA T PC 32.89 32.23a 2.06
[ - 0443 0o940 #C: LOOP 1C DELTA T PC 32.d9 33.843 -2.31 l .0463 07030 RC-LOOP 1D-DELTA T PC 32.95 30.54a 7.90 *
- 0131 27010 RCP 1 A .SE AL INJ WAT 3*M 3.06 7.933 1.61
- - 0127- 27010 RCP 1 C- S E AL INJ W AT. GPM , 8.06 8.483 -4.9o E 0123- 27010 RC' 10 SE AL INJ W AT GPM 5.06 7.773 3.90 i _ 0415 91140 RCP 1A 9T4 LOWER RA - DEGF 120.57 127.023 -5.01 *-
- 0435- 91170.RCP_18 MTR_ LOWER RA DEGF 120.57 131.031 -7.98
-0475- 91230 RC8'10 MTR LOWER RA DEGF 120.57 131.'023 -7.43-*
0035 21040 INTERMEDIATE RNG.CH MCAMP 102.67 99.963 2.72 1 0036 21040 INTERMEDIATE: RNG'CH MCAMP 102.91 95.39a 7.83
- I - 2205 34432 EXM Hoot 1A P INHGA 1.29 1.16a 11.51 *- -
365d5-TUR3 FIR $T STAGE PR PC 24.40- 26.56a -9.13 e Os939A- 0399 '005d6 TURt FIAST STAGE PR PC 24.40 26.574 - 3.17
- L 0404_ 06370 S/,G-1A WIDE-RNG LEV PC- 59.87 58.53a 2.29 0424- 00440 S/3-la WIDE RNG sEV PC 59.87 57.933 3.35 i
1 0444 loo 490x5/601C WIDE RNG LEV *C 59.87 59.933 .09 0 4 o 41 GoS40--S/i 1D WIDE RNG LEV. PC 59.87 -59.73a .24:
2418 107130 CNOSR-: INLET-LINE A DEGF 79.62 L75.394 5.61 e 0a05- 06000 S/3- 1 A _ STE AM F FT-5 'K9H 1033.44 952.30s 5.21
- 0425- -06140 S/G IdfSTEAM F FT-3 K9H 1033.48 1003.443 _2.49 0445 ~ 06220-S/311C S'EAM-F FT-5. XBN 1033.67 1104.68a -6.41.*
- 0465 06290 S/3 10 STEAM
- F-FT-5 KSH 1035.96 973.013 6.40 *
~
04TA-VALUE 9ASEDJON 31.13 % CORE 80WER k
J B
1
+
2
)
O W
t
~
BYRON SIMULATOR ANSI /ANS-3,5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 BYRON SIMULATOR 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 were within 2% plus instrument error and all non-critical parameters were within 10% plus instrument error with the exception of Intermediate Range Current, Hork Request 08-91-0005 was written to correct this discrepancy. Estimated completion date for this Horn 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 I division of the reference plant data.)
O .
o O
(BYRONSIM 113/S7 08/22/91)
07/31/91 04556 22 TASK 0 210000F4 LOAD GOULD C.S.D. MPX-32 CECO BTRON TRAINER 3ALANCE PERFORMANCE cj 0 f,, ( C .T TI C AL l'G M E TE C S
\
SHORT DiSCRIPTION UNIT ACTUAL DATA % ERROP SYG90L NORMALIZED CORE POWER DMLS .89 .695 .01 CRON 88.14 89.153 -1,14 PC 0049 21090 PWR RNG CH 41 (QUAD 0050 21090 PWR RNG CH 42 (QUAD PC 83.07 88.82a .S4 0051 21090 PWR RNG CH 43 (QUAD PC 88.06 88.87a . 91 0052 21090 PWR RNG CH 44 (QUAD PC SS.06 88.363 . 33 0400 06825 RC LOOP 1 A WR COLD DEGF 550.63 548.553 .38 0426 06870 RC LOOP 18 WR COLD DEGF 550.63 549.25a .25 044o 0o950 RC LOOP 1C WR COLD DEGF 550.63 548.243 44 0+66 07040 RC LOOP 1D WR COLD DEGF 550.64 548.25J .44 0419 06830 RC LOOP 1 A WR HOT L DEGF 601.77 604.933 52 0439 Oo910 RC LOOP 10 WR HOT L DEGF 601.77 603.373 27 0459 06990 RC LOOP 1C WR' HOT L DEGF 601.77 609.523 -1.27 0679 07080 RC LOOP 1D WR HOT L DEGF 601. 80 606.16a .72 0499 07120 AUCTIONF.ERED HIGH T DEGF- 576.18 575.97a .04 0480 06720 PRESSURIZE 9 PRESS PSIG 2231.60 2233.844 .10 '
0480 06550 PRESSURIZER LEVEL L PC 55.49 55.953 .37 0480 91245 PRES $URIZER WTA T DEGF 652.26 649. 51 a .42 0400 06350 S/G 1 A N AR RNG LEVE PC 63.11 62.094 1,64 0420 06400 S/G 13 NAR RNG LEVE FC 63.12 62. 31 a 1.29 0443 06480 S/G 1C NAR RNG LEVE PC 63.1.4 63.053 ,14 0460 06500 $/G 1D NAR RNG LEVE FC 63.14 62.50a 1.02 06590 S/G 1 A STMLINE PRES PSIG' 358.77 912.914 -2.64
{s)0400 x, 0422 066*0 S/G 13 STMLINE PRES PSIG 888.77 912.354 -2.59 0442 06670 S/G 1C STMLINE PRES PSIG 838.77 911.753 -2.52 0460 06660 S/G 1D STMLINE PRES PSIG 888.78 912.32a -2.5S 0416 34840 STM 3EN 1 A FEEDWATE DE6F 426.61 424.972 .59 0438 34850 STM GEN 13 FEEDWATE DEGF 426.61 424.873 .41 045e 34860 STM GEN 1C FEEDWATE DEGF 426.61 424.879 41 0*53 34360 STM GEN 1C FEEDWATE DEGF 426.61 424.633 46 2239 34240 S/G 1 A FW TEMPERING GPM 97.17 101.00a -3.79 2440 34250 S/G iS FW TEMPERING GPM 97.21 99.03a -1.S3 2241 34260 S/G 1C FW TEMPERING GPM 99.57 99.003 .57 2242 34270 S/G 1D FW TEMPERING GPM 101.45 102.003 .54 0403 06040 S/3 FW F FT-510 (3H 3334.72 3308.84a .78 0424 06130 S/G 16 FW F FT-521 (aH 3334.86 3297.923 1.12 0443 06200 S/G 1C FW F FT-$30 (BH 3334.37 3332.618 .05 0464 06340 S/G 10 FW F FT-541 K9H 3334.49 3282.36a 1.59 2dOO 17070 SEN MW MW 1030.10 1018.17 a 1.17 GPM 75.56 74.87a .91 0407 07040 3/G 1 A LOWER BD LIN 0427 07050 S/G 13 LOWER 30 LIN GPM 75.56 74.878 91 0447 07060 S/3 1C LOWER 90 LIN GPM 75.56 74.87a
- 92 0467 37070 S/G 10 LOWER BD LIN GPM 75.56 74.873 . 91 D ATA V ALUE B AS ED ON 89.47 % CORE POWER O
07/31/91 05:04:25 TASK C 1F0000FE LOAD GOULD C.S.D. MPX-32 '.
...............----------------~~~~~~----~~~~--~~~~~~~~~~~~--~~~-------
CECO BTRON TRAINER BALANCE PERFORMANCE (J C h AJOV c[IT7c4L PACMETifL SHORT J ES CRIPTI ON UNIT ACTUAL DATA % erg 0g SYM90L CRON NORMALIZED CORE POWER DMLo .90 .905 .01 0600 06010 RC LOOP:1A F FT -414 PC 99.18 99.109 .08 0420 06090 RC LOOP 18 F FT-424 PC 99.19 99.64a 45 0440 06170 RC LOOP 1C F FT-434 PC 99.22 98.723 .50 0460 06250 RC LOOP 1D F FT-444 .PC 99.21 99.04a ,17 1000 09080 CONTAINMENT *RESS PSIG 47 473 .53 0403 06823RC LOOP 1A DELTA PC 91. 45 93.70a -2.40 0423 06800 RC LOOP 18 DELTA T PC 91 .45 90.343 1.23 0443 06940 RC LOOP 1C DELTA T PC 91. 44 92.723 -1.38 0463 07030 RC LOOP 10 DELTA T PC 91. 43 89.14a 2.63 0131 27010 RCP 1A SEAL INJ WAT GPM 9.24 8. 81 a 4.92 0129 27010 RCP 13 SE AL INJ WAT GPM 9. 24 9.39W -1.52 0127 27010 RCP 1C SE AL INJ W AT GPM 9.24 9. 31 a .70 0125 27010 RCP 10 SE AL INJ WAT GPM 9.24 5.843 4.52 0415 91140 RCP 1 A MTR LOWER RA DEGF 136.09 128.663 5.77
- 0435: 71170 RCP 13 MTR LOWER R A DE4F 136.09 132.959 2.36 0455 91200 RCP 1C MTR LOWER RA DEGF 136.09 128.963 5.53
- 0475 71230 RCP 1D MTR LOWER RA DEGF 136.09 132.764 2.51 0035 21040 INTERMEDIATE RNd CH MCAMP 327.72 294.454 11.30
- 0036 21040 INTERMEDIATE RNG CH MCAMP 328.21 266.7Sa 23.03
- 2205 34432 'EXH MOOD 1AP IhMGA 2.24 2.42a -7.18
- 06585 TURS FIRST STAGE PR PC 87.94 87.17a .38
.s00398 0399 0$580 TUR3 FIRST STAGE PR PC B7.94 S8.053 .13 0404 00390 S/G 1 A WIDE RNG LEV PC 61 . 2 0 60.743 75 D424 36440 S/G 18' WIDE RNG LEV PC 61 . 21 60.14a 1,76 0444 06490 S/G 1C WIDE RNG LEV PC 61 . 21 61.753 .89 0464 06540 S/G 10 WIDE RNG LEV PC 61 . 21 61.753 .87 2413 07130 CNDSR INLET-LINE A DEGF 34.1 3 88.67a -5.12
- 0405 06060 S/G 1 A STEAM F FT-5 (dH 3354.14 3583.63a -6.40
- 0*25 06140 3/G 13 STEAM F FT-5 KSH 3354.96 3644. 'a -7.95
- 0645 06220 S/G 1C STEAM F FT-5 KBH 3354.37 3664.16a -8.44
- 0465 06290 S/G 1D STEAM F FT-5 KBH 3355.67 3584.448 -6.38
- DATA VALUE 34560 ON 59.33 % CORE POWER O
mus
BYRON SIMULATOR ANSI /AN3-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O BYRON SIMULATOR STEADY STATE TEST .
100% P0HER TEST The 100% Power Steady State Heat Balance Test was performed from a beginning of life, 100% power initial Condition (IC?l).
Data was collected and compared using the P0HER 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. Hork 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 trai,ntng. (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 .
O ,
(BYRONSIM 113/58 08/22/91)
l 07/31/91 04: 39432 TASK 4 320000EE LOAD G0ULD C.S.D. Cox.32 CECO BYAON TRA!HER BALAkci PERFORMANCE t(w % ,,', '; e c.U Tzc44 MA'MIdb f}
x_/
$YOROL SHORT OESCRIpTION UNIT ACTUAL DATA t E# ROP C80N NORMALIZED CORE POWER DMLS 99 995 0.00 0400 06010 RC LOOP 1A F FT-414 PC 98.70 99.244 47 0420 06090 RC LOOP 10 F FT-424 PC 98.71 97.758 95 0440 06170 RC LOOP 1C F F1 -4 34 PC 98.73 98.518 .22 0660 06250 RC LOOP 1D F FT-444 PC 98.72 99.369 . 07 1000 09080 CONTAINHENT PRE $$ PSIG . 31 .32a .
.s4 0403 06823RC LOOP 1A DELTA PC 100.35 100.298 .09 0423 06860 RC LOOP 10 DELTA T PC 100.37 97.A6a 2.79 0443 06940 RC LOOP 1C DELTA T PC 100.36 100.744 .
.38 0463 07030 RC LOOP 10 DELT A T PC 100.40 96.47a 4.05 013' 27010 RCP 1A SE AL I NJ WAT JPM 9.84 9. 21 3 6.93
- 0129 27010 RCP i s SE AL INJ WAT G8M 9.84 10.083 -2.38 0127 27010 RC8 1C SE AL INJ WAT GPM 9. 85 10.16a -3.06 0123 27010 RCP 10 SEAL INJ WAT GPM 9.84 v.304 5.92
- 0435 91170 RCP 1d NTR LOWER RA DEGF 137.26 13 3. 96 W 2.46 0655 91200 RCP 1C MTR LOWER RA DEGF 137.26 129.00d 6.40
- 0475 91230 RCP 10 MTR LOWIP AA DEGF 137.26 13 3.18 a 3.06 0035 21040 INTERMEDIATE RNG CM MCAMP 369.94 326.323 13.37
- 003t 21040 INTERMEDIATE RNG CH MCAMP 370.98 288.008 28. 81
- 2205 34432 EXH HOOD 1A 7 INHGA 2.56 2. 35d 8.v2
- r N 0391 06585 TURB FIRST STAGE PR PC 100.16 97.54a 2.69
( ') 0399 00566 TURB FIRST STAGE PR PC 100.16 98.904 1.26 0404 06390 S/3 1A WIDE RNG LEV PC 61.e4 61.674 .27 0424 064 0 S/G 1B WIDE RNG LEV PC 61.64 61.733 .15 0446 06490 S/G 1C WIDE RNG LEV PC 61 . 75 63.048 -2.04 0464 06540 S/G 1D WIDE RNG LEV PC 61.64 62.189 .87 2418 37130 CND SR INLET-LINE A DEGF B6.51 82.48a 4.Su 0405 06060 S/S 1 A STE AM F FT-5 K9H 37M2.23 4058.30a ~ 6. 50
- 0*25 06140 S/G 19 STEAM F FT-5 KdH 3791.76 1998.08a - 5. 41
- 0445 06220 S/G 1C STIAM F FT-5 KOH 3732.16 4127.183 -3.36 =
0465 06290 S/G 10 STEAF,F FT-5 r.0 H 3783.41 4018.554 -5.d5
- DATA VALUE BASED ON 79.1 6 % C OP. E POWER
07/31/91 04:29:02 TASK v 090000E4 LOA 0 GOULD C.S.D. cpr.32 CECO BYRON TRAlhER DALANCE PERFORMANCE l cf h C. r' z 7 2 C A l '% dWi ?i E h
)
SYMBOL SHORT DESCRIPTION UNIT ACTUAL DATA % ERROR CRQN NORMALIZED CORE POWER DMLS 99 .995 .02 0049 21090 PWR RNG CH 41 (QUA0 PC 99.$6 99.544 .02 0050 21090 PWR RNG CH 62 (QUA0 PC 49.74 99.06a .66 0051 21090 PWR RNG CH 43 (QUA0 PC 99.24 98.903 .34 0052 21090 PWR RNG CH 44 (QUA0 PC 99.65 78.483 1.19 0406 06825 RC LOOP 1A WA COLD DEGF 552.16 550.70s .26 0426 06810 RC LOOP 10 WR COLD DEGF 552.16 550.92a .22 0446 06950 RC LOOP 1C WR COLD DEGF $ 5 2.17 550.213 .36 0466 07040 RC LOOP 10 WR COLD DEGF 552.17 550.218 .36 0419 36530 RC LOOP 1A WR H0T L DEGF 608.36 610.218 .30 0439 06910 RC LOOP'19 WR HOT L DEGF 608.36 608.613 .04 0459 06990 RC LOOP 1C WR HOT L DEGF 608.36 615.873 -1.22 0479 07080 RC LOOP 10 WR HOT L DEGF 608.39 612.578 .68 0499 07120 AUCTIONEERED HIGH T OCGF 580.24 579.578 .12 0480 06720 PRESSURIZ6R PRESS PSIG 2231.85 2236.$9a .21 0460 06550 PRES $URIZER LEVil L PC $9.95 59.86a .15 0480 91245 PRESSURIZER WTR T DEGF e52.31 649.993 .36 0400 06350 S/G 1 A N AR RNG LEVE PC 63.07 62.204 1.41 0420 06400 S/G 18 NAR RNG LEVE PC 63.07 63.263 .31 0443 06450 $/3 1C NAR RNG LEVE PC 63.57 63.003 91
< 0460 06500 S/G 10 NAR RNG LEVE PC 63.08 63.083 .01 1 06590 S/G 1 A STMLINE PRES PSIG 885.14 895.301 -1.14
(~N 0400 855.14- 882.528 l (_) 0422 066*0 $/G 10 STMLINE PRES PSIG .30 l 0442 06670 $/G 1C STMLINE PRES PSIG 885.14 864.35a .09 l 0460 06680 S/G 10 STMLINE (PES PSIG 885.14 884.350 .09 0416 34640 STM GEN 1A FEED. ATE DEGF 439.26 434.518 1.09 0438 34850 STM GEN 1B FEEDWATE DEGF 439.26 434.693 1.05 0456 34900 STM GEN 1C FEE 0WATE DEGF 439.26 434.493 1.10 045d 34860 STM GEN 1C FEEDWATE DEGF 439.26 434.37a 1.13 i 2239 3 240 S/G 1 A FW TEMPERING GPM 97.19 101.008 -3.77 2240 34250 S/G is FW TEMPERING GPM 96.30 100.923 -4.57 2241 34260 S/G IC FW TEMPERING GPM 99.59 100.92a -1.32 2242 34270 $/G 10 FW TEMPERIkG GPM 101.47 101.044 .43 0403 06040 S/G FW F FT-510 KBH 3770.76 3762.73a .21 0424 06130 S/G 13 Fd F FT-521 KSH 3771.53 3725.85a 1.25 0643 06200 S/G 1C FW F FT-530 KBH 3765.52 3805.04a .' 9 6 0664 06340 S/G 10 FW F FT-541 KBH 3770.50 3781.153 .25 2!00 17070 GEN MW MW 1153,95 1149.27a 41 0407 07040 S/G 1 A LOWER 80 LIN GPM 79.58 79.800 .27 0427 07050 S/G 13 LOWER B0 LIN GPM 79.58 79.79a .26 0447 07060 t/G 1C LOWER 80 LIN GPM 79.59 79.793 ,
.20 0467 07070 S/3 10 LOWER 80 LIN GPM 79.58 79.79a .26 OATA VALUE 9 AS ED ON 99.15 % CORE POWER l
l
- -. . - - - - ~ ,Q,
BYRON S!HULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT SEPTEMBER, 1991 V BYRON SlHULATOR STEADY STATE TEST 100% STABILITY TEST The 100% Power Stability Test was performed from a beginning of life, 100% power Initial Condition (IC21).
Data was collected wtth the POWER program. The simulator was run for 60 minutes.
Following 60 minutes of operation, data was recorded again. The final values did not vary more than t 2% of the initial values.
R The results of the 100% Power Stability test were acceptable, O .
e O
(BYRONS1H 113/59 08/22/91)
03/01/v1 vi 3Vt 45 TASr a ?!00CJ56 LCac 000L C.$.. *p=-
- ICO LYROA isA %ia ALANCE *EtF0PSAN(F
- % T) Q SY*10L bb
$n3*T ?!SCRI2T CA M%B UNIT ton ACTUAL 01TA gn:r 1 f#800 C 8 9 t. 40RNAL ZED C085 #0dit C*L: 1.00 # 1.CC: . ']
0343 210VC ?a* *NS CW 41 (1U40 PC 101.59" C9.4Ci 1.tv '
0]$s 21090 PW8 DNG CH 42 (.UAC #C 101.1G' GS.4?? 1.77 0C51 21C90 OWR *NG Ch 43 (;uat 9'. 101.14" G9.?ti 1. o.
0C52 2109C *n' DNG CH 44 (ius? t 100.92" 9!.t$2 2.70 +
0*Db 3ct25 RC LOCP 14 W4 COLO DIG 8 5 5 2. 3C ' 55C.?C: .??
0426 Oct70 RC LSOS it wk COLD DFCF !! 2. 30 ' 551.004 .24 0*4e Go95C PC LOC' 1; 8 COLD DiGF $ 5 2. 31 ' 550.30s .37 0*6c 07C*0 PC LJ08 it 4 C0t3 Df55 !52.31' 590.!Ds .37 0419 06E30 RC Loco te FP NOT L DE0F t00.00* 610.402 .23 3439 OtV10 RC LOOP 1: b5 WOT L DECF e09.00' eCF.FCi .03 04$4 Oc7+3 RC Loco 1C 5 40T L Oftr e04.00* s i e .10 4 -1.15 0 79 37030 cc L7CP 10 at H;T L Dr0F e 00.0 2 ' 612.tCC .62 0*99 0 71/0 AU:!! chi!9 E F is T Dt0F ? ?O.6 2 " $79.7Ci .1o CVd!LTDra IhtT $0P0N LTON Nx ?aV F55.01' 77e.Ctr 10.57 .
04s0 Oc7tC SR333Vo!!E# *RfL$ PC:3 2224.1?' 2236.70s .5e Ce!C 0o550 SFiSSUE: Zie LEVEL L #C (0.10' t0.00T .1 o 0430 712 5 3Rt3:VoIZER .Ta T 0805 ?!1.?C- oSO.CC? .2r 0*00 06350 S/7 14 Aap R%G trV5 *C t3.25' $2.?CA 1.69 0420 Ot400 4/4 to hAR PNG L'vr pc (3.74- 43.3gt .
.09 0 43 0:43C S/3 1C nap aNy lev! oC $2.50' e3.001 79 0 60 Oc500 S/G 10 N46 FNG Lf vF DC ( 3. 24 ' 63.10s .23 0*00 OcS90 $/S 1A 5TvL;Ni SPE% 80:G .$ P 5 . 0 0 - h44.7Ci -1.0e 0 24
- Sto*C S/G 1 :- ETMLINi epis 0;13 f t !.00 - ef1.40t 41 C642 Je673 C/3 10 STwLIM 98!! 03;J ! 8 f.LC # Ff3.3CE .17 0 60 J:csC S/3 10-3T*LINi **it P5:1 !!$.01- ??3.301 .19 01- !*t40 STd 3L4 is Fif0WATr DrC8 440.51 ' 4!*.600 1. 31 043e 34tLO STV i!N .1 : F ! C D L T t. D c. 'i r 440.51" 435.CGt 1.?7 05: 2.Sc0 CTv Gih it si!D.'ATr Dr3r ( 4 0. 51 < 434.10; 1.31 0 5s 366t0 CT# Gih 1C Fic.D ATC DfGF 440.51
- 434.702 1.T4 2d39 3,24C S/3 1A r. Tivect:NG G$t 101.3t' 101.CCC .H 2: 40 3 250 S/G 1L 3 TI+9?d!N4 3rr 100.17' 1C1.002 .92 2241 3 2s; s/S 1C FW TiepC2!NG 3:M 95.74' 101.004 -1.25 244J 3 27C S/1 1D FW Tc9p'EI65 00' ici.!C # 101.00?' 70 0403 ]cC4C S/G Fa 5 F T - 510 <-e ??13.32' 3770.004 41 0426 h15C S/5 1r pa r rt.371 (:e 3r14,14e 1741.CC# 1.9s C442 0:200 S/3 1C Tw r 57-530 U+ 3 t 14. 0 3- I!22.CJi .21 C*os *)e3 0 S/3 1 c F .' F TT-541 888 351% 87- t?99.20s 41 2c0J 17C70 GEN *e % 1169.77* 1153.907 1.37 0 07 370*C S/3 1A LO.14 :D L !': Gev F0.Ge' FO.CCd .07 C%27 0703C S/S 12 L?m!* d L;N Co* in.Dt' EC.CCE .09 i
C647 37000 5/1 1C LOWis 4. 0 L:N Gov 80.0t* !G.CCa .09 C407 J7070 3/3 10 L3 30 10 LIN 03* '0. 0 t- 90.004 .07 CATA VALLI S AS ED 3N 10C.20 1 C 0 3 r. Staia t
s3/01/91 0: 24v 4? Tab <
- 3 COL 900& LOAC GOULC :.s.n. wot-Ci!O iVR0A Td!!\fr 'ALAACE Si#r3DMAN(r O
V Syms 0L CH0PT DTSCDIATICN UNIT ACTUAL DATA FP'08 CRJN NOP*LLIIID CORE $3.!# PWL5 1.00' 1.00* 71 0,00 06012 oC LOOP 1A 8 FT-414 pt 95.t3e 08.20 44 0 20 Ot090 oc LOOD 1, i FT-426 *C 0:.th' 07.7Ci .uy 0440 Jt170 PC L7C# it F fi-634 "C 74.t P' Gh.5CE .1B 0 oC 0:25C RC LOOP 1D F cT-e=4 pC 0!.ot' 09.=Cs .74 012S 27010 CHA33fNG Hbr, Flow Gap 131.3o- 90.400 45.34
- 0134 2 7C10 lit a3dh LJN! FLOW Lar 113.Cd' 54.00I 34.62
- 1000 07060 CONin:NMENT **rt$ at:G . 31 ' .31 2 -1.10 0 03 N; 4C LOO
- G6.70i 4.73
- 0131 27010 LCP 14 $1A( !NJ WAT GCW Q.$Q# 9.222 3.QQ
- 0124 27C10 kC8 19 EE8L IhJ WA1 Go* 9.50' 10.115 -e.05
- 0127 27010 aca 1C !!AL thJ WAT 4** 9.50' 10.147 -o . 7 7
- C125 27010 #C5 1D 5tAL 1hJ WAT Gem 4.50' 9.223 1. 91 C VF SLI AL < F PCP 1A 3 7. A L s1 L(CrF FLc5 L9/r .47- .009.*=*******
- CVF3L1?LKF RCD li SfAL #1 L<CFF FLCW LE/S 67r .CCS* *******
- CVFSLICL(F RCD 1C $~AL *1 L(CFF FL0h L'/3 47 e .00e* <*******
- PVF$L1DLK7 PCP 1D SIAL #1 LMCFI FL0w Lu/5 47 ' .009**********
- r~ 0415 911*O RC: 1A gio La.is sa p?se 135.41' 12E.CCi 5.79 +
( ,3) 0435 91170 PCS Id rTR lower 4A erJr 125.41' 134 CC;. 1.05 6455 91200 PC# 1C PTA Lo=n!F Pa OtG8 11 t . 41 ' 129.004 4.97
- 047s 91230 *C8'13 Min LOWit FA DEGF 135. 1' 113.20s 1.6t OC3h 2104'J INT!*>F0!ATF R t4 0 Cw NCAwo 373.15' 327.456: 14.17
- Oile 21C43 INT 54ME): ATE ANS C4 VCAVA 373.9%r 2e?.712 2C.52
- 2205 N3 LXH H3Ce 1A P !tHG4 2.4C" 2.159 2.04
- 24Uc 45 IXe H000 is F IANGa E.vo, 3.01; . 50 2207 NJ Ex5 dOOD 1C INNOA 3.50' 3.46t 1.73
- TCPieP Hu Tu a s 190iJL55 otF53 Pt:5 680.30* 660.004 1. 37 039: 0:555 TU?! f!A!T 3TAGE 55 oC 1C1.37' 97.502 3.54
- 0; rs 0: 5:e TUP 4 f!RST STA"! De PC 1C1.37' 9G.304 2.04
- G404 9e39C S/2 1* Li>C *NG LEV PC e 1. 74
- 61.!Of .39 0,44 0:4 0 S/3 lu w;t? *N- Liv aC 61.74- 61.50s .00 044. Jt490 $/G 1C WI): SN) LEV PC (1.11 ' t 3.1 C a -2.05
- 0.04 0:54C .5 / 5 10 wi>i RN3 L~v ot e1.74 (2.202 .74 2000 14010 LF TUE0 la :NetT >< : es:1 14 4 . e 5 ,' 150.CCi -3.43
- 2001 teCJC LP TU8F 1h INLit ut 0 7 : :, 144.tfa 144.002 -2.72
- 2004 1c030 LC TURF 1C INL2T M5 0 S ! .' 144.M' 157.000 ' . 74
- 241: 0 7130 C N) 3 R It4Lt?-L1ht 4 DEG8 14.h0- 32.208 2. 90
- Deut CoCs0 S/s 1A STitv F rT-f <is 3?75.04' 4075.eC4 -+.15
- C425 Ot1*C 0/3 12 3 T I A V. F FT-! M: P 3'?5.07' 4010.20; -4.50
- 0*45 d6220 S/3 1C 3 TEA
- F FT-5 <0F 3t?h.10' 4144.(CF ~7.e7
- 0*c5 O t 2 v' J 5/3 10 STi&"
- FT-$ 6: ~ e Tt27.3 4034.CCs -5.12 *
, 14TA VALui EASIC ON 100.21 i C] E 00WE8 I
i I
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L3/01/01 04:4esat T 4 5(
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- L ,- 1.00 1. c :. ,69 0044 210#0 Pd' RNi CN 41 (20AD FC 101.40 G4.5CT 2.00 +
0L50 21090 odo eNG Cm 42 (3UAD PC 101.50 5 % .41 t 2.0*
- 0051 ?107J 'W8 'Ni CH 43 (;U4D oC 101.46 oV.2ti 2.24
- 0052 21Cvc #d4 RNG CH 44 ( J t' A D PC 101.22 Of.!5s 2.40
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BYRON SIHULATOR ANSI /ANS-3.5-1985 CEPT!flCATION REPORT INITIAL REPORT, SEP1 EMBER, 1991 BYRON SIMULATOR NORMAL OPERATIONS TEST The objective of the Normal Operations Tests is to verify that the Byron Simulator performance meets the criteria of ANSI /ANS-3.5-1985 Sectlun 3.1.1. The Normal Operations Tests were performed per the attached using Byron Station Ceneral Procedures. The tests performed and results are as follows:
- a. Plant Startup - Cold Shutdown to Hot Standby Accepted
- b. Reactor Startup to 100% Power Accepted (includes turbine startup and generator synchronizatirin)
- c. Reactor Trip followed by Recovery to 100% Power Accepted (includes operations at hot standby and load changes)
- d. Plant Shutdown from 100% Power to Hot Standby Accepted and Cooldown to Cold Shutdown e
O (BYRONSIM 113/60 08/22/91)
BYRON SlHULA10R ANSI /ANS-3.5-1985 CERT!flCATION REPORT INITIAL REPORT, SEPTEMBER, 1991 e
BfRON SlHULA10R NORMAL OPERA 110NS TES11NG A. PURPOSE The purpose of this procedure is to verify that normal plar t evolutions can be conducted on the simulator 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.
- 2. B6P 100-1 + 5: Byron General Procedures.
- 3. PTAO-105: Simulator Certification Reporting and Testing Program C. IN111AL CONDITIONS
- 1. The Initial Conditions (IC's) will be specified under Section C, lest Instructions.
D DATA COLLECTION O
- 1. DGP flowcharts shall be used to verify and document simulator compliance with the normal operations testing.
E. 1EST INSTRUCTIONS
- 1. Using the latest revision of the Byron Unit One General Procedures (BGP's),
perform the following evolutions:
- a. Plant startup f rom cold shutdown to hot standby. Use the cold S/D IC which enters BGP 100-1 at Step 1.
- b. Reactor startup to 100% power. Use the BOL, hot standby IC which enters BGP 100-2 at Step 1.
- 1) This evolution includes turbine startup, generator synchronization and load cht.nges.
- 2) Startup survelliances may be documented in accordance with Surveillance Test.
- c. Reactor trip from full power followed by recovery to full power. Use the BOL, 100% power, equilibrium xenon IC to start the evolution (Unit 2 BGP may be used).
O 1) This evolution includes operations at hot standby, turbine startup.
generator synchronization, and load changes.
(9YP:0NSlH 113/61 08/22/91)
i BYRON SlHULATOR )'
ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 BYRON SlHJLATOR NORMAL OPERATIONS TEST (continued)
- d. Plant shutdown from full power to hot standby and cooldown to cold shutdown. Use the BOL, 100% power, equilibrium xenon IC and enter BGP 100-4 at Step 1.
- 1) This evolution includes operations at hot standby, load changes, and shutdown operations with less than full reactor coolant flow.
NOIES
- 1. ' tartup and power operations with less than full reactor coolant flow are not performed since only
- full reactor flow critical operation is allowed *
- at Byron Stations.. *
- 2. Operator conducted surveillance testing on safety
- related equipment or systems, plant heat balance *
- and shutdown margin determination are addressed
- in the Simulator Surveillance Testing Procedure.
- Heasurements of reactivity coefficients and
- 3.
p control rod worth'will not be performed since g
- thest 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.
- c. t ...
.i v. .i t y c. a...
.l c. u. .l a. t i o.. n. . .( T. e.. c. h. . S....
t a. f. f. . f. u. n. c t. .
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 of nature.
3.. The simulator shall not fail 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 Byron Unit One would not cause an alarm or automatic action.
G. DOCUMENTATION
- 1. Retain the flowcharts to document simulator compliance.
(v (BYPONSlH 113/62 08/22/91)
O O O 1P,GP 100-1T1 ENTER ItEVISION 2 DATE 3l etc)1 C
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1BGP 100-7T1 Revision 1 1BGP 100-7T1 REI ERENCE REACTIVITY DATA WORKSitEET O
. e***enenesseeeeeeeeeeeeeeeeenesenemoneenene nenne nenemannenee a g e
- This worksheet will be retained as plant documentation. *
- DO NOT DISCARD. forward completed form to the Operating a
- Staff when no longer required on shift for reference.
- ennemmeneeeeeeeeeeeeeeeeeeeeeeeeemene ..e**enaneaeamennenenennen 1.a. Shutdown Date: 5' il #37 Shutdown Tirrst M2 1.b. Control Bank at steps, a 1.c. Insertee Control Bank North l (From BCB-1, rigure 12): (-) O pem
- 1.d C;itical Boron Concentration f rom (CIRCLE mode of analysis used):
Just prior to a planned shutdown, 2). Just af ter a reactor trip, or 3). Calculated by the Qualified Huclear Engineer (Attach calculations, logs, point history used)
CB= ppm Sample or Calculated Time / Dates / ,
i.e. Power level prior to shutdown f rom (CIRCLE it formation source used):
1). NR-45 2). 1BOS NR-1 Computers Type / Program C M d Pt M A M *m Cond*4aN Power prior to :,hutdown / Oo. 3 g 1.f. Total Power Defect f rom (CIRCLE information source used):
1). BCB-1, Tigure 417A 2). BCB-1, Table 2-1 Total Power Defeett (-) / IOE' pem AFPROVED FEB 151990 t (1403V/0111V/011590) B.O.S.R.
1 1
FEB 151990 1BGP 100-771 B.O.S.R. RtrtRenCc istACriv1Tr oATA wCRKSutrT
/~' (continued) k 1.g. RECORD accumulatto core average burnup at shutdown from (CIRCLE information source used):
, 1BOS NR-1 2). Computers Type / Program Core Average Burnups h ETPH 1.h. Equivalent Power for Samarium Calculation from (CIRCLE information source used):
IBOS NR-1 2). Computer Type / Program:
Sm Eq. PWR = Unweighted average power over 5 days (120 hrs) prior to shutdown Sm Eq. PWR = f00 %
1.1. Determine the Equivalent Power for Xenon Calculation from (CIRCLE infor1mation st,arce used):
1 180S NR-1 2). Computer; Type / Program Hours Average Hou'sr Average Prior to Power Multiplier Product Prior to Power Multiplier Product Shutdown (%) Ehutdown f%)
O to 1 N x6 a 18 to 19 b x2 =
1 to 2 '
x5 = 19 to 20 i x2 =
2 to 3 z5 = 20 to 21 i x2 =
l x2 3 to 4 ! x5 = 21 to 22 =
' x2 =
4 to 5 x4 = 22 to 23 i
' x2 5 to 6 x4 = 23 to 24 8
=
' x4 = 24 to 25 8 x2 =
6 to 7 '
7 to 8 '
x4 = 25 to 26 x1 =
8 to 9 x4 = 26 to 27 x1 =
' x1 9 to 10 x3 = 27 to 28 =
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 r1 =
14 to 15 _
x3 = . 32 to 33 x1 =
15 to 16 m3 = 33 to 34 x1 =
16 to 17 x2 = 34 to 35 x1 =
17 to 18 T x2 = 35 to 36 4 x1 =
TOTAT. n M OC (1403V/0111V/011590)
1BGP 100-771 Revision 1 1BGP 100-7T1
- REFERENCE REACTIVITY DATA WORKSHEET (continued) 1.1 (continued)
Equivalent Power for Xenon a _ Int.aL. = OIC 91 91 Ke Eq. FWRt IDO %
Remarkts V IMP RS 9 hA% $6 LTulbl$$0 dd
... .. ... .............. ..ee*......... .................... ..
11Q1T
- II this procedure is perfor:aed by an NSO, 211Q1 this *
- procedure shall be reviewed by a Qualified Nuclear *
- Engineers or, II this procedure is performed by a Quallfled *
- Nuclear Engineer, IllD! this procedure shall be reviewed *
- by the NSO. Typically, this procedure should be prepared *
- by the Technical Stef f Nuclear Group.
- e.............................................. ......... ...... ,
Perfcrmed by 4& / 3r I Qualified Nuclear Engineer)
Name Dat Reviewed by: / (NSO, Qualified Nuclear Engineer)
Hame Date ,
SRO: /
Name Date APPROVED FEB 151990 (rinal) B.O.S.R.
h (1403V/0111V/013590)
O O O IIbt' 100-5TI REVISION 3 ENTER O SE
%? 1BGP 100-5 Flowchart c PREREQUISITES Exceptions D PRECAUTIONS E U WTAT M S AND ACTIONS Initial each ROO suo -
p (p - g ggg
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APHtoVED FEB ?. 31969
- a. o c: 9
O O O IBGP 100-5TI REVISION 3 1BGP 100-5 Flowchart e em acs , cme ",a m ,
Exceptions VAcuu N g tv N W 64tA t..
Initial each ROO suo -
LETDOWN 4I RH RH SX SUCT MODE RCS RCS SI MODE RH SI/ C V 212*F 4-5 AF PZR CV PZR CC 1BOS LETDOWN VLVS PRESS,, P- 11 < ACCUM 3-4 l
aLEVEL 38 39 40 41 42 43 44 -
gp 28 30 31 34 36 4
,, r .< - -
h PORV b Q4 U
=
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d APPROVED FEB 2 31989
-2_ B.O.S.R.
Q O O IBGP1004TI REVISION 3 1BGP 100-5 Flowchart Exceptions le uov mm c 9 coci . A u ~ i e 7 a MckG &
(
e.
v
- s.,. ,._______,
19 %9 . REDUCED s - _ - _ _ _,_ - _ _ - _,
______ __L___ SID '
((/'2 e
' RCS l WVEPRORYll DRAN
@ts l CHEM l scuo CiD RCP PRESS TRANNG es RCS l HVAC l
- . Cs . Ano , nCP .. ,'
a CS 57 58 59 60-61 62 63 C P E 64 53 54 55 56 l
i GS ! MS S/G F W Pp C&CR
! OG VACUUM m<E ct<co
- b. g 9 ,,
,, lgl 9 4 DA" V V V V l sE Ir(or EXIT l
' APPROVED (FINAL ) Qg g } g,g B.O.S.R.
1BCS 4.9.1.1-1 Revision 51 REACTOR 0;CLANT SYST O.
k PRESSURE / TEMPERATURE LIMIT SURVEILLANCE A. STATEMr.i CF AFPLICA3!L!TY:
This procedure applies to the verification that RCS pressure and temperature are within limits in all modes during:
- 1. Heatup (RCS)
- 2. Cooldown (RCS)
- 3. Inservice Leak Testing (applies to RCS pressure / temperature limits only)
- 4. Hydrostatic Testing (applies to RCS pressure / temperature limits only)
B.
REFERENCES:
- 2. BGP 100-1 Plant Heatup
- 3. BGP 100-5 Plant Shutdown Cooldown b C. PREREQUISITES:
- 1. Receive permission 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. PRIrAtTfIONS:
- 1. None E. LIMITATIONS AND ACTIONS _
l.
As stated in Technical Specifications Limiting Condition for Operation (LCO) 3.4.9.1.
- 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 4.9.1-la.
for RCS heatup
- 3. The limits of Byron General Operating Procedures (BGP) and cooldown are a maximum rate of 50'F/hr (Admin. Limit) gWB@ APPROVED Q AUG 141985 B. O. S. R.
~
(2534P)
l 1BOS 4.9.1.'.-l l Revision $1 f
/] F. MM M PCCY:
U 1. direr the starting date on the Datt Sheet (D-2). l
- 2. Place an X in section 2 of the Data Sheet for the condition (s) that initiated this procedure.
........................................................ a
- NC7rE
- Steps 3 through 8 must be performed at least once *
- per 30 minutes during conditions requiring this *
- procedure. For ease in determining that the
- Acceptance Criteria has been met. the data should be **
- taken at the same ti.:.e interval for every reading l
- 3. DTIER in the First Line of Columns 3, 4. and 5 the intial time, RCS pressure using step 4 criterra and RCS Temp using Step 5 criteria.
ENTER the highest indicated RCS pressure from any of the following. l 4.
An operable Pressuriser channel. RCS Loop A Wide Range, RCS Loop C Wide Range or an RCS Low Range pressure channel in column 4. Use the following list to verify that the chart recorder for the selected pressure is recording.
Pressure Channel Chart Recorder
/~)
- a. IPI-455A IPI-456 IPR-455 b.
- c. IPI-457 1PR-455
- d. 1PI-458 1PR-403
- e. IPI-403/403A 1PR-403
- f. IPI-405/405A none
- g. IPI-RCO21 I
- 5. ENTER the reading on the lowest operable RCS Cold Leg Ada Range tenperature 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 1TR ~13B
- a. ITI-413B 1TR-413B
- b. ITI-423B 1TR-433B
- c. 1TI-433B PPROVEI ITR-433B
~
- d. ITI-443B AUG 141985
-2 (2534P) 8. O. S. R. ,
1
15CS 4.9.1.1-1 .
Revision $1 l
- 6. - RECORD the Time, TCS pressurt. and 4*-~ :rst.rt usin; step 4 and 5
.;nutes.
criteria at intervals no greater tr.1.:
~
I CALCULATE the Temperature change ry :. 4 To11owing:
_7 .
T re et:ur te ; ('T)
Temp Change : Present te c t'? -
Enter Temp Change in column * :n . ata Sheet.
Negative change indicates- coo
- i-wnr..
positive change indicates hea:.g.
followin; method: l
- 8. CALCJLATE-the heatup or cooldown by .r.r
-Temp Changa (Col.7) x 60 min Elapsed Time (mins) - hr.
-Enter Rate in Colume 8.
. VERITY RCS temperature and pressure t re within the limits of ' l-9.
Technical Specifications Figures 1.i . i. or 3.4-3a as appropriate. . j In the case of a cooldown, use -..t rate calculated in step 6 to a.
select the appropriate limit :. . e en Tigure 3.4-34.
- b. Limit lines for cooldown ' rates :sts: ween _ those presented in Figure-
- 3.4-3a may be obtained by in a ;c -lation, c.. - If temperature and pressure an wvithin limits- then place intials
'in column 9 of the Data-Sheet.
- d. If - performing a RCS Inservi:a *.4a t.,: Tes or RCS t'ydrostatic Test-above the-limit curves for hear;; _ or cooldown then verify that y.
' the . limit of 10*F temperature : .asange in any 1-hour period is not exceeded and place initials i: ::.:kmn 9.
USE comments column to provide ad.d.it: onal information if necessary. -l l
,10.
' Such information may include exp'.a.:n: :.:ns for large or small changes / variations for system tec enr. ure' or pressure
- ' . . PERFCTd the cal ulations at _ leas
- .: : per l' -inutes while ene of [
the following conditions exists:
- a. RCS Heatup
'b. RCS Cooldown
- c. RCS Inservice Leak Testing
- d. 'RCS Hydrostatic Testing
- 12. COMPLETE the Data Package Cover St.ai .- (D '.). ED AUG 14 $85 (2534P) B. O. S. R.
1BCS 4.9.1.; '.
l Revision 51 G. ACCEPTNCE CRI*ER! A:
- 1. RCS pressure and temperature are within the limits shown on Technical Specification Figures 3.4-2a and 3.4-3a with:
- a. A maximum heatup of '.00*T in any 1-hour period.
I b. A maximum cooldown of 100*F in any 1-hour pariod, and
- c. A maximum temperature change of less than or equal to 10*F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
O e
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c t 1BOS 4.9.2-1 Revision 51 PRESSL*R::'ER O TEMPERATURE LIMIT SURVEILLANCE A. STATEMDIT OF APPL CABILITY:
This procedure applies to the verification that Pressurizer temperature and spray water temperature differential are within limits in all modes during system heatup or cooldown.
B. REFERDICES:
- 2. BGP 100-1 plant Heatup
- 3. BGP 100-5 Plant Shutdown Cooldown C. PREREQUISITES:
- 1. Receive permission from the Shift Engineer or designated SRO licensed assistant prior to performing this surveillance by having the Da:a Package Cover Sheet (D-1), signed and dated.
D. PREAUTIONS:
- 1. None E. LIMITATIONS AND ACTIONS:
- 1. As stated in Technical Specifier.tions 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 heutup of SC'F/hr (Ad.m n. Limit) and ,
- b. A maximum cooldown of 100*F/hr (Admin. Limit)
$ T5Y O aeesoveo AU314 $85 ,
(4990P) o l
1BOS 4.9.2-1 Revision $1 F. tiAIN BODY:
I
- 1. ENTER 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 n e ne n e n en n em an ne ne n e n em a n n e e n e e * **e e e e e e e e e e ee e e n e n **
- a g .
e n
- Steps 3 through 8 must be perforined at least once *
- per 30 minutes during conditions requiring this *
- procedure. For ease in determining that the *
- Acceptance Criteria has been met, the data should *
- be taken on the same minute of each succeeding hour.*
- een neenem one**e n e....nonn ee e e enmen ne ne ***enene***ene e.
- 3. ENTER the date and time in column 3 of the Data Sheet.
- 4. ENTER the resding of the Pressuriser water . temperature channel (1T1-453) in column 4 of the Data Sheet.
- 5. RECORD the rate of Pressurizer temperature change ! rom the previous entry as follows:
- a. CALCULATE:
Rate ('F/hr) e Present tenp ('r) - Previous temp (*F) s jMD Elapsed time (min) hr Negative-rate indicates cooldo*<n.
Positive rate indicates heatup.
- b. RECORD the rate of temperature change ('F/hr) in column 5 of the Data Sheet, ene***emeeeeeeeeeeeeeeemenene ****e ........e. .............
tlQII *
- If only auxiliary spray is being used then skip steps
- 6 through 8 and enter N/ A in columns 6 through 8 of the *
- Data Sheet. a meneenamenenneneseenanmenennenemmenemenenemonemanneenneeeene
- 6. RECORD the lowest kCS cold leg wide range temp (*F) of the operating loops providing pressuriser spray (ITI-433B or 1TI-443D) in column 6 of the Data Sheet.
- 7. RECORD the temp.('F) from pressuriser vapor space, 17I-454, in column 7 of the Data Sheet.
APPROVED
-2 AUS1 4 BBS (4990P)
B. O. S. R.
1B05.4.9.2-1 Revision 51 ft 8.. DETERMINE the spray water temperature differential using the formula in this step and record it in column 8 of the Data Sheet.
Pressuriser Temp. (1TI-454) - Cold Leg Temp. (1T1-4338 or 171-4438)-
{-: = Spray Water Temp. Diff.
- 9. REPEAT steps'3 through 8 at least once per 30 minutes while one of l the following conditions exists:
i
. Pressuriser Heatup
- b. Pressuriser Cooldown
- 10. COMPLETE the Data Package Cover Sheet (D-1).
l G. ACCEPTANCE CRITERIA: ,
- 1. Pressuriser temperature is limited to:
- a. A maximum heatup of 100'F in any 1-hour period, and b.: A maximum cooldown of 200*F in any 1-hour period.
- c. A maximum spray water temperature differential of 320*F. ,
"[. .
- v
.I APPR0VED ng 803 1 4 1985
_3 s. c. s. =
(4990P)
APPROVED IBOS 4.9.2-1 Revision 51 l
[gj * } 4 $j$
// B.O.S.P ACTUAL REQUIRED ACTUAL KEQUIRED SPUAY WATER h/h/W 5. MTE RATE 6. COLD LEG 7. Fief 6URIZER 8. SPRAY WATER TEMP DIFF (*F) T m P DIFF
.,DATE 4. PRESSURIZER TDiP (*F) VAPOR TEMP (*F)
WATER TDiP (*F) (*F/IIR) (* F/f tR)
TIME OE ?
K47 66 3 ( < Limit
!"!'"BCooldown fS7 # < 320*F O 86 3 t < 320*F t I bd3 d < Lamt B d
< Limit A fleatup_ g.
/ // < umit B Cooldown S25 If(fo /35 < 320 r CfD f, (f55 e
< Limit A Ileatup t < 320*F L < Limit B Cooldown
< Limit A Ileatup_
< umit B C-id-n 46 7 &zz Is7 e < 320 r ce47 9 zo e
< Limit A Ileattf ,,
3(cT ' t < Limit B CooldoN lb 5 hO Z63 t < 320*r
~(340 < Limit A fleatup_
< Limit B Cooldown (65 dlO [.ET # < 320*r (KT .) N 30 #
< Limit A Ileatup hk 310 ( 320*F fdlO h 'v0 t < Limit B Cooldown [69 t .
- Limit A Ileatop
< Limit B Cooldown [6 2h ( < 320*F__
[Ir2h 3h O d
< Limit A Ileatup d < 320'r
[4 h d A pctilt [ t < Limit B Cooldown
< Limit A fieatup h d < Limit B Cooldown (65 3T 7. o T s < 320 r lb/O
< Limit A IIeatup _
y /
) t < 320*F
/d32- 3M M7 e < Limit B Cooldown [ 5
?W 20 i --
g a /FT E?h YU g < 320 7 Z O ( 320'F
( < Limit B [ f
[ < Limit A Ileatup d < 320*r
- < Limit B Cooldown
< Limit A IIeatup (, < 320*F__
~
t < Limit B Cooldown
< Limit A Ileatup f ( 320'F_
( < Limit B Cooldown
< Limit A Ileatup_
- _< 320*F t < Limit B Cooldown D-3 (4990P)
FINAL L.________ l
. . IBOS 4.9.2-1 AppHOVED Revision 51 IsuJ 1 4 2 5
- 13. O. S. P PRESSURIZER T mPERATURE LIMIT SURVEILLANCE
~
- 1. TIME f Z. L DATE 3/ / ) /
LIMITS:
- 2. APPLICABILITY: ADMIN < 50*F/HR
- a. F PZR Heatup ,X a. T/S < 100*F/Hr
- b. T/S < 200*F/lle ADMIN < 100*F/1tR MEGIIRED
- b. F PZR Cooldown ACTUAL ACTUAL REQUIRED
- 7. PF1 5 URIZER 8. SPRAY WATER SFRAY WAlh
- 5. RATE RATE 6. COLD LEG TD4P DIFF
- 3. DATE 4. PRESSURIZER TD4P (*F) VAPOR TD4P (*F) TD4P DIFF (*F)
TIME WATER TDiP (*F) (*F/HR) _ (*F/HR) '7)
< Limit A Heatup Try'a / .
I8 DO I ( < 320*F
< Limit B Cooldown dr /. t -
j
< Limit A Heatup f e / ,9y 7 '7 O. f < 320*F C L,
- ,,5 p~~ d
- < Limit B Cooldown '
0 l < Limit A Heatup .
f ,2O
'/ '3 -[. t < 320*F 50 [- [ O bU g < Limit B Cooldown g Q)
< Limit A Heatup jyp ' > g/) _
' O g ( 320*F g 9'7- 9 f e. ,
< Limit B Cooldown LUd / d
! f VE '
f ( 320*F T#I 27I ( mt B ur ld"R^"**;",",.n 2zr z7o ?'r o, < 3,o.,
yw z vv ,
yc @
-gp s
< Limit A Ileatup
' '> < f ( 320*F g
/~ C ' _.j d ( < Limit E Cooldown
< Limit A 11eatup < 320*F
(
, f 'e 11 3 J& . J'/ r.) ,Nr'7/A ( < Limit B Cooldc E e $
>)p
< Limit A Heatup f _' '
'" g ( 320*F 4-,
gMee
,'l 72C ( < Limit B Cooldown P _J N lt 'C O [ t < B down W 5* d .E e < 320*F
< Limit A Ileatup
( < 320*F t < Limit B Cooldown
< Limit A Ileatup f ( 320*F
( < Limit B Cooldown
< Limit A Heatup
( < 320*F
( < Limit B Cooldown
< Limit A Heatup < 320*F
(
t < Limit B Cool _dcun
< Limit A Ifeatup g < 320*F
( < Lisait B Cool _down ATTACll ADDITIONAL Sittra.5 (D-3) as needed.
~ D-2 n
Q av E & p ruast&fx k .% s (4990P) .
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 O BYRON SIMULATOR SURVEILLANCE TESTS 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 (BOS) were performed on the Simulator. The results are as follows:
- a. Shutdown Margin Surveillance Accepted
- b. RCS Minimum Temperature for Criticality Surveillance Accepted
- c. Movable Control Assemblies Monthly Surveillance Accepted
- d. Shutdown Rod Insertion Limit During Approach to Accepted Criticality Surveillance
- e. Quadrant Power Tilt Ratio Surveillance Accepted
- f. Calorimetric Calculation Daily Surveillance
- g. Turbine Throttle, Governor, Reheat and Intercept Accepted Valve Monthly Surveillance
- h. RCS Controlled Leakage Monthly Surveillance Accepted
- 1. RCS Hater Inventory Balance 72 Hour Surveillance Accepted
- j. Reactor Containment fan Cooler Monthly Surveillance Accepted
- k. CC System Valve Lineup to Safety Related Equipment Accepted Monthly Surveillance
- 1. CC Pump Operability Monthly Surveillance Accepted
- m. lA D/G Operability Monthly Surveillance Accepted
- n. 18 D/G Operability Monthly Surveillance Accepted
- o. DC Bus Train Operability Heekly Surveillance Accepted O \,
(BYRONSIM 113/63 08/22/91)
I
BYRON SIHULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITI AL REPORT, SEPTEMBC'1,1991 BYRON SIHULATOR SURVEILLAHCE TESTIl4G A. PURPOSE The purpose of this procedure is to:
Verify that cperator 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.
- 2. Byron Unit One Surveillance Procedures.
- 3. PTAO-105: Simulator Certification Reporting and Testing Program C. SURVEILLANCE SELECTION CRITERIA The selection criteria used to meet ANSI /ANS-3.5-1985, section 3.1.l(10) requirements (simulator surveillance testing) are:
- 1. Surveillance is safety-related.
- 2. Surveillance frequency is monthly or less. .
- 3. Surveillance contains control room indications or requires control board manipulations.
D. INITIAL CONDITIONS
- 1. Use the BOL,1007. power, equilibrium xenon initial condition (IC) unless a lower power level is noted in the surveillance procedure.
E. DATA COLLECTION
- 1. The Control Room data required by each surveillance procedure shail be collected.
- 2. Data that is obtained from outside the Contro1 Room shall be obtained, if available, from the simulator data pool variables. If the data is not available, mark that step N/A, (BYRONSIM 113/64 08/22/91)
l l BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIflCA110N REPORT INITIAL REPORT, SEPTEMBER, 1991 O BYRON SIMULATOR SURVEILLANCE TESTING (continued)
F. TEST INSTRUCTIONS
- 1. Ensure that the simulator meets the initial condition as specified in Section D.
HOTE
- The simulator has the capability to conduct the
- shiftly/ daily surveillances, various channel check *
- surveillances and the system lineup surveillances. **
. . . Th e s e.surveillance
. . .. . . . . . . . . . . . . . will
- s. . . no t . b e p e r f o r me d .
2, Using the latest revinton of the Byron Unit One Surveillances (BOS's),
perform the following procedures:
- a. 1805 1.1.1.1.e-1: Shutdown Margin Surveillance
- b. 1805 1.1.4.a-1: RCS Minimum Temperature for Criticality Surveillance 6O c. 1805 1.3.1.2-1: Movable Control Assemblies Monthly Surveillance
- d. IBOS 1.3.5-1: Shutdown Rod Insertion Limit During Approach to Criticality Surveillance
- e. IBOS 2.4.1.a-1; Quadrant Power Tilt Ratto Surveillance
- f. 1BOS 3.1.1-2: Calorimetric Calculation Daily Surveillance
- g. 1805 3.4.2.a-1: Turbine Throttle, Governor, Reheat and Intercept Valve Monthly Surveillance
- h. IBOS 4.6.2.1.c-l: RCS Controlled Leakage Monthly Surveillance
- 1. 1805 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. 1805 7.3.1-1: CC System Valve Lineup to Safety Related Equipment Monthly Surveillance
- 1. IBOS 7.3.2.a-1: CC Pump Operability Monthly Surveillance
- m. 1805 8.1.1.2.a-1: 1A D/G Operability Monthly Surveillance
- n. IBOS 8.1.1.2.a-2: IB D/G Operability Monthly Surveillance
- o. 1805 8.2.1.1-1: DC Bus Train. Operability Heekly Surveillance O
(BYRONSIM 113/6S 08/22/91)
BYRON SIMULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 BYRON SIMULATOR SURVEILLANCE TESTING (continued)
G. ACCEPTANCE CRITERIA
- 1. Each surveillance can be performed satisfactorily using installed control board instrumentation or variables avalleble on the simulator data pool snd 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. The simulator shall not fail 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 Byron Unit One would not cause an alarm or automatic action.
O H. 00CUMENTAT. ION
- 1. Retain the surveillance procedures.
O .
(BYRONSIM 113/66 08/22/91)
1BOS 1.1.1.1.e.1 Revision 7 UNIT ONE
!.i?TIDONN MARGIN SURVEILLANCE A. STATEMENT OF APPLIC ABILl'III
- 1. This procedure applies to the verification of Shutdown Margin in Mode 2 when the reactor is not critical and MODES 3, 4 and 5.
- a. After detection of an inoperable control rod,
- b. Daily in Modes 3, 4, and 5.
B. REFERENCES 1
- 1. Technical Specifications (Su veillance Requirements):
- a. 4.1.1.1.1.a
- b. 4.1.1.1.1.e
- c. 4.1.1.2.a ,
- d. 4.1.1.2.b
- 2. Station Procedures
- a. BCB-1, Byron Curve Book - Unit One,
- b. 1BGP 100-7-91, Reference Reactivity Data Worksheet,
- c. 1BOS NR-1, Power History Hourly Surveillance.
- d. 1BOS 1.1.1-la, LCOAR - Boration Control - SDM - Tave > 200'F.
- e. 1BOS 1.1.2-la, LCOAR - Reactivity Control - SDM - Tave 1 200'r.
C. PREREOUISITESt Receive permission from the Shift Engineer or designated SRO licensed assistant prior to performing the surveillance by having the Data Package Cover Sheet signed and dated.
1*
(h APPROVED b laR 2 31989 B.O.S.R.
(0210V/0023V/022489)
IBOS 1.1.1.1.e.1 Revision 7 O D. EREIAUTICats.1 None.
E. L1HITAT10NS 1yD ACTIONS 1
- 1. As stated in Technical Specification Limiting Condition for 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 surveillance, IMMEDIATELY notify the Shift Engineer or designated S3011eensed assistant to initiate LCOAR procedure 1BOS 1.1.1-la or IBOS 1.1.2-la as applicable.
T. MAIN BODYt
- 1. Present Conditions senseeeeeeeeeeeeen *****eneeeemenneaeaeeeen ...... ee.......... ,
a e g
- Use Reference Reactivity Data worksheet for power history *
- prior to shutdown - R.R.D. 1BGP 100-771. Initial as *
- applicable.
eeeeeeeeeen ne eene eeeeeeeeeeeeeeeeeeeeeeeeeeeemme ............
,O eeeeeeeeee****eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen. ............ .
e m e e Dual verification of this surveillance will be. performed *
- by an SRO upon NSO completion.
e..... .. .. ... ..... . . .......... ... e e e e e e e e e e e e e e e e e e m e n e n e . . . . ...
- a. RECORD date 'and time of calculation.
- b. RECORD core average burnup Crom 1BOS NR-1 (multiply the number of ETPR by the ETPH to MWD /MTU conversion factor for this cycle as found in the note on BCB-1 Table 1-6).
- c. RECORD core average temperature.
- d. RECORD time sinco plant shutdown for menon/ samarium calculations (T .1. a Date/ Time - R.R.D Step T .1.a) ,
- e. RECORD power level prior to shutdown (R.R.D. Step T.1.c).
- f. RECORD the present boron concentration.
- 2. Minimum Boron Concentraticu
- a. RECORD Hinimum Boron Concentration from BCB-1 Table 1-1 at temperature from step T.1.c and burnup from step T.1.b.
APPROVED
_2 MAR 2 31989 1 (0210V/0023V/022489) 8.O.S.R.
I 1BOS 1.1.1.1.e.1 Revision 7
/ b. SUBTRACT the present boron concentration as recorded in Stop k-s T.1.f f rom the minimum boron concentration recorded in Step T.2.a.
- c. If the result of the subtraction in Step r.2.b is negative, the Technical Specification SDM requirement is satisfied, provided not more than 1 rod is stuck out of the core, and no further calculation is required. If the result is sero or positive, continue with Step F.3.
emeneeeeeee e e ee e e nesee eeeeeeeno e nes e eee ee e ee ee eee e e eee ee e ee e eee n a ggpg a e
- 1).The minimum boron concentrations in Table 1-1 are
- calculated assuming that no menon or samarium are present*
- in the core, and that all rods are inserted minus ths *
- highest worth RCCA. *
- 2).A fe.ctor of safety (100 ppm) has been added to the *
- miulmum boron concentrations calculated in Table 1-1 *
- to account for calculational uncertainty. e e 3). Included in the table are the changes in the total *
- temperature defect and rodworth associated with *
- changes in tempereture and burnup. *
- 4).No Further calculatians are required: *
- a. *If no corrections to account for menon and samarium *
- are required and, *
- b. if the SDH for the conditions in F.1 above is 1300 *
/N
- pcm, or 1000 pcm for Mode 5, and, *
(s-
- c. if no more than on RCCA is stuck out of the core and,*
- d. the present boron concentration in T.1.f is greater *
- than the minimum taron co'ncentration in F.2.a.
- eneeeeeeeeeeeeeeeeemennae,eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee
- 3. Xenon Worth Correction (b or c)
- a. RECOLD power level prior to trip (IBGP 100-7T1 RRD step F.1.e)
- b. RECORD worth of zenon present from BCB-1 Table 1-2 or BCB-1 Figure 8C (based on the time f rom step F.1.d and power f rom step T.1.e).
1). Table 1-2 and Figure 8C are total senon worth as a f unction of equilibrium power level and time f ollowing a plant trip.
2). Read the zenon directly f rom the table or the figure and enter the value onto the data sheet.
- c. RECORD xenon worth correction f rom BCB-1 Table 1-2 or BCB-1 Tigure 8C (based on the time f rom step r.l.d and equivalent power).
ALPP Fic)\/ ECC) 1). The Equivalent power for Xenon Calculations portion of the Reference Reactivity Data worksheet from 1BGP 100 771 is pgg g 3 jggg used in conjunction with BCB-1 Figure 8C or Table 1-2 11
(( the reactor was not at an equilibrium condition with
Pect to menon prior to ae trip.
E3. C). 55. fR.
(0210V/0023V/022489)
1BOS 1.1.1.1.e.1 Revision 7 (N
/
\,,] _
Samarium Worth Correction eenneeeee.. e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen e NOTE e
- When the reactor conditions before the shutdown are at
- present can be read directly from the table. *
- If the reactor is not at equilibrium at the time of *
- ehutdown, the average power over the previous 5 days should *
- be used to rent the table. Samarium entractions need not *
- be accounted for until core average burnup is at least *
- - 1000 MWD /HTU.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- a. RECORD average power level prior to shutdown (average over previous 5 days).
- b. Samarium 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. SDN Requirement Correction
- a. RECORD SDH requirement correction.
1). If the core average temperature from step r.l.c is 1 200'r enter -120 pcm.
- %~ / 2). If the core average temperature f rom step T.1.c is > 200'r
, enter C. ,
eeneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenneneneeeeeee*e e ggg - e
- The minimum boron concentration in Step r.2.a is calculated *
- assuming all rods are inserted minus the highest worth RCCA.*
eeeeeeeeeeeeeeeeeeeeeeeee**eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- 6. Immovable /Untrippable Rod Correction.
a.- RECORD the number of known immovable and/or untrippable control l
rods and subtract 1.
1-een......eeeeeeeee eneeeeeeeeeeeeeenmenneesee eeeemenemonenemone
- NOTE *
- If step r.6.a is i sero then enter zero in step r 6.b.
- l e....eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
?~
t- b. Multiply the number of- immovable and/or untrippable control rods 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 APPROVED n
g MAR 2 31989 B.O.S.R.
(0210V/0023V/022489)
1BOS 1.1.1.1.e-1 Revision 7
- 7. Corrected MinLawn Boron Concentration Calculation (A)
- a. Total Konon Worth Correction (1 or 2).
1). RECORD the value f rom T.3.b f or stable conditions prior to shutdown.
2). RECORD the value from F.3.c for unstable conditions prior to shutdown.
- b. Total Samarium Worth Correction 1). RECORD the value used in step T.4.b
- c. For total Xenon and Samarium Correction add the total Xenon worth f rom step F.7.a and the total Samarium worth f rom step F.7.b and record on data sheet.
- d. Integral Boron Worth 1). Determine the integral boron worth f rom BCB-1 Table 1-5 at the temperature recorded in step T.1.c and the boron ,
concentration from step F.2.a.
- e. RECORD the Correction Factor for Boron ef fects on Kenon and
,- Samarium worth f rom BCB-1, Figure 8B, at the boron worth f rom (s F.7.d.
- f. Total reactivity correction times the reactivity multiplier.
1). Multiply the value obtained f rom step F.7.c by the value obtained f rom step F.7.e and record on data sheet.
- g. Total Reactivity Correction 1). Add step F.5.a F.6.b and step F.7.f and record on data sheet.
- h. Corrected minimum Boron concentration integral boror worth.
1). Obtain the value f rom step F.7.d and subtract the value f rom step T.7 g and record on data sheet.
enneme**ee... wee..........nenne ........ ................ **e ..
. g a
- If the result of the subtraction in Step F.7.h is positive, *
- use O ppm boron concentration i.. Step r.7.1.
- emenennenseeen............... **e.......... a .. ...............
- 1. Corrected Minimum Boron Concentration.
1). Using the boron worth f rom step F.7.h and the temperature
(-'s MAR 2 31989 from step r.l.c, obtain the corrected mint um baron
\_-) concentration f rom BCB-1 Table 1-5 and record on data sheet.
B.O.S.R.
-s-(0210V/0023V/022489)
1BOS 1.1.1.1.e-1 Revision 7
- 8. Shutdown Margin Boron Requirement.
(
- a. Corrected minimum boron concentration f rom step F.7.1 minus present boron concentration from step T.1.f.
- b. If the result of the subtraction in step T.8.a is negative, the Technical Specification SDH requirement is satisfied, neeeeeeeeeeeeeeeeeeeene**eenemone**enemonee*********************
g a
- If the result of the subtraction in step F.B.a is positive,
- e
- IKKEDIATELY notify the Shift Engineer or designated SRO
- licensed assistant to initiate LCOAR 1905 1.1.1.-la nene e * *** e *** **** ****eeeeeeeeee**eeee e eeeee eeee e eeee***** ** **e e n G. ACCEPTANCE CRITERI A The actual boron concentration must be i the corrected minimum boron concentration as recorded in Step r.2.a or Step r.7.1.
O APPROVED MAR 2 31989 O (rinal)
B.O.S.R.
(0210V/0023V/022489)
1BOS 1.1.1.1.e-1 Revision 7
- UNIT WE SHUTDOWN MARGIN CALCULATIW SHEET UNIT bN[ DATE I TIME /6lE SHUTDOWN DATE 3 i TIME 00I 3 (R.R.D Step F.1.a)
- 1. PRESENT CWDITIWS eeeeeeeeeeeeeeeeeeeeeee. nnen....eeeeeeeeemenee ne......eeeeeene
- liCIE
- Use reference Reactivity Data Worksheet R.R.D 1BGP 100-7T1 *
- for power history prior to shutdown. Sign off each step as
- it is completed.
..... **e.........e**e s.......e****e.......e******** .........
eeeeeeeeeeemene**eeneenenamenene..............e** ........... ..
- tIDIE
- Dual verification of this surveillance will be performed *
- by an SRO upon NSO completion.
- eeeeee**ee *ee****eeeeeeeeeeeeeeeeeeeeeeemenemonemenene***e see
- a. Calculation fort Date #M Time /b / S neeeeeeeeeeeeeeeeeeeeee.....eeeeeeeeeeeeeeeeen....eeeeee****e*ee
- NCYrE *
[\
- Multiply the number of ETPH by the EFPH to HND/NTU *
- conversion factor for thin cycle as found in the note
- on BCB-1, Table 1-6. *
- eeeeeeeeeeeeeeee Aeneeeneen..................................
- b. Core Average Burnup O MWD /MTU
- c. Core Average Temperature M7 *F
- d. Time since plant shutdown for renon/ samarium calculations b brs
( F.1. a Date/ Time - R.R.D. Step F .1. a)
- e. Power level just prior to shutdown (R.R.D Stop F.1.e) i OIL 3 percent
- f. Present Boron Concentration A ppn
- 2. MINIMUM BORCN CCHCENTRATION
- a. Minimum Boron Concentration (BCB-1 Table 1-1) at temperature (F.1.c) and Burnup (F.1.b) 904 ppm
........eeen... e***ene ****** eene......... nemone e**e *******
- gggg a
- The value in (T.2.a) was conservatively calculated with no *
- xenon or samatlum and the maximum SDN of 1300 pcm is
- provided.
- e .............. nonne .....................................e**e O APPROVED V
\
-D2- MAR 2 31989 1 (0210V/0023V/030988)
B.O.S.R.
. . - ,u. m3 m mm. _ _ m -.2 4 _._-_2_ _ , . __.-.____m _-__1 _..vu . _ - _ _ .u__. .._
1805 1.1.1.' e-1 '
Fevision 1 O UNIT CHE V SHUTDOMW MAPGIN ..ALCULATICM SEEET (Continued)
~ 9 04- pp . 247 op . 57 pp ,
concentration Concentration from T.2.a from f.1.f I
- c. If the result of the subtraction in Step r.2.b is negative, and no more than 1 RCCA is stuck out of the core, then the 'lochnical Specification EDH requirement is satisfied and no further !
calculations are required. l
/ /_
NSO DATE SRO CATE
- d. If the result is sero or positivi continue to Step r.3.
- 1. XENCM WORTH CORR 9CTICN (b or c) e n 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... .....is .e e..... ...e *
- e n e e e e e e. "
IfD21
- If the plant is at or or,ar equilibrium with respect to son >n*
- before trip use T.3.a and T.3.b to calculete the menon worth *
- correction, otherwise use F.3.c. If the reactor was at *
- non-equ111 brawn conditions before trip then use BCB.1 Table *
,Q
- 1 2 or BCB-1 figure SC at an equivalent power determined * '
Q
- from the 1BGP 100-771 RRD performed after the tra .) *
- determine the menon correction and record in F.3.. * *
- ee4.e...............e*** ......eeeeeeeeeeeeeeee*** ne......... <
- a. Power level before trip $0 3 oorcent (RAD step r.l.e)
- b. Worth of sanon present (fron ;
BCB-1 Table 1-2 or rigure 9C)-
using Power (r.3.a) and time (r.l.d) ~'30I7 pcm
- c. Kenon worth correction 4 can
- 4. SAMA M UM WORTE CORRECTICM !
eseeeeeeeeeeeeeeeeeeeenoneeeeeeeeeeeeen eeeeeeeeeeeeeeeeeeeeeeee e utgg .
- Samarium corrections need not be act 'unted for until Core * '
- Average Burnup is at loset 1000 hvD/M 'J. *
$*eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenneenee, someteme**eneeneseenee
- a. -Average power level before trip (average over previous 5 days). __
M oorcent
- b. Samarlu n worth present (f rom APPROVED
( BCB-1 Table 1-4) based on power (T.4.a) and time (r.l.d) ~ b, pcm NAR 2 3 Oli i
-Ds. B.O.S.R.
(021ov/co23v/0309ee) -
. . ,_ - _. . . _ _ - ,e ,,. -_._,, , _ , _ - - . - , - _ . , . ,,.,,_..,_y ~y ., w, m- _ , . . . --, - - ,
, , , , , c...m., y
l 190S 1.1.1.1.e-1 Revision 7 ,
.i UNIT CNE SHUTDOMW MARGIN CALCULATION CREET (Continued) I
- l
! 5. SDM REQUIREMENT CORRECTIC'A
- a. SDM Requirement Correction '
((!! core average ttmperature (r.l.c) is 1 200'r enter .300 pcm, otherwise enter 0.)] O ocs
- 6. IMMOVABLE /UNTRIPPABLE ROD CORRECTICH 4
- a. Record the number of known immovab3e and/or untrappable control rode then subtract 1 O rods .1 =
I eneeseeeeeeeeeenenneeeeeeeeene**
)~ e grygg
- If Stop r.6.a is i sero then*
e
- enter sero in stop r.6.b.
- q enseeeeeeeeeeeeeeeeeeeeeeeeeeeee l b. Correctic.: for imunovable and/or 3
untrippable control rods 4
((r.6.a) cycle specific value of the predicted highest worth O stuch rod from the note on BCB-1, Table 1-.6) _. O (r.6.a)
,od, , ocmfrod e o ocm.
i l.
- 7. CORRECTED MINIMUM DOR (36 CCBICENTRATICM CALCULATICBI
- a. Total Kenon Worth Correction ,,3 (r.3.b) or (r.3.c) pen 4
- b. Total Samarium- Worth Correction (r.4.b)
~
2 oca
- d. Integral Boron Worth (from BCB.1 Table 1 5) at _ cy temperature (r.l.c) and boron- yt/* -)/t/Cl concentration (r.2.a) ~~ O 5 W ocm
- e. Correction factor for. Boron O ._
effects on Xenon and Samarium l vorth (BCs-1 rigure 88) at APPROVED Boron Worth from T.7.d.
MAR 2 31969 g f. Total Reactivity Correct!on U .
times the Reactivity Multiplier B.O.S.R.
.[(r.7.c) : (r.7.e))
- ?V/'4 com x .9 (correction ,33y factor) oca
-D4-(0210V/0023V/030988)
W 190S 1.1.1.1.e.1 Revision 7 UNIT ONE i
SHUTDOWN MARGIN CALCULATICH SMEET (Continued) 9 Total teactivity Correction l
Itr.$.a) e (r.6.b) e (r.7.f)]
O pem e C _pem e ~ 37l f pem . ~ 33Il pcm {
- h. h Corrected Minimum Boron !
Concentration integral baron worth ((r.7.d) - (r.7.g)] ~ g p 479l
. , p.,
- m e,em . - Mil oc. .
s(> pc.e i
"918 dos ee n e K.4 eeeeeeeeeeeeeeeeeeeeeeeen.e.ne.nomeamen.e.neen.***...ees a
gggg . *
- {
If the results of the subtraction in Step r.7.h is positive.*
use O pp boron concentration in Step r.7.1. e neeeeeeeeeeeeeeeeeeeeeee**eneeeeeee**enennee**eeeeeeeeee****enen -;
- 1. Corrected Minimum Boron Concentration (from BCB-1 Table 1 5) corresponding to boron worth (T.7.h) and temperature g y &!f" 7q 9 g (r.l.c) ~J*--' ppm .
l
- 8. Shutdown Margin boron REQUIREMENT i Corrected mlalmum boron (T.7.1) minus actual boron concentration (r.l.t) = Shutdown boron i
G3A (r.7.1) pp R47 ( r.1. f ) pp .~ 3 I 3 _pp t
, 64 / '$fH f91 /
NSO Date SRO Date eneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene e
ggg a If shutdown boron is positive inanediately notify the Shif t
- Engineer or designated SRO licensed assistant and initiate *
- LCOAR 190S 1.1.1-la.
- en.......... neeeeeeeeeeeenemenceaemenenneeeeeeeeeeeeeeeeeeeeeen i
4 i-6 RviC
-O
' masu
-os.
MM 2 3170 7 (0210V/0023V/030988) 8.O.S.Ft.
.. _- - _ _ - _ _ _ _ - - - . _.. __-. - ~_ . - - . . - . _ - .- .-
1805 1.1. 4. a-1 I Revision 51 REACTOR COOLANT SYSTEM MINIMUM TD@ERATURE ICR CRITICALITY SURVEILLANCE A. STAT 1XENT OF APPLICABILITY:
This procedure applies to the verification of RCS tereparature (Tave) in Mode 2,15 minutes prior to achieving criticality.
B.
REFERENCES:
- 3. BAR's 1-14-A3, 1-14-83, 1-14 C3, 1-14-D3 and 1-14-E1.
C. PRIJtEQUISITES:
- 1. This BOS must be performed within a 15 minute period prior to achieving criticality in the reactor..
D. PRECAUTIONSI
- 1. The RCS temperature must be greater than or equal to 550*r prior to . ,
achieving criticality.
- 2. If greater t. nan 15 mins, has passed from step lb and the reactor is not critical, this BOS sust be performed again.
E. LIMITATIONS AND ACTIC3rS:
- 1. As stated in Technical Specifications Limiting Condition for Operation (L.C.O.) 3.1.1.4.
- 2. In the event the Acceptance Criteria is not met during the performance of this surveillance, IMMEDIATELY notify the Shif t Engineer to initiate ICOAR procedure BOS 1.1.4-la.
F. MAIN BODY
. g .
- Inital each step in the i, pace provided adjacent to the
- Main Body step number af tet the step has been sucessfully *
- completed. *
...............................................n...............
M. Enter
- a. Date / / / /9/
- b. TLee 02) Y0 APPROVED AUS 141985 B. O. S. R.
(2536P)
inos 1.1.4.a-1 Revision 51 Within 15 minutes prior to anticipated criticality, log RCS Loops Teve using ITI-412(Loop A),1TI-422(Loop 3),1TI-432(Leop C), and 1TI-442(Loop D)
Temperature W p 1A Tave (171-412): e d;37 'r toop 14 Tave (1T1-422) e s57 *r toop 1C Tave (1T1-432): e sn 'r Loop 1C Tave (171-442): e r$7 ,'r VERITY that the lowest loop Tave is 1550'r.
Record time of criticality.- C 95 k att engin.or=
JL= - I d 9/
/ Date Signature ACCEPTANCE CRITERIAt
- 1. The Reactor Coolant System temperature (Tave) shal) be determined to, be 1 550' within 15 minutes orior to schieving reactor criticality.
O 4
O .
^eeaovso AUG 14 885
- s. o. s. R.
333q3 y v v -9 fmw--<hr tg , --opyweg---r--g ,-+---*ye-w, q-- -,-----e-g, gem-e- y-ey-+-w-am+g-ge-s*w<* -se-e-c-e*w *-am-- e w ww-*, ~ - -w-P--,"e e- m- mP*Niwee+-se--'e4t--ew Y r2-+
.oa s.s.... .
Revision 1 NOVEARLE CONTROL ASSEMBLIES HNTHLY SURVEILLANCE A. SIAIDtIHLQI_AffLICARIL1211 (N
\'~')
This procedure applies to the verification of control assembly operability in Modes 1 and 2, B. RITIREHCE11
C. FAKRIC511112f11
- 1. Receive permission from the Shift Engineer or designated SRO licensed assistant prior to perfot. ming this surveillance by having the Data Package Cover Sheet signed and dated.
- 2. A visual inspection inside of all 5 RD power cabinets indicates thet no blown fuse indicators are tripped.
D. ERECAlllist(11
- 1. Defore transferring to automatic control, ensure permissive C-5 is estinguished.
- 2. Avoid variations in plant load, reactor coolant temperature, and
- boron concentration.
- 3. During the surveillance, reactor coolant average temperature changes 3' greater than .4*r or +1'r shall be compensated for by moving rods intermittently to match 7 AVE and TREF.
~4. Maintain WI within prescribed limits.
- 5. Before transferring to automatic reactor control, manually adjust Tavg to within s 1*r of the reference temperature to avoid a transient following the transfer.
E. LIMITATimE_ AND ACTIWS1
- 1. As stated in Technical Specifications Limiting Condition for Operation 3.1.3.1.
- 2. In the event the acceptance criteria is not met during the performance of this survelliance. 1HMEDIATELY s.Stify the Shift Engineer to initiate LCOAR 1BOS 1.3.1-la.
FBR REFERE APPROVED JAN 0 81990 O 8.O.S.R.
V (0665v/0061v/olo$9o)
1805 1 3.1.2 1 Rovision 2 T. NAIN BODYt neceeen..................caseeee................................
- HCTEE
- O
- Initial each step in the space provided adjacent to the main body step number AFTER the step has been SUCCEstrVLLY
- completed. Persons performing ladopendent verification
- should initial in the space provided after the step. e eenene,eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.
- 1. ENTER: Time Date .
- 2. TRANSFER /VER!rY tod control to manual
- a. PLACE /VERIFT bank tselector switch to MANUAL position.
- b. Utilising the tod Hotlos Control switch MAINTAIN TAVE matched with TREF.
- 3. Shutdown banks
- a. ENTER la column 34. the initial group 1 and group 2 step counter readings for Shutdown Banks A, B, C, D, and E. (Note . There are no group 2 Stop Counter Readings for S/D Banks C, D & E)
- b. SELECT Shutdown Bank E by placing bank select switch in SBE position. '
t
- c. Utilising the rod motion control switch, INSERT Shutdown Bank E 10-15 steps.
- d. RECORD la column 3d group 1 and group 2 step counter readings.
e.' VERIFT, tec ilising DRP!, tht each rod in Shutdown Bank E moved
, 10-15 steps and signify this by laitiallag in space provided la column 3e.
- f. Utilising the rod motion control switch, WITHDRAW Shutdown Penk E to 231 steps.-
- g. RECORD la colurr.n 39 final group 1 and group 2 step counter readings.
- h. VERIFY that the DRP! Andication for all rods in Shutdown Bank E le 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.
3 i
APPROVED
~
JAN 0 61990 q ,,,
B. O. S. R.
. J (0665V/0061V/010590) l l
l
1805 1 3.1.2 1 Ravlsion 2 Shutdern Rod Bank '3a. Initial liep '3d. Step Counter '3e. fach Rod In '3g. Flaal $tep '3h. All toes in Counter Readings After Sank Moved Counter Bank at 10 15 lieps Rgadinen 231 Steps O ). Ragging G uun 1 _Graum 2 Greue I le n tf_ Lien Greum 2 Greue i Graum 2 hutdown tank A 77/ 23/ 7E/ 77J f '# 5' H 2U J nuna 8,en ? .s.' DI 11) 7'Z/ a OP nl 7%l i' l+
l . 1huidara_ Bank C l' N/A N/A e [!h @l . N/A f
.1hutdown monk o 7U N/A 7EJ N/A f N / N/A 7#
.1huidann,Benk f / 5! N/A N/A r N/A i
_4 . Control Banks
- a. ENTER in column 4a the initial group 1 and group 2 step counter readings for Control Banks A, B, C, and D.
ene......eeeeeeeeeeeeeeeeeeeeeee...eeeen....eeeeeeeeeeeeeeeeeeen a gggg e
- If the bank is fully inserted, record the group 1 and e
- group 2 step counter read.ings, mark all other columns on
- l
- l-
- Data Sheet N/A and do not proceed with surveillance for
- i
- that bank.
l neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenoonenen
- b. SELECT Control Bank A by placing beak select switch in CBA position.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene..........
e
( e nozz .
- Control Banks may be moved 10-15 steps in or out at the e a
- discretion of the S/E or his designeo to meet the r requirements of this surveillance. Monitor Reactor Power
- a- and Tave closely had correct as necessary to minimise plant *
e ........e eerseeeeeeeeeeeeeeeeen.......eeeeeeeeeeeeee.........
- c. -Utilising the rod motion control switch, MOVE Control Bank A 10 15 steps.
- d. RECORD in column 4d, group 1 and group 2 step counter readings.
- e. VLR1FT, utilising DRP!, that each rod in Control Bank A roved 10 15. steps and signify this by Initia11ag in space provided in column (s.
- f. Utilising the rod motion control switch, POSITION Control Bank A to original controlling position.
i -APPROVED l
JAN 0 6 W 3
l (o665v/oosiv/olos90)
B.O.S.R.
l l
r l
~
1805 1.3.1.2 1 R$ vision 2 )
I
- g. RECORD in colwnn 4g final group 1 and group 2 stop countor readings. i
- h. VERITY. utilising DRP1 and group stop counters, that all rods in !
j
%> Control Bank A are RESTORED to their original position and l signify this by initialing in space provided in column 4h. ,
- 1. REPEAT steps b. through h. for Control Banks B, C, and D. t f
a ;
Centrol pod Bank '4a. Initial $tep '4d. Step Counter 'de, tech Red In '4 9. Final Step '4h. all redt at !
(Dunter leadingt After Bank Moved Counter original l
- 4. ...._. Randlat,, M yamant 10 15 Stept _ Ragtimat petttien .
5 Greum 2 ,_Creum 1 Qtsue 2 Graus 1 Greus 2 Graue 1
.t ntr.1 sank a ri/ n/ 22/ P2/ r s'7# 7 $/ 23/ /# l'
_g.natret mini n 23/ F V/ ?T/ F2/ , ?// p'T I /?/ (J#
Cahlte1 " C ' 'l Yl! I l t Y ?N ?I YN j M7 M /' . #7 /f4 r J /s 73l 73/ M D ntret sank o ,
RESTORE tod control to autornatic.
- a. VER!rY Low Power Interlock C-5 NCrt LIT.
INDEPENDENT VER!r! CATION f
ejj.
sl b. VER!rY TAVE.TRST deviation A l'r. [
i INDEPENDENT VERIr! CATION O- .
N/ c. PLACE bank selector switch in Atr20.
i j
e .
INDEPCdDENT VERIr!CATICH
. 6. Not!!y Chemistry Department of rod movotnent to determine if RCCA cladding defect sampling should be obtained per BCP 210 19 t and/or DCP 210 20. ,
G. ACCII'lAtLCI_C11II11AL
- 1. Each rod not fully inserted in the core shall be determined OPERABLE i at least once each 31 days by movement of at least 10 steps in any-one direction.
APPROVED (rinal) JAN 0 61990 4 B.O.S.R.
(0665V/0061V/010590)
1 1105 1.3.5-1 R:visien 51 f
$11UTDOWN ROD fa INSERTION LIMIT I
G DURING APPROAQ{
)
TO CRITICALITY SURVEILLANCE l
l A. ETATEMDrT OF APPLICABTLITYt l
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 NODE 2.
B. PITERENCES t
' l '. Technical Specification 4.1.3.5 *
- 2. BGP 100-2 C. PREREQUISITPS
- 1. Receive permission from the Shift Engineer or d*,signated SRO licensed assistant prior to performing this surveill .co by having the Data package Cover Sheet signed and dated. .
D. PRDCAUTIONSt r 1. None E. LIMITATIONS AND ACTIObl5 v
. 1. As stated in Technical Specifications Limiting Condition for ,
- Operation (140) 3.1.3.5.
- 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 18061.3.5-la.
T. !iAIN BODY b/[1. ENTER
- a. Starting Time Ob2d a
- b. Starting Date r/icr/0t VERIFY on the Chart Below by initials that for each Shutdown Bank all Rods in that Bank are fully withdrawn } 221 steps as displayed on the digital rod position in.lication panel. ?g ,,
Shutdown Bank A d f 3I h Shutdown Bank B e ?3/
Shutdown Bank C d e%i Shutdown Bank D t 2M Shutdown Bank E e v 's (
O >eeaovso AUG 121985
~
B. O. S. P.
(2511P)
l 1BOS 1.3.6-1 Revision $1 9F. 3 om:n th. ti and date control hanx rod withdrawal h. van.
rS E7 <~ / //#v/4' bA-t ,4 . VERIFT that each shutdown rod was determined to be fully withdrawn 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.
G. ACCEPTAM3 CRITDtIAt
- 1. Each shutdown rod shall be determined fully withdrawn within 15 minutes prior to withdrawal of any rods in Control bar.ks A, B, C, or
' D during an approach to reactor criticality.
l ,
s i
6, i
I APPROVED
- FINAL AUG 121985 B. O. S. R.
(2511P)
1905 2.4.1.4 1
'l R3visica 2 i
a QUADRANT PONER TILT RATIO CA!OJW3 Cat '
^
1, i
- A. gritw nrt or ApptfeintLYTYt ;
I f This proceduto applies to the verification of Quadrant Power Tilt Ratio in Mode 1 above 504 Rated Thorwal Power, weekly when either the computer ,
< alors or the flus deviation alarms for MIS Power Range Tilts are operu.le l
{
and Shiftly when all alarms are looperable. This procedure also verities !
' Ouadrant Power Tilt Ratio hourly when any alarm indicates a tilt is j present. If one Power Range escore channel is inoperable and the unit is 4 4 in mode 1 above 75% of Rated Thermal Power, this proceduto may be utilised to calculate the Quadrant Power Tilt Ratio utilising the three remaining 1 power range chamaels for comparison to incore flus map results per 1BVS 5
2.4.2 1.
B. REFEREMCEEi
!. 1.. Technical Specification 4.2.4.1.a
- 3. LCOAR 1905 2.4.1-la.
+ .
l C. PREntmfis1 Test 4
j 1.. Receive permission from the shift Engineer or designated SRO licensed ,
assistant prior to performing this surveillance by having the Data Packas cover Sheet signed and dated. {
(
- - 2. Reactor power should be coastsat while recording data from NIS.
i 3. Obtain the last determined 100% Power NIS Detector Currents f rom the Station Nuclear Engineer or the Operator Aid on 1PM07J.
1 +
f D. PRECAUTICEfB 1 Nome
)- E. LIMITATICME AND AETICEfE t ,
- 1. As stated in Technical Specification Limiting condition for operation 3.2.4
- 2. In the event the Acceptance criteria is not met during the performance of this procedure IW(EDIATELY notify the Shif t Engineer to Initiate LCOAR 1908 2.4.1-la.
1 i
1 APPROVED SEP 1219%
1 B.O.S.R.
(1466V/0113V/090490) .
--,,,,,e~-..,-,,e ,,-_ ,,- . <,-,,,,.~, -- nn- -. v n.- w-n v .v m -
- - . - - - _ . - - - - _ _ ~ . - . - ~ - - . . . - _ _
d 1905 2.4.1.c.1 R3visics 2 4
F. MAIM 20DYi 1 . 1 e een... .eeeeeeeeeeeeeeenene e neeeeeeeee...eeeeeeeeeeeeeeee..e
- MQ2E
- i
- Initial each stop in the space provided adjacent to the
- e e Main Body step number &Z2EE the step has been EUCCIEETULLY
- completed.
- eneesenesee**eneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemonee eeeeeeeeeeeeeeeeeeeeeene**eeeeeeeeeeeeeeeeeee****eeeeeeeeeen.**e ;
e ggzE e
- If one Power Range Channel is inoperable, the QPTR may be .
- calculated uslag the three operable channels. Record N/A *
- for the inoperable chamael
- eeeeeemenenene....... ... eeeeeeeeeeeeeeeeeeeeeeenemoneen ne e**
- 1. - Record the reactor power from the NIS Power Range Drewers.
4 NR41 NR42 NR43 NR44 Ng 77, /_g Yk. f) g #1,7
/ g
- 2. DETL*RINE the Quadrant Pner Tilt Ratio, for the Upper ( A) t. Lower (B) Detectors, la the Data Tables belows
- a. Paesent Detector Current
- b. Last determined 1004 Power NIS Detector Currest, (obtato from '
Station Nuclear Regineer or the operator aid on 1PM07J).
E't*"t*' E"" *
- t
- c. Normalised Detector Currents a 100% current
- d. Averaqe Normalised Current e Eum of Maremm11 mad Latacter currmata 6 of NIS Chamaels o;-c able
- e. Power Tilt Ratio e Marmalised Detectar currmat }
Average Normalised Current APPROVED SEP 121990 B.O.S.R.
2
\ . (1466V/0113V/090490)
..,,gvq. , -c.e,e ew-, w
1905 2.4.1.0-1 R:visies !
UPPER DETECTORS (A) N41 N42 N43 N44 O- a. Detector Current *
,17 (. )cy 2 / (- ) e '/
, , ))fl 2M 9 22 C f } ,~ c
*:~:" ,a., .m3 .mo . 't ? , e .vis,
- 6. Average Normal. ///////////////
//////////////
//////////////
* ,77 y ///////////////
imed current o 1.02) l. W l t l* 00 t I* I t * 'l'l b t LOWER DETECTORS (B) F41 M42 N43 N44
- s. Detector Current 73( /f[ ] / 4/ 2 /.f
- b. 100% Detector Cut .'emt 12 (, '{ / 'i(,Y ~) l Y, ( )/;", '/
- c. Normalise6 Detector Current ,9M 2 /. Oc. 3 / .7777 , if S/
6.-Average Mornal- /////////////r /////////////// isea Current ////////////// eiii3 /////////////// R 1 1.02) e /* t /* M Y t
- t . II t G. ACCEPTAMCI C11't2RIAt No Power Tilt natio shall escoea 1.02.
4 APPROVED (Flaal) SEP 121990 B.O.S.R. O 3 (1466V/0113V/090490)
~ . - . - - _ - . - . - . . - - - - - - . - . - . . - . . . _ . - . . _ _ -
1905 3.1.1-3 Rsvisica 3 CALOR 1 METRIC CALCULATION DAILY SURVEILLANCE A. ETATEMENT Qf APPLIela1LITYt This procedure provides the necessary instructions and worksheets to perform a secondary 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 channels. B. REFERENCEEi j f 1. Technical Specific 6 tion 4.3.1.1 1 e i
- 2. SNUPp's GEN-N-08
- 3. 1BGP 100 4. ASME Steam Tables C. - PRE 1EOL!IEITES1
- 1. Receive permission from the Shift Engineer or designated SRO licensed assistant prior to performing this survelilance 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 and the unit has been at a steady state load for greater than $ minutes.
O 3. The steam generator's levels and steam pressures have been constant for greater than 5 minutes. 4 .* There has'been no rod motion for greater than $ minutes.
- 5. F6e4 water flow and temperature have been constant for greater than-5 minutes.
4
- 6. Steam Generator Slowdown flows have been constant for greater than 5 minutes.
D. PRECAUTICalE I
- 1. When using the process computer to perform the calorimetric calculation, care must be taken to ensure that the steam generator blowdown flowrates are correctly input into the computer AI ALL
- 2 DIES . - This must be doce in order to ensure the eight hour average power values are correct.
- 2. If any process computer calorimetric program input value is added, removed, or modified. a minimum of 15 minutes must elapse prior to ir.itiation of the calorimetric to ensure that the 10 minute nistorical calculation performed by the computer contains the new value(s) for the entire 10 minute calculated period. APPROVED JUN 111990 1
(0437V/0043V/ Ob3190) B. O. S. R. --
IBOS 3.1.1 2 R::visisa 3
- 3. Unit operating parameters shall not be changed while pertoriaing the calorimetric or adjusting the NIS Power Range channals.
- 4. Any poser range channel (N!41, N!42, N143, N!44) shall be adjusted it, based on the calorimetric, the absolute difference is greater than two percent, or if indicated power is less than t. hat obtalped in this calculation.
- 5. Data shall be obtained concurrently so that it is -~ n itible'.
l
- 6. If the calorimetric indicates the need to adjust the NIS power Range 1 channels, this adjustment shall be accomplished prceptly af ter 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 escessive rate of adjustment and/or f ailure to reset rate trips prior tci adjusting subsequent channels.
- 8. Changes in Steam Generator Blowdown will affect Reactor Power.
Verify Reactor Power t 100% prior to increasing Blowdown flow. E. LIMITATICalE AMD AL"ff taf Q
- 1. In the event the Acceptance Criteria is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Engineer to initiate LCOAR procedure 1905 3.1.1-la.
- 2. If t.be process computer calorimetric program is used to calculate power, the Data sheet and Worksheat are not required to be used.
O The cc.mputer printout should be attached to the NIS Workbbeet and retained. , a 3., The following applies to the QUALITY assigned to the values used in Plant Process Computer applications. See Appendia A for a list of computer inputs to the Calorimetric programs
- a. SUSPECT (an "S" follows the value) means the data was not collected under optimal conditions or is the result of a manually entered input. *rha vaine is necentable 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. DAD (*XXXX" is dirplayed in place of the value) means the value is unacceptable for use,
- d. The qualif ty for each value is carried through any calculation 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 a MAD quality. APPROVED L
, JUN 111990 (0437V/0043V/053190) B.O.C R.
. 1805 3.1.1-2 R:visies 3 4 5
- 4. Any value that will require manual loput for greater than one shift shoulp be tracked on unit turnover sheet. (BAP 316-176 Unit HSD turnover.)
, T. HAllL3tQ2X1 1 1 1. ENTER the date and time the calorimetric was started and the name of 4 the operator performing it in Block 1 of Calorimetric Data sheet. 4 i ......eemen...... nee.no..aee...noaa.eeeen..me..e.e. a.o......... 3
. gggg e
- The computer points listed on the Data sheet may be used e
- if the computer is in service. This will increase data *
- accuracy and lower calculation time. e l
- 2. ENTER the gross megewatts electric and the control rod bank positions ,
- in the spaces available and ensure that all FREREQUISITES (Section C) I are fulfilled in Block 2 of the Data sheet.
- 3. ENTER percent power readings from HR-41, NR-42, NR-43, and NR-44 in
! Block 3. l
.... .... . .................................... .. ...........e
)
- HDIE
' It is possible to perform the colorimetric calculation
- a using the program on the process computer. If this is *
'
- done, a 10 selnute average calorimetric with a long output *
- must be used. This is to average out feedwater flow values
- 4 p
- to obtain more accurate results.' If the computer is used.
- i * *
.j proceed to stop 21. i
...e.ee .............. .ee...... .................. .'. .........
- HQII
- I
- If the computer is unavailable, request Instrument *
[
- Maintenance to obtain readings with rauke mult.' meter from *
- amplifiers inside IPA 50J for feedwater temperature.
- 41
. c.e ...... .......... ......e..........................eene...en ~
i
- 4. ENTER computer points '10418, 70438. 70458, and 70478 in Block 4 of the Data sheet.
, $. ENTER steam pressures for each loop from indicators or the average from computer points listed on the Data sheet in Flock 5. If the
- f. Indicators were used. CALCULATE the average pressure for each loop and record in Block 5.
- 6. ENTER feedwater flow for each loop from flow indicators or ENTER feedwater DP from computer points listed on the Data sheet in Block 6.
APPROVED JUN 1 11990 (0437V/0043V/053190) B. Cl. S. R.
}-
m
-- ,-a,.., . , . v,.~.c , , , . , . . , , ,y, ,,- m %,. ,,,,,,,,.,s, , -.,..,,,.-,,,,,,,,,%.,_ _ , . ,, ,,. _ . . , . , ,
1805 3.1.1 2 R?vielen 3
- 7. ENTIR blowdown flow for each loop in gpm on the Data sheet in Block 7.
] .....'...........................................................
. non .
- If tempering line flow is isolated enter 0 for tempering a
- flow in Block 8. *
- 8. CNTER ttmperlag 1&ne flow for each loop in gpm in Block 8 on the Data sheet.
- 9. CONVERT the average steam geocrator pressure for each loot to pela by adding 14.7 pel to convert to pala. RECORD in Block 9 of the Worksheet.
- 10. CALCULATE the average f eedwater flow if the Indicators were used and record in Block 10 of the Worksheet. If the computer points were used, CALCULATE the average feedwater flow in KBH using the equations in Block 10 of the Worksheet,
- 11. - CALCULATE blowdown flow in F.BH using the equation listed in Block 11 of the Worksheet.
- 12. CALCULATE tempe-Ang line flow foi each loop in KBH using the equation listed in Block 12 of the Workaneet.
- 13. CALCULATE met feedwater flow by adding f eedwater flow f rom Block 10 ,
and tempering line flow in Block 12. RECORD in Block 13 of the Work j sheet. (' 14. DERIVE the steam enthalpy, he, using saturated steam at the average steam generator pressure for each loop. RECORD in Block 14 of the Worksheet.
- 15. DERIVE _the steam generator blowdown enthalpy,3h , using saturated 11guld at the average steam generator pressure for each leop.
RECORD in Block 15 of the Worksheet.
- 16. DLRIVE the feedwater enthsipy, h,, using compressed linuld at the average steam generator pressure and feedwater temperature for each loop. RECORD An Block 16 of the Worksheet.
- 17. DERIVE the steam enthalpy, h,, by using the following equation and
' RECORD in Block 17 of the Worksheet.
h, a h9 (1-s)hg where a e steam quality . 9979 .
- 18. CALCULATE each loop's thermal power by using the following equation in Block 18 of the Worksheett (W.w)h, + wh3 - W h, o Thermal power (Stu/lb) ~
W e Het Teodwater Flow (1b/hr) w . Blowdown riov (ib/hr) APPROVED h, a Steam Enthalpy (Btu /lb) h1 . Blowdown Enthalpy (Btu /lb) JLNi111990 h, . Teodwater Enthalpy (Stu/lb) 4 B.O.S.R. (0437V/0043V/053190) " - - ' tWe
?.bOS 3.1. .i .2 R2vislan 3 i
19.- ADD all fout loops thermal power together in Block 19 of the 7 Workshort. l
~ !
- 20. Utillaing the following forinula, DETERMINE the percent power and l ENTER 1p Block 20 of the Worksheet. I Eun of Loop noggr_(alock 10) Enl/Ag K 100% 0.49% e Percent power I 11.6417 K 109 ptu/lb i
... ................n..n.... nee *eeeeece eeeeeeeeeee....eeeeeeene e ggIg .
- The 0.49% la the equation accounts for RCP heat input and *
- amble at losses.
- e n ne ve.eeeeeene ***eeee eeeeee ee en*ene****en enene....n eeme ne.no i enemonene. .eeeeeeeeeeeeeeeeeee.e.........n...n. . .. ........ . j
- K2IE !
- Perforin steps 21 through 23 only it using the process
- l
- computer. If the manual method is used. go to step 24. *
[ emanneenenenemenenneaemenneeemenemoneneeeeeeeeeeeeeeeeeeeeeeeeen
- 2. . DEPRESS MENU.
- 22. StLECT option 23 (Calorimetric).
.en*e.....................n............. ...... ................ l
*- CAUTIM
- i
*
- I
***EAM GENERATOR BLOWDOWN FLOWS .MUST = BE MANUALLY ENTERED \
- UNTIL MODIr! CATIONS CONNECTING THEM TO THE COMPUTER * )
- ARE tKatt. ALL MANUALLY ENTERED VALUE5 MUST DE VER!rIED *
- CORRECT AND REPT UP TO DATE SO THE EIGNT NOUR AVERUit
- l
- CALOR! METRIC 15 ACCURATE. ALSD, M[I MANUALLY ENTERED * !
- VALUE 114AT 15 ADDED, SPEMOVED, OR MODir!ED, REQUIRES THAT
- l
- A MINIMUM OF 11 MINUTES ELAPSE PRIDP. TO INITIATION OF A ;
- 10 MINUTE AVERAGE CALOR! METRIC TO EN8URE THAT CALCULATION * *
- PERFORNED BY ThE COMPU1ER CONTAIH8 fME NEW VALUE(5) TOR THE *
- ENTIRE 10 MINUTE CALCULATED PERIOD. SEE APPENDIX A TOR *
*- A LIST OF THESE INPUTS.
- i eeeeeeeeeeeeeeeeeeeeee meneneme. ...e,e*n.... .......e. n......e !
F I i I APPROVED l Ja 11 mo 1 B.O.S.R. i (0437V/0043V/053190). j i I l i i t
- p g r. .w- , ,,-,m, . . .m. - , . , . . , . . - , - , , , , _ _ +- ,_.,,,y..._..
1905 3.1 1 2 R;visien )
.............................. *ee....... ......................
e e , gggg a
- Data for the process computer calorimetric program may be
- s taken from control board indication and manually entered e
~
- to allow the computer to perfore the calculations. Also, *
* !! a channel is out of service, a value consistant with *
- remaining instrumentation as verifled by a channel check *
- may be manually entered into the computer. *
... eeeeee***eeeeeeee****eeeeeeeeeemennen............. ee.......
- 23. a. CNTER 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 eacn loop.
- e. DEPRESS EXECUTE.
- 24. On the NIS Worksheet in Block 24. CNTER the 1818 Andicated power from block 3 of the Calorimetric Data sheet for each channel. !
l 2$. ENTER percent power calculated in ster 20 of the Worksheet for all four chant.e s in Block 25 of the NIS Worksheet. I
- 26. Using the formula below, DETERMINE power difference and ENTER results in Block 26 of the N15 Worksheet for all channels.
Block 24 (NIS andicated power) Block 25 (Calorimetric Power) e Block 26 (Power difference).
- 27. If' Block 26 is a positive number and less than 2%, INITIAL in Block
- 27. REPEAT for all four channels. If any answer is negative or
('~'g greater than or equal to a positive 2%, PROCEED to step 28. If all 1 ( f answers are positive and less than 2% adjustments to NIS power range ; channels are not required but may be performed at the discretion of , the Shift Engineer or his designee.
- 28. RECORD the CURRENT peacent power readings from NR.41, NR.42, NR.43 and NR.44 in Block 28.
- 29. SUBTRACT the Power difference (Block 26) from the current HIS readings (Block 28) to detenmine the indicated power level to adjust to. RECORD la Block 29.
i
- 30. PLACE the Rod control system in MANUAL.
- 31. Perform this step only if one NIS Power Range Channel is }noperable.
***e...... ...... ........... ..e**e.........e**ee............
e ggIg a
- Ensure the Technical Spe.lfication Action Statement f or *
- one inopvrable Power Range channel is complied with. *
*emene ne ......................... *** ........... e**eneesenes
- a. INSTALL the control power f use for the inoperable channel.
APPROVED 6 JUN 1 11990 (0437v/0043V/053190) g, g), g, p, i
1D05 3.1.1 2 f R3visito 3 :
)
oneneeeeeeeeeeeeeeeeeeeeeeeeneeneeseeeeeeeeeeeeeeeeeeeeeeeeeeeen ; b * ,
- The Lo RK Trip cannot be reset above 10% RTP. *
{ eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen ;
- b. ADJUST the gain potentlemeter (R303) on the inoperable N!S f channel power range drawer B until the H! Rs trip blatable can i be reset.
neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenooneneeee , e ggg a
- The negative and positive. rate trips must be reset on the *
- inoperkble channel prior to adjusting the gains on the *
- operable thennels. This will ensure that a 2/4 colacidence *
* (Rs trip) 4111 not occur. *
*eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- c. Then RESET the followingi
- 1) Positive rate trip
- 2) Negative rate trip
- 6. If any of the applicable trip blatables cannot be reset, then DO NDT continue and NOTirY the Shif t Engineer.
e.- If all of the applicable trip b! stables are reset on the inoperable NIS channel, then PRDCEED to step 32 of this procedure.
- 32. ADJUST the'out of tolerance channels one at a time' utilizing the following formatt neneeeeeeeeenne n e neoaneeeeeeeeeeeeeeee.** eeeeeeeeeeeeeeeeen e CAUT!aN e
- T1tt FOLLOWING ACTION COULD CAUSE A FLUK RATE TRIP OF THE
- a DETECTOR (5) BEING ADJUGTED. TWO Or FOUR CHANNELS WILL
- CAUSE A REACTOR TRIP. . ADJUST ONE CHANNEL AT A TIME.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeen,anennenenseeeeeeeeeeeee**eeeeeeen ene**eseene**enneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee***eeeeeen e ggg a If gain potentiometer R303 cannot be adjusted.enough to
~
- obtals agreement with the calculated value of percent *
- _ power, contact the IM Department. Have the Techalcian *
- adjust the course grain pot R312 and R303 as necessary a
- to obtain agreement with the calculated value.
- eneeseeeeeeeeeeee**eneeeeeeeeeeene eemeenennenenene**enameneneen
- a. ADJUST the gain potentiometer _'R303) on one of the operable NIS
-power range drawer B uhtil the percent power reading agrees with the calculated value from Block 29.of the MIS Worksheet.
b.- . VERITY / RESET the rate trip. APPROVED J(p())1990 (o437v/0oesvios31,o) EB.C).StFt. ({ }) c-T1 - 77tiTeM- gT-4e--e v g tv---3 yyyy -p 3 i-- y wr e y- -y- e -y w yy
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ...._,m._ .. 1905 3.1.1 2 R3 vision 3 i
- c. REPEAT a and b for the remaining operable channels if necessary. l b
- d. 1HITIAL in Block 32 for each channel adjustment completed.
M. PERFORM this step only if an inoperable NIS power range channel was j restored in step 31 of this procedure. ; I , s. VERITY / RESET the following bistables on the (* stable channels.
- 1) Hi Rs trip ,
- 2) Positive rate trip ;
3). Negative rate trip i i
- b. If the applicable trip bistables cannot be reset on the operable f channels, then DO NOT continue and NOT!!T the Shitt Engineer. j
+
- c. If_the trip bistables are reset, then CONTINUE to the nest step. 6
- d. REMOVE the contrt,1 power f use f or the inoperable ptiver range channel. f
- e. VERITY the following bistable tripped
- 1) Lo Rs trip !
- 2) Mi Rs trip ;
- 3) Positive rate trip !*
- 4) _ Negative rate trip
- 34. RETURN the Rod control system to AUTO when Tavg is within 1.0 F of I
Tref. G. ACCEPTANCE CRITERIA ,
, All NIS. power range instruments to be within a positive 2% reading of . i calculated thermal power of the calorimetric as indicated by initial in [
Block 27 or adjusted _to within a positive 2% as indicated by initial in l Block 32. t i
.f '
APPROVED JUN t t 1990
- e. B. O.F R. -
(0437V/0043V/053190)
?
r,-u+w.~en-re,--n,w_ w ,_,m-,- ,m, nrn-.
1805 3.1.1 2 R:visica 3 APPENDIK A i Calorimetric Process Computer loputs 001NT.ID DEscR1PTig!! LT11HS l N0049 PWR RNG CH 41 (QUAD 4) DET Q PERCDf7 N0050 PWR RNG CH 42 (QUAD 2) DET Q PERCDIT N0051 PWR RNG CH 43 (QUAD 1) DET Q PERCENT N0052 PWR RNG CH 44 (QUAD 3) DET Q PERCENT U1150 PWR PNG NUCL CHANNEL AVG T1H Q PERCENT 70418 S/G 1A TEEDWATER IN 7 DEGr 70438 S/G 18 FEEDWATER IN 7 DEGr 70458 S/G 3C FEEDWATER IN 7 DEGr 70478 S/G 1D TEEDWATER IN 7 DEGr U0490 AVERAGE TEEDWATER TEMP DEGr , l P0400 S/G 1A S1MLINE PRESS PT-514 PSIG PO401 S/G 1A STHLINE PRESS PT-515 PSIG PO402 S/G 1A S1MLINE PRESS PT-516 PSIG U0414 S/G 1A AVG STH PRESS PSIC PO420 S/G 1B S1MLINE PRESS PT-524 PSIG PO421 S/G 18 STMLINE PRESS PT-525 PSIG PO422 S/G 1B 57MLINE PRESS PT-526 PSIC U0434 S/G 1B AVG STH PRESS PSIG PO440 S/G 2C STMLINE PRESS PT-534 PSIG p PO441 S/G 3C STMLINE PRESS PT-535 PSIG t I PO442 S/G 2C STMLINE PRESS PT-536 PSIG O U0454 S/G IC AVG STM PRESS PSIC PO460 S/G 1D STHLINE PRESS PT-544 PSIG P0461 S/G 1D STMLINE PRESS PT-545 PSIG PO462 S/G 1D STMLINE PRESS PT-546 PSIG U0474 S/G 1D AVG STM PRESS PSIG UB020 S/G 1A RAW rW DP TT-510 INWC U8021 S/G 1A RAW PW DP PT-511 INWC 08022 S/G 1B RAW rw DP TT-520 INWC U8023 S/G 1B RAW TW Dr TT-521 INWC UB024 S/G IC RAW TW DP TT-530 INWC U8025 S/G 1C RAW TW DP TT-5k1 INWC U6026 S/G 1D RAW Th DP TT-540 INWC V8027 S/G 1D RAW TW DP PT-541 INWC 70407 S/G 1A BLOWDOWN GPH T0427 S/G 1B BLOWDOWN GPM 70447 S/G IC BLOWDOWN CPM 70467 S/G 1D BLOWDOWN CPM T2239 S/G 1A TW TEMPERING LINE F GPM r2240 S/G 1B rW TEMPERING LINE T GPM APPROVED F2241 S/G IC FW TD4PERING LINE F GPM F2242 S/G 1D TW TEMPERING LINE F ' GPM JUN 1 1 1990 (rinal)
-9 B.O.F R.
O (0437V/0043V/053190)
. . . - . . - - - . . - - . _ _ - - - _ . _ .-- . - . ~ - . . . - . . . . - - -
1805 3.1.1 2 R3 vision 3 i t CALORINETRIC DATA 5!!EET i
- 1. Dates "- / Y '/ /
\~ Times /r /t Performed byl [ f
- 2. MWe (grossli // f 6' Control Bank Positions: C1 2 'l steps C2 2'd steps D1 /W steps ;
D2 / '< & steps All prerequisites have been met (RO) id f I
- 3. Initial HIL Power NR41(N0049) #/ 7 % HR43 (H0050) 9f,[% NR43(N0051)#f / % NR44(H0052) M f%
- 4. Feedwater temperature (computer points):
A. 70410 #/3'/1 *r B. m438 93tl *r C. m450 /A'/.1
- r D. 70478 M'/. 7 ' r l
- 5. Steam Pressure (psig)
Average A. PI-514A Yif P!-515A #C PI-516A @ or 00414 M i[ N ' Average or U0434 TiO i B. P!-524A[/# PI-525A ffo PI 520A Average C. PI-534A YSO PI-535A 4'E PI-536A W or UO454 SiO ( Average D. PI-544A N PI-545A 49 P!-546A N cr UO474' 3 6 Feedwater Flow (KBH or inches water) , i A. r!-510 277l' r!-511 IN or U6020 U8021 f B. r!-520 N'I r!-521 3 7##b or UB022 U8023 C. rI-530 b ? '" r2 531 37 T or U8024 U6025 D. TI-540 NPl' r!.541 M' or UB026 U8027 ; l
- 7. Blowdown rlow (gpm)
- k. T'Ir h i D . ]O
- W C , ?9$D. 9 '1 l' '
~
- 8. Tempering flow (gpm)
A. rK-251 (r2239) #U
/ B. rK-252 (r2240) U C. rK (r2241) iY D. TK-254 (r2242) l7 i APPROVED ,
_,,, JUN 1 1 199') I (0437V/0043V/053190) gg9q i t
, . , .n.,
1805 3.1.1-2 l Rovisico 3 t i CALORIMITRIC WORK 5REET ! i
- 9. Average steam. generator pressure l
/9 i b A. Ave ?' h', l + 14.7 . "l'/'1 psia A"I.quVED l B. Ave '$0 f + 14.7 m 'I N' psie gg j C. Ave F'If F + 14.7 = <l f 'I' 7 psia j D. Ave UC5
- 14.7 s 9f 3 pela O' O'
- S'
- 10. Average reedwater riow
!! from lodicatorst )
A. F1 510 37 O + r!-511 JFI , , ,7, g / 2 B. r!-520 3 7 '/U + r!-521 [ ff' . 3797; 2
- c. r!-530 3WO + r!-531 3N
.s 779t<
2 D. r!-540 3 W O . + r!-541 U 77cp 2 If from computer points: I We a ra Where W = feedwater flow (LBH)e'er a particular tap a = feedwater flow constant for appropriate to ra e thermal espansion iactor ((1.824 s 10-5)p (rW (seetemp)] below)+ .9989 DP e feedwater DP from computer points v . specific volume of feedwater at tw temp and steam pressure reedwater flow constant (c! tan $10 511 520 521 530 531 540 541 a 2.493E4 2.50$E4 2.ig1E4 2.484E4 2.47BE4 2.477E4 2.484E4 2 . 4f,.in reedwater loop A B C D i l a 2.d2JU 2.50$E4 2.481E4 2.484E4 2.47BE4 2.477E4 2.484U 2.485E4 ra DP v . W , Average feedwater flow in KBH (W) = Ng + H2 for each loop 2(1000) Loop A Loop B Loop C Loop D Ave FW flow KBH KBH KBH KBH O -D3-() (0437V/0043V/053190)
1805 3.1.1-2 R3visica 3 CALOR 1 METRIC WORKSHEET
- 11. Blowdown flow (KBH)
A. 77 6 g;e i,008021 , 3% C KBH (.01660) B. ! T gge f.008021 , _ 3_t'. C gBH (.01660) C. 7 . vpmLJ010n , 3i' f gBH (.01660) D. 7#/+ S E gpm f 00 eon , 39 f KBH (.01660)
- 12. Teepering Line riow (ESH)
TF = (.00802) II-Loop A Loop B Loop D T1 'I S 'il Loof'C
'I1 'l 7 v ,rtit% , t / *r /4 , c. t 't / W r /*j sv TT 34, fl 2 % 47 3 *lo %! Vf fl
- 13. Het Teodwater riow
.- 2IN A. Ave reed Flow 37V's KBH + TT .W 'l KBH e 'Mf,KBH (1000) = 3*YdU LByr B. Ave Feed flow I 7 'l O KBH + TF K KBH s %' 5 KBH (1000) = h.fl.1[ LB'ti f C. Ave feed Flow 3 7 '/ / 2 KBH o TT 31 - KBH e Th'2L3 KBH (1000) e 1 Kn3 bhy D. Ave Feed Flow D %(' KBH + TF '/t /- KBH e M KBH (2000) e MT('f.,i'BH '
14 Steam Enthalpy 15. Blowdown Enthalpy 16. Teodwater Enthalpy 17. Corrected steam (h9) (hi) (h,)- enthalpy (h s) Loop A f / 'll . 4 5 ?( ,'i 4,' / ',1, !C 8 s 9 f (- Loop B II Al <l 52'ia f *! ' 1 J e !! '14, V Loop C ff61i1 E77 i _ '/ / 4 i- M ^ * / e V Loop D 11ifi3 5 77,I *//5, SS / r te e t , 7 Where h,= shg + (1-s) h}s e steam quality = .9979 APPROVED JUN 111990
-D4-(0437V/0043V/053190) - bl.O..C R.
O
l 1805 3.1.1 2 R3 vision 3 CALOR! METRIC WORKSl!EET C 18. Loop Thermal Power (W.w)h, ~
+
wh3
. W h, e Power A. .
9 (hMV+ .c;M) st //n;r* - ( .e 342,Itti#.f) J o E v' . ). O !/.(tlivr 'i ( u/ t. %)f?.r ? 'k 2 Y /t
~
B. ('M </.. 3V8 ) "M# T 2 '. - y w
+
s h[ (U78 ) . TI'I $ ( '//t h')* , 2, r ? n s or ' /, ( c c i > /.'. , 2, f 'lY t /r,7 ' C. ams YC242 > n
. nt) aw . +.nz( 'o ene . n.w/us)
_ 2. r ! r *i x o?! . I.f r R s k i e
'71 'I W II Y , l D. ( 3 W4
*/, _r3 tN8) /// #f ++ 3T2*c?17sr_1 5 ( 'I27 k ) . M(f *//Y' t 'f cE) '
- ae .7.'f W t 1 If y
1 vu'
- 19. Sum of loop powers //< 7/3 4 //
- 20. Calculation of % Power 1 Sum of loon newers) Btu /hr a 100% . 0.49% e / ('It / % Power 11.6417 K 109 Btu /hr
\
e 8 APPROVED JUN 1 1 1990
.D5 A
(0437V/0043V/053190) B.O.S.R. i
1905 3.1.1 2 Revision 3 NIS WORF.SHEE7
- 24. HIS Power 25. Calorimetric 26. Power Difference 27. Initial for Ho Poygr His AdiustmenL Nt2 'i 'r /tt. l
- fI
* /, f Hg2 $ $. l _ /et (
H43 t f /*/>( ~2i/ _ 9 ' ' /et'l ' l' N44
- 28. Current HIS Power 29. (Step 26-26) ?ower to 32. Adjustment Complete adiust NIS to .
'/ 'i , ,, 7 g N41
'r '> ! grg,(
H42 "'.' H 4 3_ *i - s , c f . ,. ~ 4 ' . 'l if(,g U44 O APPROVED (""2 ) JUN 1 i 1990
- 6 B.O.S R.
(o437v/oo43v/os329o)
I 1BOS 3.4.2.0-1 Rovision 2 O 'IURBINE THRCTITLE, GOVERNOR , REliEAT, AND INTERCEPT VALVE I (,) MCtiTHLY SURVEILLANCE A. SIAT!21!2iT Df_ AffLLCABILIT11 This procedure applies to the monthly verifichtlon, by direct observation. of the Turbine Overspe3d Protection System operability in modes 1,2 and 3. B. fir.IRZ2 ICES 1
- 1. Technichl Specification 4.3.4.2.a.
- 2. Westinghouse Instruction Book No.13A4930, Vol. _.
- 3. Station Procedure 1BOS 3.4-la, LCOAR-7 rbine igrspeed Protection.
- 4. Westinghouse 10CTR50.59 Notification on Turbine Valve binding, January 21 & 22, 1988.
- 5. Station Constitments,
- a. 88-6-0499.
- b. C7-6-0020.
- 6. Westinghouse Operation and Malater, .:e Memo :190.
C. EREREQUISITEst
- 1. Receive permission f rom the Shif t Engineer or designated SRO licensed assistae prior to performing this surveillance by having the Data Packige ,over eheet signed and dated, t /. DEH systa.n 2st be in "O M AUTO".
J. Impulse Prassure Fesobeck (" MP 7N") is selected.
- 4. Megawatt Feedback ("MW CUT") is selected.
Jf f b-7 *
. Unit Icad shall be greater than 15% and less than or equal to 85%. l
- 6. An operator must be swailable to directly observe each valu's movertent, for sniooth operation, as it is tested.
D. ' RECAUT?Iti, 4
- 1. The observing operator shall stand clear of all turbine valves th?oughout the test. -
. Number 1 and 3 Throttle Valves interlock with NDCT Rit.er Valves.
When the Throttle Valves close, the HDCT will transfer from the riser to bypass mode of operation if the NDCT Turbine Trip Interlock switch is NOT in the OVERRIDE position.
'~ -
FOR REFEENCE AUG 2 81989 (052?V/0049V/0028E9) B.O.S.R.
1BOS 3.4.2.4 1 Revision 2 ( 3. To ensure the probability of an overspeed condition or destructive overspeed condition due to a stuck open Throttle Valve is adequately (- reduced, prior to testing any Throttle Valve, the associated Governor Valves must bath have been antgrA2Lully tested.
- 4. Monitor HW meter during the transfer from single valve to sequential valve mode of control and vice versa to verify generator load remains stablo.
- 5. Various valves will stroke as a result of closure of Throttle Valve 1 and Thr,ottle Valve 3.
- a. Components affected by the TV-1 Limit Switch closed.
1). 1ES005 ADV HP Heaters 17A & 17B Ekt chk. 2). 1ES006.AOV LP Heaters 15A & 1EB Ert chk. 3). 1ES011A ADV LP Heater 12A Ext chk. 4). 1ES015A AC .P Heater 13A Est chk. 5). 1ES017A ADV LP Heater 14A Ext chk. 6). '55022 A0V RP Heaters 17 A & 17B Eat. Sta. Spill Viv. 7). 1ES028A ADV LP Utr 12A Ext Stm Spill V1v. 8). 1ES030A A0V LP Htr 13A Ext Stm Spill Viv. 9). 1ES032A ADV LP Htr 14A Ext Sta Spill Viv. 10). 1ES024 ADV LP Htrs 15A & 15B Ext Stm Spill V1vs. 11). 1ES062A ADV MSR 1A first Stage Rhtr Ext chk. 12). ICWOO4C NDCT Riser V1v. l's ) . ICWOO4D NDCT Riser Viv. 14). ICWOO4E HDCT Riser V1v. 15). ICWOO4F NDCT Riser Viv.
- b. Components af fected by the TV-3 Limit Switch closed.
1). 1EP002 ADV LP Htr 16A & 17B Ert chk. 2). IESOf'B ADV LP Uct 12B Ext chk. a 3). IES011C A0u LP Htr 12C Ext chk. 4). 1ES015B AOV LP Htr 13B Ext chk. PPROVED
'~ 5), 1E5015C ADV LP Ett 13C Ext chk. AUG 2 81989 6). 1ES017B AOV LP Htr 14B Est chk. B.O.S.R.
(0529V/0049V/082889) .
1BOS 3.4.2.0-1 Revision 2 7). 1ES017C ADV LP Htr 14C Est chk. 8). 1E8019 ADV LP Htr$ 16A & 16B Est Sta Spill V1v. 9). 1ES02BB ADV LP 7tr 12B Est Stm Spill V1v. 10). 1ES028C ADV LP Htt 12C Est Stm Spill V1v. 11). 1ES030B ADV LP Htr 13B Est Sta Spill V1v. 12). 1ES030C ADV LP Htt 13C Est Stm Spill V1v. 13). 1ES032B A0V LP Htr 14B Eat SLm Spill V1v. 14). IES032C ADV LP Htr 14C Eat Sta Spill V1v. 15). 1ES062B ADV MSR 1B Tirst stage Rhtr Eat chk. 16). ICWOO4A NDCT Riser V1v. 17). ICH004D HDCT Riser V1v. E. LIMITAUCt!E_AND_ACnatiS1
- 1. As stated in Technical Specification Limiting Condition for Operation 3.3.4.
() 2. In the event any of the Acceptance Criteria is not met during the performance of this procedure, IMHIDI ATELY notify the Shif t Engineer to initiate LCOAR erocedure IBOS 3.4-la, e
- 3. During the performance of the Gove nor Valve Single /Seque..ial Transfer if an uncontrolled rapid celllations treurs, then depress
" TURBINE MAFUAL" on the DEH Turbine Control Panel and "GV Raise" or "CV LOWER" to adjust governor valve position to maintain desired turbine load.
- 4. The perferred method for performing this test is with the Impulse Pressure f eedback loop in serve and the Megawatt Feedback loop out_of service. The test may be performed with the loops in a different configuration at the discretion of the Shift Engineer. If the test is performed with both feedback loops out of service unit load swings can be expected.
- 5. If during the stroke te.st of a governor or throttle valve any evidence of bindiag occurs the System Engineer should be notified as the probability of a destructive overspeed could be lucreased to unacceptable levels. *, 5.a
- 6. The throttle valve under test should not be lef t in the f ully closed 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 s thermally induced binding is present. *, 5.a APPROVED
_3 AUG 2 61989 l (0529V/0049V/082889) EL CL SL it.
.. . . _ _ - . ~. .. . - -- - ~ ~ - .~.....-. -.-.. - _ _
IBOS 3'.4.2.0 R3 vision 2 [ T. MAIN.1DD1L
.............................e..................................
e gggg .
- When performing this surve10ance at power, ONLY Section *
- One (1), Testing At Power, should be performed. *
- When performing this surveillance as part of the Unit *
- Startup per the BGP's, CHLY Section Two (2), 7esting During *
- Plant Startup, should be performed. 6
......a........ ................... nee.....ne.ee.a..en......ee.
1.c Testina__At Power 1.1 Enters DATE
/ /
TIME O8 b e......en.w 2e..e..........co....a... .....ee.......**.nen.**.** ,
. NOTE
- If, during the performance of Throttle Valve testing, * *
- the operator wishes to temporarily interrupt the test to
- utillve the dispiny for other purposes, all lights
~
- associated with t!e test will turn off. To resume the *
- Ltest, the operator will have to depress the " VALVE TEST"
- and "TV" pushbuttons.
y -_ ...........................e...........e......................e.
............ ............ee. ................................. . *
- RQIE
- Perfe rm steps F.1.2 and F.1.3 if it is requ.8 red to - transfer *
- the Governor Valves from " SEQUENTIAL VALVE" te " SINGLE
- VALVE" mode of operation otherwise proceed to step F.1.4. *
.eeen.ne.een.ee.ne.see......u.nen**een... ..aeena.ne.ee........e ,
ni
..een eenee. ...e...ee.. .ea..eae..e.ne.eene.a....e.....*..*****
- CAUTIN
- IT RAPID VALVE OSCILLATIWS OCCURS, 'DIEN DEPRESS " TURBINE e
- MANUAL" (N THE DEH TURBINE PANEL, AND "GV RAISE" OR "GV * .
- LOWER" TO ADJUST GOVERNOR VALVE POSITION TO MAINTAIN DESIRED *
- TURBINE LOAD.
e.ee.ee.*emee.ea.....e**.a.a. .e...eenee..a.....nev.a.a.a.......c
- e . . . . . m e *
- e e n . e . e m . n e . : . . . . . . . . e a . n e * * . . . a a e . ., * * ,. . . . . a * * * * * . *
- ggzg e a
- The transfer from sequential to sinrJ1e valve mode may require several minutes. Upon depressing the pushbutton, a
!- *- the SEQ VALVE lamp will go out and the SINGLE VALVE lamp
- will begin flashing. Completion of the transfer-is -*
- indicated by the SINGLE VALVE lamp being steady-on. -
i
- 3) ..eae.. e.e..e........ ... ..........u... ..............me**....
' 1. 2 DEPRESS " SINGLE VALVE / SEQ VALVE" pushbutton on the DEH Turbine e
Control Panel located on IrH02J. APPROVED
+
AUG 2 81969 l: y.g '(052FV/0049V/082889) B. O. S. R. g ,
IBOS 3.4.2.a.1 Revision 2
, .g c g_ q 12 bd i
f 3 VER!rY the SINGLE VALVE lamp stays steady on. - 7g O/ J ' bW d '
. hl' . 4 VER1rY/ PLACE the U-1 NDCT Turbine Trip Interlock switch to OVERRIDE. *, 5.b 1.5 ENSURE an ope ator is stationed t1 directly oba ne movement of 1 each ' valve to be testod through one complete cyc. om the running
- position.
ennanaeanne**enemanneseea.nannaneaneaneamene**enameaneenaeannene
- HME
- Due to the operating characteristics of the governor,
- a reheat stop, and intercept valves, the local method of a
- testing is not an acceptable alternative for these valves. *
-eenamenneenennename***eenenemannenenennemennenenee**eneneanneene i
'- *eenanne****ane*****aanamennenenneenan**eanen nennen****enea nna 4 HOTE
- The preferred method of testing the Throttle Valves is f rom *
- the MCS (Remotely). If the remote test falls the Throttle *
- Valve (s) may be tested locally. If local steps are not
- performed the sign off blanks for these steps can have *
- N/A (Not Applicable) written for them.
aan+.eanee***eaan**esenneenneaeoneaone*enaeanan**aenneaaananeeeee
**aenaea**aanneene**enenamenaneamen.**en enneenanmenennenneenne
- KOIE l
- Stops F1.6 through T1.33 may be done ludependently, or
- l g
- ladividually, for Partial Surveillances provided steps *
- F1.1 through F1.5 and T1.24 through T1.27 are performed. *
, *eene**eenneenenneneeen e** *****eanaemenemenenanneeeeeen neenee
*enene**anamne**=ennenneeeee ama**an*** **na*******enemaneneneen HDIE .
If, during the performance of th governor valve test, the *
- test-is interrupted by rob cting w ;her display function, *
~~
- the "OPEN" and "CLOSE' buttons al; remain illuminated,
- to resume the test, depress'the *
* *ut s will be inoperative.
* ""W TF.5:* pushhton cMing it and " VALVE STAWS" and *
* -E ,*" pushbuttons to illuminate. The governor valve no. *
- oeing tated will. appear in the _" DISPLAY DF. MAND" wlMow
-* and its percent of full open position will appear in the *
* " DISPLAY" window.
een........aaeneen............ana....an......................a..
-.a.ne.ne nananeenen............... an.***e.... .. **....a****en*
CAH 10H O-
- IT, DURING THE PERFORMANCE OF THE GOVERNOR VALVE TEST, '*-
THE TURBINE CONTROL SYSTEM IS TRANSTERRED TO TURBINE MANUAL,* g' *
- THE vtRN a. VALVE sEING TESTED cAN DE REOPr.NED Br O *@
*- DEPRESSING THE "OPEN" PUSHBUTTON, HOWEVER, THE "GV LOWER"
- g *
-g Q _ PUSHBUTTON MUST BE ALTERNATELY DEPRESSED 'M MAINTAIN THE *
% dg
- LOAD APPROKIMATELY CCMSTANT. THE VALVE UNDER TEST WILL T N
- MOVE AT A FASTER RATE THAN DURING " VALVE TEST" CO UNIT *
-g _(
- LOAD. CHANGES MAY OCCUR.-
...........a..........................aea............e.. ... ...
(0529V/0049V/082889)
1 DOS 3.4.2.a-1 Revisinn 2 eeeneseeeeeeenemene** .....aneenennen... anne neseeeeeeeeeee*****
.,O.
- lim As soon as a Goverror Valve begins to close, the "CLOSE" O
- and " PEN" pushbuttons illuminate, signifying that the *
(g
> g%
c::
- test is in progress. When the Governor Valve is fully
- closed, the "OPEN" light will go out. The "OPEN" and
- O ao W * "CLOJE" lights will both go out when the valve is returned
- Q' cv *
- to its original position. As the Governor Valve modulates, the other 3 Governor Valves will automat.ically modulate to
- O- ca
- kQ
- maintain the set load.
n o....e e n e. *
- e n e e e n.n e e e n. .e n e n n e n e n e m e n e * * * * * * * * * * * * *
- e n e n.
eeeeeeeeeeeeeeeeeeeeeenneeeeeeeen*ennenene****eeeeeeeeee******en
- tim
- In per f orming step T.1.6.e, r.l.7.c, F.1.B.c, T.I.9.c
- valve closure time will be dependent on the set rate.
**e****enameneeseanneameneneenemanneenene **eneneenenne*********
1.6 Governor Valve No. 1 test.
- V d.t p'7b 'A n
V a. ,DEPRESSJ.he :"VALVI TEST' pushbutton. VERITT " VALVE TEST" and (" VALVE STA'11]S" pushbuttons illuminate.
/
m 'M i M Nb. DEPRESS the "GV" pushbutton and VERIFY it illuminates. b c. DEPRESS No. "1" on the keyboard and VERITY 0001 appears in the ( " DISPLAY DEMAND" window. t ,
*" d.
e A ) -l* :?
~
DEPRESS " ENTER 'i""""1 Tie 3etual Gov #rnor Ve.lve position ~UTII .. appear
'P I,.,,,,,
in the " DISPLAY" window as percent of full open. Q g prH r /' N n w / 4 er . DEPRESS and HOLD the "CLOSE" pushbutton until GovernerTKlve 1 is fully closed, y j $ m --2 7 s.sf3 u n %
/,M G (1 f . LOcity VEPirY/ OBSERVE Governor Valve No. I travels fully CLOSED.
E g. VERIFT "GV 1 CLOSED" indicator is illuminated and
- I l' 5PDt"l indicator is off. 04 4 h. RELEASE the "CLOSE" pushbutton and DEPRESS and HOLD the "OPEN" ,
pushbutton until the "OPEN" and "CLOSE" pushbuttons' lamps go off, indicating that the Governor Valve I has returned to its protest position.
) g [,/
n MfC t kl. Lottitty VERITY / OBSERVE Governor Valve No. 1 travels OPEN to approximately its original position, y md 1.7 Governor Valve No. 2 test. 'T 1 b] on the hefboard and VERIf7 0002 appears in the M,"I l' kr10
- a. DEPRESS No. "2"
" DISPLAY DEMAND" window. _. ,
% 2~ b . DEPRESC "DITER"". The actual Governor Valve position will I appear in the " DISPLAY" window as percent of full open.
7 g /p yx {N (0529V/0049V/082BB9) l I I _ _- . _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - - _ - _ _ - _ - _ - _ - _
APPROVED 11105 3. 4. 2. a-1
** vial a 2 AUG 2 61989 B.O.S.R. P DEPRESS and HOLD the "CLOSE" pushbutton until Governor Valve 2 c.
O is fully closed. t d. Locally VERITY /OESERVE Governor Valve No. 2 travels fully CLOSED.
- e. VERITY "GV 2 CLOSED" indicator is illuminated and "GV 2 OPEN" e indicator is off.
t RELEASE the "CLOSE" pushbutton and DEPRESS and HOLD the "OPDl" [ f. pushbutton until the "OPDl" and "CLOSE" pushbuttons ' lamps go of f indicating that the Governor Valve 2 has returned '.o its protest position. t g. Locally VERITY / OBSERVE Governor Valve No. 2 travels OPEN to approximately its original position. 1.8 Governor valve No. 3 test. q, n . 4' f d
, DEPRESS No. "3" on the keyboard and VERITY 0003 appears in the
" DISPLAY DEMAND" window..
- 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 unti: Governor Valve 3 p is fully closed.
Q ~
- d. Locally VERITY / OBSERVE Governor Valve No. 3 travels fully CLOSED.
Q U f t I e. VERITY "GV 3 CLOSED" indicator is 11Minated and "GV 3 OPEN" 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 positiot..
1 ( g. Locally VERITY / OBSERVE Governor Valve No. 3 travels OPEN to
- approximately its originni position.
70 1.9 Governor Valve No. 4 test. 3 4 sOff _ V \ -^Q '1 '
- a. DEPRESS Ho. "4" on the keyboard and VERITY 0004 appears in the
" DISPLAY DEMAND" window.
O
- 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" pushbuttot 2ntil Governor Valve 4 is fully closed.
p+
') t d. Locally VERITY /OBSD VE Governor Valve No. 4 travels fully CLOSED.
- e. VERITY "GV 4 CLOSED" indicator is illuminated and "GV 4 OPEN" ,
L indicator is off.
-7 :- l (0529V/0049V/082B89) ,
_ - . . -- - - --- . - ._ . - -._. - ~--,-. .. - . - - - , - ~ _ . . . -
-.- APPROVED IBOS 3.4.2.e-1 AW 2 8 2 Rovision 2 B. O. S. R.
HOLD the "OPEN"
~
- f. RELEASE the "CLOSE" pushbutton and DEPRE
pushbutton until the "0 PEN" and "CLOSE" ) -
.attons' lamps go off indicating that the Governor Valve 4 ..as returned to its
? pretest position.
j t g. Locally VERITY /0BSERVE Governor Valve No. 4 travels OPEN to ' approximately its original position. ; i 1.10 Throttle Valve No. I test. (Remoto) ; i
- 4. DEPJtESS-the " VALVE TEST" pushbutton. VERITY " VALVE TEST" and "XALVE STAWS" pushbutton illuminate.
M-.. ,'.
.I_ . b . DEPRESS the "TV" pushbutton. VERITY "W" pushbutton illuminatws.
. c. DEPRESS No. "1" on the keyboard. VER1rY 00oL appears in the
" DISPLAY DEMAND" wiodow.
V d.. DEPRESS " ENTER". The actual Throttle Valve position will appear in the " DISPLAY" window as percent of full open. /d0 7
- e. DEP!iESS and HOLD the "CLOSE" pushbutton until the Throttle y Valve 1 is fully closed.
n t* '- t f uccnA4y VERITY /0BSERVE Throttle Valve No. 1 travels fully CLOSED..
'* / a.
lg. . ' VERITY "TV 1 CLOSED" indicator is illuminated and "TV 1 OPEN' O .- -
/ indicator is off. M c.) g y ,
')
- h. RELEASE the "CLOSE" pushbutton. and VERITY the Throttle Valve 1 reopens to its original position by observing the " DISPLAY" window and the position indicating lights.
,/ n PC.-
t 1. 6 .1,1y VERITY /0BSERVE Throttle Valve No. I travels OPEN to y approximately its original position. 1.11 Throttle Valve No. 2 test. ( R em*. te ) M )#
- a. DEPkESS No. "2" on the keyboard. VERITY 0002 appears in the
" DISPLAY DEMAND" window.
- b. DEPRESS " ENTER". The actual Throttle Valve position will appear in the " DISPLAY" window as percent of full open.
- c. DEPRESS and HOLD the "CLOSE" yashbutton until the Throttle Valve 2 is fully closed.
q g/ t d. Locally VERITY /0BSERVE Throttle Valve No. 2 travels fully CLOSED. d e. VERITY "TV 2 CLOSED" indicator is illuminated and "TV 2 OPEN"
- Indicator is'off.
e
.-Q A f. RELEASE the "CLOSE" pushLutton and VERITY the Throttle Valve 2 reopens,to its original position by observing the "DISPkAY"
' - O~ window and the position indicating lights. .
-8 !
(0529V/0049V/082 ) s
-- .- . . ~ - - . . :- , . , - - - ,-
APPROVED 1BOS 3.4.2.a-1 Nk b Rovision 2 B.O. S. R. -
- g. Locally VERIFT/ OBSERVE Throttle Valve No. 2 travels OPEN to
-IgQ- A t
approsimately .ts original position. (1, 1.12 Throttle Valve No. 3 test. (Remote)
- a. DEPRESS Wo. "3" on the keyboard. VERIFT 0003 appears in the
" DISPLAY DEMAND" window.
- b. DEPRESS " ENTER". The actual Throttle Valve position will appear in the " DISPLAY" window as percent of full open.
L~ c. DEPRESS and HOLD the "CLOSE" pushbutton until the Throttle Valve 3 is fully closed.
\ ht G c7 d. L WeVERIFT/ OBSERVE Throttle Valve No. 3 travels fully CLOSED.
/
4' . VERIFT "TV 3 CLOSED" indicator is illuminated and "*IV 3 OPEN" indicator is off. j'3 .'I
- f. RELEASE the "CLOSE" pushbutton and VERIFT the Throttle Valve 3s reopens to its original position by observing the " DISPLAY" window and the position indicating lights.
W g. VERIFT/ OBSERVE Throttle Valve No. 3 travels OPEN to f approximately its original position. ~[ r 1.13 Throttle Valve. No. 4 test. (Remote) h
~ a. DEPRESS No. "4" on the keyboard. VERIFT 0004 appears in the
- " DISPLAY DEMAND" windmv.
o
- b. DEPRESS " ENTER". The actual Throttac valve posi:lon will appear in .the " DISPLAY" window as percent' of full open.
- c. DEPRESS and HOLD the "CLOSE" pushbutton until the Throttle. Valve 4 is fully closed.
C W d. Locally VERIFT/ OBSERVE' Throttle Valve No. 4 travels fully CLOSED.
- e. VERITY "TV 4 CLO9ED" indicator is illuminated and "TV 4 OPEN" indicator is off.
- f. RELEASE the "CLOSE" pushbutton and VERIFT the Throttle Valve 4 reopens to its original position by ob e sing the " DISPLAY" window and the position indicating 129 tu .
W g. Locally VERIYY/ OBSERVE Throttle Valve No. ( travels OPEN to approximately its originel position. 1.14 Throttle valve No. I test. (Local) g a. DEPRESS the " VALVE - STA'IUS" pushbutton. VERIkT " VALVE STtTUS" illuminate,
-g) t
- b. DEPRESS the "TV" pushbutten. VERIFY "TV" pushbutton illuminates.
g (0529V/0049V/082aB9)
c. 1908 3.4.2.'o-1 Rsvisica 2
- c. DEPRESS the No. "1" on the keyboard. VERITY 0001 appears in the
}O " DISPLAY DEMAND" window.
- d. DEPRESS " ENTER" pushbutton. The actual Throttle' Valve position will appear in the " DISPLAY" window as parcent of full open.
__ e. CLOSE 1EH5009A, High Pressure EH Fluid Supply Isolation Valve. t- f. When 1EH5009A is CLOSED, locally VER1rY/ OBSERVE Throttle Valve No. I travels fully CLOSED.
- g. VERITY "W 1 CLOSE" indicator is illuminated and "TV 1 OP^ 78" .
indicator is off after valve has stroked closed.
- h. OPEN 1ER5009A, High Pressure EH Fluid Supply Isolation valve.
t 1. When 1EH5009A is OPENED, locally VERITY / OBSERVE Throttle Valve ,
= No.1 Travels OPEN to approximately its origiual position.
- j. VERITY Throttle Valve 11 reopens to its original position by observing the " DISPLAY" window and the position indJcating lights.
1.15 Throttle Valve No. 2 test. (Local)
^
a.: ' DEPRESS the " VALVE STAWS" pushbutton, VERITY " VALVE STAWS" pushbutton illuminates.'
- b. DEPRESS the "W" pushbutton. VERITY "TV" pushbutton illuminates. ,
- c. DEPRESS No. "2" on the keyboard. VERITY 0002 appears - in the
" DISPLAY DEMAND" windr.,w. *
, - d. DEPRESS " ENTER" pushbutton. .The Actual Throttle Valve position will . appear ;in the " DISPLAY" window as a percent of f ull open.
- e. CLOSE 1EH5009B, High Pressure EH Fluid Supply Isolation valve.
t f. When 1EH5009B is CLOSED, locally VERITY / OBSERVE Throttle Valve No. 2 travels fully CLOSED. 9.- VERITY "TV 2 CLOSE" indicator is illuminated and "TV 2 OPEN" indicator is off after valve has stroked closed.
- h. OPEN.1EH5009B, High Pressure EH T1uld Supply Icolatiou Valve.
# 1. When 1EH5009B- is OPENED, LOCALLY VERITY / OBSERVE Throttle Valve No' 2 Travels OPEN to approximately its original position.
- j. VERITY Throttle Valve $2 reopens to its original position by observing the " DISPLAY" window and the position indicating lights.
APPROVED-AUG 2 8 669
-(OS29V/0049V/C82889) B.O.S.R.
L
1BOS 3.4.2.e-1 ! Revision 2 l l 1.16 Throttle Valve No. 3 test..(Local)
)
d s. DEPRESS the " VALVE STATUS" pushbutton. VERITY " VALVE STAWS" O e W pushbutton illuminates, I g- m . a, ,0 b. DEPRESS the "Tv" pushbutton. vERiry "W" pushbutton illuminates, b I qN c. DEPRESS the No. "3" on the keyboard. VERITY 0003 appears in the
" DISPLAY DEMAND" window.
- d. DEPRESS " ENTER" pushbutton. ~The Actual Throttle Valve position will appear in the " DISPLAY" window as a percent of full op,s.
.e. CLOSE 1EH5009C, High Pressure EH T1uid Supply Isolation Valve.
t f. When IEH5009C is CLOSED, locally UERITY/ OBSERVE Throttle Valve ' No. 3 travels fully CLOSEb.
- g. VERITY "TV 3 CLOSE" indicator is illuminated and "TV 3 OPEN" l
indicator is off after valve has stroked closed.
- h. OPEN 1EH5009C, High Pressure EH T1uld Supply Isolation Valve.
t 1. When.1EH5009C is OPENED, locally VERITY / OBSERVE Throttle Valve No. 3 travels OPEN to approximately its original position. ! j. VERITY Throttle Valve 83' reopens to its original position by li observing the " DISPLAY" window and the position indicating lights. l l . . 1.17 Throttle Valva No. 4 test. (Local)
- a. DEPRESS the " VALVE STAWS" pushbutton. VERITY " VALVE STATJS" pushbutton illuminates. ,
- b. DEPRESS the "W" pushbutton. VERIrf "W" pushbutton illuminates.
t
- c. DEPRESS'the No. "4" on the keyboard. VERITY 0004 appears in the
" DISPLAY D* MAND" window.
- d. DEPRESS " ENTER" pushbutton. The Actual Throttle Valve position will appear in the " DISPLAY" window as a percent of full open.
- e. CLOSE 1EH5009D, High Pressure EH T1uid= Supply Isolation Valve.
c' f. When IEH5009D is CLOSED, locally VERITY / OBSERVE Throttle Valve No. 4 travels fully CLOSED.
- g. VERITY _"TV.4 CLOSE" indicator is illuminated and "Tk 4 OPEN" indicator is off after valve has stroked c1csed.
- h. OPEN 1EH5009D, High Pressure EH T1nid Supply Isolation Valve, t 1. When 1EH50S9D is OFENED, locally VERITY / OBSERVE Throttle Valve
- No. 4 travels OPEN to approximately its original positioa.
.i (0529V/0049V/082889) .
l'
~ -.
i 1BOS 3.4.2.0-1 4 Revision 2 . h j. VERIFT Throttle Valve 44 reopent to its original position by l Q obnerving the " DISPLAY" window and the position indicating 4 lights. j ggg O
....................a*..........................................
* =
- 2gi/x ,
o
-g . a.
g
- The test circuits are interlocked so it is not possible to
- Lgfr/
,O . -test the reheat stop and intercept valves on one side or a . i g (D
- low prescure turbine when the corresponding valves on the
- i
(
- other side are less than full open.
- 0 ()
................................................................ j l f,b g-1.18 Lef t Side 1RV and IIV test.
DEPREES and HOLD the " TEST" pushbutton associattrd with the IRV and IIV until the associated "10V CLOSED" and "1IV CLOSED" indicators are 111tuninated and "1RV OPEN" and "1IV OPEN" indicators are off. t 1). Loce.'ll VERIFT/ OBSERVE the Lef t Side 1RV travels fully CLOSED. W 2). Locally VERIFT/ OBSERVE the Lef t Side IIV travels fully CLOSED. 4 .y i% 6 g' b. RELEASE the " TEST" pushbutton and VERIFT 1RV and IIV are open as indicated by the associated "1RV OPEN" and "1IV OP':N" indicators A illuminated and "18V CLOSED" and "1IV CLOSED" indicators off. Q
. ,t 1). Locally VERIIT/ OBSERVE the Lef t Side 1RV travels fully OPEN. ,
t 2). Locally VERIFT/ OBSERVE the Lef t Side IIV travels fully OPEN. 1.19 Right Side 1RV and IIV test. LEPRESS and HOLD the " TEST" pushbutton associeted with the 1RV and IIV until the associated "1RV CLOSED" and "1IV CLOSED" indicators are 111tsnicated and "1RV OPEN" and "1IV OPEN" indicators are off. t 1). Locally VERI!T/ OBSERVE the Right Side 1RV travels fully CLOSED. h j g W 2). Locally VERI /T/ OBSERVE the Right E.4ds XIV travels fully CLOSED.
- b. RELEASE the " TEST" pushbutton and VERIIT 1RV and IIV reopen as indicated by the associated "1RV OPEN" and "1IV OPEN" indicators are illuminated and "1RV CLOSED" and "1IV CLOSED" indicators off.
W 1). Locally VERIfT/ OBSERVE the Right Side IRV travels fully OPEN.
~(N' t 2). Locally VERIPT/ OBSERVE the Right Side IIV travels fully OPEN.
(0529V/0049V/082889)
I D IBOS 3.4.2.0-1 {f 4 R3visloa 2 /N 1.20 Lett Side 2RV and 2IV test. U 'Ip .
- a. DEPRESS and HOLD the " TEST" pushbutton associated with the 2RV (7\
and 2IV unt!I t.be associated "2RV CLOSED" and "2IV CLOSED" g indicators are illuminated and "2RV OPEN" and "21V OPEN" g g% St:
. indicators are off.
Q eo d t 1). Locally VERITY / OBSERVE the Left Side 2RV travels fully C cy 8""' O'
,,g d t 2). Locally VERI.Y/ODSERVE the Lef t Side 2IV travels f ully
~
CLOSED.
- b. RELEASE the " TEST" pushbutton and VERITY 2W' End 21V reopen as indicated by the associated "2RV OPEN" and 21V OPF:N" indicators are illuminated and "2RV CLOSED" and "21V CLOSED" indicators off.
( 1). Locally VERITY / OBSERVE the Left Side 2RV travels fully OPEN. t 2). Locally VERITY / OBSERVE the Left Side 21V travels fully OPEN. 1.21 Right side 2RV and 21V test. i x DEPREL3 and HOLD the " TEST" pushbutton associated 'sith the 2RV f and 21V until the associated "2RV CLOSED" and "2IV CLOSED" indicators are illuminated and "2RV OPEN" and "2IV OPEN"
- .h ([ \ indicators are off.
& $[3 , t 1). Locally VERITY / OBSERVE the Right Side 2RV trave 11 fully CLOSED. , t 2). Locally VFRITY/ OBSERVE the Right Side 21V travels fully CLOSED.
- b. RELEASE the " TEST" pushbutton and VERITY 2RV and 2IV reopen as indicated by the associated "2RV OPEN" and "2IV OPEN" indicators are illuminated and "2RV CLOSED" and "21V CLOSED" indicstors off.
t__.__. 1). Locally VERITY / OBSERVE the Right Sids 2RV travels fully OPEN. I f 2). Locally VERITY / OBSERVE the Eight Side 2TV travels fully
.. [ , OPEN.
- &,.(
s 14 22 Lef t Side 3RV and 3IV test.
- DEPRESS and HOLD the " TEST" pushbutton associated with the 3RV and 31V until the associrated "3RV CLOSED" and "3IV CLOSED" indicators are illuminated and "3RV OPEN" and "3IV OPEN" indicators are off.
t 1). Locally VER;TY/ OBSERVE t;he Lef t Side 3RV travels f ully CLOSED. (m) t 2). Locally VERITY / OBSERVE the Lef t Side 3IV travels fully CLOSED. (0529V/00497/082889)
- . - _ , _ . . . - _- .- . ..-- . . -.- - ~ . . - . . -
I t IBOS 3.4.2.o.1 i Revisios 2 .
.g b. RELEASE the " TEST" pushbutton and VERIFT 3RV and 3IV reopen as indicated by the associated "3RV OPEN" and "31V OPEN" ladicators
- f(-
are illuminated and "3RV CLOSED" and "31V CLOSED" indicators off.
# 1). Locally VERITY / OBSERVE the Lsit Side 3RV travels fully OPEN. [
t 2). Locally VERITY / OBSERVE the Left Side 31V travels fully OPEN. t i 1.23 Right side 3RV and 31V test. ; h a. DEPRESS and HOLD the " TEST" pushbutton associated with the 3RV and 3IV until the associated "3RV CLOSED" and "3IV CLOSED" i indittators are illuminated and "3NV OPEN" and "31V OPEN" indicators are off, I p 'j)n \ W . 1). Locelly VERIFY / OBSERVE the Right Side 3RV travels fully CLOSED.
\'\ t_ 2). Locally VERITY / OBSERVE the Right Side 31V travels f ully ;
CLOSED. [
- b. RELEASE the " TEST" pushbutton and VERIFT 3RV and 31V reopen as f indicated by the -associated "3RV OPEN" and "31V OPEN" indicatorsi !
-are illuminated and "3RV CLOSED" and "31V CLOSED" indicators off. 3
# 1). Locally VERIFT/ OBSERVE the Right Side 3RV travels fully !
OPEN. l I
- \ '
t 2). Locally VERIFT/ OBSERVE the Right Side 31V travels fully OPEN. i VERITY valve position limit reset to-its pretest value. ,
.. g .
- Perform steps T.1.25 end T.1.26 if it is desired to *
- transfer the Governor Valves f rom "SINCLE VALVE" the l
* " SEQUENTIAL' VALVE" mode of operation at the discretion
- l
- of the Shif t Eng!xeer, otherwise proceed to _ step r.l.27. *
........................................+....................... j l
...........................................................r.... ;
- CAUIIM -l
- IT RAPID VALVE OSCILLATICES OCCURS, THEN DEPRESS "WRBINE [
- MANUAL" (M THE DEH 'IURBINE PAKEL, AND "GV RAISE" OR "GV * ;
* = LOWER" TO ADJUST GOVERNOR VALVE POSITION TO MAINTAIN
- DESIRED TURBINE LOAD. ,
i t i
?
APPROVED ! l ! 1~ AUG 2 81989 i i ' . . .R. (0529V/0049V/082889) _.. -A.,..'. - w n v .:- , , -
i l 1805 3.4.2.a-1 Revision 2 en.......a***ene................. .............. **.***a .....a
- tKZII
(
- The transfer f rom single to sequential valve mode may *
- require several minutes. Upon depressing the pushbutton, *
- the SINGLE VALVE lamp will go out and tha SEQ VALVE lamp
- will begin flashing. Completion of the transfer is *
- Andicated by the SEQ VALVE lamp being steady on.
.................. .......................... .aen.... ana ......
(W' 1.25 DEPRESS " SINGLE VALVE /SEO VALVE" pushbutton on the DEH Turbine Control Panel located on IPM02J. L 1.26 VERITY the SEQ VALVE lamp is steady on. 1.27 VERITY / PLACE the U-1 NDCT Turbine Trip Interlock Control Fwitch to NORMAL, if desired. l INDEPENDENT VERITICATION
*e ne** e ena nn eeennee n ame n a*n eanane ne ne n a nnaann emen *** **aea n n ** e n.
, s_ llQTE jTkfollowinfste, s are to be performed in conjunction with **
.a Plant Startup ing performance of the applicable '
*Mortions of IBGP 100-2 and/or 1BGP 100-1.
noene******nneene***********ne****en**$a*********e****enan***e 2.0 Testing _Rurino Plant Signtup g M 2.1 ENSURE an operator is stationed to directly observe the movement of each valve to be tested through one cornplete cycle f rom the running position. 2.2 During the step for PREPARATION FOR ROLLING Ti!E MAIN 'IURBINE (IBGP 100-2), locally ENSURE the following D a. All ISV's are OPEN.
- b. All RSV's are OPEN.
All Governor Valves are OPEN. 2.3 When the TURBINE TRI A pushbutton is depressed (IBGP ' 100-2), locally VERITY / OBSERVE the following: WW a. Lef t Side IRV traveled fully CLOSED. t b. Right Side 1RV traveled fully CLCSED. t c. Lef t Side 2RV traveled fully CLOSED. tU . Right Side 2RV traveled fully CLOSED. t e. Lef t Side 3RV traveled f ully CLOSED. APPROVED W f. Right Side 3RV traveled f ully CLOSED. gggg
-15' B.O.S.R.
(0529V/0049V/082BB9)
IBOS 3.4.2.a-1 Hsvision 2 l ('N! t" 9 Left Side 11V traveled fully CLOSED. t V ^ t.L/ h. Right Side IIV traveled fully CLOSED, t 1. Left Side 2IV traveled fully CLOSED. W j. Right Side 21V traveled fully CLOSED. ; t k. Left Side 31V traveled fu.sy CLOSED. t 1. Right Side 3IV traveled fully CLOSED. t1 m. Governor Va?ve No. I traveled fully CLOSED. 4 W n. Governor Valve No. 2 traveled fully CLOSED. t o. Governor Valve No. 3 traveled fully CLOSZD. t p. Governor Valve No. 4 traveled fully CLOSED. 2.4 Nhen the TURBINE LATCH Pushbutton is depressed following the Tusbaw Trip (IBGP 100-2), locally ENSURE the following: W a. Lef t Side 1RV traveled fully OPEN. t b. Right Side 1RV traveled fully OPEN. im W (U c. Left Side 2RV traveled fully OPEN. (M ' d . Right Side 2RV traveled fully OFLN. t ', , - e. Lef t S!.de 3RV traveled fully OFLh. , t f. Right Side 3RV traveled f elly Wrff. t/$ g. Lef t Side 11V traveled filly OPEN. h Right Side IIV traveled tully OPDi. t h.
# 1. Lef t Side 2IV travelel fully 0FM.
n f Y- j. Right Side 21V travelsd fp)1y DPIN. tf k. Left Side 3IV tra.'eled fully OPEi. t .b i
- 1. Right Side 31V travelc4 fully OPEN.
t m. Governor Valve No. I traveled fully OPEN. Ce t t- n. Governor Valve No. 2 traveled fully OPEN. t o. Governor Valve No. 3 traveled fully OPEN.
.q '4 ,.
APPROVED (j t p. Governor Valve No. 4 traveled fully OPEN. AUG 2 81989
-le- B. O. S. R.
(0529V/0049V/082889)'
_m. ._ _ _ _ 1805 3.4.2.c-1 Revision 2 4
/'
2.5 During the step for T'JRDIHE SPEED INCREASE TO IMQ RPM (IBGP 100-3), T]/ locally ENSURE:
- a. All Throttle Valves are OPEN.
2.6 During the step for ACWAL WRBINE TRIP TEST (IBGP 100-3), locally ENSURE the followings W .__ a . Throttle Valve No. I traveled f ully CIA. .:D . b ( / b. Throttle Valve No. 2 traveled fully CLOSED. Wf c. Throttle Valve No. 3 traveled fully CLOSED. W. d. Throttle Valve No. 4 travelvd ful)y CLOSED. 2.7 When the turbine is latched and the TRANSTER TV-GV Pushbutton is depressed (IBGP 100-3), locally ENSURE thu following W a. Throttle Valve No. I traveled fully OPEN. W b. Throttle Valve No. 2 traveled fully OPEN. .j
#_ c. Throttle Valve No. 3 traveled f ully OPEN.
W,. d. Throttle Valve No. 4 traveled fully OPEN. , (O/- G. ACCEPTANCE CRIIERIA1
. 1. Ew;h.high pressure turbine throttle and governor valve and each low pressure turbine reheat and intercept valve shall be cycled-through one complete cycle from 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.
6 APPROVED
-A
(^,) (Pinal) AUC 2 01909 B.O.S.R. (OS29V/0049V/032BB9)
1BOS 4.6.2.1.e-1 Revisien 51 l
- REACTOR COOLANT SYSTEM CONTROLLED LEAKAGE MONTHLY SURVEILLANCE Q.
b A. STATEMENT OF APPLICABILf'nlf This procedure applies to the monthly verification of Reactor Coolant System Controlled Leakage in Modes 1, 2, 3 and 4. B. REFERDICES t
- 1. Technical Specification Surveillance 4.4.6.2.1.c.
C. PREREQUISI_TESJ
- 1. Receive permission f rnn the Shift Engineer or designated SRO Licensed Assistant prior to performing this surveillance by having the Data Packaga Cover Sheet signed and dated.
- 2. Reactor Coolant Pressure det ,en 2215 and 2255.
- 3. One Centrifugal charging pump shall be in operation and flow control valve FCV-121 shall be under aut;matic pressurizer icvel control.
D. PRECAUTIONS: .
- 1. As defined by Technical Specification, CONTROLLED LFMAGE rhell be that seal water flow supplied to the Reactor Coolant Pump sesis.
[D ( E. LIMITATIONS AND ACTIONS _t
- 1. As stated in Technical Specification Limiting Condition for Operation 3/4.6.2. ,
- 2. If the Acceptance Criteria is not met, IMMEDIATELY notify the Shift Engineer to initiate LCOAR procedure 1BOS 4.6.2-la.
T. MAIN BODY:
- 1. RECORD the Time and Dates TIME _id 9D DATE 3 / ls /9/
- NOTE
- Perfonn Steps F.2 through F.4 quickly to prevent an **
- excessive change in Pressurizer Level.
FOR REFERENC 1
/G APPROVED =
Q (2514P) kij314 G85
- 9. O. S. P i -- .
1BOS 4.6.2.1.c-1 Revision 51 1 PLACE mv 121 in MANUAL and slowly OPEN to 100%. LF2. ADJUST HCV 182 as necessary to MAINTAIN Total Seal Injection Flow to O M3. all 4 RCP's 1 40 gpm.
- 4. RII:ORD individual RCP Seal Injection flows, position of ICl-121, and RCS pressure.
RCP SEAL INJECTION TLOWS
- a. lA RCP (IRC01PA) IFI 145A 9.l gpm
- b. 1B RCP (IRC01PB) 1FI 144A ?f gpm
- c. 1C RCP (IRC01PC) 1FI 143A 4.I gpm
- d. 1D RCP (1RC01PD) 1FI 142A %1 gpm NV-121 position /CO % open(100%)
- e. c_
- f. RCS pressure c ?s4c psig(2215-2255 psig)
[ 5. ADJUST HCV-182 to ESTABLISH normal charging and seal injection flows. N 6. SUM the . seal injection flows f rom step 4 and enter: e 3 (c . (e (1 40 gpm). M 7. ADJUST FCV 121 to MAINTAIN normal pressurizer level, then PLACE NV 121 in AUTO. . NCTIIIT the Shif t Engineer that this surveillance ist completed. f 8. G. ACCEPTANCE CRITERIA:
- 1. RCS CONTROLLED LEAIAGE at a Reactor Coolant System pressure of 2215 to 2255 psig shall be limited to 40 gpm with NV-121 100% OPEN.
FINAL. APPROVED Ay3 14 $85 3 ,,
- 9. O. S. P
1908 4. 6. 2.1.d-1 R: vision 2 ; l REAC"IDR COOLANT SYSTEN WATER INVENTORY BALANCE 72 HOUR SURVEILLANCE 'L A. gn7txnrr OF APPLIc1BILITY1 This procedure provides the steps necessary for detemining the Reactor Coolant System identified and unidentified leakage in Mode 1, 2, 3, and 4 using a hand calculation, or the Process Computer RCS Leakrate Code. l B. REFERENCES 2
- 1. Technical Specifications 4.4.6.2.1
- 2. NUREG-0986
- 3. Station Procedures:
- a. BCP 300-9 Steam Generator Tube Leak Rate Determination
- b. 1BOS 4.6.2-la, LCOAR - Reactor Coolant System - Operational Leakage C. PREREQUISITES: ,
- 1. Receive permission f rom the Shif t Engineer or designated SRO licensed assistant prior to perfcraing this surveillance by having the Data I. Package Cover Sheet signed an.d dated.
/2. Divert valve ICV 112A must be in the VCT position. - IF ICY 112A is diverted to the EUT,' THEN terminate the surveillance and restart only when ICV 112A is in the VCT position.
- 3. When performing _the Computer Code method of this surveillance -the following asemptions are made due to instrument limitations.
Therefore, the computer can only be used in Moden 1, 2 and- 3 with the following conditions:
- a. The pressuriser must-be in a condition of sattiratloa.
- b. RCS pressure must be between 2150 and 2350 PSIG.
- c. RCS temperature (TAVG) must be between 530 and 650'r.
- d. . RCDT pumpdowns are not allowed during the course of this procedure,
- 4. In the event the Process Computer is going to be used for the leakrate calcult cion, the Process Computer will need ,to be rable over the entire surveillance period.
y o APPROVED V AUG 141989 (0793V/0068v/070889) B.O.S.R.
1BOS 4.6.2.1.d-1 tovision 2 l D. REICAUIICllS1
- 1. While performing leak rate calculations, plant parameters must remain
(\_/'~} fairly coustant (e.g. no power significant changes or menon oscillations). Considerations should be given to making borations/ dilutions prior to initial data taking such that RCS Tave remains fairly constant.
- 2. Any draining or snmpling activities must be terminated during '.he performance of this surveillance.
- 3. Any drain inputs or outputs to the PRT or RCDT other than f rom RC or CV, must be terminated during the performance of this surveillance.
- 4. Makeup to the VCT may invalidate the results of this calculation.
Minimise the need for makeup by starting with a VCT level on the high
.end of the normal Aperating band.
E. L11112ATIQ{S_.AND ACTICHFd
- 1. As stated in Technical Specification 3/4.4.6.2.
- 2. In the event the Acceptance Criteria is not met during the performance of this surveillance, IMHEDI ATELY notify the Shif t .
Engineer to initiate LCOAR 1BOS 4.6.2-la.
, 3. Required data taken during the performance of this procedure shall be recorded on the surve111suco data sheet.
6 r. HAIE_aQnit HDIE
- If using the Process Computer Leak Rate Program to *
- determine the RCS Leak R4te THEN perform Section A and *
- use the Process Computer Data Sheets. IF manually *
- calculating the RCS Leak Rate THER perforu Section B and *
- use the Manual Calculation Data Sheets.
- e e e eno . .....ee n e * *. .....ee e e ee n o.....e e s e ee n e.n e.. . .... n o SECTICH A, PROCESS CCMPUTER LEAK RATE CALCULATICH:
- 1. RECORD start Date.
- 2. Manually pun.p down the RCDT to a lov level, if desired.
- 3. PLACE the RCDT pumps to the STOP poaltion.
- 4. RECORD the following initial data on da s sheets
- a. PRIMARY WATLR/ BORIC ACID TOTAL IuJW IhTEGRATOR readis.g.
- b. RCDT Level & Temperature (obtain readings locally at panel ORE 01J from Rad Haste Operator).
7. k c. TIME / INITIALS. JAPP Ft(31/ EEE) Aug 141969 i (0793V/0068V/070589) 8.O.S.R.
1905 4.6.2.1.d 1 Revisica 2 aanne*******eene neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeneseenesee
- HQTE *
- Ramping the Unit, load following, boration/dllution for *
( ; ls
- Tave/AI control will not allow the RCS parameters to *
- be steady long enough for a valid RCS leaktate. The
- 3
* . optimum time f rame for the leak rate is 2 hours but may *
- be changed at the discretion of the SE/SCRE. *
****enen e n eesen eeeeeeeeeee**eess eeeeenesee nes ee n emonee se neee ee e n
- 5. AFTER the desired time has elapsed, RECORD the final data for tha parameters listed above in step 4.
- 6. DEPRESS " MENU" on the Process Computer Terminal.
t
- 7. SELEC? Ca oup $29, RCS Leak Rate menu option and DEPRESS the esecute button. ,
r m ee eee e ee ee e e e eeeeee eee eee e e e eeee e**mee ee e e*** * ** e e e ee e e e e ee e e es
- HDIE l
- The Lesst Squares fit Method is the pref erred method. *
- IF the t oast Squares rit is unacceptable, a Point to *
- Point Method Leak Rate Calculation may be used. If the * !
- point to point method is unacceptable the computer method
- a may not be used. Continue to Section B for Manual Leak * .
*- Rate Calcualtion. * ,
.ieeeeeee**.neeeeeeeeeeen neenseeeeeeeeeeeeeee***eeeeeeeeeeeeeeen :
-[ [ 8. ENTER the following: .f
[sp a. Select "1" for Least Squares Calculation method, or select "2" 1 ( ,J ._
- for Point to Point Calculation. .
- b. Select desired output device. ,
- c. ENTER recordsd PM/ BORIC ACID INTEGRATOR initial and final values ;
into ths provided entry fields.
- d. ENTER recorded RCDT initial and final values into the provided entry fields.
- e. Of7ER a "0" for the initial and - final RCDT pump run times.
- f. SELECT the desired time interval, correreunding to stop 4.c.
- 9. DEPRESS execute and obtain output.
- 10. Evaluate Erc_r/Marning messages against Appendix B and.INITIAT4 6.ny required action.
- 11. If the output results are acceptable attach printout and proceed to step 12.
APPROVED AUG 141989 O b/ B. O. S. R. (0791V/0068V/070889)
IBOS 4.3.2.1.d-1 Rovision 2
...........$e................................... ..n..... ......
HQTE
- O
- If the confidence error is greater than the acceptable
- limit or the correlation coefficient is lower than the acceptable limit an error code will be printed.
enneene **nnennenaa.nemanneannemanennenneenanneenneenmeenaneenen
- 12. COHPLETE the Process Computer Data Sheet.
- a. CIRCLE the method used.
- b. CALCULATE the Total Identified Leakage by adding the latest S/C Tube Leakage tn the Known Leakage.
- c. Total S/G Tube Leakage.
- d. Individual S/G Tube Leukage,
- e. DETERMINE the Unidentified Leakage Rate by subtracting the Total Identified Leak Rate f rom the Reactor Coolant Gross Leak Rate.
- f. PLACE the RCDT pumps to the Auto position. INITIAL Data Sheet and receive Independent verification by having another NSO initial the Data Sheet.
- g. DETERMINE if 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. IF the acceptance criteria is not met, IMMEDIATELY notify the
, Shif t Engineer to initiate LCOAR 1BOS 4.6.2-la and then PAOCEED to Appendix A to help locate and isolate any leakage sources.
i APPROVED AUS I 41989 B. O. S. R. l (0793V/006tv/0708L9) l
1805 4. 6. 2.1. d-1 R;visica 2 SECTION B, MANUAL POINT TO POINT LEAR RATE CALCULATION n v aa2z . Use the process computar to call up the individual points. .
* (Group 105) If it is not available, use instrumentation *
- on MCB. - .
- 1. RECORD start Date.
- 2. MANUALLY pump down the RCDT to a lov level, if desired. !
- 3. PLACE the RCDT purtps to the STOP position.
- 4. RECORD the following laitial datas
- a. PZR LEVEL, Point OLO480, LO481, or LO482 and RECORD point used.
- b. PZR TEMPERA 7URE, Point GT0480.
- c. VCT LEVEL, Point OLO112.
- d. PW/ TOTAL TLOW INTEGRATOR reading. .
tLQII .
- If Tave < $H'T omit step,e. If Tave 1 3E*r
- v]
[
- v. alt steps f & g.
g
- e. RC Tave (average) Point OUO484 for Tave's 1530'T.TNod J4ud W w ftLTAQk (lf4)\
- f. HCrf LEG WR TEMPERATURE, Point l's T0419, 70439, 70459, and 70479.
- g. COLD LEG NR TEMPERATURE, Point 8
- s 70406, 70426, 70446, and 70466. _
- h. PRT LEVEL, Point GLO485.
- 1. PRT TEMPERA 7URE, Point 70485
- j. RCDT LEVEL, (obtain reading locally at panel CRE01J f rom the Rad Maste Operator). M b. WblRebT
- k. TIME /INITTALS APPROVED
/
( AUG 04 29
-5 s.o.s.n.
! (0793V/0068V/070889) i
.~s
IBOS 4.6.2.1.d-1 R visios 2
. amenenneenseneer reneseeeeeeeeeeeeen ne e eeeeeeeeeeeeeeeeeeeeen
- HQ11 *
/
- Ramping the Unit, load following, boration/dllution for a
}
\./ -
- Tave/41 control will not allow the RCS parameters to *
- be steady long enough for a valid RCS leskrate. The *
- optimum time frame for the leak rate is 2-4 hours but may *
- be changed at the discretion of the SE/SCRE.
- eeeeeeeeeeeeeen neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- 5. ATTER the desired time has elapsed, RECORD the final data for the parameters listed above, in step 4.
- 6. DETERMINE the difference in PZR level (fing1-initial) and convert it to gallons.
- 7. DrTERMINE the dif ference in VCT level (final-initial) and convert it to gallons.
- 8. DETERMINE the tots 1 makeup volume by subtracting the initial integrator reading f rom the final.
ne****=eeeeeeeeeeeeeeen*eneesenenennene *ene.**enenene neenennen a gggg a
- If Tave < ilQ*r omit Stip 9. .If Tavs 1 310'r omit Step 10. * .
e a e ne n m e e n n e e e e e ee e e e e e e n e n e n e ***
- e e e e e e e e e e e e e e e n e n....e e e e e e e n.e l' 9. With Tave 1310'r, DETERMINE, the RCS Average Tave.
~
- 10. With Tave < IM*T, DETERMINE average tave by totaling ti.e Hot i. Cold leg temperatures and dividing by 8 for both initial and final data
. and - then DETERMINE the RCS Average Tave.
- 11. DETERMINE the change in RCS density by selecting a value for Ap/'r f rom Table A using Ave T ave and multiplying it by the change in Tave.
- 12. CALCULATE A RCS volume per the Data Sheet.
- 13. DETERMINE the average PZR temp and obtain the p PZR f rom TABLE B.
- 14. DETERMINE the Ernas Leakage Rate by performing the calculation on the Data Sheet.
- 15. OBTAIN PRT (Final and . initial) gallons and density f rom TABLE D and C respectively, and . enter into the APRT mass equation.
- 16. CALCULATE APRT mass and RECORD the results.
- 17. DETERMINE the laakage into the PRT by performing the calculation on the Data Sheet.
APPROVED U AUG 141989 B.O.S.R. (0793V/0068v/070889)
s% 1 A $3h y e: g-~ 4'0 0, v + 4 "' ,9 '. ta
't. t, V IMAGE EVAL.U ATION
\ /,o// 'k.[ $f8 TEST TARGET (MT-3)
/ f).f/ eg
.pp %'E' hs f
+
l.0 "t " M i l ,;l BEE l.I f"'EM= l "l!{, m.8 m l.25 1.4 [ 1.6 _= 4 150mm > 1 4 6" >
$?%y
,97 @p,j> ' jy ,
-- - ~-~- -
/%f.gTe ggy N
'Q' ,
- (fQb Kf
<p <p o;, , .
/ ; 19
'n .
- b .
. .)
s
'v @@ Y vcf 3% 1 IMAGE EVAL.U ATION c
3%
.4
\ 4' /
~
\ ha,b 0 ,[, ?
TEST TARGET (MT-3) n %,
~ .,
c ?p
\\ %9' sh~o*
'$9 Y+hf 4e l.0 i iL't E " BE 1.
Y.!- .: l,l - On 1.25 1.4 g 1.6 9, 4- 150mm *
- 6" *
- w. . A?% "O ;r '
/ ..
/ 9%sse u. la
<{k.b '. ,.
- o O '
9@ eg$
T zy p E l%(gw IMAGE EVALUATION , s Je, R. O g'j[, /
\o -( '
<'( f9 TEST TARGET (MT-3) ; f ,jg 8a
>gg,
%s# 9
& try,4g%;'f 4 l.O ,
- u m
L. _. i, ti ^ME L $ \ l,l u == =
~
ul I.8 U-ma 1.25 il I.4 i ll - rdc=.6 4 150mm > 4 6" > A or L> ry,% t jy ,jA ;, - - -
+++,,fr
<p,o v xxN f go ;f::,
oyj gy.e
,p
'"~ . - ., , l. , ]
L_- _ .. . . ,
190S 4.6.2.1.d-1 R: vision 2
- 18. OBTAIN FCDT (Final and Initial) gallons f rom TAELE E and determine the leakagc into ths RCDT by perterming the calculation on the Data
.fS Sheet. I / ~
"'~I 19. DETERMINE the RCS Known Leakage Rate by performing the calculation on the Dsta Sheet.
- 20. OBTAIN the latest RC Steam Generator Tube Leakage Rate and add it to the- RCS Known Leakage Rate to obtain the Total Identified Leakage Rate.
s n e e e e ee ee eee * * ** e * **e e ee e e e e e e e e e e e e ee e** : e e e e e m e n e e se e e e e e e e e n a gg23 e
- The A error calculated for the Gross Leakage Rata must be e e carried over to the Unidentified Leshage Rate in step 21 *
- and must be assessed as a penalty when comparing the e
- calculated Unidentified Leakage Rate to the Acceptance e
- Criteria. e neeeeeeeeeeeeeeeeeee.....mee....eeeeeeeeeeeeeeeeeeeeee...... een
- 21. DETERMINE the Unidantillad Leakage Rate by subtracting the Identified Leakage Rate f rom the Gross Leakage Rate.
- 12. PLACE the RCDT pumps' to the AUTO position. INITIAL Data Sheet and
- receive INDEPENDENT VERIFICATION by having another NSO initial the Data Sheet.
/
- 23. DETERMINE if acceptance criteria is met and signify such by placing a fLg circle on yes or no on the Data Sheet and INIT1 I. and date space provided.
$v)
- 24. IT the acceptance criteria is not met, IMMTDI ATELY nu ,' f ? the Shift Engineer to initiate LCOAR l'OS 4.6.2-la and then PROCEED to Appendix A to help locate and isolate any leakage sources.
G. ACCEPTANL'E CPITERIA;
- 1. RC Leakage Rate shall be less than or equal to lQ gpm Total l Identified and 1 gpm Unidentified. Included in the IQ gpm Identified Leakage, Reactor to Secondary Leakage through all Steam Generators not isolated f rom the RCS shall be less than or equal to 1 gpm with no more than 192 gpd (1347 GPM) through any one Steam Generator. l.
AP.* ROVED
;(y' -
- AUG 141969 B. O. S. R.
(0793V/0068V/070889)
.. . __. - . _m . _.__ __ . __ _. -. _ _ _ ..
1906 4.6'2.1.d-1 R4 vision 2
.f 7ABLE A V['~} AVERAGE RATE Or CEANGE Or - DENSI7T PER 'r f i
rOR COHPRESSED LIQUID A7 2250 PSIA , Aye Tave og a ( /ft Aye Tave og = i */ft ) Ave Tave og n ( "/ft ) (*r) 'r 'r (*r) 'r 'r (*r) 'r *r ! i t 200-209 0.023 430-439 0.043 575-579 0.074 ; 210-219 0.025 440-449 0.045 580-584 0.076 i 220-229 0.025 450-459 0.045 585-589. 0.080 l 230-239 0.027 460-469 0.048 590-594 0.082
- 240-249 0.027 470-479 0.048 595-599 0.084 -i 250-259 0.027 480-489 0.050 l 260-269- 0.029 490-494 0.050 270-279 0.029 495-499 0.052 280-289 500-504
{ 0.030 0.054 290-299 0.030- 505-509 0.054
- 300-309 -0.032 510-514- 0.056 7 310-319 0.032 515-519 0.056 320-329- -0.033 520-524 0.056 i j 339-339 0.034 525-529 0.058 ,
[
?v s - 340-349 0.034 530-534' O.060 )
i 350-359 0.036 535-539 0.062 ! 360-369 0.036 540-544 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 $60-564 0.068 :
410-419 0.041 565-569 0.070 l 420-429 0.042 ! 570-574 0.072 I t
}
I APPROVED fQ j ._ AUG 141989 B. O. S. R. l (0793V/0068V/070389) i f tr -- .- 2 -
. - -- .. - . - . - - - - . ~ _ - ~ - . - - . . - . . - - .. - -
{ M r t* s w * == = IBOS 4. 6. 2.1.0 1 , AW 14W .
'i.vi. ion 2
"~
- 5. U.S. R.
i TABLE B- l ' - DENSITY OF l
- SATURATED TLUIDS/ GASES I,
! Temp ('r) p(1bm/ft3) Temp ('r) p(1bm/ft3) [ 400 53.65 600 42.3012 t 410 53.2481 602 42.1408
-420 52.7983 604 41.9815 430 52.3697 606 41.8060 440 51.9211 608 41.6320
+' 450 51.4536 610 41.4594 455 51.3149 612 41.:882 460 50.9944 614 41.1015 465 50.7421 616 40.9165 470 50.5051 618 40.7332
~475 50.2513 620 40.5515 480 50.0000 622 40.3633 485 49.7265 624 40.1768 490 49.4682 626 39.9760 495 49.2126 628 39.7772 500 48.9476 630 39.5804 505 48.6559 632 39.3856 510 48.3793 634 39.1773 l 515 48.1058 636 38.9712
- 520 47.8240- 63s St.7522 525 47.5172 640 30.5356 530 47.2255 641 -
38.4246 535 46.9208 642 38.3142 0 540 545-550 46.5983 46.2963 45.9664 643 644 645 38.2044 38.0952 37.9795
- 552 45.6295- 646 17.8644 554 45.7038 647 ,
37.7501 556 45.5789 648 37.6364 558 45.4442 649 37.5164 l' 560 45.3104 650 37.3972 j 562 45.1671 651 37.2787 j
$64 45.0248 652 37.1609 566 44.8833 653 37.0336 568 44.7427 654 36.9072 570 44.3030 655 36.7816 572 44.4642 656 36.6569 574 44.3164 657 36.5230
.576- 44.1696 658 36.3901 578 44.0238 659 36,2582
-580 43.8789 660 36.1272 582 43.7254 661 35.9874 584 43.5730 662 35.8487 586 43.4216- 663 35.7111 588 43*.2713 664 35.5745 590 53.1127 665 35.4264 592 42.9553 666 35.2796 594 42.7991 667 35.1339 596 42.6439 668 34.9895 34.8280
,O
-598 42.4719 669 670 34.6681 9
0793V/0068V/080389
1906-4.6.2.1.d-1 Revision 2
- TABLE C CCNPRESSED LIQUID AT 50 PSI A T(*F) of /ft i T('F) of /ft ) T('r) gi /ft 1 *rf*F)
. of Dft $
50 62.42 70 62.32 114 61.81 158 61.04
-51 62.42 71 62.31 115 61.80 159 61.02 52 62.42 72 62.N 116 61.78 160 , 61.00 53 62.41 73 62.29 117 61.77 161 60.98 54 62.41 74 62.28 118 61.75 162 60.96 55 62.40 75 62.28 119 61.74 163 60.94 -
56- 62.40 76 62.27 120 61.72 164 60.92 57 62.40 77 62.26 121 61.71 165 60.89 58 62.39 78 62.25 122 61.69 166 60.88 59 62.39 79 62.24 123 61.67 167 60.86 60 62.38 80 62.23 124 61.66 168 60.84 61 62.38 .81 62.22 125 61.64 169 60.82 62 62.37 82 62.21 126 61.63 170 60.79 63 62.36 83 62.20 127 61.61 171 60.77 64 62.36 84 62.19 128 61.59 172 60.75 , 65 62.35- 85 62.18 129 61.58 173 60,73 66 62.34 86 62.17 130 61.56 174 60.71 67- 62.34 87 62.16 131 61.54 175 60.69 68- 62.33 88 62.15 132 61.53 176 60.67 62.32 89 62.14 133 61.51 177 60.64
-o_ -
69 90 91 62.13 62.11 134 135 61.49 61.47 178 179 60.62 60.60 92 62.10 136 61.46 180 60.58 93 62.09 137 61.44 181 60.56 94 62.08 138 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 61.33 181 60.42 100 62.01 144 61.31 186' 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 6L.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 S F"F"M O V E D -O AUS 141989,- (0793V/0068v/070889) . O. S. R.
' ~
h
~
v l 1805 4.6.2.1.d-1 Revision 2 i PRESSURIZER RELIEF TANK, (PRT) LEVEL / VOLUME CONVERSIONS l TABLE D
% LEVEL VOLUMEfGAL) % LEVEL VOLUMEfGAL) % LEVEL VOLLMEfGAL) % LEVEL VOLUMEfGAL) % LEVEL VOLUME (GAL)
. 0 322.81 21 2530.40 41 5402.34 61 8474.01 81 11300.15 1 394.59 22 2661.97 42 5554.89 62 8624.95 82 11426.24 2 tiO.94 23 2795.20 43 5707.89 63 8775.25 83 11550.34 3 551.57 24 2930.u3 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 9660.03 89 12248.02 9 1112.52 30 3768.65 50 6786.37 70 9904.09 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 10088.82 92 12561.97
, 12 1434.92 33 4204.05 53 7249.64 73 10229.34 93 12660.64 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 10777.54 97 13021.17 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 80 11172.16 100 13249.93 20 : .0. 58 322.82 gal to top of tank f
. APPROVED AUG 141989 (0793V/0068V/070889) B.O.S.R.
/3 A
/]
I . IBOS 4.6.2.1.d-1 Revision 2 l l REACTOR COOLANT DRAIN TANE, (RCDT) LEVEL / VOLUME CONVERSIONS l TABLE E I l i
% LEVEL Vof fwidif-) % LEVEL Vnf YMidif-) % LEVEL V"f fM I n a r ) g Lgygt vnt_frME f CAL) % LEVEL VOLthIf dat-)__
0 17.84 21 74.36 41 144.70 61 219.73 81 288.91 1 19.96 22 77.58 42 148.43 62 223.42 82 291.97 2 22.15 23 80.85 43 152.17 63 227.09 83 295.00 3 24.42 24 84.16 44 155.91 64 230.75 84 298.00 l 4 26.74 25 87.50 45 159.67 65 234.39 85 300.94 5 29.13 26 90.88 46 163.42 66 238.01 86 303.85 6 31.59 27 94.30 47 167.19 67 241.62 87 306.72 7 . 34.10 28 97.74 48 170.96 68 245.19 48 309.54 8 36.67 29 101.22 49 174.73 69 248.75 89 312.31 9 39.29 30 104.73 50 178.50 70 252.28 90 315.04 10 41.97 31 108.26 51 182.27 71 255.78 91 317.71 11 44.69 32 111.81 52 186.05 72 259.26 92 320.33 12 47.47 33 115.39 53 189.81 73 262.71 93 322.90 13 50.29 34 119.00 54 193.58 74 266.12 94 325.42 14 53.15 35 122.61 55 197.34 75 269.50 95 327.87 15 56.06 36 126.26 56 201.09 76 272.85 96 330.26 16 59.01 37 129.92 57 204.84 77 276.36 97 332.59 17 62.00 38 133.59 58 208.58 78 279.42 98 334.85 18 65.03 39 137.28 59 212.31 79 282.64 99 337.04 19 68.10 40 140.98 60 216.02 80 285.80 100, 339.15 20 71.20
- 17.84 gal to top of tank l APPROVED AUG 141989 8.O.S.R.
l 1BOS 4. 6. 2.1.d-1 R3visloa 2 Appendia A
,-\
(s,- ) LIAEAGE SQURCES CHECELISI . 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 equit eent 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. ALARA concerns should be considered as well when determining the order of checks. It should be noted that a leak rate calculation need not be performed af ter isolating each component. Maintaining Pressurlier level and Tave constant will result in the slope of the VCT 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 eliminated as a source of leakage. i enanneeeeceeeeee**eneeeeeeeeeeennemmeneenemonene***enenneneen...
- NOTE *
- Excess letdown has n2 cleanup capability. Therefore the
- nornal letdown flowpath should only be isolated for as *
- long e6 it takes to determine whether it is a source of *
- 1ealege. *
, eene...S.eenennenene nemenenanneeneenenennemannen. .eeee........ f N () 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 normal letdown flowpath. If this proved to be a source of leakage, then further steps could be taken once normal letdown is restored. Switching le<.$own heat exchangers, bypassing domineralisers, bypassing the RC filter, and isolating the ICV 112A flowpath to the HUT's are all steps that should be conaldered. Any components listed below 'tdiat have been checked for proper alignment should be initialed as such in the appropriate space. This will prevent unnecessary rechecks 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. VERITY / ISOLATE the valves / components one at a time (unless otherwise authorized 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 I 41989. (0793V/0068V/070889) * *
- t IBOS 4.6.2.1.d 1 .
Revisica 2 !
. ggyg . - l-A$
- Notify Rad Chem prior to changing the pcsition of any *- i
-Q a process sampling valves.
j Procena same11ng f i IPS9354A PZR Stm Sample Inside Isol V1v IPM11J ! i^ 1PS9354B PZR Sta Sample Outside Isol Viv 1PM11J I 1PS9355A PER Lig Sample Inside Isol Viv 1PM11J j 1 1PS9355B PZR Lig Sample Outside Isol Viv IPM11J } IPS9356A RC Loop Sample Inside Isol V1v IPM11J IPS9356B RC Loop Sample Outside Isol V1v IPM11J i IPS9358A RC CL Sample Isol V1v Loop 1 1PS27J 1PS93588 RC CL Sample Isol Viv Loop 2 1PS27J r 1 1PS9358C RC CL Sample Isol Viv Loop 3 1PS27J f i IPS9358D RC CL Sample Isol V1v Loop 4 1PS27J ; i 1PS9351A- RC RL Sample Isol Viv Loop 1 1PS27J t -
-y n IPS93518 RC RL Sample Isol V1v Loop 3 1PS27J !
, t IPS9350A PZai Sta Sample Isol V1v IPS27J f i
, IPS9350B PZR Lig Sample Isol V1v IPS27J 1PS152 LTDWN EK Sample Isol V1v- IPS27J t
IPS153 CV Domin Sample Isol V1v IPS27J , i 1PS154 BR Domin Sample Isol Viv IPS27J [
+
1PS198 RC Pilter Sample Isol Viv IPS27J f Letdown Heat Exchamaer f ICV 011A LTDWN EK 1A Shell Vent V1v 383*'V16 f ICV 032A LTDWN HK 1A Tube Vent V1v 383' V10 I i l- APPROVED . D- .- AUG 141989 l p 1,_ B.O.S.R. . (0793V/0068V/070889) -[ i r I i
^
r I
~ --. ., , . . _ . . . . - ,_ _
[ 1BOS 4.6.2.1.d-1 Rovision 2 Letdown Heat Enchanger (Continued) ICV 228A LTTHH HK 1A Inlet Vent Viv 383* U16 1CV229 LTDWN HK 1A dutlet Vent Viv 364' U14 1CV0118 LTDWN HK 1B Shell Vent Viv 383' U16 1CV0328 LTDWN HK 18 Tube Vent V1v 383* U16 1CV228B LTDWN HK la Inlet Vent Viv 383' U15 Verify no flow through the following signtglasses: 1WE13MA LTDWH IDt 1A Shell Drn Sightglass 3 8 3 ' U15 l IVT10MA LTDWN HK 1A Sightglass 383' V16 INE14MA LTDWN HK 1A Shell Vent Sightglass 383' U15 IWE13MB LTDWN HK 1B Shell Drn Slghtglass 383' V15 1VT10MB LTDWN HK 1B Sightglass 383' U16 IWE14MB LTDWN HK 1B Shell vent Sightglass 3 8 3 ' V15 Seal Water HK f- ICV 008A Seal Water HK Tube Vent Viv 383' S16 V 1CV008B Seal Water HK Shell Vent Viv 383* S16 , 1CV010A deal Water HK Tube Drn Viv 383' S16 1CV010B Seal Water HK Shell Drn V1v 383' S16 1CV208 Seal Water HK Inlet Vent V1v 383' S16 Verify no flow through the sightglass: 1VT09M Seal Water HK Sightglass 383' S16 LDN CMLR H1 IBR010A LTDWN CHLR HK Shell Vent V1v 346' U16 IBR010B LTDWN CHLR HK Tube Vent Viv 346' U16 IBR013A LTDWN CHLR HK Shell Drn Viv 346' U16 1BR0138 LTDWN CHLR HK Tube Drn Viv 346' U16 APPROVED (6) AUG 141989 (0793V/0068V/070889) * * *
- t
IBOS 4. 6. 2.1. d-1 j Revision 2 l l Verify _no flow-through the following sightglassest l l -1VF12M LTDWN CHLR HK Vent Sightglass 346' U16 INE10MA LTDWN CHLR HK Shell Drn Sightglass 346' U16 INE10MB LTDWN CHLR HK Tube Drn Sightglass 346' U16 LDN RET HK 1BR002A LTDWH RHT HK Shell Vent Viv 346' U.0 1BR002B LTDWN RET HK Tube Vent V1v .346' U16 1BR003A LTDWN RET HK Shell Drn Viv 346' U16 ^ 1BR003B LTDWN RET HK Tube Drn Viv 346' U16 Verify no flow through the following sightglasses: 1VF13M LTDWN RET HK Vent Sightglass 346' U16 INE12MA LTDWN RET HK Shell Drn Sightglass 346' U16 INE12MB LTDWN RET HK Tube Drn Sightglass 346' U16 Seal Iniection Filtern A 1CV8385A 1A Seal Inj Filter Vent Viv 383' P11 U 1CV8386A 1A' Seal Inj Filter Drn Viv 383' P11 1CV838SB 1B Seal Inj Filter Vent Viv 383' P11 1CV83868 1B Seal Inj Filter Drn Viv 383' P11 Verify no flow through the following sightglasses: IVF06MA 1A Seal Inj Filter Vent Sightglass 383' P11 1WE04MA 1A Seal 'Inj Filter Drn Sightglass_ 383' Pil IVF06MB 1B Seal Inj Filter Vent Sightglass 383' P11 1WE04MB 15 Seal Inj Filter Drn Sightglass 383' P11 Seal Return Filtg1
~ 1CV8533 Seal Wtr Rtrn Filter Vent Viv 383' Pil 1CV8534 Seal Wtr Rttn Filter Drn Viv 383' Pil APPROVED o
V = Als 141989 : B.O.S.R. i t . (0793V/0068v/070889) 1 4
1BOS 4.6.2.1.d-1 R visica 2 Verify no flow through the following L Iqhtglasses:
.-O. IVF07M . Seal Wtr Rtra Filter Sightglass 383'P11 0:
1WE05M Seal Wtr Rtro Drn Sightglass 383'P11
-RC Filter ICV 8423 BC Filter Vent Viv 383' P11 1CV8424 BC Filter Drn Viv 383' P11 Verify to flow through the following sightglasses:
1VF11M RC Filter vent Sightglass 383'P11 1WE09M RC Filter Drn Sightglass 383'P11 CV Domina 1CV8515 CV Cation Domin Resin Fill / Flush V1v 410' S17 1CV8517 CV Cation Domin vent V1v 401' S17
~
1CV8520 CV Cation Domin Drn Viv 401' S17 1CV8523A CV MB Domin 1A Resin' Fill / Flush Viv 410' 517
-1CV8525A CV MB Domin -1A Vent V1v 401' S17
'% ) .
1CV8528A CV MB Domin IA Drn viv 401' S17 ICV 230A- CV MB Domin 1A Inlet Vent V1v 410' S17 1CV85:3B CV MB Domin-1B Resin Till/ Flush Viv 410' S17 , ICV 85255 C7 MB Domin IB Vent Viv 401' 517 -l 1CV85285. CV MB Domin IB Drn Viv 401' S17 I ICV 230B CV MB Domin IB Inlet Vent Viv 410' S17 t BR Domina IBR7011A SRFP to 1A Domin Isol Viv 416' V17 IBR70118 SRFP to IB Domin Isol Viv 416' V17 1BR7011C SRFP to IC Domin Isol Viv 416 ' V17 IBR7011D SRFP to 1D Domin Isol Viv 416' V17
- . . APPROVED
. U AUG 141989
~
(0793V/0068V/070889) B.O.S.R. i i
1B05 4.6.2.1.d-1 R3visica 2 1BR7011E SRTP to 1E Dwmin Isol V.'y 416' V17 IBR7012A 1A Domin Edr Drn V1v 401' U17
~
IBR70125 1B Domin adr Drn Viv 401' U17 1BR7012C 1C Domin Edr Drn Viv 401' U17 IBR7012D 1D Domin Edr Drn Viv 401' U17 IBR7012E 1E Domin Har Drn V1v 401' U17 IBR7016A 1A Domin adr Den V1v 401' U17 1BR70168 1B Domin Har Drn V1v 401' U17 IBR7016C IC Domin Rdr Drn Viv 401' V17 1BR7016D 1D Domin Udr Drn V1v 401' V17 1BR7016E 1E Domin Edr Drn Viv 401' V17 e e e eeeeeeeeeeeee eeeee enene=* e e ee ee e e e e ee .e e e e eee e e e e ee e e e e e ennee e g 9 , The flowpath to the- HUT f rom the ICV 112A valve should only *
- be isolated for as long as it takes to determine whether e c is a leakage source.
- aneeeeeenennenene***eneaemenenameneeeeeeeeeeeeeeeeeeeeene... nee
[ .( icv 112A
- OAB8249 AB Evap rd Domin Inlet Bypass V1v. 401' Q17 OAB8584A AB Evap rd Domin Inlet Cont V1v Upstream Isol Viv N 401' Q17 APPROVED i AUG 141969 B. 0. S. R.
(0793V/0068V/070889)
.. ~_. .. . .
1BOS 4.6.2.1.d-1 APPROVED R2 vision 2 AUG 141969 D B. O. S. R.
\ COMPUTER ERROR CODES AND VALIDATICH BASELINE NUMBERS WARNING / ERROR MESSAGE REQUIREILACI12(
**** WARNING - PRIMARY WATER / BORIC Indicates a software problem. LEAKRATE ACID ADDITIUh NCT CCHPENSATED RESULTS UNACCEPTABLE. Perform Hand Calculation Method. Notify Management Information-Services of error message.
ERROR MESSAGES RAVE OCCURRED LEAKRATE RESULTS ACCEPTABLE. SEND OUTPUT M TYPER M SEE THIM No action required.
****0NE PRESSURIZER LEVEL INPUT WAS LEAKRATE RESULTS ACCEPTABLE. No LOCKED OUT ,,,,,,,,, MINUTES AGO DUE TO imediate action required. Notify (DEVIATION DETECTION, MANUAL LOCKOUT, Tech Staff that error message occured. l BAD QUALITY)**** -
****ONE PRESSURIZER PRESSURE INPUT LEAKRATE RESULTS ACCEPTABLE.
'WAS LOCKED MINUTES AGO DUE TO No imediate action required. *
(DEVI ATICH DETECTICH, MANUAL LOCKOUT, Notify Tech Staff that error BAD QUALITY)**** message occurred.
**** TIME INTERVAL SELECTED IS LESS Minimum recomended interval is one
'IMAN RECOMMENDED INTERVAL **** bour for Least Squares Fit method and Point to Point method. Notify SE/SCRE to determine if leakage res'ults are acceptable.
****CONTIDENCE ERROR GREATER TRAN When this applies to the REACE R ACCEPTABLE LIMIT **** COOLANT GROSS LEAKAGE parameter (Confidence Error > 0.2) the LEAKRATE RESULTS ARE UNACCEPTABLE.
Perform Point to Point calculation or Manual calculation.
****CORRELATICM COEFFICIENT LOWEt When this applies to-the REACTOR
. THAN ACCEPTABLE LIMIT **** COOLANT GROSS LEAKAGE parameter (Correlation Coefficient < 0.7)
LEAKRATE RESULTS ARE UNACCEPTABLE. Perform Point to Point calculation or Manual calculation. AN IMPROPER MASS VALUE HAS BEEN LEAKRATE RESULTS UNACCEPTABLE. bETECTED Perform Point to Point calculation or Manual calculation. DOBAL READ / WRITE ERROR'IN LEAKPNT Indicates a hardware problem. LEAKRATE RESULTS UNACCEPTABLE. Perform Manual Calculation Method. Notify Management Information Services of error message. 19 (0793V/0068V/080189)
1BOS 4.6.2.1.d-1 Rovision I APPENDIX B i COMPUTER ERROR CODES AND VALIDATION BASELINE NUMBERS O. HARNING/ ERROR MESSAE RICUIRED ACIlft! ; ENTRY FIELD UNREADABLE - TRY AGAIN Improper entry. Re-enter data. 1 REQUESTED DEVICE IS PRESENTLY Improper entry. Re-enter data. UNAVAILABLE. TRY ANOTHER t CALC METHOD ENTRY OUT Of BOUNDS Improper entry. Re-enter data. DEVICE ENTRY OUT OF BOUNDS Improper entry. Re-enter data. ! IlrTERVAL ENTRY CUT OF DOUNDS Improper entry. Re-enter data. INTERVAL ENTRY GREATER THAN NUMBER Improper entry. Re-enter data. l OF VALUES STORED 4 l DOBAL READ / WRITE ERROR IN PROGRAM Indicates a hardware problem. ! LEAKSCN LEAKRATE RESULTS UNACCEPTAPLt,. > Perform Manual Calculation NLhod. Notify MIS of error mest. age.
****A LEAERATE CALCULATICN CANHCTI Perf orm Manual Calculation Method.
. BE PERTORMED, AVERAGE PRESSURIZER ,
LEVEL COULD NOT DE CCHPUTED - NOT e ENOUGH GOOD IITPUTS**** t
****A LEAKRATE CALCULATICH CANNOT Perform Manual Calculation Method.
BE PERFORMED, AVERACT PRESSURIZER ! PRESSURE COULD NOT BE CCHPUTED - NOT ENOUGH GOOD INPUTS **** i y i APPROVED (Final) (t AUG 141989 (0793V/0068V/070889) B. o. S. R.
- i
i l 1805 4.6.2.1.d-1 Revision 2 REACTOR COOLANT SYSTDI HATER INVENTORY BALANCE SURVEILLANCC O PROCESS CCHPUTER DATA SHEET DATE PARAMETER INITIAL DATA FINAL DATA to PRIMARY HATER / BORIC ACID Tt7FAL FLOW INTEGRATOR . 4b RCDT Level RCDT Temperature 4c Time & Initials / / l O f i i 1 t APPROVED > D.2 AUG 141989 , ( 07 93V/ Ot,68v/ 0708 89 ) g , n
IBOS 4.6.2.1.d.1 Revision 2 PROCESS COMPUTER DATA SHEET p l 12a. Method used: Least Squares or Point to Point 'l (Circle one) 12b. TOTAL IDEt{U{ LED LEAEACE RATE I RCS Known Leakage + S/0 Tube Leakage Total Identified Leakage 4 l 91* + gpm = c gpm 1 (Total Identified Leakage 1 10 gpm) 12c TMAL S/G ' RIBE LEAFAGE W gpm (1 1 gpm reactor to secondary leakage through all ) S/G not isolated from the RCS) j 12d INDIVIDUAL S/G TUBE LEAKAGE ) W yp6 (1 500 gallons per day through any 1 S/0) 12e IRLIM2iHIlED LEAKAGLJATE f1 t RCS Gross Leakage - Total Identified Leakage . Unidentified Leakage l gpm - gin = _ t gIm * * , (Unidentified Leakage i 1 gle) (O) 12f RCDT Purnps in the AUTO position. Initials INDEPDTDENT VERIPICATICH 12g Acceptance Criteria Satisfied YES/NO / Initial Date
** If negative, redo surveillance using Hand Calculation (No LCOAR required).
APPROVED , o_3 M 14 2 i 0793V/0068V/070889) 5.n S. R. l l
1Bos 4.6.2.1.d.1 ' Revision'2
-REACTOR-COOLANT SYSTEM WATER -1NVEN'!ORY ~ BALANCE SURVEILLANCE '
g MANUAL CALCULATICH DATA SHEET
) 4 p,gyg 'yus3 CCMPUTER PARAMETER POINTf11) 11 SED INITIAL DATA ' TINAL DATA 4.a PZR Level l"' [pO. I b 'V ' - E# % $4 M
- b. P2R Temperature '!O480 b61 Y'0 b#' ' 662
- c. VCT Level 14112 Ill M b. -
7 42.7 6.bd0 "-* : 3 0
- d. Total Flow Integrator .
Mone 0
- e. . Average Tave - UO4 8 4 - bD 7 I ~71 1 610 . "
getn
~
- f. Hot Leg WR Temp 70419 6^t 4 Mi 537 -
bir 6
-(N/A 1 530'T) 10439 . g' " .r 20459 .'N a e' '
70479 "' w: *- ' 9 Cold Leg WR Temp 70406 'M 2' i M~ 6'" 692 i '
~~' ;"-*
(N/A 2 530'r) -70426
'!O446 ^r' ~'_ "'--**'
V ' "r' 70466-e g . p- ~~ *
%' mI 7/i1
~
" '~~
- h. PRT Level LO485 '*$ -
Ob
- 1. lPRT Temperature.- 70485 N7 7~ i +O' j.- RCDT Level None. 0-
"O* NS '
.> s > >
- k. TIME / INITIALS None Fif *1 /~* C 07 ',/ N f . j p")
- APPROVED s AUG 141989 I
D-4 B.O.S.R. (0793V/0068V/070889) . P y ,-.,-se, , .n-e-v.- , , - - - ~ , - ..w- -
. . ~ . - - . - , _ e.- .~4 . . - - - - ,. .e.-. ,,w, - , - . w- v- ..,.....s . - . - - ,7.= e.rr--
r O. ..
)
E APPROVED laos 4.6.2.1.a-1 Revision 2 AUG 141989 , B.O.S.R.- wAnuAL CALCutATxw oATA sucET
. gross rraraGE RATE PaniMETTRM I
SO bo o
- 6. APZR = (PZR L f I % - PZR L 1 Y %) x 128 gal /\ = 0 gol (. Inoicate. . voli ,e increase)
! VOL en.7 w.7 ca .79 bb (+ indicates a volume' increase)
- 7. AVCT = [VCT L f % - VCT L' %) x 19.3 gal /% = gel i VOL i
o o o !" 8. AM/U gal 'IUTAL rLOtf INT Cd gal = 0 gal (+ indicates a' volume increase) VOL = TOTAL rtDi INT _ Y '3 x. I
% 9t).T St> 7 5 9g ,g i Tave D3 'r + Tave bD 'I *r $ y'i'f
*r (AVE RCS Tave)
- 9. Tave 1 530 *r i =
1 2 jr OR , ,~
> 10. Tave < 530*r TCTIAL T = 70419 + 70439 + TO459 +.T0479 + T0406 + E 426 + TO446 + 'IU466 Tg = ~*r + "r + '*r + *r + 'r + *r+ *r + *r = *r
- r. r. r. r. r. r. r. r= r
,,p-.' T, =
Tave(f) = i = *r Tave(i) i i *rs 8 8 Ave RCS Tave s ""*f *
*1 = *r 2
,93 %%O3 -
%Q? O
- 11. ap = O x(Tave g - Tave g) =(-)' 9fu /ft xl
- r .L D 'I *F) = 094 (+ Indicates a
*r *r- ft) volume increase) 0 .
O
- 12. ARC 10386.5 :t '(Ap
~
OTb /ft') O tf gal - (+ indicates a volume increase) VOL " =
'8.3378 Ibn/gni
. D-5 a nvowinnsovininnao s - .
O V l 1805 4.6.2.1.d-1 Revision 2 4
- MANUAL CALCULATION DATA SHEET GRQSS__ LEAKAGE RATE PARAMETERS -
(fil STZ 692 7 I = b *F AVE PZR f
- 13. =
2
"" /ft p PZR =
- 37. ;I, .
GROSS LEAKAGE _ RATE CALCULATION (GLR) GIVENS Assume VCT and TUTAL FLOW water temperature of 100*r Assume RCDT density is constant lbra 3 p VCT 62 Iba/ft 3 p Total Flow = 62 ilt 3 p reference = 62.31 Ibm /ft ARC 10.6 callonsi (AM/U VOL x pM/U)-(APZR VOL x pPZR) - ( AVCT'VOLx pVCT) - VOL A
- 14. GLRs = ATIME tTIME ATIME I p reference 6.'79
~
3S ? a r c
~ '
gal i 10.6 gal O /ft )-( O _ gal x - /ft ) - ( '" - gal x 62 /ft ) , ( gal x 62 13 " min 35" min Itsa 3 -r' "
.s3 17> ._ min x 62.31
/ft ,.7 y.
tb 17 ,g O 53 't,i/ 3st ,q gal 1bre /ft3 - 7 1J gal Ibm /ft 3 t_y gal Iba/ft3 ,- *? , gpm 2 gpm GLR = pg.3 min Ita,ges u n t. . z APPROVED cLR =
'i i /
g:. 2 *7/ gp.e l AUG 141%9 l
.277 z .53 D-6 B.O.S.R.
(0793V/0068v?O73889) . I I l
IBOS 4.6.2.1.d-1 Revision 2 MANUAL CALCULATICH DATA SHEET IDl2ClflED LEAKAGE RATE CALCULATION
,r Q,l '
l
- 15. APRT gg a (PRT VOLf a PPRTg) -
(PRT 2 pPRT ) VOM g l APRT O '" gal 2 ' MASS = (">"e3 3)-( f 3 46 C gal 2 '-
- 3) i ft ft
- 16. APRTggg a
- "c-. g gal 3
ft APRTgggs
- 17. APRT =
A TIRE z p reference 7xE gal II"/ft3
=
il min x 62.31 lbn/ft3 i a i3I gal / min l l
- 18. ARCDT = RCDTyot g . RCDTyon 1 -
1 A TIME '
.- -o!
ga1 . n 3 3 .i _ ,q,3 w
- I
. [eN, -~
_ I . . q) w
- min
=_2 ga3/mlu
- 19. RCS Known Leakage = APRT (Step 17) + ARCDT (Step 18) a
,J O 9al/ min
- gal / min !
= '
'3 gal / min l
t APPROVED ( , AUG 14198 (0793V/0068V/080389) D-1
1BOS 4.6.2.1.d-1 Revision 2 MANUAL CALCULATION DATA SHEET
- 20. TOTAL IDENTIFIED LEAKAGE RATE RCS KNCWN LEAKAGE + TOTAL S/G TUBE LEAKAGE = IQIAL IDENTIFIED LEAKAGE
' I gpm +
CI gpm =
- 1 t gym (1 10 gpm)
TOTAL S/G TUBE LEAKAGI - (Primary to secondary leakage through all steam generators not isolated 4 from the RCS.) O t gpd (1 1.0 gpm) INDIVIDUAL S/G TUBE LEAKAGE (Primary to secondary leakage through any one steam generators. ) O t ypd (1 500 gpd or i .347 gym)
- 21. UNIDENTIFIED LEAEAGE RATE CALCULAIlQti (GROSS LEAKAGE) - TOTAL IDENTIFIED LEAKAGE = UNIDENTIFIED LEAKAGE
( 4!T gpm 2 + 2I gpm) - 'IS gym = M gpm 2 Y' gpmit (1 1 gym)
- 22. RCDT Pumps in the AUID. Initials M~ INDEPENDENT VERIT
\
[
- l 23. Acceptance Criteria Satisfied YES/NO. --4 R~~ / 'h *00 i
Initial /Date 1 ................................................................
- NOTE *
.( \- ')
- 6 Because of instrument tolerances and inherent calcula- *
- tional errors ir. estimating RCS gross leakage, a total *
- possible error et 2 10.6 gallons has been used as a *
- bounding value. The actual penalty in leakage rate in *
- terms of gpm is dependent on the duration of the test. *
- For exP.mple: A 30 minute leakage test will result in a *
- tolerance of 10.35 gpm on both the gross and *
- unidentified leakage rate, whereas a 2 hour test will a
- result in a 10.09 gym tolerance. Negative values of a
- unidentified leakage may result due to the above stated *
- errors and are acceptable provided they are less than or *
- equal to the tolerancs value. Negative values for a a leakage in excess of the tolerance value require a rerun *
- of the RCS leakage determination procedure and does not *
- constitute entry into an action requirement unless the *
- time interval for this surveillence is exceeded. *
- Excessive negative values for leakage may be due to- *
- either 1) Transient conditions in the RCS during the *
- 1eakage test. 2) Leakage f rom sources other than the RCS *
- into the PRT & RCDT or 3) Inleakage into the CVCS *
- Charging or Letdown.
- g3 APPROVED I
I (Final) AUG 141989 (0793V/0068V/070889 D-8 B.O.S.R.
1BOS 6.2.3.o-1 R vision 6 REACTOR CONTAINMENT TAN COOLER MONTHLY SURVEILLANCE d A. STATEMENT OF APPLICABI M This procedure applies to the Monthly Verificat Reactor Containment Fan Cooler Operability in Modes 1, 2, 3, and 4. B. RETERENCES:
- 1. Technical Specification 3.6.2.3 l 1
- 2. Technical Specification 3.6.1.5
- 3. TSAR 9.4.8.1 j
- 4. LCOAR IBOS 6.2.3-la
- 5. LOP SX-1
- 6. BOP VP-1
- 7. Station Commitments
- a. 6-90-0079 C. PREREOUISITESt p
t f 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.
D. PREC AUTIONS t -
- 1. ENSURE the containment air temperature is maintained within limits during the performance of this surveillance.
E. LIMITATIN S AND ACTINS
- 1. As stated in Technical Specification Limiting Condition for Operation 3.6.2.3.
- 2. Fans should be run in pairs; Tan IVP01CA with IVP01CC and IVP01CB with IVP01CD due to SX or WO Line-ups.
- 3. 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 6.2.3-la.
- 4. The SK System is flow balanced to provide required RCTC flow when two SX Pps are running.
APPROVED AUG 2 3 590 (">'. s_- B.O.S.R. (1218V/0099V/082190)
1B05 6.2.3.a-1 Revision 6
- 5. LOCALLY RECORD flow rates from the appropriato ficw indicators listed on Data Sheet for the RCFC's started in step T.3, then log on Data i
Sheet. enemoneeneneenesee*eneene******eeeeeeeeeeeeeeeemen**eeeeee****ee a t[(yIt a
- Each RCFC has two flow indicators that must be summed to
- a attain total SX flow rate.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemenemmenneeneseenemenenene*** SUM the actual flow rates for each RCTC started in step T.3 and LOG 6. total flow and VERITY 22 660 gym on Data Sheet.
- 7. RETURN the RCTC'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 appropriate RCTC and VERITY 115 on the Data Sheet.
- 9. REPEAT steps F.3 through F 8 for the remaining pair of RCTC's. if desired.
- 10. RETURN 1A and IB SX 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 required.
G. ACCEPTANCE CRITERIAt
- 1. Each Reactor Containment Fan Cooler must' be started f rom 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 gpm.
APPROVED (Final) AUG 2 81990 B.O.S.R. 1 (1218V/0099V/082190) l 2
. - - - - ~ - - _ _ . , . , - , - _ - _ , - - - . _ - ~ _ _
1805 6.2.3.a-1 l Rovision 6
- 5. -Operation of an RCFC may affect the associated RCP's temperature sensitive seal cavity and allow the 02 Seal to open causing il Seal Leakoff Rate to dect-'-se. The affected RCP may be operated under
- this condition wich t'a o fellowing precautions.
- a. Monitor for increased 42 Seal Lenkage causing 42 Seal Leakoff Flow High Alarm, increased flow to the RCDT and possible TCP
- Standpipe Level Alarm.
- b. Monitor RCP bearing temperature. ;
1
- c. Consider switching RCFC's to verify cause of leakoff problem.
T. MifM BODYr eeeeeeeeeeeeeeeeeeeeeeeee.neeeen.eeeeeeen.nennee.eeen.e eeeeeeee I
. a, e .
- This-surveillance may be performed as a partial *
- surveillance to prove operability of any component listed *
- on the data sheet, provided all Prerequisites, Precautions, 6
- and Actions are verified and/or followed.
- ene**e ....e** e *******ee**eeee**eee**eeeeee******** e**eneeen.
- 1. RECORD the "As Found" position of the MCB C/S for all RCFC's, , ,
-IVP01CA, B, C and D and SK Pps, ISK01PA and ISK01PB on Data Sheet.
- 2. VERITY / START 1A and 18 SK Pps per BOP SK-1 a
-t c::)
c **eeeeeeeeeeen.eeeeeeeeeeeeeeeeeeeeee***eneseeeeeeeeeeeeeee.ee.
- CAUTICEI a
- ENSURE THE CONTAINMENT AIR TEMPERA'IURE IS MAINTAINED W4 THIN * *
- LIMITS DURING THE PERFORMANCE OF THIS SURVEILLANCE
- neeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemeneseeeeeeeeeeeeeeeeeeeeeeeeee*
- 3. VERITY / START *1VP01CA and IVP01CC or IVP01CB and IVPOICD in low speed per DOP VP-1.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemenneeeeeeeeee***e-a ggg; e
- Each Fan group must run in low speed for at least 15 minutes.*
ne**eneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen-4.- LOG.the start time for the appropriate fans on Data Sheet. APPROVED nv AUG 2 81990 B.O.S.R.
'(1218V/0099V/082190)
u) s)
- G is S 6.z.3..-1 APPROVED Revision 6 AW28M REAC OR COnTAINMEMT rAN COOLER MONTHLY SURVEILLANCE B.O.S.R.
(1) (10 and 11) - EOUIPMENT AS FOUND POSITION FINAL POSITIN OPERATOR INITIAL INDEPENDENT VERIFICATIN 1A RCFC HI SPEED /C /8v
- AC [$A[ g/A
_1A RCFC LO SPEED A7 /T < 447 IB RCFC HI SPEED A (- M NC -- ' i IB RCFC LD SPEED ,4 / A[ 64/I 1 RCFC HI SPEED A6 ed 46 h 1C RCFC LO SPEED AT A7 9"in~ l
^ $
1D RCFC HI SPEED d[ A7 bd ID RCFC LO SPEED 4Y AT b 47 l 1A SX PP G f~ b% 'l M bbP IB SX PP N7 NI ' (4) (7) (8) (5) (6) KCFC START STOP RUN TIME SX ACTUAL TorAL SX TIME TIME 115 MIN FLOW INSTR FLOW (GPM) FEDf 12669 gpm 1A RCFC 1FI-SX122 (377* 20-16) 3 :~ /M ,. de/c LO SEEED C's 13 6't iU e ( +: <, IFI-SX112 f377* RO-14) r e , . l ,r/ r/< c .J e v*5 e 1C RCFC IFI-SX118 (401* RO-4) s} 7c c a j f., # /j . 3 fc/ s-, LO SPEED _ fN1 e 9W' d t **!> 1FI-SX124 f377* RO-1) / /" 7#* e ti5 e IB RCFC 1FI-SX123 (401' RO-16) q ,, f ,, / . 7y y LO SPEED fh11 C / t ,v f 5 1FI-SX115 f377* RO-19) t 1/e 5 t ID RCFC 1FI-SX121 (401* RO-7)
- 37/Tppg LO SPEED [' N C9iO t gi #3 IFI-SX125 (401* RO-10) e v e5 e (Final)
(1218V/0099V/082190) -D2-
1B06 7.3.1-1 Revision 51A COMPONDtf rm Tr, WATER SYSTEM VALVE
/N LINEUP TO SAFEI? RELATED ECx1IPMENT
() M NTHLT SURVEILLANCs A. STATDENT OF APPLICABILITY: 1 This procedure applies to the sonthly verification of the valve lineups for the Component Cooling Water System servicing safety related equipment in Modes 1, 2, 3 and 4. B. REFERENCES _
- 1. Technical Specification 3.7.3
- 2. BOP CC M-1 j
- 3. P & ID M-66, Component Cooling i
C. exuavu1 SITES: Receive permission from the Shift Engineer or his designated SRO 1. licensed assistant prior to performing this surveillance by having him sign the Data Package Cover Sheet signed and dated. D. L1 CAUTIONS:
- 1. Do not attempt to change any throttled valve position. Flow indication may be used to verify valve position on throttle valves p)
( ~' that have no position indication. This will prevent upsetting a previously established flow balance. E. LIMITATIONS AND ACTICNS:
- 1. As stated in Technical Specification Limiting Condition for Operation (ICO) 3.7.3
- 2. In the event the Acceptance Criteria is not toet during the performance of this surveillance, IMMEDIATELY notify the Shift Engineer to initiate LCOAR 130S 7.3-la.
P. MAIN BODY:
............e****ee...................................e**********
- l. e pyre
- This surveillance may be performed as a partial *
- surveillance to prove operability of any component listed *
- on the data sheet, provic'ad all Prerequisites, Precautions *
- and Actions are verified and/or followed.
e............e****e......e*************e.e***e3e****ee.........
- 1. RICORD Time and Date on all data sheets.
- 2. PERKRM the valve position checklist by recording the actual valve l
- position ou the data sheet.
APPROVED (q\j (2651P) DEC 111987 i B. O. S. R.
I 1BOS 7.3.1-1 Revision 51A f i eneeeeee*****eeeeeeeeeeeeeee**ee................................
- NOTE
- Proper Flow Indication will be used to verify proper valve *
...P.osition for throttled valves 1CC9506A and 1CC9474A
......e***e.................................................
- 3. 141CA11Y VERITT the flow rate for the valves listed on data sheet (D-4) and record in the appropriate section.
G. ACCEPTANCE CRITERIAt
- 1. All valves should be in the required position as listed on the data sheets.
- 2. All Flow rates should be within the required Flow rate tolerances as listed on the data sheets.
O APPROVED O- (Final)
-2_ DEC 111987 (2651P/0180P)
- 8. O. S. R.
O 0: O 1808.7.3.1-l' Reviolon 51A CunePONENT COOLING ST5TBI VALVE LINRIP TO SAPETT REATED EQUIPteff BIDImE.T SINIVEIEJANCE DATA Serf , 1. TIIS: CiCV DATE: 7-/7 'I/ . CEESCHErr ',dBnUIRED ACTUAL fingarWTPTI N ' POSITIN POSITIM
- 2. EPIf IACATIW
; 10C9506B. IA WE Pp OC Inlet Isol
*' Viv, + 3 343' U12 RIB 1 OPEN N/4 d 1- 10C083A 1A Mt PP OC Outlet .-
IFIS-446 I4 Side Isol viv. +17' 364' U16 AB 'OPEN N/4 i ICC083C 1A Mt Pp 0C Outlet 1FIS-646 HI Side Isol Viv. +17' 364' U16 AB' OPBf N/A d ICC9504A RH RK 1A (X: Inlet Isol i V1v, +14' 364' 816 AB OPBf U FE d d 1(X:9507A 1A MI HK Outlet Butterfly TIWt0TTLED 1 V1v'+ 12' 364' 516 AB 35% OPBf YObe d eematun
+
10C9412A- MOW CC to 151 HK 1A Isol .
- Viv +12' 364' 516 AB ***OPBf Ch 5 E O d 10C095A 1A E51 HK CC Rtra Hoc i
j 1FT-689 Hi Side Isol Viv. + 7' 364' P17 AB OPBf //4 d ICC0958 1A WI ItX OC Rtra Hor To IFT-689 ta'81de Isol Viv. +7 364' P17 AB OPB8 v/A d
, t I
i ** Applicable when EH le not in operation i eeeApplicable when Et le in operation i APPROVED
-D2- DEC11 ag7 (2651P/0180P).
a o. s. a.
, ,9 J '
IBOS 7.3.1-1 Revision 51A B TRAIM RH
- 1. TIME: ICc1 DATE: 9-IMI
- canv0wsNr REguIRED w DESCRIPTICBI LOCATICEI POSITICBI POSITION
- 2. ERf 1(2:9474B IB RH Pp CX; Inlet FCV, 343 112 RxB1 OPEN v/# g
+ 6' 10C0835 IB Rr1 Pp CC Outlet 1FIS-647 Lo Side Isol Viv. +13'~ 364' U17 AB OPEN v// f ICC083D 15 NH PP CX: Outlet To ITIS-647 Hi Side Isol V1v. +13' 364' U17 AB OPEN r/4 d ICC95043 IB RH HE CC Inlet Isol Viv. + 12' g 364' V17 AB OPEN cifd ICC9507B IB RH HK Outlet Butterfly Viv. + 12' THRorTLED 1 ,.
364' V17 AB 20% OPEf1 N' & (
**c rrymn ICC9412B MOV CC TO RH HK 1B Isol V1v, + 12 C (c5Ed 364: V17 AB ***OPEN g ICC085A IB RH HK CC Rtrn Hde g IFT-688, Hi Side Isol V1v. + 12' 364' U17 AB OPEN oM ICX:0855 1B NH HK CI: Rtra Hdr g 1FT-688, Hi Side Isol V1v. + A2' 364' U17 AB OPEN N//
ICC9458 CC Pp Doch Hdr Isol T .If.") d V1v, +10' 364* L17 AB OPEN ICC9459A CC Pp Suct Hdr Itie C I'E d g V1v, +8' 364' M18 AB OPEN ICC94593 CC Pp Suct Hde Itis Isol e /~E _ / d Viv, +8' 364' L17 AB 94 CPEN ICC9467A CC HK Doch Hor Non Xtie Isol . O Ffd g Viv, +9' 364' N15 72 OPEN ICX:9467B CC HK Doch Mdr Man Xtie Isol #4 OPEN c; E2'/ g Viv, +9' 364' M16 AB CC HK Sup Hde Xtie Isol ICI:9467C V1v, +10' 364' L17 AB OPEN e @) g ICC9473A MOV CC Pp Doch Hde Xtie rTid ( 364' L17 AB 94 OPEN V1v, +10' ICI:94735 MOV CC Pp Doch Hde Xtie r fy f,/ g 364' L18 AB 44 OPEN V1v, +10'
**( rtymn: applicable wtun RH is not in operation
***OPEN: applicable when RH is in operation nppROVED ttThese U-1 <alves are nornelly Open, while the analogous U-2 valves are Adelnistratively OCS. 1F these valves are not in gjjg the required position, the S.E. should evaluate for CC Operability.
-D3- g, g, g, g, (2651P/0180P)
, - -- m ._, , s% - , e,---
O - O O 1908 7.3.1-1 Devision SIA l CDEUtWT OXKJNG MTM ETITM YALVE LIERJP To SK REATW WMerf N N REVEILLANCE DA1A SW ET
- 1. TIM: /f C1 h1: 9-17'7 I '
CXBENWT N POS @ IRED (3) ACIUAL FIDE INST.
- 3. EPW merwrPTIGf FRCN MEL rTm FTD MhTE (GFM) FTDt RATE (td. INST. 14CATIGE 1A IEE PP C1g M r IPLS1JA ICC9506A Outlet FCV 1/4 TINet 6.0 to 9.0 g
- 1FI5-646 364' Q-17 l IB BH Pp C1g M r IPL31JB g
s ( 1FIS-647 364* 8-17 ICC9474A Outlet FCV 1/4 7155r 6.0 to 9.0 l (Final) APPROVED _o4_ DEC11 tg (2651P/0180P) D. O. S. R.
1308 7.3.2.a-1 Revision 51A t COMHatENT COOLING MATER PLMP OPERABILITY MONTHLY SURVEILLANCE A. STATDGDiT OF APPLICABILITTt This procedure applied to the monthly verification of the operability of the component cooling pumps.
- 3.
REFERENCES:
-1. Technical Specifications 3.7.3 & 4.7.3.2A
- 2. BOP CC-2(9), 30P CC-15(10), 30P CC-El and BOP CC-M1
- 3. P_& ID M-46 Component Cooling C. PREREQUISITES:
- 1. Receive permission from the shift Engineer or designated SRO. licensed assistant prior to performing this survelliance by having the Data package Cover Shee* algned and dated.
- 2. Ensure BOP CC-M1 h(., been completed.
D. Pit 3 CAUTIONS t ,
- 1. Ensure the CC surge tank is within its normal opprating level. (35%
to 65%)..
- 2. Taking a control switch from the pull-to-lock position can aut start the pumps due to low system pressure.
- 3. Use applicable procedures when starting, stupping or swapping pumps.
E. 1.33GTATIONS AND ACf!ONS: i
- 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 DeEEDIATELY notify the Shif t Engineer .
to . initiate IC0AR 1908 7.3-la. .
.F. lgg_BCOT: [
..................s............................................. ;
. !!gn .
'* Initial each step in the space provided adjacent to the i
- Main Body step number M the step has been SEI255FUIR * '
- completed. persons performing IMDEFENDENT VERIFICATICat
- l
- ahould initial in the space provided below the step.- * ;
i O -(5182P/0303P) APPROVED DEC i i 1987 l
- s. o. S. R. [
I t
1308 7.3.2.0-1 Revision 51A
............eeeeeeeeeeeeeeeen...................................
e - y e O
- In order to verify the operability of a ecumponent/ system the Shif t Engineer may elect to perform individual stape 8
l
- of this proceure provided all Prerequisites, Precatitions .
- and Limitations and Actions are obsered.
e................................. .............................
- 1. ENTER the date and time. ,
DATE_J. / M/ TIME ef71
........................................ .e********e............
- NOTE *
- The start time for a running pump shall be the time when * :
- the surveillance is started.
- eeen...................... e**ee......... ee....................
D[ 2. ENTER the start time for each running pump on CC ptung Data Chart. 3 c a .r 3/l/' 3. ENTER data for each ruri dag pump (s) in the Data Chart af ter 14-hewes from the time recorded in step F.2.
..............***ee.... ** ...e********eeeen...................
. g .
- If necessary to swap pumps then refer to DOP CC-15.
eeeeeeeeeeeeeeeeeeeeeeeeen ....eeeene..........~ ..... **eneeee. 7 c .- , . O h 4. Etat each non-operating pump for 1-F hours and record data on Data Chart. CC PLSIP DATA CHART CC PLAIPS 10C01PA 10C01PB OCC01P REQUIRED DATA M 7 7- c *i f'l / 0 ,'li - MOTOR CURRENT e/f eg t/f i 50 AMPS SS System 150 PLBIP DSCH PRESS / 3 .'R / 33 /3/ psig < Pressure < psag j XX OUTLET TEMP yg d g[ d 7g d ( 118'F ,- ('9 69 / 0 '/9 / / '/ 7
**"' 3] 4
- St -
- c%* g 9_ ;} fy,, ,,_,, y.
,7..., r. i. - n, sa,-
(* C Ines h tenffs ype-r cs, ,ps,/ f v s %. .-e l/ro. y av //
& h. %: /lr+ . . , ll. ;. s 74,; * , , , , , '
APPROVED
-O L
(5182P/0303P) l B.O.S.R.
+w" ~r, ,-- e w, ,,-,-n ,-. , , en. - , - , - , - - - - - , - - - -_ _ _ - - - - - - , - - - - - - - - - - < - - - - - - - - - - - - - - - - - -
m... _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ . _ - . _ ,_- - DM?3..pA e t ha nA
- 5. VIstIFY 2 CC pumps will auto-scart on an &~ Mkid,1C; !
' Initial the OPEltABLE CC pump on Div. 11:
a. 6 % [ 1A CC pump racked in to BUS 141 and NE in Pull-out
-CR-
*/' O CC pump racked in to BUS .141 and NOT in Pull-out and 1A CC pump in Pull-out.
INDEPENDENT VEltIFICATION 4 /-/
- b. Initial the OPEltABLE 'JC pump on Div.12:
j @ 1B CC pump racked in to BUS 142 and ,N_OT in Pull-out ,
. Cit-eM 0 CC pump racked in to BUS 142 and NOT in Pull-out and 15 CC psump in Pull-out.
INDEPENDENT' VERIFICATION , /4
$ ( c. VERIFY one CC pump OPERABLE on each Div. in F.S.a and F.5.b above.
G. ACCEPTANCE CitITERIA: ,
- 1. At least two component cooling water pumps shall be demonstrated operable by verifying that each pump starts upon actuation, operates
- for at least four h*.tre, satisfies the cooling requirements for the routine operation of the component cooling water system, and is capable of auto-starting on an BEF actuation.
................................ 3..............................
. g .
- If a CX: ptay is running than it shall be implied that the *
- pump has started upon actuation.
........+ ..............................................<,.......
(Final) APPROVED DEC 1 i 1987 (5182P/0303P) B. O. S. R. e ge m e e, m 96J . +8 +.es e aese9 - -- ,,--m , ~ , , ,m,~-e ,en.,-s,--wem., ,, y ,- c ,.,--.w.-.
~ , , - - + , - - - - , , - -ex
sewe v.......s . R:visio2 2 UNIT OHE 1A DIESEL GENERATOR OPERABILITY MCHTHLY (STAGGERED) AND SEMI-ANNUAL (STAGGERED) SURVE!LLANCE ,r k A. STATEMENT Of APPLICABILITX
- 1. This procedure outilnes the steps necessary to verify. for Unit 1, the OPERABILITY of the 1A Diesel Generator. This Unit I requirement la applicable when Unit 1 is in Modes 1-6.
- 2. Also verified, for Unit 2, the capability of the 1A Diesel Generator to be crosstled to Bus 241 (Hat actually crosstled). This Unit 2 requirement is applicable prior to entry into and during Unit 2 operation in Modes 1, 2 and 3.
e.nonneenenenanne eeeeeeneseeneeseeeeeenennenseeeeeeeenneeeeeeen e umg e e !! Unit 1 is in Modes 5 or 6, only one Diesel Generator is *
- required to be OPERABLE f or Unit 1. af the 1A Diesel e a G9nerator is looperable, then ensure the IB Diesel a
- Generator is OPERABLE.
- eneseeeeeeeeeeeeeeeeseeeeeneneseeeee**eeeeeeeeeeeeeeeeeeeeeeeeen O M 0 .
- Inoperability of the 1A Diesel Generator may impact Unit 2 *
- operations if Unit 2 As in or entering Modes 1, 2 or 3. *
- The impact of the 1A Diesel Generator looperability must *
- be evaluated by the Shift Engineer. .
6 B. eeeeeeeeen.....eeen.....eeeeeeeen RIEIEIHCIS ne eeeeeeeeeeeeeeeeeeeeeeeeen
- 1. Cooper Bessemer KEV Diesel Generator Instruction Manuals Vol 1 & 2.
- 2. NRC Regulatory Guide 1.108.
- 3. Technical Speelfications:
- a. Limiting 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 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.
APPROV D [0R REFE DEC 161969 O) As (1178V/0095V/120289) B. O. S. R.
4eva b.4 4...a-A Revision 2
- 4. Station Procedurost
- a. BOP DG-11, Diesel Generator Startup.
i
- 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. BOP DG-13, Trouble-Shooting Diesel Generators.
- f. 1905 3.2.1-806, Unit One ESTAS Instrumentation Slave Reisy Surveillance - Train A Auto SI - K511.
9 180S 8.1.1.2.a-2, Unit One IB Diesel Generator Operability Monthly (Staggered) and Semi-Annual (Staggered) Surveillance. h, 2005 8.1.1.2.j-1, Bus 141 to 241 Crosstle 18 Honth Surveillance.
- 1. 1BOS 8.1.1-la, LCOAR - AC Sources - Operating.
3 1BOS 8.1.2-la, LCOAR - AC Sources - Shutdown.
- k. 2BCS 8.1.1-la, LCOAR - AC Sources - Operating.
- 5. US HRC Inspection Report 50-456/86052; 50-457/86040 (Braidwood) dated 12 Nov 1986 (Enclosure 2, item 2.0).
- 6. Station Comitmental
- 6. 6-87-048
+ b. 6-87-056 -
- c. 6-87-019 C. R E LQQ111IES
- 1. Receive permistion from that Shift Engineer or designated SRO licensed assistant prior to perf orming 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 blank Diesel Generator Start /Stop Log (BOP DG-1171) and Diesel Generator Operating Log (BOP DG-11T2) when perf orming this surveillance.
APPROVED DEC 181969 O (1178V/0095V/120289) B. O. S. R.
suvo s.......e . R visios 2 D. PRECAUIICES l
- 1. The Diesel Generator will Auto Start if an emergency signal is
-~ received. '~# 2. If the pressure drop across the full-flow Lubricating 011 filter reaches 19 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 for testing.
- 5. Do not start or continue to operate the Diesel if the Diesel Generator Room temperature escoeds 111'T.
- 6. Do not onceed Diesel Generator rating of 1932 KW or 191D amps load for greater than 2 hours.
- 7. Operate only QHI Emergency Diesel Generator per Unit in parallel with of f site 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 parallaled to the grid, DO NOT return the Emergency Mode Speed Voltage Control Switch to AUTO if it is currently in the MANUAL EMERGENCY position.
A k ,) s
- 9. Do not crosstle the 1A Diesel Generator to Bus 241 unless also '
performing 2BOS 8.1.1.2.j-1 (Bus 141 to 241 crosstle 18 month ! surveillance) in conjunction with this procedure. . E. LIMITATICHS AND ACH QiS .
- 1. As stated in Technical Specifications LLmiting Condition for Operation (LCO) 3.8.1.1 and 3.8.1.2. _
- 2. The Tech Spec requirament for the Diesel to start f rom ambisat and accelerate to at least 10D RPM in less than or equal to 10 seconds she11 be considered met if frequency exceeds AD Be within 19 seconds.
- 3. The routinely scheduled Monthly and Semi-Annual portions of this surveillance each shall be performed on a Staggered Test Basis with IBOS 8.1.1.2.a-2.
- 4. Verify / Maintain at least 23 percent fuel oil level in the Diesel Fuel Oil Storage Tanks during the Diesel Generator run (unless the DG is already IHOPEFABLE).
APPROVED e DEC 161969 t ! I \~ (1178V/0095V/120289) J3, (), c( pg,
euwe o.......... R3 vision 2 l S. In th3 ov:st Lb3 Acceptcsco Critorio (W) is set m3t during performance of this surveillance, IMMEDIATELY notify the Shift Engineer or designee to initiate LCOAR 1905 8.1.1-la if in Modes 1-4 or LCOAR 1BOS 8.1.2-la if in Modes 5-6. l
.O4 6. Inoperability of the 1A Diesel Generator may impact Unit 2 operations l if Unit 2 is in or entering Modes 1, 2 or 3. The impact of the 1A )
Diesel Generator inoperability must be evaluated by the Shift Engineer.
- 7. If this survelliance or a portion of this surveillance is performed i for purposes other than scheduled testing, NO CREDIT shall be taken l for its- perf ormance on the surveillance schedule. The Shift Engineer l or designee shall designate those portions to be perf ormed. I l
Notations should be entered in the comments section of the Data Package Cover Sheet containing the reason f or performing the survelliance. F. MAIN BODY , 1
.eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeensneeeeeeeeeeeeeeeeeeeeeeeeen a gggg a
- Initial each step in the SPACE provided adjacent to ths *
- procedure step number ATTER the step has been 511CCESSI11LI.I
- completed. Person (s) performing INDEPENDENT VER1r! CATION e
- shall initial in the space provided after the step, ,
! .....eeeeeeeeeeen eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee....... Subsections F.1, F.4, T.7, F.8, r.9 and T.10 must alxAy2 be performed F.0 seguentially.- Parallel Subsections F.2/r.3 and F.5/r.6 are independent of one another so that either subsection may be 4 O performed. Only one of each parallel subsection may be performed. The Shif t Engineer or designee shall designate which subsections shall be performed (Monmally shown on the Surveillance Schedule). . l 1 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- HQIK a
- Sequential performance of the required Subsections and the
'
- following parallel Subsections provides _
- e T.2 and F.5
- Manual local start and gradual loading. *
*
- r.3 and T.5 1
- Auto start from EST and gradual loading.
- l
- e T.2 and F.6 Manual local start and 1 AD sec loading. *
* -e T.3 and F.6
- Auto start from EST and i 10 sec loading.
eeeneneeseneeeeeeeeeeeeeeeeeeeeeenneeeeeeeeeeeeemene.... . menee i 1 APPROVED
' i A DEC 161969 i
(1178V/0095V/120289) 8. C). S. R. I w
. a. . , 6........ .
Reviolon 2 ! r.o l EnEI l.LL l Initiel Conditions
- l. l Auto Start From Manual Local l1Ll l LLl EST (2BOS 2.2.1-806)
(Quarterly) Start (BOP DG 11) x
~ . . . . -
llLl Intermediate Conditions and Veri!! cations Load to 1 liQQ Di _ Load to 1 1120 KW (Gradual) l 1 1_l llLl (within 1Q seconds) (Honthly) , (Semi-A.nnually) t N . , - l11 l Crosstle Capability verification l1Ll ruel Oil Transfer Operability llLl One Hour Loaded Run and Shutdown O l110l Final Conditions END r.1 I;.!Jimi conditions
- a. PECORD the following C C /Q'Q d3 DATES-lky n ,In_e l
ji T1HE N /V i' HODE
- b. PECORD the following for the stopwatcht Inst CA 4:
~
Calibration datet
- c. RECORD the Diesel fuel Oil Day Tank level from 1L1-DOO351 t % (1 11 48)
APPROVED DEC 181969 0 (1178V/0095V/120289) B. O. S. R.
sovo s.......e . Rsvisics 2 T.1 eneeeeeeeeeeeeeeeeeeeeeeeen. ...eeeeeeeeeeeeeeeeeeeeeeeeeeemenee
- gggg e e verify / Maintain at least 15 percent fuel oil level in the e
- Diesel Fuel Oil Storage Tanks during the Diesel Generator *
- run (unless the DG is already INOPERABLE). e eeeeeeeeeeeeee...eeeemeneseeeeeeeeeeeeeeee**eeeeeeeeeeeeeeeemeno
- 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 INOPERABLE):
~
- 1) RECORD 1A DG TO Sto Tk 1A Level from ALI-DOOO1A %.
)
- 2) RECORD 1A DG TO Sto Tk 1C Level from 1LI-D0021A: %.
~
- 3) ADD both tank levels and RECORD totals %.
~
- 4) DIVIDE total by 2 and RECORD results: # %
(1 2LA lit) r.2 Manual Local ftart ( BOLDG-11) neeeeeeeeenannenamenomaanneeeeeeeeeeeeeeee* eee**eeeeeeeeeeeeeee
- HQII *
- Prior to starting the Diesel, ensure a stopwatch is *
- available to record the time it takes for the Diesel to *
- reach > 10D2 volts.
- e e e e e e e e e e e e e e n e...e n... e e e e e e e e n e.,n e e e e e e e e e e e e e e e e e e e e e e e e e e e n s
p
- a. RECORD the DG Right T. Left' Bank Air Receiver air pressures at 1PLB7J V
- 1) Right Bary: psig *
- 2) Left Banks psig *, 6.a
- b. VERITY / PLACE the DG 1A ACB 1413 Auto Reclose Circuit Arm Selector Switch in the SURV TEST position at IPM01J. *, 6.c
- c. Locally-at 1PLO7J, 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 > 10DD volts, STOP the stopwatch and then immediately verify 1 ADD RPM and f requency between $L1 to
*, 6.b ALl H z .
APPROVED DEC 161969 (1178V/0095V/120289) B. O. S. R.
lbOS 8.1.1.2.4 1 R0visics 2 r.3 Auto start Fron rsr iinos 3.2.1.ao61 M.3\ ,$# eneee. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee...eeeeee...
- CAUIICH
- O *-- 1BOS 3.2.1-806 WILL ENERGIZE SLAVE RELAY R611 WHICH WILL
- START DIESEL GENERATOR 1 A IN THE D4ERGENCY HODE. UNTIL
- THE DG IS SELECTED TO MANUAL IN 1BOS 3.2.1-806, ALL NORMAL
- e
- PROTECTIVE PEAnlRES ARE BYPASSED. IP ABNORMAL CCMDITIONS e ARISE, STOP THE DG USING Tilt FMERGENCY STOP PUSHBLTITON AT *
- 1PLO7J.
- eeeeeeeeeeeeeeeeeeeneneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen..........
eneseeeeeeeeeeeeeeeeneineneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenemone e ggIf a e Prior to starting the Diesel, ensure _a stopwatch is e
- available to record the time it takes for the Diesel to *
- reach 10.Q9 volts.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**eeeeee
- a. RECORD the DG Right & Left Bank Air Receiver air pressures at IPLO7Je
- 1) Right Bankt _ psig
- 2) Left Banks - psig *, 6.a h. . b. VERITY / PLACE the DG 1A ACB 1413 Auto Reclose Circuit Arm Selector Switch in- the SURV TEST position at IPM01J. *, 6.c
- c. START the 1A Diesel Generator per 190$ 3.2.1-806.
f/
- d. At the same time the Test Switch 5834 is depressed in 1BOS 3.2.1-806 to start the Diesel, START the stopwatch. As soon as .
/8,e f[*#C. the Diesel reaches > 120.Q volts, STOP the stopwatch and then * " levnediately verify 11AQ RPM and frequency between 1.1 to E l Es. *, 6b r.4 Intermediate conditions and verifications ee e e e ee e eee e e e e ee ee e ee e eeeee e e ee eme**ee e e e e ee e ee e e e eene seee e e eee e ggIg e
- Monitor the Diesel for abnormal conditions. If trouble *
- occurs,. refer to BOP DG-13 or the appropriate BAR.
- eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene
- a. DMEDIATELY RECORD the- DG Right & Lef t Bank Air Receiver air pressures at 1PLO7J and VERITY a pressure decrease from the value recorded in steps T.2.a or T.3.a'as applicable:
- 1) Right Bankt psig
^
- 2) .Left Bankt psig
^
- 3) Pressure decrease verified in both Air Receivers. *, 6.a
. APPROVED (1178V/0095V/120289) l S. O. S. R.
l
owe e...e.e.e-e R3vielen 2 r.4 r' b. VERIFT 1A and/or 1C Fuel 011 Transf er Pump STARTED. t c. RECORD the following data
- 1) From the stopwatch, time for the DG to reach G 0C -
> 10AD volts: /
5 t Y see (,t 10)
- 2) DG running RPM: t b RPM ($18 to 112)
- 3) DG running voltages /,J,8d Ml90 V (121D to 1112)
- 4) DG running frequency: GOSt W5 us (l u to n u ) .
~
i d. UPDATE BOP DG-1171, Diesel Generator Start Stop Log.
- e. VERITY / PLACE the DG 1 A Control Mode Selector Switch In the
< REMOTE position at 1PLO7J.
5 knad to 1 5500 KW (Graduall eeeeeeeeeeeeeeeeeeeee. .eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen...... e gggg a i
- erste the Diesel Generator for approximately 1 minutes a '
l
- before loading. When performing the following step, the *
,
- Diehl Generator should be loaded gradually to reduce *
- therma \ stresses in ths cylinder heads. When increasing
- load from Q p to 1102 W , the load should be applied in (q *
- s j
- 10A0 p steps over a period of 1 to i minutes. .
e 4 NJ *
- e e e e ee e e e e e n ee n e s e e e e e e e e e e e e e ee e ee e e ee e e e e e e e e e e ee e e e ee e e e e e n
\N .
I
- a. Request that the NSO synchronise the Diesel Generator to its ;
associated EST bus and gradually load it to 111Q0 p as per ' BOP DG-11. \ x 1
- b. When the Diesel Gener) tor output reaches 1110D p, RECORD the following: N
\
Clock time when the Diesel Generator output
- 1 110A KW: s
- - N F.6 . Load to 1 5500 KW_(within 60 secondal e3eeeeeeeeeeeeeeeeenmeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene HQIE
- Before synchronising the Diesel Generator to its associated *
- EST bus, have a stopwatch ready to measure the time it *
- takes to reach 1 1192 KW.
en seeeeeeeeeeeeeeeeeeeeeeeeeeemen.e en..eeeeeeeeeee....neenemen
- APPROVED (1178V/0095V/120289)
ssue 6.s s.o.s.e R3vielen 2 r.6 eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee e ugu o
- When 1cading the DG to 1 $500 KW in 160 seconds, utilise e O *
- as much of the 60 seconds as possible to minimise stress
- on the engine and turbocharger.
eneneeneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee...
- a. Request that the NSO synchronise the Diesel Generator to its associated EST bus and load it to 1152D EW as per BOP DG-11.
When closing the breaker, OBSERVE and PERTORM the f ollowing 9N 1) At the same time the Diesel Generator Output Breaker is closed, START the stopwatch.
- 2) LOAD the Diesel Generator to 1 1120 EW per BOP DG-12 within AD seconds.
hv 3) When the Diesel Generator output reaches 115D) EW. STOP the stopwatch and RECORD LLe followings a) Time it,took for the Diesel Generator to load
# 1LM see (A 10) h) Clock time when th . 'Diesel Generator output 1 1120 KW C9h ,
r.7 Crosatie capability Verificatins
- .......... ..e....... . . .. ................. .................
a p (,,7 e
- Stepc F.7.a uan and T.7.b mutt be performed independently of a
a
- each other. *
. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.*eeeeee . -
- a. Cycle ACB 1414 as follows:
- 1) VERITY /OPEN ACB 1411.
p 2) Turn ON the synchacope for Div 11 EST bus crosetle breaker ACB 1414. t 3) CLOSE Div 11 ESF bus crosstle breaker ACB 1414. , . 4) OPEN Div 11 EST bus crosstle breaker ACB 1414. INDEPENDENT VERITICATION
- _ 5) Turn Orr the synchscope for Div 11 ES' bus crosstle breaker ACB 1414.
I APPROVED DEC 161989 O l -/ (1178V/0095V/120289) EI. C). fi. Ft. I
abA s.l.a.4.a-A Revision 2 T.7 l
- b. Cycle ACB 2414 as f ollow s:
, _ , _ 1) VER1rY/OPD4 ACB 2811.
- 2) Turn UH the synchscope f or Div 21 EST bus crosstle breaker ACB 2414.
t 3) CLOSE Div 21 EST bus crosstle bresn tt ACB 2414.
- 4) OrDi Div 21 EST bus crosstie breater ACB 2414.
INDEPD4 DENT VERITICATIOi
$) Turn Orr the synchscope for Div 21 EST bus crosstle breaker ACB 2414.
F.8 f_ ngl _Innsf er. Pump Cte r ab111ty _ Ve rif1E Ali2D eenennenseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeneseeeeeeeeeeeeeeeen
- HQIT.
- Stop T.8.a and b verifies that the fuel Oil Transfer Pumps
- transfer fuel from the oil storage tanks to the day tank. *
- This step should be started shortly after the *)G is fully *
- loaded. Both transf er pumps should be tested, however, * .
- only one transf er pump in regning to be OPERABLE. If a a transfer pump is Out-of-f,ervice, mark the step for testing *
- it N/A.
eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenneeeeeeeeeeeeeeeeeeeesos
- a. VERITT 1A ruel Oil Transfer Pump maintains Day Tank level.
- 1) VER1f7/ PLACE 1A ruel Oil Trazfsf er Pump to the AUTO positlon.
_ , , , . _ _ 2) VERITY / PLACE IC ruel Oil Transf er Pump to the Orr position. t 3) VERIfT Day Tank level is maintained for 1$ minutes.
- 4) PLACE 3C ruel Oil Transfer Pump to the AUTO position.
- b. VERITY IC ruel Oil Transfer Pump maintains Day Tank level.
- 1) VERITY / PLACE IC ruel Oil Transfer Pump to the AUTO position.
. 2) VERIFT/ PLACE 1 A ruel Oil Transfer Pump to the Orr position.
t 3) VERIIT Day Tank level is maintained f or 15 minutes.
- 4) PLACE 1A Tuel Oil Transfer Pump to the AUTO position.
APPROVED DEC 161969 O (117BV/0095V/120289) B.O.S.R.
Attub 6 1.A.3.a.4 [ Revision 2 [ F.9 Dat.neut Leased nun and shulgora f
. merg . : 'O
- The Diesel Generator must be maintained at 1 $500 RW for
- the duration of the test (1 AD mins). HONITOR CLOSELY and *
- ADJUST RW output to malatain 1 $$00 RW.
[ [ i
................................................................ j
- a. After the Diesel Generator has run loeded at 2 $100 rw for ;
1 10 minutes, SHUTDOWN the Diesel Generator per Bor DC-12 and i RECORD the following datal i
- 1) Clock time KW output < $$QQ KW
- 2) Clock time KW output 1 $$09 KW 3 from step r.5.b. or step r.6.a.3)b) !
as applicablet ; I
- 3) Total time RW output 1 $10D KW W min (1 10) !
r.10 final'Conditlona- i
- a. VERIrY/ PLACE the DC 1A ACB 1413 Auto Reclose Circuit Arn I Selector-Switch in the NORM position at 1PN01J. {
i INDEPENDENT VERITICATION !
)
b.- After the Diesel Generator is shutdown and the cooldown cycle is I complete, ALIGN the Dlesel Generator for standby operation by ! i performing the followings t 1) VERITY the ** UNIT AVAILABLE FOR ENERGENCY lamp la lit. !
- l t 2)- VER!rY all 4 DC Power indicators are lit. 1
[
-t 3). VER!rY/ PLACE the DO 1A Control Mode Selector Switch in the l REMOTE position at 1PLO7J. .j INDEPENDENT VERITICATION I l
- 4) REMOVE _the key and return it to the Shift Eng!neer or
i desAgnee. W 5) VERITY.all the local annunciators are not lit. If any 'f* annunciator is lit, NOT!rY the Shif t Engineer or designee for evaluation and RECORD lit annunciators. 7 L i APPROVED
DEC 181969 i l -) -
l(117sV/0095V/120289) B.O.S.R. t-1 l '. ? I ! > -.a
.ove 6...... a..
Revision 1 F.10.b LOCAL ANNUNCIATORS LIT - O EVALUATED ACCEPTABLI:s SE or designee l t 6) VERITY the Diesel Generator Output Breaker in ATTER TRIP. l INDEPEHOENT VERIr! CATION
- c. VER1rY/ PLACE 1A ruel Oil Transf er Pump in the AUTO position.
l INDEPENDENT VERITICATION
- d. VER!ry/ PLACE 1C fuel Oil Transfer Pump in the AUTO position.
INDEPENDENT VERIr! CATION
- e. RECORD the Diesel fuel 011 Day Tank level f rom 1LI-DOO35: ,
a < r <1 1s ee> , INDEPENDENT VERIr! CATION
- f. r!LL the 1A DG ruel Oil Storage Tanks, as necessary.
- g. CALCULATE the jetal fuel oil in the Diesel fuel Oil Storage .
Tanks in the Io110 wing manners
- 1) RECORD 1A DG FO Sto Tk 1A Level f rom ILI-D0001At %.
- 2) RECORD 1A DG 70 Sto Tk 1C Level from 1LI-D0021A %.
- 3) ADD both tank levels and RECORD totals %.
(_.___. 4) DIVIDE total by 2 End RECORD resultas t %. (1 11AA e ll) INDEPENDENT VERITICATICRI
- h. WH5N the respective air compressors have cycled off, RECORD the DG Right & Left Bank Air Receiver air pressures at 1PLO7J and VERITY pressure greater than or equal to 110 psig in at least ant of the twon i
- 1) Right Banks psig (1 212)
APPROVED () (1178V/0095V/120269)
-12 DEC 161969 g g
ace a.4 4...a 4 R3 vision 2 f.10.h
- 2) Left Banks psig (2 110) l t 3) Pressure verified 1 210 psig in at least one of the tvc.
O- 1. DRAIN water off the Diesel Generator fuel O!! Day Tank by performing the following steps
- 1) OPEH 1D0116A. 1A D/G Day Tank Instrument Leg Drain Valve.
t 2) CLOSE 1D0116A when the drain flow is f ree of wtter. INDEFENDENT VER3r!CA710H
- 3) Clean up any residual oil on the floor.
- j. VER1rY the Eshaust Silencer Rupture Disc is Antact.
- k. DRAIN any water present. from each alt receiver by performing the following steps:
- 1) OPEN ISA147A and 1SA147C,1A DG Starting Air Receiver Drain valven. ;
I r b. CLOSE 1SA147A and ISA147C when drain is f ree of water. 1HDEPENDENT VER!rICA71CBI
- tt021;
- l O * #.' Il the Percentage fuel D6y which Specifications.
Tank as is equal required to 150 gallons contained in by Technical *
- lli Percentage is equal to t.he required tank level necessary * .
- to meet Technical Specification limits (> 44.000 gal) *
- plus the unusable fuel percentage (Ll% ) . *
- G. ACCyJTANCE CRfTERfl All the data entered is within the limits specified in the steps designated as acceptance criteria by r for Modes 1-6. Steps containing data have the acceptable parameter following the data blank in (parenthesis). Steps containing a required action meet acceptance criteria when signed off. ,
g3,,33 APPROVED DEC 161969 13 (117av/oo9sv/laoze9) 8. 0. S. R.
avvo s,s.s. .o.e Rovlsica 2 UNIT CHE 1B DIESEL CENERA'!OR OPERABILITY HCD4TMLY (STAGGERED) AND SCH2- AFliUAL (STAGGERED) SURVE! *i LANCE O A. STATEMENT Or APPLICABILITI This procedure outlines the steps necessary to verify the OPERABIL1'lT of the 18 Diesel Generator. This requirement is applicable in Modes 1 6. eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.
- ltQII
- It Unit 1 is in Modes 5 or 6, only one D,iesel Generator is *
- required to be OPERABLE for Unit 1. If the 1B Diesel e
- Generator is anoperable, then ensure Lht 1A Diesel Generator *
- is OPERABLE.
eneseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee neeseene.neeeeeeeeeeeeeeeene D. REFERENCEE
- 1. Cooper St4semer KSV Diesel Generator Instrvction Huhuals Vol 1 & 2.
- 2. NRC Regulatory Guide 1.108.
- 3. Technicti Specifications ,
- n. Lusiting 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 Requirementes .
- 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, Diesel Generator Startup.
- b. BOP DC-1171, Diesel Generator Start /Stop Log.
- c. BOP DC-1172, Diesel Generator Operating Log.
- d. B0P DG-12. Diesel Generator Shutdown,
- e. BOP DGt13, Trouble-Shooting Diesel Generator APPROVED DEC 161969 m
s-(1176V/0095V/120289)
' C ' I' EI'
esso ses.s.s.e s Revistos 2 ,
- f. 190$ 3.2.1-816. Unit One ESrAS Instrumentation Slave Relay Surveillance - Train 8 Auto S1 - K611.
- g. 1805 8.1.1.2.a-1, Unit One 1A Diesel Generator
('-'I Operability Monthly (Staggered) and Semi-Annual (Staggered) Surveillance.
- h. ISOS 8.1.1.14. LCOAR - AC Sources - Operating.
- 1. 1805 8.1.2,la. LCOAR - AC Sources - Shutdown.
i US HRC Inspection Report 50-456/86052s 50 457/86040 5. (Braidwood) dated 12 Nov 1986 (Enclosure 2. Item 2.o).
- 6. Station Commitments:
- n. 6-87-048
- b. 6-87-056 ,
- c. 6-87 019 C. LEERT.QUISITES
- 1. Receive permission f rom the Shif t Engineer or designated SRO licensed assistant prior to performing this surveillance by ,
having the Data Package Cover Shoot 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 blank Diesel Generator Start /Stop Log (BOP DG-1171) and Diesel Generator Operating
. Log (BOP DG-1172) when perf orming this surveillance.
D. PRECAUTiWS
- 1. The Diesel Generator will Auto Start if an emergency signal is received.
- 2. If the pressure drop across the full-flow Lubricating Oil i
illter reachew la psi, the elements must be replaced before L further operation of the Diesel.
- 3. Car protection should be worn by personnel in the Diesel Generator Room during Diesel operation.
- l. 4. An operator shall be stationed in the Diesel Generator Room
( whenever the Diesel is. started for testing. ' APPROVED DEC 161969
~
2 EI. C). Si. Ft. (%--']' (1176V/0095V/120289)
e s+e s.....s.s s Rovision 3
- 5. Do not statt or coutinue to operate the Diesel !! the Diesel i
Generator Room temperature escoeds 132'r. Do not esceed tiesel Generator rating of 101Q FM or I ( 6. 1D1D mmps load for greate than 2 hours.
- 7. Operate only Ot1I Lmergency Diesel Generator per Unit in parallel with offsite power at any one time. This w!11 prevent dkmage to more than one Diesel Generator p:'r Unit !!
a fault condition develops on the grid.
- 8. In order to prevent Isochronous Operation when s Diesel Generator is in the F.mergency Mode and paralleled to the grid, F E teturn the f.mergency Mode Speed Voltage Control Switch to AUTO if it is currently in the HANUAL Extp00HCY position.
C. Lili11AT1WE AND ACI1CtlS
- 1. As stated in Technical Specifications Limiting Condition for Operation (LCO) 3.8.1.1 and 3.8.1.2.
- 2. The Tech Spec requirement for the Diesel to start from ambient and accelerate to at least AQD RPM in less than or equal to 10 seconds shall be considered met if frequency ,
escoeds iQ Hs within 10 seconds.
- 3. The routinely scheduled Monthly and Semi-Annual portions of this surveillance each shall be performed on a Staggered Test Basis with 190S 8.1.1.2.a-1~.
- 4. Verity / Maintain at least 21 percent fuel oil level in the Diesel Tuol Oil Storage Tanks during the Diesel Generator a run (unless the DG is already Ill0PERABLE).
- 5. In the event the Acceptance Criteria (t) is not met during performance of this surveillance. IMKEDIATELY notif y the Shift Eagineer or designeo to initiate LCOAR 1BOS 8.1.1-la if in Modes 1-4 or LCOAR 1805 8.1.2-la if in Hode t 5-6.
- 6. If this surveillance or a portion of this survellinnee is perforned for purposes other than scheduled testing, NO CREDIT shall be taken for its performance on the surveillance schedule. The Shift Engineer or designes shall designete those portions to be performed. Notations should be entered in the comments section of the Data package Cover Sheet containing the reason for performing the surveillance.
APPROVED DEC 161969 EB. C). S. It. O' (1176V/0095V/120289) 3 1
n ow ........... R0visies 2 T. MAIN BODY eseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen O a ggIg Initial each step in the SPACE provided adjacent to the a e i
- procedure step number ArTra the step has been 512rcIssrULLY i
- e completed. Person (s) performing INDEPENDENT VERIFICATICM
- shall faltlal in the space provided after the step. e seeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeemene .....e.
T.0 Subsections r.1. F.4, F.7. T.8 and T.9 must plyay.s be performed sequentially. Parallel Subsections F.2/r.3 and F.5/r 6 are l independent of one another so that alther subsection may be performed. Only one of each parallel subsection may be performed. The Shift Engineer or d.dignee shall designate which subsections shall be performed (Hormally shown on the Surveillance Schedule). seeneen eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene gggg a e
- Sequential perforvance of the required Subsections and the ,
- following parallel Subsections provides * .
*
- f.3 and F.5
- Manual local start and gradual loading. * ;
*
- T.3 and F.6 *
- Auto start f rom EST and gradual loading. .
- e T.2 and F.6
- Manual local start and 1 kQ see loading.
- e T.3 and T.6
- Auto start f rom EST and A AQ sec loading.
- e ............................ enenneene een.........enneenenen SIAILI l_ . ,
l . r .1. l Initial Conditions i Manual Local Start (BOP DG-12) l l, r . 2._ l l l1l
.LL l_
Auto Start rrom ESr (280S 3.2.1-816) (Quarterly) 4 Intermediate Conditions lr.4 - l and Verifications I Load to 1.8ilAQ KW l ! Load to 1 fiQQ ICW-(Gradual) l4Ll l.LLl (within 1.0 seconds) (Semi-Annually) (Monthly) l l ruel Transfer Pump l1Ll Operability 0- , W E One Hour Loaded Run, and Shutdown
, f l1Ll g _
L c.3 - . l Ll rinal Conditions 4 3 El og END O
^
'(1176V/0095V/120289)
-4
sow. ........e-. R visica 1 l T.1 Initlti conditl2AA f
- a. RECORD the followingt DATE: 11 *I TINE: b HODE:
i
- b. FECORD the following for the stopwatch Inst QA it !
~
Calibration dates
- c. RECORD the Diesel fuel Oil Day Tank level from 1Lt.DOO38 ,
t" % (,1 33 II) eeeeeeeeeeeeeeeeeeeeeeseseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee.......
- l itc H, e
- Verify / Maintain at least in percent fuel o!! level in the e ;
- Diesel fuel Oil Storage Tanks during the Diesel Generator e ;
- run (unless the DG le already INOPERABLE). e j
- d. Calculate the total fuel oil in the Diesel fuel 011 Storage !
Tanks in the following scanner ( Acceptance Criteria (t) N/A Af , the 1A DG is already INOPERABLE)
- 1) RECORD 18 DG r0 Sto Tk 1B Level f rom 1L1-DOOO2A %.
y
- 2) RECORD 18 DG TO Sto Tk 1D Level f rom 1LI-DOO22A: ,, %. ,
\ #
- 3) ADD both tank levels and RECORD totals %. ,
e /* ,
- 4) DIVIDE total by 2 and RECORD resultat t %. l (1 93.8 til)
F.2 Manual Loemi Start (BOP DC-11) n..........e..... ..... . ......eeee.eeeeeee.e**eeeeeeeeeeeeenne e g a !
- Prior to starting the Diesel, ensure a stopwatch is . .
- available to record the time it takes for the Diesel to e
- reach > 1Q20 volts.
- l
+
eeeeeeeeeeeeenneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- a. RECORD the DG Right & Left Bank Air Receiver air pressures at IPLO8J
- 1) Right Banks psig APPROVED -
- 2) Left Banks psig *. 6.a DEC 161969 <
B.O.S.R. ( C (1176V/0095V/120289) P _ _ _ _ - .-,-,.-n.-- ,-_. -.
1b06 6.1.1.3.4 2 ! R3visies 2 < l l T.2.
* / b. VERITY / PLACE the DC 18 ACB 1421 Auto Reclose Circuit Arm Selector Switch in the GURV TEST position at 1PM01J. *, 6.c I a
g o c. Locally at 1PLOBJ, STAR 7 the Diesel per 20P DC.11.
*[ d. At the same time the Diesel is started, START the stopwatch. As soon es. the Diesel reachJs > 1000 volts, SWP the stopwatch and l
then inmediately verify 2109 RPM and f requency between R1 to ! AL2 He. ., 6.b { r Agte start rtom,Jgt,_11aos 3.2.1 elft1
- CAllIMM * !
- OS 3.2.1-816 WILT. ENER0!EE SLAVE RELAY K611 WHICH WILL *
. START DIE $EL CENr. RAMP 18 IN THE tMERGENCY MODE. UNTIL
- THE G IS SELECTED TO MANUAL IN 1 DOS 3.2.1 816, ALL HOPJ4AL .
- PRCrft IVI: FEAWRES ARE BYPASSED. If ABNORMAL COND1710HS
- ARISE, .
- )P THE DO USING THE EMER0tNCY STOP PUSMBUTTON A7
- 1PLOSJ.
.............b...............................................* .
................N..n.............................................
N gqgIg
- Prior to starting the Diesel, ensure a stopwatch is .
- available to record the time it takes for the Diesel to *
[ -
- reach > 10A0 volts. \
..........................e................................
p .... G
- a. DECORD the DG Right t. Left'9ank Air Receiver air pressures at ,
1PLOBJ: .
- 1) Right Banks psig
- 2) Left Banks psig *, 6.a
~
*s b. VERITY /PLACEtheDC18ACB1423Auh.oRecloseCircuitArm Selector Switch in the SURV. TEST position at 1PM01J. *, 6.c
\
- c. START t.he 18 Diesel Generator per ISOS 3.2.1-816.
\'
* .d. At the came time the Test Switch 5834 is depressed in 180s 3.2.1-816 to start the Diesel, START the stopvatch. As soon as the Diesel reaches > .40D9 volts, STOP the stopwatch and then inenediately verify 2, itDD RPM and f requency between it.d to R.2 Hs.
- 6.b
-APPROVED DEC 161969 a.o.s.n.
O (1176v/0095V/120289) _..._..a._.. . . _ _ ._ __..___.____._u_ . _ .._ . _ _ . . _ . _ -
Abut e.A.4...a.. 1 R:visica 2 T.4 Initratditta Cond1Lisna_.ana varifIcat12ns
, e....... ... .....................................e............e ' ' a gag e
- Monitor the Diesel for abnortaal conditions. If trouble
- e occurs, refer to BOP DG-13 or the appropriate BAR. *
. e eeene.......eeeeeeeeeeeeeeee.. .... ........e ....e.........
- a. 1HHEDIATELY RECORD the DG Right f. Left Bank Air Receiver alt pressures at IPLOBJ and VERITY a pressure decrease f om the value recorded in steps T.2.a or F.3.s as applicables
.- - l
- 1) Right Banks ,_, psig
- 2) Lett Banks __
psig
/ 3) Pressure decrease verlfled in both Air Receivers. *, 6.a f "# b. VER1rY 18 and/or 1D Tuel 011 Transfer Pump STARTED.
t h- c. RECORD the following data:
- 1) From ihe stopwatch, time for the DG to reach
> iQAD volts: # see (.i 10) ,
- 2) DG running RPM: f. OO RPM ($11 to $12)
- 3) D0 running voltages t dMU V (2110 to 113A)
- 4) DG running frequency: t-- beh Hs (R) to fL_2)
-* d. UPDATE BOP DC-1171, Diesel Generator Start Stop Log. .
b / e. VER!rY/ PLACE the D0 IB Control Mode Selector Switch in the REMCrft position at 1FLO8J. T.5 Load to 1 4QS_fGIAduali enamene4e eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**ee
- IL'ZIE
- x
- Operstw the Diesel Generator for approsimately $ minutes *
- before loading. When performlog the following step, the
- e Diesel Generator should be loaded gradually to reduce *
- thermal stresses in the cylinder heads. When increasing a
* ' load from A KW t'No 11AQ RW, the load should oe applied in
- e 1Q20 KW steps over a' period of 2 to $ minutes. *
........ we eeeeee**eene neeeeeeeeee... . .. ....e.. ..........
- a. Request that the NSO synchronlee the Diesel Generator to its associated EST bus and gradually load it to l M AQ KW as per BOP DG.11.
APPROVED DEC 161969 . -lC ' u (1176V/0095V/120289) B. o. s. Ft. l _ _ _ _ _ __ __ _ . . _ _ . _ - . _ _ , _ . _ _ _ _ _ _ . _
4 eve ... 4... . [ R3visica 2 ; i t r.$ N f
- b. Wl'en the Diesel Generator output reaches 1 5500 KW, RECORD the l followings \ !
O \ Clock time when Ehe Diesel Generator output
\
1 15@ *W
?
r.6 Load to 1. 5500 KW _(ylthin AD maggadsl [ I eseeeeeeeeeeeeeeeeeenneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeene... a RQII f e Before synchronising the Diesel Generator to its associated **
- EST bus, have a stopwatch ready to measure the time it
- takes to reach 2 11QQ KW. :
nemoneaeeeeeeeeeeeeeeenooneeeeeeeeeeeeeeeeeeeenoneeseeeeeeeeeene annaan.eeen..ee.een.nene ....... .e.een.een.een eeee.....ne ee.e : NOIE
- when loading the DG to 2 5500 KW in 1 60 seconds, utilise l
- as much of the 60 seconds as possiblae to minimise-stress *
[
- on the engine and turbocharger.
eeeee*eenemoneeeeeeeeeeeeeeeeeeeeeeeeneseeeeeeeeeeeeeeeeeeeeeeee i
- a. Roguest that the MSO synchronise the Diesel Generator to its
- i associated ESF bus and load:it to A $120 RW as per BOP DG-11.
When closing the breaker, OBSERVE and PERTORM the following !
/ 1) At the same time the Diesel Generator Output Breaker is closed, START the stopwatch.
(
- 2) LOAD the Diesel Generator to 1 1120 KW per BOP DG-il within AD seconds. . .t
.p
+
+~.- i
- 3) _
When the Diesel Generator Jutput reaches 1 MQD KW, STOP the stopwatch and RECORD the follawings [ l a) Time it took .for the Diesel Generator 6o loads e N sec (A 10) b) ' Clock time when the Diesel Generator output k 2 ihan sW OG "' ; I. t i b ( APPROVED i D00161969 f f B.O.S.R. ! (1176v/0095V/120289) , i I
. _ c. - . . -_-_ _ . . _ __ ._ _ _ __ _ ,__ _ . _.._._,_ _ _ ._._ _ _ ___ __ _ ., _ . _ _. _ ,_,n......_,-_,
A W6 46.1. A . 2.e-a Revistoa 2 [ r.7 rusi Tranatar P== oomIAh111ty_Yat.111sakina ! 7 nau * . y
- Step r.7.a and b verifies that the fuel 011 Transfer Pumps .
- transfer fuel from the 012 storage tanks to the day tank. *
- This step should be started shortly after the DG is fully * ,
. loaded. Both transf er pw.ps should be tested, however, e t
- only one transfer pump is taquitad to be OPERABLE. If a *
. transfer pump is Out-of-Service, mark the stop for testing .
. It N/A. .
i
- a. VERITY 18 fuel 011 Transfer Pwep maintains Day Tank level. !
- 1) VERITY / PLACE 18 fuel 011 Transfer Pump to the AUTO position. l l
- 2) . VER177/ PLACE 1D ruel 011 Transf er Pump to the Orr position. f i
t_ -3) VER1rY Day Tank level is maintained for 1$ minutes. [ 5
- 4) PLACE ID ruel Oil Tr#Losfer Pump to the AU70 position. j
- b. VER1rY 1D-ruel 011 Transf er Pw.p maintains Day Tank level. l
, 1) VER1rY/ PLACE 2D ruel 011 Transfer Pw.p to the AUTO position. f i
, 2) VERITY / PLACE 18 fuel Oil Transfer Pump to the Orr position. j
~
r 3) VER!rY Day Tank leve1 1s maintained for 15 minutes. i
- 4) PLA!E 18 fuel 011- Transfer Pw.p to the AUTO position. f
. i F.8- One_Rour Loaded Run ama Ehulenza 'I
................................................................ 3
- HDIE *
- The Diesel Generator must be maintained 'at 1 $399 RW for
- l
. the duration of the. test (A 12 mins). MONITOR-CLOSELY and- . (
- ADJUST RW output to maintain 1 1199 RW. *
(
..............................................* ...........a....
k
- a. After the Diesel Generatnr has run loaded at 1 110D W fur ,
a 10 minutes. SffUTDChet the Diesel Generator per 800 DG-12 and .i RECo*D the following datat [ i
- 1) Clock. time FW output < $102 RW . j
- 2) Clock time'rW output 1 15AQ RW !;
-from step r.$.b or step r.6.a.3)b)
?.s applicables i
- 3) Total time- KW output 1 $$AQ RWI . ( ,,,,, min (1 AD) >
t
, APPROVED l
... DEC 161969 ,
(1176V/ooe5v/120249) i B.O.S.R. >
~
h L
aus e.a.4...a-. j Revision 2 l t 4 T.9 f.inal Con 111.t1DA8 j
- a. VER1rY/ PLACE the DG 18 ACS 1423 Auto Reclose Circuit Arm ,
O Selector Switch in the NORM position at 1PM01J. INDEPENDENT VER1rICATION
*, 6.c j
- b. After the Diesel Generator is shutdown and the cooldown cycle is ;
complete, ALIGN the Diesel Generator for standby operation by ) - perfotining the followings j v- 1) VER1rY the
- UNIT AVAILABLE FOR EMERGENCY" lamp is lit.
l 5 t 2) VERITY all 4 DC Power indicators are 11t. t 3)- VEktrY/ PLACE the DC 18 Control Hoda Selector Switch in the REMOTE position at 1PLO8J. INDEPENDENT VERIr!CATIW __ 4) REMOVE the key and return it to the Shif t Engineer or designee.- t 5) VER17Y all the local annunciators are not lit. If any annunciator is lit, h0T1rf the Shift Engineer or designee , for evaluation and RECORD lit annunciators. LOCAL ANNUNCIATORS LIT - ! EVALUATED ACCEPTABLEt SE or designee d 6) VERITY the Dlesel Generator Output Breaker in~AFTER TRIP. INDEPENDENT VERIFICAT1W
- c. VERITY / PLACE 18 fuel 011 Transfer Ptap in the AUTO position.
1 INDEPENDENT Vt.RIFICAT.!CH , , , , , , , . , _ i d. VER!rY/Pl. ACE 1D ruel Oil Transfer Ptep in the AUTO position. INDEI'ENDDIT VERIFIC ATION ,,,,,,,,,,. g f e. RECORD the Diesel fuel 011 Day. Tank level.from IL1-D0038: gf W. % (A AL H ) - APPROVED iI INDEPENDENT VERIFICATICtl g gg t 8,0.S.R. O (1,06V/0095V/120389) 30-1 o= - _ . _ . _ .. -
1805 8.1.1.2.a-2 [ Revision 2 T.9.
- f. r!LL the IB DG ruel 011 Storage Tanks, as neesssary, h,/ ; - g. CALCULATE the total' fuel oil in-the Diesel-Tuel 011 Storage i Tanks in the following manners l
- RECORD 1B DG TO Sto Tk 1B Level f rom ILI-DOOO2Ar %.
1) RECORD 1B DG TO Sto Tk 1D Level from ILI-DOO22A %.
- 2) j
- ADD both tank levels and 8eanD totals %.
- 3) ,
DIVIDE total by 2 and RECORD results: f %. t 4) , (2 21d til) [ INDEPENDENT VERIF.tCATION
- h. WHEN the respective air compressors have cycled of f, RECORD the t i
DG Right & Left Bank Air Receiver air pressures at IPLC8J and VERITY pressure greater than or equal to 210 psig in at least gm of the two ,
-t
- 1) Right Banks psig (1 210)
- 2) Left Banks psig (1 110) . ;
e 3) Pressure verified 2 lid psig in at least one of the two.. j
- 1. DRAIN water off the Diesel Generator Tuel Oil Day Tank by '
-( perfo:1ning the following steps: i
- 1) OPEN 1D01165, 1B D/G Day Tank Instrument Leg Drain Valve. p
. s . !
t 2) CLOSE ID0116B when the drain flow'is f ree of water. ; i INDEPENDENT VERITICATIOP j b
- 3) ' Clean up any residual oli on the floor.
- j. VERITY the Exhoust Silencer Rupture Disc is intact. :
'I
- k. DRAIN any water present, from each air receiver by perforiaing the following steps -
- 1) OPEN ISA147B and 1SA147D, 18 DG Starting Air Receiver Drain Valves. ,
f
-t APPROVED j DEC 181989 l
- B. O. S. R. j
'p .
.(1176V/0095V/120289) t L
h t'
+-,-e,s+ - ,,e , e-n, ,r- , e , ,e- -
1BOS 8.1.1.2.a-2 Revision 2 T.9 3
- 2) CLOSE ISA141B and ISA147D when drain is f ree of water.
O e INDEPENDENT VERITICATION
- EDIE
- ll Percentage wnir.h is equal to iSD gallons contained in the**
- Tuel Day Tank as required by Technical Specifications. .
- fit Percentage is equal to the required tank level necessary **
- to ::.e.t Technical Specification limite () 11 D20 gal) .
- plus de unusable f uel percent age (7 J%).
.............es.................................................
G. ACCLETANCE CRL'IEEIA All the data entered is within the limits specified in the steps designated as acceptance criteria by e for Modes 1-6. Steps containing data have the acceptable parameter tollowing the data blank in (parenthesis). Steps containing a required action meet acceptance criteria when signed off. O . APPROVED DEC 181989 B.O.S R. (Tinal) O. (1176V/0095V/120289)
}
APPROVED 1805 8.2.1.1 1 , g4 g Revision 1 . B. O. S. R. DC BUS TRAIN OPERABILITY WEEKLY SURVEILLANC.P. A, pf OF iPPLYf*inf LTTYt This procedure applies to the weekly verification of 125VDC Bus 111 and/or 112 operability in MODES 1-6. eneeeeeeeeeeeeeeeeeeeeeee ...eeeeeeeeeeeeeeeeeeeeeeeeee. ) e kCTTE o
- If the Unit is in MODES 1-4, both 125VDC ESF Bus *
- trains are required to be operable. If the unit * }
- As in MODES 5-6, only one 125VDC ESF Bus train e
- As required-to be-operable. e l e eeeeeeeeeeeeeeeeeeeeeeeee**eeeeeeemenese:eeeeeeeeen...
B. REFERENCES 1
- 1. Technical Specification 4.8.2.1.1.
I 2. Technical Specification 4.8.2.2. C. PRERECEIIEITEE t
- 1. Receive permission from the Shift Engineer or his designated SRO licensed assistent prior to performing this _ surveillance by having j him sign and date the Data Package Cover Sheet.
, i D. PRECAUTI(MS1
Y
, 1. None E. LiufTATrans inn Acticaggt
- 1. As stated in Technical Specifications Limiting Condition for Operation 3.4. 2.1 and 3. 8.2.2.
- 2. In the event the Acceptance Criteria is not met during the performance of this procedure, IMEEDIATELY notify the Shift Engineer to initiate LCOAk procedure 1908 8.2.1-la if in MODES 1-4 or LCOAR procedure 190s 8.2.2-la it in MODES 5-6.
F. MAIN BCI]Yt eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen HEIE
- This surveillance may be performed as a partial surveillance a e
'as applicable in modes 5 and 6 or to prove operability of
- l
- any individual component. * '
eneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen
- 1. ENTER Time, Date, and Unit Mode on Data Sheet D-2.
- 2. For the desired bus (busses) listed on the Data Sheet, perform the followings (0618v/0057V/100388)
l I 1BOS 8.2.1.1 1 Rsvision 1
*ta. RECORD DC Bus Voltage (b. RECORD Battery charger feed breaker position ec. RECORD Charger AC input breaker position.
td. RECORD Charger DC output breaker position. to. RECORD Feed Breaker from Battery Charger (cub Arl) position. ef. RECORD F6ed Breaker from battery (cub AT2) position
- g. RECORD Bus tie breaker (cub Drl) position.
I
- 3. Circle any actual data not meeting the required conditions prior to returning data sheets to the Shift Engineer.
G. ACCEPTANCE CRITEffAt
- 1. MODES 1-4: Actual data recorded on data sheet meets the required conditions listed on the data sheet for 125VDC EST Bus 111 AND 112.
- 2. MODES 5-6: Actual data recorded on data sheet meets the required conditions listed on the data sheet for 125VDC EST Bus 111 OR 112.
O , 1 APPROVED O (Final) OCT 141333 (0618v/0057V/100388)
i 1808 8.2.1.1-1 l Revision 1
~ ,V [3 DC BUS TRAIN OPERABILITY WEEKLY SURVEILLANCE 1
l
- 1. TIMEt /D 07 DATEt 4 M! UNIT MODEt a
125 VDc EEP Bus 111 Raoulred Actual . Minintan l ot , 2a. Bus Voltmaa 125 VDE e l7b l e C/rifD 2b. Batterv ehartrar fand brenhar iBus 131X cub (B) cloaad 2e. charner Ac innut breaker closed d A/// j 2d. f*ha rne r DC ci eut brenhar closed d d'IA N/A ' 2a. Fr2nd brenhar from Battery rharner fenh AF1) clomad d - p9l 2f. Faad brenhar front Battery (cub AF2) closed dr-Les/O 2a. Rua tie breaker to DC bum 211 (cub DF11 Imehad Onan A ff4' 4 5 i 125 VDC EEF Bus 112 Raoulred Actual Minlassa ot , 2a. Bun'Voltaan 125 VDC d 12b 2b. Battery charner fand bramkar (Bus 132X cub 4B) clomad d e tc Sf C 2c. charner Ac innut'branhar Clemed , d A> IA 2d. Pharner DC outnut branker clemed W 4 A4 2a. Faed bramher fran Battery charner fcub AF1) cloaad d MIA 2f. Faed brenhar from Battery fenb AF2) cloaad d Clhft7 ~- 2a. Bum tie breaker to DC bus 212 fenb JF1) Locked Onen (MlM
* .In MODES 1-4 both BUS 111 and 112 must.be operable.
- .In MODES 5 QR 6 only BUS 111 QE 112 must be operable. APPROVED .
V D-2 OCT 141988 (0618V/0057V/100388) FIN E B.O.S.R.
BYRON S!HULATOR ANSI /ANS-3.5-1985 CERTIFICATION REPORT INITIAL REPORT, SEPTEMBER, 1991 ( BYRON SlHULATOR i REAL TIME TEST I The objective of the Real Time lest is to verify that-the Byron Simulator performance 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 j valve travel times during normal plant operation and then during a loss of coolant accident with a loss of off-site power. l The results of the Real Time tests were satisfactory,'with a less than 1% difference in the steady state travel times and the accident condition travel times,
.V-lO
-(BYRONSIM 113/67 08/22/91) l l
BYRON SlHULATOR ANSI /ANS-3.5-1985 CERTIflCATION REPORT INITIAL REPORT, SEPTEMBER, 1991 BYRON SlHULATOR TRANSIENT TESTS 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 0.2.2. All Appendix B.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. The simulator response was reviewed by the Byron Simulator Transient Test Review Board. 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 Transient Test Review Board is located in Appendix 4. As indicated on the enclosed trantient test review sheets, the Transient Test Review Board accepted the individual dad plots and the overall test results with the understanding that any discrepancy reports (DR's) written as a result of the transient review will 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 flow were
- used because total steam flow and total feed
- flow are unavailable. ..a.......***...............
.........................a O
(BYRONSIM 113/68 08/22/91)
l DESCRIPTION OF TERMS AND UNITS USED IN TRANSIENT DAT A PLOTS TI TLE, DATE AND O TINE THA T THE DA TA WAS Pf_0 T Tr0 7216"'MAXIMm R ATE P0wtR R AaaP t 100 75 8001 01/09/91 Od 3d 50 THE ELAPSED TIME OF : 1 Diviss0N . 7106 secowos EACH TRANSIENT WAS 'O OlVIDEO INTO 20 INTERVALS I I I I I I I I I I I I I I l I (DIVISIONS) FOR PLOTTING . Y _ THE ELAPSEO TIME Of e _ _ EACH DIVISION IS LISTED l>'i SECONOS
~ \ I DI VISION
~
6 _
~ ~
THE VERTICAL AXIS OF EACH PLOT DIVIDES THE VARIABLE RANGE (LIS TED * ~ ~ BELOW) BY 10. FOR THIS PLOT, THE VERTICLE AXIS WOULO BE 2 - - FROM SSS TO 56S*F, WITH EACH DIVISION BEING !*F ,. . I l l i l l l l 1 1 kSi l l i
\ 0 $ lo 15 20 Ting -
RxT AVG (1) ( 555. , 565 1 01200 LOOD TAB,( Y f VARIABLE NAME VARIABLE RANGE DESCRIPTION Of VARIABLE r 1 VARI ABLE UNITS FL O W VARIABLES (Except RCS Loop Flo w).. . . lcm /s e c RCS Loop Flo w.. . . . R TEMPER A TURE VARI ABL ES.. . .. . . . . . . . . . D e gr e e 's F L E VEL VARIABLES. . . .. .. .. K PRESSURE VARIABLES (Except Pressurtzer Pres s ure).. . . psia , Pressurtzer Pressure.. . .. . . , , , . . .pstg NEUTRON FLUX VARIABLES: Power Range..... . . . .. . . .. . .R Source Range.. . . . . counts /sec t I i l U I s h e
BYRON SIMULATOR TRANSIENT TEST REVIEW O DATE : AUGUST 19, 1991 TRANSIENT TEST #/ TITLE : 7.2.1/ MANUAL RX TRIP
- 1. Baseline data utilized for test comparison in order of preference (highlight appropriate choices)
- a. Actual plant transient data EVENT.
- b. Analytical or design data DATA:
- c. Transient data from similar plant PLANT : BRAIDWOOD LER 201-90-008
- d. Panel of experts (best estimate)
COMMENTS:
- 2. Data Comparison Summary VARIABLE COMMENTS RESOLUTION RX PWR - PR TOE ACCEFihD n SIMULATOR @ 560'F, PLANT @ 557 F ACCEPTED W/
V AUC HI TAVE WR 08-91-0006 PZR PRBSS TOE ACCEPTED PZR LEVEL TOE ACCEFiED PZR VAPOR TEMP VERY SLIGHT INCREASE AT 18 MINUTES ACCEFibD HOT LEG TEMP TOE ACCEF1ED COLD LEGTEMP SlMULATOR @ 560 F, PLANT @ 557 F ACCEPTED W/ WR 08-91-0006 1 A S/G PRESS SIMULATOR @ 1112#, PLANT @ 1090# ACCEPTED W/ WR 08-91-0006 1 A S/G LEVEL AF THROTTLED @ 6 MINUTES ON SIMULATOR ACCEFitD 1 A S/G FW FLOW PLANT RESTORED MAIN FW FLOW ACCEFiED 1 A S/G STM FLOW SLIGHT SPIKE AT TIME OF TRIP ACCEPTED W/ WR 08-91-0007 1 A S/G WR LEVEL LEVEL DROPPED FURTHER ON PLANT ACCEPTED W/ WR 08-91-0009 O
BYRON SIMULATOR TRANSIENT TEST REVIEW VARIABLE COMMENTS RESOLUTION l]
- 3. Comparison Results Simulator capability to reproduce the defined transient: (circle one) c<a' ACCEPTABLEN _/
- b. UNACCEPTABLE
- 4. Review Board Signatures ( differing opinions must be documented )
NSin .t n. hn nkth bd Ob s t .. e / k L i h) W $ / COMMENTS: ese _ _ . _
O ATP 721 YCN0049 05/20/91 09:09:05 1 DIVISION = 60.00 SECONDS 1r i I I I I I I I I I I I I I I I 8 __ 6 __ 4 _. 2 __ I kl l I I i 1 l 1 l l l l l l 1 0 5 10 15 20 TIMI YCN0049 ( .000 , 105. ) 21090 PWR RNG CH 41 (QUAD 4) TOT O
ATP 721 -RXTAVG 05/20/91 09:12:30 -!
- 1. DIVISION = 60.00 SECONDS
.it i I I l- l- 1 I I I I I I I I I I 8 -
6 -
)
- M 2 __ -
i 1 I I I I I I I I I I I I I I O 5 10 15 20 TIME RXTAVG ( 520. , 620. ) 01200-LOOP TABLE Q
O ATP 721 YCP0480 05/20/91 09:44:26 1 DIVISION = 60,00 SECONDS 1C .~ l ! I I I I I I I I I I I I I I 8_ __ 6 __ __ 4 __ __ 2 __ i l 1 1 1 I I I I I I I I I I I O 5 10 15 20 TIME YCPO480 ( .200E+04, . 240E +04) 06720 PREESURIZER PRESS PT-455 O
l l O ATP 721 YCLO480 05/20/91 09:25:47 1 DIVISION = 60.00 SECONDS
-1f )
l I I I I I I I I i i l I I I I i 1 8 __ __ 8 __ A 4 __ __ V . me em 4 2 __ _ l- 1 I I I I I I i i 1 I I I i 1 0 5 10 15 20 TIME
-YCL0480- ( 10.0 , 80.0 ) 06550 PRESSURIZER LEVEL LT--459
O ATP 721 YCT0481 05/20/91 09:48:50 1 DIVISION = 60.00 SECONDS 1r I I I I I I I I I I I I I I I I 8 _ 6 _ l __ W 6 2 - __ l i 1 1 I I I I I I I I I I I I O 5 10 15 20 TIME YCT0481 ( 620. , 670. ) 91250 PRESSURIZER STM T O
iO ! l l l ATP 721 YCT0419 06/11/91 13:11:49 1 DIVISION-= 60.00 SECONDS If 1 I I I I I I I I I I I I I I I I l l 8 _. _ 6 _. _. 2 _. _ I I I I I I I I I I I I I I I I 0 5 10 15 20 TIE YCT0419 ( 520. 620. ) 06830 RC LOOP 1 A WR HOT LEG T i il Lo
ATP-721 YCT0406 06/11/91 13:16:08 1-DIVISION = 60.00-SECONDS If I I l l l I I I I I I I I I I I" 8 -.- ._ 6 m Q4 - - e 1 2 . ._ 4 se - 1 I I I I I I I I I I I I I I I . 0- 5 10 15 20 1 TIE YCT0406 ( 520. 620. -) 06825 RC LOOP 1 A WR COLD LEG T 1
O 3 ATP 721 YCP0400 06/11/91 13:06:42 ) i 1 DIVISION = .0.00 SECONDS 1r 1 I I I I I I I I I I I I I I I ,
. - l 8 -. -
c f i { _ l e . 4 2 _. I I I I I I I I I I l- 1 I I I i 0 5 10 15 20
- TIE YCPO400 ( 800. . 120E+04) 06S90 S/G 1A STMLINE PRESS PT-5 0
t i L,q ' lU ATP 721 YCLO400 08/11/91 13:28:20 f 1 DIVISION = 40.00 SECONDS ! If i I I I I I I I I I I I I I I I I i 8 - - l 4 _. l 2 _. -- !
.g i
. {
I" 1 I I I I I I l- I l i I I I I I O 5 10 15 20 TIE *
. . I YCLO400 ( .000 , 100. ). 06350 S/G 1A NAR RNG LEVEL LT-51 i I
L ; i O : l- l
4. !O ATP 721 YCF0403 06/11/91 13:21:55 4
- 1. DIVISION = 80.00 SECONDS
.1f I I 1 1 I I I I I I I I I I I l-i '= a _ _
i [ -e _- _ i 4 l- + p 4 _ _ LV . h' t - F I 'l- 1 1 'l l- -l i I I I l_. I i 'I l-l 0 5 to 15 20 r TIE
-YCF0403- (_000 . 400EM4) 06040 S/G FW F FT-510 4
1
O ATP 721 YCF0405 06/11/91 13:30:19 1 DIVISION = 60.00 SECONOS If I I I I I I I I I I I I I I I I 8 _ 6 _ ] 4 _ 2 _ I l' ! ! ! l l ! ! ' ' ' ! ! 8 0 5 to 15 20 TIE YCF0405 ( .000 . 400E+04) 06060 S/G 1 A STEAM F FT -512 O i
O
-ATP-721 YCLO404 08/11/91 13:36:17-1 DIVISION = 80.00 -SECONDS If I I I I I I I I I I I l- 1 I I I )
l l 8 - l 1 .. h $ - , M SEIE i ' i
-8 _
i I I -1 1 I I I I I I I I I I I -1 lL 0 5 10 15- to i TIE YCLO404 (.000 , 100. ) 06390 S/G 1A WIDE RNG' LEVEL LT-5' i
8
- 's _ [. . _
6 ,_ j , j T _ 3 gj __a O. n $- _. O, l, - y .. 4-O _ g_
* ,{
- e. ___.-_-__.I-O_
m g- _ 1 O. ~_ L-a- m 9
- _ o a 0- _
i. j _ t - i i D
^ - _
4 f~ _ _ d e j- _ - g
- o N
- 4 _4 w '
o _ _ _ z 3 D 4 , g i J i w " ~ U -- -. - _ 4
,.___}.----- - -
- O r _ .
i o m ' C. --_..[, _.- 1_ C n
.x 1
, in
._ i L i- 2
- 3.1gk - - __
g' - , g g
*ga ~ ~
. p'; b O f .
a a ..y
.~
e
-O y--_.~, -_ ..-,-4.-
- a. *,
I O._ _ O v, o es ., w i 0, O J - . f* s c t ' o ' c
;,' ),. , y --a _ _
R "* e,~ -
?k o .5 ? e -. ___ _ . _ _ _ _._ _ _ _
t-
- ' l O 3 $ _ __.
n , _UoE I - _ .~- ,c,. ' 1 .DE 3 O i p 5:- i
.c 9 0 ,
6bE fL a li _. s !. O ., s.,' r. es s. e 4 s' 0 e.% n d, c. g as e t u
,g t e, sa sq 4*
* ** q ei Et ,
, & e. -) J <+ + e d
- v. . e
- w $4 == e t
_J ._ .
O (- i ATP 722 RXTAVG 06/11/91 13:45:38 , l ! 1 DIVISION = 55.00 SECONDS 1r ! I I I I I I I I I I I I I I I I 3- ! 8 __ , i' i E
- e __ _
)
* ~~ -
i O. i 2
- j. e I I I I l -1 l l I I I I I I I I i
0 5 10 15 20 TIE
- RXTAVG ( 520. 620. ) 01200 LOOP TABLE I
i I
L I O ATP 722. YCP0480- Os/11/91 13:54:01-1 DIVISION = 55.00 SECONDS y I I I I y -l i I I l- 1 I I l I I I J-i
.8 I
u. i-j e __ L 1 4 .w[) . - - i .2 _ n
- ;%y = _
i. l -- 1 I l I l l l l I I l I i l l ! -- 0 5 10 '15 20 TIE i PT-455
. YCPO480 ( .200E+04 . 400E+04) 06720 PRESSURIZER PRESS o
b.. 3 }..
't j'
i
O
-ATP 722 ,YCLO480. 08/11/01 13:57:50
-1 DIVISION-= 55.00 SECONDS
-12 I I I I I I I I I I I I I I I I 8 _
j. [ L- 8 _. _ l
.o -
en g -4 _. _ gg 4 gg - 9 t - -- I I I I 'l l' I I I I I I I I I I
'O 5 10 15 to
. TIE YCL0480 ( 10.0 , 60.0 ) 06550 PRESSURIZER LEVEL LT--459 4 f .. S l-M: n
t' 4
- -* i l
' 'ATP'722 'YCT0481 08/12/91 04:39:21 i i- 1 DIVISION = 55.00 SECONDS
- it l I I I I I l- 1 I I l' I I I I I
- l
~
j i
, 8 - -
l 1
. - i 4
8 ._ - i-p 4 _ _ LV 4 c - I 2 __ t i 1 1 1 I I I I I I I I i i i 1 0 5 10 15 20 TIE. I , 670. YCT0481 ( 820. )- 91250 PRESSURIZER STM T
/~)'
L
. _ b
O YCT0419 08/12/91 04:43:37 ATP 722 1 DIVISION = 55.00 SECONDS tr I I I I I I I I
-.1 I I I I I I I 8 _
8 __ O 2 i 1 1 I i 1 1 I I l i I I I I I 5 10 15 20 0 TIME YCT0419 ( 520. 620. ) 06830 RC LOOP 1 A WR HOT LEG T O !
i O ATP 722 YCT0400 06/12/01 04:47:28 1 OIVISION = 55.00 SECONOS tr - 1 I l- 1 I I I I ! I I I I I I I 4 8 - t - N. 4. A 4 ~ (j ~ ~
-2 I I i i i I i 1 1 I I I I I I I 0: 5 10 15 to TIE YCT0406 ( 520. , 620. -- ) 06825 RC LOOP 1 A WR COLD LEG T-O L.
i i I O v e
/.TP 722 - YCP0400 04/12/91 04:51:34 i i
1 DIVISION = 55.00 SECONDS 12 l- I -l I I I I I I I I I I I I l- , i i 8 .. N-w = 4
. _ _ l u !
O t
~.
- z _ _
l
. n I I l- 1 I I I I I I I I I I I I j 0 5 10 15 20 TIE YCP0400 ( 800. . .120EM4) 06590 S/G 1A STMLINE PRESS PT l I
i f O l i I E
t i O ! ATP 722 YCLO400 08/12/91 04:55:40 i 1 DIVISION = 55.00 PECONOS 18 l l l 1 I I l 1 I I l l l l I~ T 1. 8 - l e e a f 8 [ 4 _ __
. 3 -
I
.2 -
}
r
. . i I l- 1 I l -l l I I I I i 1 1 1 1 0 5 to 15 to TIE .
- YCL0400 ( .000 , 100. ) 08350 S/G 1A NAR RNG LEVEL.LT-51 l l
O ! t i
-t
.e.-,-------.w,-,--.ew.,w%...r,, . , . . . - , . . _, , _ _ . , ,_mh.,.__-_m.
i i !o
- ATP 722 YCF0403 08/12/91 05
- 07:12 1
1 DIVISION = 55.00 SECONDS It j i i I I I I I I I i I l I I I I 9 ! I j 8 _. m 6 m I
, 4 -- _
e em
$ - ~
l 1 l l _ I I I I i i i 1 0 5 10 15 20 TIE 06040 S/G FW F FT-510 YCF0403 ( .000 . 400E+04)
. _ - . _ - - . . . . . ..___ - -__. - - .-- - ~ . . _ - . - _ = . - . _ _ . - -
l O ATP722 YCF0405 07/15/91 10:16:53 1 DIVISION = 55.00 SECONDS tt i I I I I I I I I I I I I I I l 8 l 6 -. _ asema ene
~
. < r .
I LM lA &P1
~
l,M I I I I I I 1 1 I l 0 5 to 15 20 l TIME
.YCF0405 ( .000 .. 500E+04) 06060 S/G 1A STEAM F FT-512 l
O L
i ATP722 YCLO404 07/15/91 10:22:11 , 1 DIVISION = 55.00 SECONDS i 1t l I I I I I I I I I I I I I I I 8 - -- m - 8 g O
-2 -
1 I I I I I I I I I l- 1 I I I I 0 5 10 15 20 TIME YCL0404 ( .000 , 100. ) 06390 8/G 1 A WIDE RNG LEVEL .LT-5 0
BYRON SIMULATOR i TRANSIENT TEST REVIEW l DATE : AUGUST 19, 1991 O' TRANSIENT TEST :#/7.2.3 TITLE
/ TRIP OF A SINGLE FICP l
- 1. Basoline data utilized for test comparison in order of proforence (highlight appropriato cholcos)
- a. Actual plant transient data EVENT :
- b. Analytical or design data DATA:
- c. Transient data from similar plant PLANT : BRAIDWOOD LER 20 1-88 022 d, Panel of experts (best estimate)
COMMENTS:
- 2. Data Comparison Summary VARIABLE COMMENTS RESOLUTION RX PWR - PR N ACCEPTED A HOT LEG TEMP N ACCEPTED A COLD LEG TEMP- N ACCEPTED B HOT LEG TEMP M ACCEPTED B COLD LEG TEMP N ACCEPTED i 1 A S/G PRESS N ACCEPTED 1B S/G PRESS N ACCEPTED ,
1 A S/G LEVEL AF THRO 1TLED @ 5 MINUTES ON SIMULATOR ACCEPTED 1B S/G LEVEL AF THROTTLED @ 5 MINUTES ON SIMULATOR ACCEPTED 1 A S/G FW FLOW N ACCEPTED 1 A S/G STM FLOW SLIGHT SPIKE AT TIME OF TRIP ACCEPTED W/ WR 08 910007 , 18 S/G FW FLOW N ACCEPTED 1B S/G STM FLOW SLIGHT SPIKE AT TIME OF TRIP ACCEPTED W/ WR 08-91-0007 i O :
1 BYRON SIMULATOR TRANSIENT TEST REVIEW
'~ ~
(] ,, VARIABLE COAMENIS RESOLUllON
- 3. Comparison Results Simulator capability to reproduce the defined transient: (circio one)
~'
Q. ACCEPTABLE
- b. UNACCEPTABLE
- 4. Review Board Signatures ( differing opinions must be documented )
O?.?Ein fkr . . bikklOd _ IT._ & ML % thikil W ___ _ COMMENTS: _
--.e.
=*G 6 M__
__ eBIS - 4 E M OW Sue glish eup ene emme O
m i O ATP 723 YCN0049 08/12/91 05:12:40 1 DIVISION = 45.00 SECONDS tr I I I I I I I I I I I I I I I ___.i s _ e 4 _. _ 2 _ , it i I i 1 l l 1 1 I IJ l i I I 0 5 10 15 20 TIE - YCN0049 (. 000 , 105. ) 21090 P M RNG CH 41 (QUAD 4) TOT l O
i i i O : I ATP 728 YCT0419 08/12/91 08:01:41 i 1 DIVISION = 45.00 SECONDS l If i i i i i I I I I I I I I I I I I i w - 8 8 _ j i (
> 4 -
/ .t
. L -
i
. t t .
I i I I 1 1 I i 1 1 1 I I I i 1 I l- l l 0 5 10_ 15 20 t r TIE ! l YCT0419 ( 520. . 820. ) 08830 RC LOOP 1 A Wt HOT LEG .T r i O f t , .i l 7
t i
+
O ! ATP 728 YCT0408 04/12/91 05:58:07 : i 1 DIVISION.= 45.00 SECONDS l 1r ; I I I I I I I I I I I I I I I I ! l 1 s _. _ ; f l e _ _ ; r L i I r 4 - !
.O '
_ - e i 1 _. _ i i l 1 I i l I 1 I I I I i l i I ! 0- 5. 10 15 to i TIE t
+
YCT0406 ( 520. 620. ) 06825 RC LOOP 1 A Wt COLD LEG T ! i
.f i,
O J, t i l ..
n v
- ATP 723 YCT0439 08/12/91 05
- 41:21 1 DIVISION = 45.00 SECONOS 4 1e '
L I I I I I I I I I I I I I I I I S 8 2 - 1 I l l l l I I I I I I I I I l-0 5 10 15 to TIE YCT0439 ( 520. . 620. ) 06910 RC LOOP 18 Wt HOT LEG T F O I-
i l l ATP 723 YCT0428 08/12/91 05:38:36 l 1 1 DIVISION = 45.00 SECONDS
'TI 1 l- i i i i i i i i i i i i i
a _ e _ - l [ t
}4 - '
~
\
. . l; t _ _
1 1 1 1 I I I I i 1 1 1 1 I I I ; O 5 10 15 to TIE I I YCT0426 ( 520. , 570. - ) - 06870 RC LOOP 18 WR COLD LEG T l i O ! l'
?
n
,_ , - , , - , , . - . _ . _ , ,, .__.__.m.L... -,, _ , , , , _ , . , . , . . . . _..__.,.._,__...._--._.-.i,.,-...,_._.... _
O ATP 723 YCP0400 08/12/91 05:54:11 1 DIVISION = 45.00 SECONDS 1r I I I I I I I I I I I I I I I I 8 _ f . 8 _ O 2 ._ l l I I I I I I I I I I I I I I 0 5 10 15 20 TIME YCP0400 ( 800. . 120E44) 06590 S/G 1A STMLINE PRESS PT-5 O
O ATP723. YCP0420 07/15/91 10:39:37 1 DIVISION = 48.00 SECONDS . It i I I I I I I I I I I I I I I I . 8 -.- ._ 8 O Q - ' e A
'2 _. - -
1 I I I I I I I I l- 1- 1 I I I I ; 0 5 10 15 20 TIME i YCP0420 ( 750. . 125E444) . 06620 S/G 18 STM.INE PRESS. PT-5 l 3 i
.b i
O ! i 1 I Lc-..-.__.....____..______.__.._.__ _ _ _ _ - _ . _ -
. . - - _ . .- -. - . -- - ~ - - -.. . ___- _._ - - ...- -.-. . - .~ -
1 l O ! i ATP723 YCLO400 07/15/91 10:44:18 l i i i 1 DIVISION = 48.00 SECONOS If I I I I I I I I I I I I I I I I : f 8 -. _ ( j e _ l O I
'I I 1 -l l I i 1 I I I I I I I ! l 0 5 10 15 20 TI>E YCL0400 ( .000 , 100. ) 06350 S/G 1A NAR RNC LEVEL LT-51 0
I.
~~
O ATP 723 YCLO420 06/12/91 05:34:58 1 DIVISION = 45.00 SECONDS 1r I I I i i I I I I I i l I I I i 8 _. 6 _. 6 M 2 _. y _ l l I I I I I I I I I I I I I I O 5 10 15 20 TIE YCLO420 ( .000 , 100. ) 08400 S/G 1B NAR RNG LEVEL LT-52
O , i ATP 728 YCF0403 08/12/91 05:46:11 i 1 DIVISION.= 45.00 SECONOS if ; I I I I I I I I I I I I I I I I l n I l
. . p 8 -- -
..O 2 - l < 1 1 l l -l I I l- 1 1 I -l i I I o 5 to 15 to TIE I
-YCF0403 (.000 . 400E+04) 08040 S/G FW F FT-510 5
?
O - P 1 i i u..--..--_. _ . _ _ _ _ _ , _ . . _ _ . , . - . . , _ _ . _ _ _ _ . . . , _ _ . . _ _ _ . _ - . . . . . . . . . . . , - _ . . _ . . . . . _ . _ _ . . _ . _ _ _ . . _ . _ . _ . _ _ _ . , _ . _ _ - _ _ , _ . . _
O ATP 723 YCF0405 06/12/91 05:50:15 1 DIVISION = 45.00 SECONOS 1r_ l l- 1 I I I I I I I I I I I I I 8 _. 8 M M 2 __ l . . l l 1 I I I I I l l 1 1 I I I I I l 0 5 10 15 20 TIE YCF0405 -( .000 , . 400E+04) 06060 S/G 1A STEAM F FT-512 O
i l I i 1 O ! i ATP 714 YCN0049 08/11/91 08:07:58 , t 1 DIVISION = 57,00 SECONOS ; it :~ 1 I I I I I I I I I I I I I I I i 8 _. _ ! t i 4 - !
,I I
4 _ i 2 _- - ; e i I LL i l I i l I l 1 I I i 1 1 -1 ! i 0 5 10 15 to [ TIE l t YCN0049 ( 000 , 105.
) 21090 PWR RNG CH 41 (QUAD 4) T0T l O !
t r, ,...-,m. c....-,,- . -. _ . ._ _ .s
.-.-._,--..,._,,....._-..-~,_..,.._,,._.,..._,,.,_.._,.,,._,.....2
O ATP 724 RXTAVG 08/12/91 06:11:17 1 DIVISION = 57.00 SECONDS if I f I I l l l l l l l l l l 1 I 8 _ 8 - d 2 _. - t l' I I I I I I I I I I I I I I I -1 0 5 10 15 20 TIE RXTAVC ( 520. , 620. ) 01200 LO(P TABLE u O
- . . - .- . _ . - . . _ = . . . . . . _ - - - - . _ _ - _ - -
t. O ! l i ATP 724 YCP0480 08/12/91 06:39:00 l 1 DIVISION = 57.00 SECONDS 1r I I I I I I I I I I I I I I I I i I lllll////// M N Iq 8 i 4 j l >
- I 2 - _
l I l l l l I l l l l l l l l l 1 f: I 0 5 10 15 20 TIE YCP0480 ( ,190EM4, . 240E+04) 06720 PRESSURIZER PRESS PT-455 E l o , i
O i ATP 724 YCLO480 06/12/91 06:43:27 1 DIVISION = 57.00 SECONDS it il i I I I I I I I I I I I I I l 8 --
.6 -
I meses es.md 2 1 I I 1. 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 i
i I 1 ATP 714 YCT0481 08/12/01 06:47:49 , i 1 DIVISION =' 57.00 SECONDS It ' I I l l I I I I 4 I I I I I I I
. 4 _
l
. 6 M t - -
1 I i i 1 1 I I I I I I I I 1 l 0 5 to 15 to TIE
.YCT0481 ( 800. , 870. ) 91250 PRESSURIZER STM T O
t-
_. . _. _ . . . - . - --. . - . _ - . - - _ _ - . - . . - . - ~ ...._. - _ _ _ - l
- l
\
O i ATP 724. YCT0419 06/12/91 08:52:35 1 DIVISION = 57.00 SECONDS i if I I I I I I I I I I I I I I I I l s _ _ ; e _ _ i l CJ _- i 2 _. _ ; t i I I I I I I I I i i i I I I l ! 0 5 10 15 20 [ 1 L YCT0419 ( 520. 620. ) 06830 RC LOOP 1 A WR HOT LEG T f 1 [ t s LO : i l l I !
= ~
-s v ~ ,: -w w -.-an - - - . _ - - - - - - - - - - - - - - - - . . . _ . - _ _ _ _ . - - - . - . . - _ - - - . - - - - - - - . -
l O ATP 724 YCT0406 06/12/91 07:00:37 1 DIVISIDH = 57.00 SECONDS 1r i I I I I I I I I I I I I I I I 8 _. 8 4 - 2 _. _ __ i i i l I I I i I i I I I i l- 1 0 5 10 15 20 TIME YCT0406 ( 500. 570. ) 06825 RC L.00P 1A WR COLD LEG T O
t O ATP 724 YCP0400 08/12/91 07:04:38 1 DIVISION = 57.00 SECONDS if I I I I I I I I I I I I I I I I 8 .-
. =
4 M 4 # ; [ 2 - - j i e su I I I I i 1 1 I ! I I I I I i 1 0 5 10 15 to j TIE ; YCPO400 ( 600. . 120E+04) 08590 S/G 1A STM.INE PRESS P T -5 5 I i
- . . - . - - , - . . . - . . - _ . - - . . _ - _ . - _ _ _ _ . _ _ . . . _ . ._ _ _ _ _ _ . ~ _ _ . _ _ _ - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _'
O ATP724 YCL0400 07/15/91 10:50:52 1 DIVISION = 57.00 SECONDS if I I I I I I I I I I I I I I I I 8 , 8 O 4 2 . 1 I I I I I I I I I I I I I I 1 0 -5 10 15 to TIE
'YCL0400 (.000 , 100. . ) 08350 S/G 1A NAR RNG LEVEL LT-51 0
i t'.
O YCF0403 08/12/91 07:13:35 AYP 724 1 01 VISION = 57.00 SECONDS 1r I I I I I I I I I I I I i I I I
, f 8
6 _ W M 2 1 I i i I I I I I I I i i 1 I I to 15 20 0 5 TIE YCF0403 ( .000 . 400Es34) 06040 S/G FW F FT-510 0
. _ _ _ _ _. . . . _ . . . _ .___ _ _ . . _ . . . _ . - _ _ . . _ . . .~. . _ . _ . . -
O ATP 724. YCF0405 08/12/91 07:18:23 1 DIVISION = 57,00 SEcoles if I I I I I I I I I I I I I I I I
-8 --
8 - -
~ .
4 2 _. - __ I I I I I I I I I I I I I I I I 0 5 10 15 20 TIE YCF0405 ( .000 , .400E+04) 06080 S/G 1A STEAM F FT-512 Q
+
,,..m.,,,,,.,,..w,.,...-,pm,,,-, y
+- - -w,, w ,,,,,,...-,.,-.,-%,..--.,,,.,,.....,,,-_.#<-.
O ATP 724 YCLO404 08/12/91 07:09:18 1 OIVISION = 57.00 SECONDS
~l l I I I I I I I I I I I I I I 8 __
6 __ ._. es.nu IIIe 2 _. I I I I I I I I I I I I I I I I o 5 to 15 20 TIE YCLO404 ( .000 , 100. ) 06390 S/G 1 A WIDE RNG LEVEL LT-5 O
BYRON SIMULATOR TRANSIENT TEST REVIEW
, DATE : AUGUST 19, 1991 A,] TRANSIENT TEST #/ TITLE : 7.2.5 / MAXIMUM SIZE LOCA WITH LOSS OF O POWER
- 1. Baseline data utilized for- test comparison in order of preference (highlight appropriate _ choices)
- a. Actual plant transient data EVENT :
- b. Analytical'or design data DATA:
- c. Transient data- from similar plant PLANT;
- d. Panel of experts (best estimate)
COMMENTS: LOSS OF ALL AC POWER - 3 MINUTES INTO EVENT
- 2. Data Comparison Summary VARIABLE COMMENTS RESOLUTION RCS WR PRESS FOE ACCEPTED !
PZR PRESSURE FOE ACCEPTED PZR LEVEL FOE ACCEPTED CMNTPRESS FOE ACCEPTED . CMNT M ACCEPTED TEMPERATURE ; 1 A HOT LEG TEMP POE ACCEPTED 1 A COLD LEG TOE ACCEPTED ; TEMP CORE EXITTEMP NOfE ACCEPTED h v O P S
. . ~ - _
. BYRON SIMULATOR TRANSIENT TEST REVIEW
~
VARIABLE COMMENIS - RESOLUllON
'3. Comparison Results Simulator capability to reproduce the defined transient: (circle one)
(~ a. ACCEPTABLE J
~ - = = - .
- b. UNACCEPTABLE
- 4. Review Board Signatures ( differing opinions must be documented )
. St?_?Ai'n
. thi$nY/-
mrAm. Ot dLL SL de ni%' 7e,
~
}l/A;, ~$ _
COMMENTS: GEDS empre mefragene _ 4WD N i- ,
O ATP 725 YCP0491 08/12/91 07:23:47 1 DIVISION = 45.00 SECCNDS 1r I I I I I I I I I I I I I I I I 8 _ 6 4 __ ( SM uW e 2 _. q i i i i i i i i e i i i { l , 0 5 10 15 20 TIE YCP0491 ( .000 , . 250E+04) 06760 RCS WIDE RNC CH IV LP 1 P O
O ATP725! YCP0480- 07/15/91 10:55:11 1 DIVISION = .50.00 SECONDS
-ir I- l l l 1 l l l l 1 I I I I l l
'8
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t I I i I i i i l i I l~l i I 1 -l ! i 0 5 10 15-- 20 -j TIE f YCP0480- ( ,170EM4. . 250EM4) 06720 PRESSURIZER PRESS- PT- 455 j: Y LO 4
- ?
- j l- ._.-
O ATP725 YCLO480 07/15/91 10:59:32 1 DIVISION = 50.00 SECONDS 1r I I i I I I l I I I I I I I I I 8 _ 8 _- 4 2 __ l l I I I I I I I I I I I I I I 0 5 10 15 20 TIME YCLO480 ( .000 , 100. ) 06550 PRESSURIZER LEVEL LT--459 O
'l I i' Q ! l ATP 725 YCP1000 06/12/91 07:28:14 ! i i- 1 DIVISION = 45.00 SECONOS 4 it i l- I l- 1 I I I I I I I I I I i 1 3 ! 8 - _ i 4 . 6 _ vo 4 _ _ 2 - _ I I I I I I I I I I l' l i I i 1 0 5 10 15 to TIE YCP1000 ( ,000 . 100. ) 09080 CONTAINMENT PRESS PT-936 O
- . ~ . - _
O 'it i ATP 725 CHTAVCCM 08/12/91 07:31:53 ! 1 DIVISION =
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CHTAVCCM ( .000 , 300. ) 06180 AVE CNMT. TEMPERATURE .. 4 I O I l.. -.. .-. . . . - - .... -..--.. ...- . . . - - . - - - . - - .
l O i ATP-725 YCT0419 0$/12/91 07:36:02 1 DIVISION = 45.00 SECONDS it i I I I I I I I I I I I I I I l; e - I __ 4 i e __ _ 4 ._ __ i O i
}
2 - ; l I l- 1 I I I I I I I I I I l- 1 I ; 0 5 10 15 20 TIE j i YCT0419 (.100. 700. 06830 RC LOOP 1 A WR HOT LEG T
)
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O
-ATP 725- YCT0406 06/12/91 07:43:19 1 DIVISION = 45.00 SECONDS 1r i I l I I I I I I I I I I I I I 8 .u.
WWW engs uusse ensum B. and 4 2 A M M i -l I- -l l I I I -l I I I I I I I : 0 5 10 15 to l TIE - YCT0406 ( 100. 400. ) 06825 RC LOOP 1 A Wt COLD LEG T , 5 h i O i
?
lO ATP725 CRTTCEXIT(14) 07/15/91 11:04:20 1 DIVISION = 50.00 SECONDS 10 l I I I I I I I I I I I I I I I 8 __ _ 1
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2 __ _ l i I l- I I I I I I I I I I I i 0 5 10 15 to. TIME CRTTCEXIT(14) ( .000 , .100E+04) -06030 INCORE TC READING l
- l. .
lO
BYRON SIMULATOR TRANSIENT TEST REVIEW
/N. DATE : AUGUST 19, 1991 O TRANSIENT TEST #/ TITLE : 7.2.7 / TRIP OF ALL FW PUMPS
- 1. Baseline data utilized for test comoarison in order of preference (highlight appropriate choices)
- a. Actual plant transient data EVENT : BYRON LER 06-1 90-014
- b. Analytical or design data DATA:
- c. Transient data from similar plant PLANT :
d, Panel of experts (best estimate) COMMENTS: PLANT HAD OSCILLATIONS ON RCS TEMPERATURE AND S/G PRESSURE ATTRIBUTED TO STEAM DUMP AND AF FLOW VARIATIONS
- 2. Data Comparison Summary VARIABLE COMMENTS RESOLUTION RX PWR - PR N ACCEPTED (j AUC Hi TAVE N ACCEPTED PZR PRESS M ,
ACCEPTED PZR LEVEL M ACCEPTED PZR VAPOR TEMP M ACCEPIED _ HOT LEGTEMP NONE ACCEP1ED COLD LEG TEMP N ACCEP1ED 1 A S/G PRESS M ACCEPIED 1 A S/G LEVEL M ACLEPTED 1 A S/G FW FLOW AF THROTTLED @ 11 MINUTES ON ACCEPIED SIMULATOR 1 A S/G STM FLOW SLIGHT SPIKE AT TIME OF TRIP ACCEPTED W/ WR 08-91-0007 1 A S/G WR LEVEL LEVEL DROPPED FURTHER ON PLANT ACCEPTED W/ WR 08-910009 O
BYRON SIMULATOR TRANSIENT TEST REVIEW VARIABLE COMMENTS RESOLUTION
- 3. Comparison Results Simulator capability to reproduce the defined transient: (circle one) i a. ACCEPTABLE
- b. UNACCEPTABLE
- 4. Review Boaid Signatures ( differing opinions must be documented )
.!%_8h ___
efkzf1 4, aw zn esp
!ddh_ ik W COMMENTS:
O
_ . . . - ~ . . . .. .. ... _ . .. =- O ATP 717 YCN0049- 06/12/91 07:50:00 1 DIVISION = 40.00 SECONDS it I'l I I I I I I I I I I I I I I 8 i O 4 - u 2 i 1 l- 1 I I I I I I I I I I I I , 0 5 10 15 to TIE YCN0049 ( .000 , 100.. ) 21090 PWR RNG CH 41 (QUAD 4) TOT l t
O ATP 727 RXTAVG 06/12/91 07:54:27 1 DIVISION = 60.00 SECONDS
' I I I I I I I I I I I I I I I I 8 -
6 __ O
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1 1 1 I 1 1 I I I I I I I I i 1 5 10 15 20 0 TIE RXTAVG ( 500. 700. ) 01200 LOOP TABLE O i
O ATP 727 YCP0480 08/12/91 08:08:42 1 DIVISION = 80.00 SECONOS 1r I I I I I i l l 1 I I I I I I I 8 __ __ 6 ,,_ 4 ,,,_ 2 -. I I I I I I l_ l i I I I i 1 l l 0 5 10 15 20 TIE YCP0480 ( 150E+04, . 300E+04) 06720 PRESSURIZER PRESS PT-455 O
O ATP 727 YCLO480 06/12/91 08:12:00 1 DIVISION = 60.00 SECONOS 16 ' I I I I I I I I I I I I I I I I 8 _ 6 -. A - O ' - - 2 _ 7 _ I I I I I I I I I I I I I I I I 0 5 10 15 20 TIE YCLO480 ( .000 , 120. ) 06550 PRESSURIZER LEVEL LT--459 O i
O . 7 . ATP 727 YCL'0481 08/12/91 08:16:39 1 DIVISION = 80.00 SECONDS if , I I I I I I I I I I I I I I I I 6 8 _ _ L e - r
._ t f 4 _. - :
2 _. _ . I l- 1 I I I I I I I I I I I I I : 0 5 10- 15 20 ! TIE l t l i
-YCT0481 ( 600. , 700, ) 91250 PRESSURIZER STM T I' !
i t. i E I .
4 O LATP 727 YCT0419 08/12/91 08:21:02 n t,1 DIVISION = 80.00 SECONDS ! I I I I I I I I I I ~I I I I I I I i I , j- s 1 i 1 ! 8 _ _ j: .. - i:
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.YCT0419- ( 520. - , 620. -
) 06830 RC LOOP 1 A Wt HOT LEG T l
LO
i ATP 727 YCT0408 08/12/91 06:28:23 1: L 1 DIVISION = 80.00 SECONDS If I -l I I I I i i I I I I I I I I 8 _. _ l l l ! e _ _ l l l M M 2 _ _ ; 1 I I I I -l I- -l i I l 0 5 10 15- 20 TIE
- YCT0406 ( 550. 650. ) 08825 RC LOOP 1 A Wt COLD LEG T l l
j i O G 1
. ~ _ , __ _ _ . - . . . . _ _ _ . _ _ ....__ . . _ . , . _ _ . . _ .
l i i . l O 1 e l ATP 727 YCP0400 08/12/91 08:33:17 i_ 1 DIVISION = 80.00 SECONOS 4- jr I I I I I I I I l I I I I I I I i i
-s _ __
i e _ _ l-4 - - 1 2 __ _ i- 1 I I --I -1 1 1 I I I 1 I I I I i
- o 5- 10 15 to TIE i
YCP0400- ( 800. . 120E+04) 06590 S/G 1A STMLINE PRESS PT-5 4 J O M T *e-a:s e-- -
- __._m.s_-- -+=______-*m -7m + - -__ . _ - . y w -e.w - M at
O ATP727 YCLO400 ; 07/15/91 11:11:54 1 DIVISION = 60.00 SECONDS it -
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k , 1 ATP727 YCF0403 07/15/91 11:16:43 t 1 DIVISION m 60.00 SECONDS If ~ I l l l I I I i l I I I I I I I i
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f ATP727- YCF0405 07/15/91 11:21:52- a 1 DIVIsIoM = 80.00 SECONDS if I I l I- -l l l I I I l- 1 I I I I .
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-j ATP727 YCL0404 07/15/01 11:24:07 1 DIVISION = 60.00 SECONDS 1f - - . .
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