ML20081J300
| ML20081J300 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/21/1995 |
| From: | Cowen J CAROLINA POWER & LIGHT CO. |
| To: | Russell W Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.149, RTR-REGGD-1.149 BSEP-95-0139, BSEP-95-139, NUDOCS 9503270199 | |
| Download: ML20081J300 (158) | |
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CP&L Carolina Power & Ught Company John Paul Cowan PO Box 10429 Director - Sito Operations -
Southport NC 28461 Brunswick Nuclear Plant (910)457-2496 March 21,1995 SERIAL: BSEP 95-0139 10 CFR 55.45 Mr. William T. Russell Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 CERTIFICATION OF SIMULATION FACILITIES
Dear Mr. Russell:
Title 10 of the Code of Federal Regulation, Part 55.45 requires that power reactor licensees initially certify that their plant simulators comply with Commission regulations.
By letter dated March 21,1991 (Serial: NLS-91-059), Carolina Power and Light Company provided this certification for the Brunswick Steam Electric Plant, Units 1 and 2 simulation f acility. The Brunswick Plant simulation facility consists solely of a plant-referenced simulator that meets the requirements of 10 CFR 55.45 and complies with ANSI /ANS-3.5, 1985, as endorsed by Regulatory Guide 1.149.
Every four years on the anniversary of the certification, in accordance ~ w 10 CFR 55.45(b)(5)(ii), licensees are required to submit a report which Cantifies any uncorrected performance test failures and submit a schedule for correction of such performance test failures. The Brunswick Plant simulation facility certification report, NRC Form 474, and the ANSI /ANS-3.5 exceptions being taken for Unit 1 are provided in Enclosure 1. The Brunswick Plant simulation facility certification report, NRC Form 474, and the ANSI /ANS-3.5 exceptions being taken for Unit 2 are provided in Enclosure 2.
There were no uncorrected performance test failures of the Brunswick Plant simulation facility during this reporting period.
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'4 Mr. William T. Russell BSEP 95-0139/Page 2 If you have any questions regarding this submittale please contact Mr. W. B. Geise at (910) 457-2063.
- o. Very truly yours, John Paul Cowan SHC/shc (simcert.ltr)
Enclosures cc: NRC Document Control Desk Mr. S. D. Ebneter, NRC Region 11 - Administrator Mr. C. A. Patterson, NRC Senior Resident Inspector - Brunswick Mr. D. C. Trimble, NRR Project Manager (Acting) - Brunswick The Honorable H. Wells, Chairman - North Carolina Utilities Commission
ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC Pl. ANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 CERTIFICATION OF SIMULATOR FACILITIES CERTIFICATION REPORT, NRC FORM 474, AND EXCEPTIONS TO ANSI /ANS-3.5 BRUNSWICK PLANT, UNIT 1
p54C FORM 474 11S, NUCLEAR REGAATON COMMISSION Armemmk mismotas E== io/> ins nm ESTNATED BURDEN PER RESPONSE TO COMPLY Wm4 Tves MORMATON rn f UTION REQUEST. 120 HOURR. FORWARD SIMULATION FACIUTY CERTIFICATION lFECORs* "ML^"Gi"ML"T"*'"
.R E**g",Jn**."u TNu"C3 REGULATORY COMMtSSON, WASHMGTON, DC 200864001,AND TO THE PAPERWORK REDUCTON PRCLIECT (3150 01351. OFFICE OF MANAGEMENT AND BUDGET WASHINGTON. OC 20603 esfytJCnaget The form a to me fuse for mesi -- % vocortshcanon (N recunea), and for any snenge to a mmunuon teemry penormance teaung pian maae anw ruhai submnw of such a plan. Prowne the sonounrig edermahon and check the approonsie box to mdsome tenson for submmal FACluTY DOOKET NUMBER Brunswick Steam Electric Plant - Unit 1 6325 uCENSEE DATE Carolina Power and Light Company 03/21/95 Th..io rwy met t The amove named tocay incensee e useg a emumen tacility connetmg somy of a paantatowncee mmuwor tnat meets the reeuwements of 10 CFR SS.45,
- 3. The ownwinten facay meets the puedence cornamed m ANSI /ANS 3 S,1985, as enowned by NRC Regumory Guce 1.140.
W mee we any EXCEF'RONS to me comhcahon of the hem,01EOK tEME l )Q and nesenbe funy on anonianal pages as necessary NAME (w sawr amnoscewy AND LOCATON OF SNULATON F ACUfY, Brunswick Simulator - Brunswick SEP Training Building Box 10429, North Carolina Highway 87: 2 1/2 Miles North Southport, North Carolina 28461
- * *** * * * " # * "" " #" **" """'" "'" ' ~ "'"'**" " ~""'"' *** "** ~ # E X
DESCRFTON OF PERFORMANCE TESTING COMPLEED. (Anecn odotDorw papes as necessay ang soon6fy the nem aescopoon Desrig conoriued)
See Attached l
SIMULATON F ActuTY PERFORMANCE USTING SCHEDULE ATTACHED. Por the conouctaor pprommarey 25 or pegormance pass per yes for ene wrespenoa commenemy wren 7 P. one et e,s arencem; QSSCRFTON OF PERFORMANCE TESTING TO BE CONDUCTED. (Anacn asamorw papes as necessary ano cenery sne som oescapoon Deep canonued)
See Attached l l
l PERrORuANCE ttSDNG PLAN CHANGE. (Fw any modocean m e pedonnwice usong pren suommed we e pocoin pencaem) j DESCRFTION OF PUf0RMANCE TESTING PLAN CHANGE (Ansch eadmoner papes as necessary and merWry Fie asm cosanpoon Derng canonued.)
See Attached RECERTIFcATON (Desenbe consofwo accore tem senca resuRs of compmed portsmance sesong m accordance we 10 CFR 554S(b)(5)(v).
(Annen addeonar papas as . . , and toenet ye asm assegman sesng carenved.)
Any twee statemera or ommemn m snm accument, mcsuomo anacnmems, may to sunwei to swu ana enmem sancuans. e cenwy unoer penany se pequ'y that the mtormauon m the a oucument and snachments is Due and conocL SIGNATURE - AUTHolMED REPRESENT ATNE TTTLE DATE Director - Site Operations UO en _ __ unta 10 CFR del &, Communicamens, the term shas be ouemmed to the NRC as f=~ l SY Mall ADDRESSED TO: DBECfDFL ON & DANIEAft IEACTOR pura a aTEM BY DELNERY N PERSON 004:WPSTE FU(T NORTH i u1IslGIAR psra a augw rmamamena' TO THE NRC OFFICE AT; time FOOO41E F1ME I iMADesGTDet OC anenbeast MOQ041E he l
NRC FORM 474 (10 eq PRINTED ON RECYCLED PAPER
Brunswick Nuclear Plant '
Unit 1 Simulator Certification Exceptions Exceptions to ANSI /ANS 3.5 Exceptions identified during certification testing or the review / analysis of ANSI /ANS 3.5 1985 are contained in this section of the submittal. Exceptions are listed by ANSI /ANS 3.5 1985 reference and subject. Each specific exception taken and its associated justification is addressed individually and was reviewed and approved by the Configuration Control Board to ensure the exceptions do not adversely impact the license operator training program and do not prevent 10CRF55 compliant simulator examinations (operating tests) from being conducted.
- 1. ANS Section 3.2.1 - Degree of Panel Simulation The simulator is referenced to the Unit 2 control room for panels, controls, instrumentation, alarms, arid other man-machine interfaces. The differences between the control boards are limited. Plant modifications implemented on one unit usually appear on the opposite unit during a future outage. All labels and other identifiers are for Unit 2.
None of the Unit 1 back panels are simulated. See the Unit 2 :
certification for additional information on simulated back ,
panels.
Fire Detection Panel XU-69 is unique to Unit 1 and is not modeled.
- 2. ANS Section 3.2.3 - Control Room Environment Environmental dif ferences exist between the simulator control room and plant control room. The primary differences are locations of doors and windows, and the shape of the room. The simulator control room models Unit 2 only, the plant control room contains Unit 1 & 2. See Unit 2 certification
" Exceptions" for exceptions associated with the simulator control room layout.
Exceptions are taken to the plant control room physical layout. The simulator has three video cameras and permanently installed microphones that are used during examinations and training. The plant control room does not have cameras and microphones installed.
A public address (PA) station was added in the simulator which is connected to the plant PA system instead of the simulator PA system. This station can be activated to access
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Brunswick Nuclear Plant Unit 1 Simulator Certification the plant PA system for Emergency Plan drills. It is not used for normal simulator training.
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- 3. ANS Section A1.4 - Operating Procedures for Reference Plant Unit 2 controlled procedures are used for training on the simulator. The Unit 1 Technical Specifications ~are available for use on the simulator to allow a comparison of the units.
When Unit 1 training is conducted, operators use the procedures available to them. The Emergency Operating Procedures are used for both Units. When Unit 1 training is- t conducted operators use the appropriate section of the procedures. A review of Technical Specifications, Abnormal and Emergency Operating procedures was conducted to identify unit differences and possible training impact. The results of the.
review are available on-site.
- 4. The following ANSI /ANS 3.5 1985 sections are noted in the Unit 2 certification package submittal and also apply to the Unit 1 exception listing. Refer to Unit 2 " Exceptions" for additional information.
Section 3.1.1 (4) - Normal Plant Evolutions, Reactor Trip Followed by Recovery To Rated Power.
3.1.1 (7) - Ops. At Less Than Full Rated Core Flow.
Section 3.1.2 (1)a- Significant PWR Steam Gen. Tube Leaks 3.1.2 (12)- Misaligned Control Rods 3.1.2 (18)- Failure Of Reactor Coolant Pressure Volume Control Systems 3.1.2 (22)- Process Instrumentation, Alarms, and Control System Failures Section 4.3 (4) - Reactor Coolant System pressure versus temperature relationship indicative of ,
gross core voiding. !
Appendix B2 - PWR Simulator Operability Test l Performance Testing and Test Plan i Tests were performed in accordance with the test plan !
submitted with the original certification. Based on the systematic .j review of plant systems, only'two tests were determined to be j significant enough to run using the Unit i simulator option -
(discussed below). These tests were STP-TN-006.1, Unit 1, Turbine Trip at less than 30% power, and STP-MA-99.1, Unit 1, Turbine Trip from rated power. Both tests were conducted per the 1991-1994 test plan and have been completed satisfactorily. If problems were noted, they were corrected and the test performed satisfactory.
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9 Brunswick Nuclear Plant Unit 1 Simulator Certification Performance Test Schedule The test schedule for 1995-1998 is composed of annual and
, quadrennial tests. The schedule is the same as the . original certification test schedule for Unit 1. See Attachment 5 of the Unit 2 certification for the detailed test plan.
Unit 1 Testing and Training A systematic review of plant systems has identified items that are unique to Unit 1 and require systematic training. To support these items a conditional has been established to select Unit 1 simulation. This conditional changes the following items to match Unit i response:
- 1. EHC system activates 4 bypass valves versus 10
- 2. Group I isolation on high steam flow of 40% when noi in RUN is removed from isolation logic
- 4. Select Rod Insert (SRI) bus is functionally.~ removed on P610. The SRI position becomes another scram position if selected and the SRI push button on P603 will no longer function.
- 5. SBGT inlet and outlet valves do not AUTO open - on an initiation signal.
- 6. Condensate pumps.will AUTO start if booster pump suction pressure < 20 psig and either the discharge valve is closed or header pressure is < 145 psig, and the condensate pump can be manually started if the control switch is in manual and either the discharge valve closed or header pressure < 145 psig.
Certification testing for items identified in " Performance Testing and Test Plan" were tested using Unit 1 simulation.
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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 .]
DOCKET NOS. 50-325 AND 50-324 !
LICENSE NOS. DPR-71 AND DPR-62 CERTIFICATION OF SIMULATOR FACILITIES l l
l CERTIFICATION REPORT, NRC FORM 474, i AND EXCEPTIONS TO ANSl/ANS 3.5 ,
t BRUNSWICK PLANT, UNIT 2 l 1
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ffC FORM 474 U.S. NUCLEAR FEGULATORy rmmaiwiss ArmenmOm No.asamosa y seme= iomas I
EST1 MATED SURDEN PER PESPONSE TO COMPLY Wm4 MS INFORMATON m f P" TON REOUEST. 120 HOURS. FORWARD SIMULATION FACIUTY CERTIFICATION W 'M mAoEMENT'**" . "* """ ,"u"Jl*"'JA"j,T'J" REcuLATORY COMurssCN, WASHNGTON, DC 205854001,AND TO THE PAPERWORK REDUCTION PRCUECT 01904138), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON. DC 20603 SSTFEJCTENR The form a to ce thed for maw cemhoshon, sece#tshcanon (if reouped), and for any enange to a semuisten tacery penormance testmg pian snaos eher maial suomstles at auch a oesn. Promos the followm0 Irwormaten and check the i _ bon to mdmase season for sunmit:al.
F ACIUTY DOCKET NUMBER Brunswick Steam Electric Plant - Unit 2 #"'324 UCENSEE DATE Carolina Power and Light company 03/21/95 Th. ins w rinat
- 1. The above named facsiny iscensee a useg a swnuesten facility onamtmg ooiety of a piare-ee+erences esmuistor that meets tne requwements of 10 CFR SS.45.
- 2. Documemalen a owndebe tor NRC rowsw m accweance men 10 CFR SS.aSM.
- 3. The esmutaten faculty vnests the guicance cornamed m ANSI /ANS Sa,1965, as encorned Dy NFC Reguietony Gueo 1.140.
W these are any DCEMONS to the cevtsfmetion et the item. QGEK M ( $ and essenbe tuny on addnonal pages as necessary NAME iw ema mwencmen; AND LOCATON OF SIMULATEM ACluTY.
Brunswick Simulator - Brunswick SEP Training Building Box 10429. North Carolina Highway 87s 2 1/2 Miles North Southport, North Carolina 28461 BluaATON FAWTUERFORMANCE TEST ABSmACTS ATTACHED. Fw senannm mse cwoucma an me pened enong wet me can of mm ceshuom; X t DESCRIFTON OF PERFORMANCE TESTING COMPLETED. Miraca saamorw pages as necessay ana meiery me nem cesenpoon oemp carenuea.)
Sce Attached t
i SIMULATION F ACiUTY PERFORMANCE TESTING SCHEDULE ATTACHED. (For to canauce or apprommers y tr er awsonnance essa per yer av me sour-yew penos commenemy wrm me caer et rw esencahort)
DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED. JAffecn scusons pages as necessa7 ano mormry me som oescapoon Deeng carenued.)
See Attached PERFORMANCE TESMG RAN CHANE Fw any nedrAmean m a perenne mang penuornmed on a powous ne6pom)
X oEscRmoN OF eEwORuANCE TtsinG rum CHmGE essen saae-w pages - nec y we me ery r. nem eacmean meng ewenwa.)
See Attached RECERTIFICATION (Desence owrecewe ac6cne tem anaan resufts or comodered performance resang m accomance we 10 CFR Sis 5(b)(5#v).
Swace addreoner pages as necesswy and Aderesy me aem seecapoon bemp canonued.)
Any name swoment or ommsen m the occument, mciuomg anachmoms, may be sutnect to csvu ano snmmes sanctions. I cofttry unoer penany of perjury that the entonnaien m ths documern and attachments a true and conect SONATURE - AUTHOFCED REPFESENTATtVE 11TJ DATE Director - Site Operations O
. o _e_,.CFR a. _ h_.n .__ t.m. C _
BY MAL ADDRESSED TCk EWuCITNL CNN CF P&K1. EAR PEACTCH N 8 ATEM BY DEUVERY IN PERSON CBE WaffE R.NT femt UA fAK1 EAR fuNE E ARMf rmasam TO THE NRC OFFICE AT: Itself00041EPgE tuMpesGTON,DC Stuusemat F000fE1E, bE3 NFC FORM 474 (10 823 PRINTED ON FECYCED PAPER
z
. j Brunswick Nuclear Plant Unit 2 Simulator Certification .
Exceptions I Exceptions to ANSI /ANS 3.5 Exceptions identified during certification testing or the review / analysis of ANSI /ANS 3.5 1985 are contained in this section of the submittal. Exceptions are listed by ANSI /ANS 3.5 1985 reference and subject. Each specific exception taken and its associated juarification is addressed individually and was reviewed and approved by the Configuration Control Board to ensure the exceptions do not adversely impact the license operator training program and do not prevent 10CRF55 compliant simulator examinations (operating tests) from being conducted.
- 1. ANS Section 3.1.1 - Normal Plant Evolutions ,
(4) - Reactor Trip Followed by Recovery to Rated Power.
The test recovers the plant to 3% power vice full power.
Continuation of this evolution is the same as the start-up from a cold shutdown condition. Additionally, the transient is not part of the training program.
(7) - Operations at Less than Full Rated Coolant Flow.
This is a PWR specific transient.
- 2. ANS Section 3.1.2 - Plant Malfunctions (1) a. - Significant PWR Steam Generator Tube Leaks.
This is a PWR specific transient and not related to BWRs.
(12) - Misaligned Control Rods.
This is a PWR specific transient and not related to BWRs.
(18) - Failure of Reactor Coolant Pressure Volume Control Systems.
This is a PWR specific transient and not related to BWRs.
(22) - Process Instrumentation, Alarms, and Control System Failures.
Presently no malfunctions exist that fit under the heading of " alarm failures". However, each annunciator can be overridden by the Instructor to provide no ttarm, false alarm or random actuating alarms. An override is not considered to be a malfunction and in accordance with ANS/ ANSI 3.5 they do not require testing. Therefore, an exception is being taken to the standard Section 3.1.2 (22) requiring malfunctions for the failure of alarms.
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r Brunswick Nuclear Plant Unit 2 s Simulator Certification
- 3. ANS Section 3.2.1 - Degree of Panel Simulation i
The simulator is referenced to the Unit 2 Control Room for panels, controls, instrumentation, alarms, and other man-machine interfaces. All labels and other identifiers are for Unit 2. r An exception is taken on the location of the back panels.
Simulated back panels do not match the reference unit in size, shape, or configuration. A training value assessment was conducted to reanalyze the scope of simulation needed to support training. As a result of the assessment and review, the most effective and ef ficient. training environment was !
selected for each task. A backpanel upgrade was completed in ,
June 1993 resulting in the addition of four new panels, r
- 4. ANS Section 3.2.3 - Control Room Environment j Environmental differences exist between the simulator control room and plant control room. The primary differences are locations of doors and windows, and the shape of the room. The simulator control room models Unit 2 only, the plant control ,
room contains Unit 1 & 2.
Exceptions are taken in the control room layout. The location of the STA desk is not the same as the plant. The desk is placed several feet away from where it is in the plant control room.
The location of the Shift Supervisor / Communicator table in the plant control room is located near the end of the P601 .
panel. However, due to constraints in the simulator for access to doorways, the table is located near the XU- 5 panel.
The raised section of the SRO platform is located approximately one foot further away from panel P601 than in the plant control room. It has been verified that this difference does not affect the ability to see items on the ,
RTGB. !
The simulator has three video cameras and permanently -
installed microphones that are used during examinations and training. The plant control room does not have cameras and microphones installed.
A public address (PA) station was added in the simulator l which is connected to the plant PA system instead of the 2 !
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k Brunswick. Nuclear. Plant' !
Unit 2 Simulator. Certification !
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. simulator PA system. This station can be activated to access the plant'PA system for Emergency Plan drills. It is not used' ,
for normal simulator training, j i
Simulator control room annunciator sound is different from the ;
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Unit 2 control room annunciators. The annunciator for Unit'2.
ECCS panels have a distinctly different sound from Unit 1 and .
the simulator. The sound of Unit 2's ECCS annunciator coul'1 not be replicated because of a physical difference in .e plant mechanism. Therefore, Unit 1 annunciators sounds were used for tuning the simulator. j
- 5. ANS Section 4.3 (4) - Reactor Coolant System pressure versus !
temperature relationship indicative of gross core voiding. l This is a PWR specific transient and not related.to BWRs. [
This item is specific to PWRs only.
E Performance Testing and Test Plan Tests were performed in accordance with the test plan I submitted with the original certification with the following exceptions. Forty-nine malfunction tests'were added, five removed ,
and five annual Plant Performance tests added. Malfunctions and 'l plant tests added were based on-instructor input for new .
malfunctions or expansion of training programs and broadening the r scope of simulation. Attachment i summarizes malfunction tests j deleted, Attachment 2 and 3 tests added and Attachment 4 contains t the abstracts for new tests. ,
All tests conducted for the 1991-1994 test plan have been !
completed satisfactorily. If problems were noted, they were corrected and the test performed satisfactorily.
Performance Test Schedule !
The test schedule for 1995-1998 is composed of annual and
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quadrennial tests. The schedule is similar to the original certification test schedule with modifications as noted in .
Attachments 1-3. Additionally, STP-SS-001 30% Power Steady State Comparison has been deleted and STP-MA-425 EHC Pump Fail to Auto !
Start is added to the plan. Performance of a steady state test at ;
30% plant condition proved to be of no value. The ANSI 3.5 1985 requirement is met with the performance of the 50, 75 and 100%
tests. Attachment 5 contains the detailed test plan.
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e ATTACHMENT 1 CERTIFICATION TEST DELETIONS- DELETED MALFUNCTIONS TEST MALF ANSI /ANS 3.5, DELETED ,
NUMBER NUMBER YR 1985 MALFUNCTION TITLE REASON FOR DELETION ;
CROSS REFERENCE l STP-MA- 227 1 3.1.2 (9) and RFP FLvW Implementation of the Digital Feedwater System 074 (22) CONTROLLER FAILS (SMR 92-0337; PM-89-00*/2) required deletion HIGH of this malfunction. The associated controllers have been removed and replaced by j DFWCS controllers STP-MA- 228 3 3.1.2 (9) and RFP FLOW Implementation of the Digital Feedwater System 075 (22) CONTROLLER PAILS (SMR 92-0337; PM-89-001/2) required deletion LOW of this malfunction. The associated controllers have been removed and replaced by DFWCS controllers.
STP-MA- 235 2 3.1.2 (9) and FEEDWATER CONTROL Implementation of the Digital Feedwater System 078 (22) STEAM FLOW (SMR 92-0337i PM-89-001/2) required deletion TOTALIZER FAILS of this malfunction. The associated component has been removed.
STP-MA- 237 1 3.1.2 (9) and THREE ELEMENT Implementation of the Digital Feedwater System 079 .' 2 2 ) CONTROLLER OUTPUT (SMR 92-0337; PM-89-001/2) required deletion !
LOSS of this malfunction. The Dynamic Compensator (CR-K650) has been removed and replaced by DFWCS solid state componemts.
STP-MA- 344 4 3.1.2 (3) LOSS OF POWER TO Implementation of the new process computer 034 THE PMS (SMR 90-0189) new computer uses ERFIS UPS system with several feeds to PMS vs one power feed previously. The Simulator Configuration Control Board determined a new malfunction would not have training value.
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ATTACHMENT 2 ,
CERTIFICATION TEST ADDITIONS TEST MALF TEST ANSI /ANS 3.5, 1985 MALFUNCTION NUMBER NUMBER YEAR CROSS-REFERENCE TITLE STP-MA-148 138 2 3.1.2 (1) (b) s (c) & (20) HPCI Steam Brk HPCI Room STP MA-149 146 4 3.1.2 (1) (b) ; (c) & (20) H.PCI Steam Line Break in the Mini Steam Tunnel ,
STP-MA-150 099 4 3.1.2 (21) LPRM Bypass STP-MA-151 121 2 3.1.2 (1) (b) & (c) Recire Pump el Seal Failure STP-MA 152 111 1 3.1.2 (23) Manual Scram Defeat STP- MA- 15 3 123 3 3.1.2 (1) (b) & (c) Recire Pump Seal 42 Fails STP-MA-154 144 4 3.1.2 (17) & (22) Recire Pump MG Set Scoop Tube Failure STP-MA-155 149 2 3.1.2 (non-specific) RWCU Resin Injection Into Reactor Vessel STP MA-164 164 3 3.1.2 (22) MSL Rad Monitor Fails Downscale STP-MA-167 167 2 3.1.2 (23) MSIV Failure to Auto Close STP-MA-382 182 3 3.1.2 (15) Loss Of Turbine Bearino Oil Pressure STP-MA-188 188 4 3.1.2 (1) (b) RWCU Break In Heat Exchancer Room STP- MA- 2 31 231 1 3.1.2 (1) (b) RWCU Break In Triangle Room 77' STP-MA-232 232 3 3.1.2 (1)(b) RWCU Break In Return Line 20' STP-MA-250 250 3 3.1.2 (B) RBCCW Hi Rad .
STP.MA-251 251 3 3.1.2 (B) RBCCW HX/SW Tube Leak STP-MA-264 264 1 3.1.2 (22) & (23) HPCI Hydraulic Failure STP MA-268 26B 4 3.1.2 (22) RCIC Turbine Trip STP-MA-271 271 4 3.1.2 (17) & (22) RCIC Inadvertent Start STP-MA-275 275 4 3.1.2 (17) RCIC Injection Valve Overload STP-MA-276 276 1 3.1.2 (17) RHR Inj Vlv F015 Stuck Closed e
STP-MA-292 292 1 3.1.2 (17) RHR Heat Exchanger Bypass Valve Trip STP MA-298 298 1 3.1.2 (3) & (22) Auto Voltage Reg. Failure STP MA-304 304 2 3.1.2 (3) Grid Load Increase STP-MA-306 306 4 3.1.2 (3) 230KV Transmission Line Trip STP-MA-309 309 1 3.1.2 (3) & (B) Main Transformer Cooling System Failure STP- MA- 3 2 8 32B 3 3.1.2 (1) (b) & (c) Small Recire Suction Line Rupture STP-MA-354 354 2 3.1.2 (2) 2D Air Comp Fails to Load STP-MA-361 361 2 3.1.2 (22) Rx Building Vent Monitor Fails Downscale STP-MA-362 362 3 3.1.2 (22) Rx Building Vent Monitor Fails Upscale STP-MA 369 369 2 3.1.2 (22) SBGT Inadvertent Start STP-MA-399 399 4 3.1.2 (22) MSL Rad Monitor Fails Upscale STP-MA-403 403 2 3.1.2 (22) C32-PTN002 (Feed Flow) Failure STP MA-405 405 3 3.1.2 (23) Broken Downcomer Quadrant 1 STP-MA-406 406 4 3.1.2 (23) SRV Tailpipe Rupture STP-MA-409 409 1 3.1.2 (3) Station Blackout STP MA-410 410 2 3.1.2 (17) & (22) HPCI Auto Start Failure i
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b TEST MALF TEST ANSI /ANS 3.5, 1985 MALFUNCTION t NUMBER NUMBER YEAR CROSS-PEFERENCE TITLE I
STP-MA-411 411 4 3.1.2 (17) & (22) RCIC Fail to Auto Start Core Spray Failure to Auto Start '
STP MA-412 412 3 3.1.2 (17) & (22)
STP-MA-413 413 2 3.1.2 (17) & (22) RHR Failure to Auto Start STP-MA-415 415 1 3.1.2 (3)C & (22) DG #3 AVR Trip 6 i
STP-MA-416 416 1 3.1.2 (3)C & (22) DG #4 AVR Trip STP-MA-417 417 2 3.1.2 (3)C & (22) DG AVR Fails High f STP MA-418 419 3 3.1.2 (3)C & (22) DG AVR Fails Low STP MA-419 419 4 3.1.2 (3)C & (22) DG Differential Trip STP-MA-421 421 2 3.1.2 (22) Isolation Of Condensing Pot D004A BTP-MA-422 422 3 3.1.2 (22) Isolation of Condensing Pot D004B STP-MA-423 423 4 3.1.2 (5) CW Screen High DELTA Pressure i
STP-MA-424 424 4 3.1.2 (7) & (23) RHR Suction Strainer Clogging f
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ATTACHMENT 3 PLANT PERIODIC TEST ADDITIONS PIJJJT SIMULATOR PERIODIC TEST TITLE REASON FOR ADDITION OR DELETION PERIODIC TEST TEST PROCEDURE NUMBER NN OPT-04.1.2 STP-MV-747 Main Stack Radiation Monitoring Back Panel addition to simulator (SMR-92-0167).
System Channel Functional Test PT Tests Radiation Monitoring equipment not previously modeled.
OPT-04.2.1 STP-MV-748 Turbine Building Exhaust Vent Back Panel addition to simulator (SMR-92-0167).
Radiation Monitor Channel PT tests Radiation Monitoriing equipment nct functional Test previously modeled.
OPT-04.1.1 STP- MV- 74 9 Reactor Building Vent Exhaust SSR-93-0184 upgraded Radiation Monitoring logic Radiation Monitoring System to more closely model plant. Software was beyond Functional 1est the original scope of simulation. PT used to verify logic on the simulator.
OPT-8.1.4A STP-MV-750 RHR Service Water System Test added to verify RHR SW pump and valve timing Cyerability Test - Loop A data matches reference plant.
OPT-8.1.4B STP-MV-751 RHR Service Water System Test added to verify RHR SW pump and valve timing Operability Test - Loop B data matches reference plant.
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l ATTACHMENT 4 P TEST ABSTRACTS ,
t Attachment 4 contains the abstracts for tests added during the i 1991-1995 certification period.
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PERFORMANCE TEST ABSTRACT PTA-MA-148 ,
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE l 1.1 STP-MA-148, HPCI Steam Break HPCI Room 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (1)
Loss Of Coolant (b) inside and outside Primary Containment (c)large and small reactor coolant breaks (20) Main Steam Line as well as Main Feedwater Line Break ,
2.0 AVAILABLE OPTIONS ;
2.1 Severity of 0 to 100% line break located downstream of Pressure Transmitter N013 in the HPCI Room. -
2.2 Severity Rate of 0 to 60 minutes 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:138 3.2 MALFUNCTION SYMBOL.: MESO 47F 3.3 MALFUNCTION MENU...:ES i 3.4 This Malfunction is tested with a severity of 100% and i a severity rate of 0 minutes.
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. The HPCI System is in standby readiness in accordance with OP-19.
4.2 A recording device is setup to record the following test ;
parameters simultaneously versus time with a resolution ,
of 0.5 seconds or less: ;
i 4.2.1 Total Steam Flow............:MSW4111 4.2.2 Total Feedwater Flow........:CFW1REV 4.2.3 Reactor Pressure . . . . . . . . . . . . :NBPITAPT (32 )
4.2.4 HPCI Room Temperature.......:HVT4030A OR HPCI Room Temperature.......:HVT4030B 4.2.5 South RHR Room Temperature..:HVT1009B OR I South RHR Room Temperature..:HVTRBRS- 1 4.2.6 North RHR Room Temperature..:HVT1009A OR 1 North RHR Room Temperature..:HVTRBRN l 4.2.7 HPCI Raum Sump Level........:WDLO900S I SSP PTAMA148 REV 0
5.0 TEST DURATION ;
5.1 The simulator will be placed in the FREEZE mode after 10 f
- minutes has elapsed or unit conditions have stabilized.
6O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. '
7.0 DATE PERFORMED:10/30/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE i
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PERFORMANCE TEST ABSTRACT PTA-MA-149 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-149, HPCI Steam Break - Mini Steam Tunnel l 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (1) !
Loss Of Coolant (b) inside and outside Primary Containment (c)large and small reactor coolant breaks :
(20) Main Steam Line as well as Main Feedwater Line Break 2.0 AVAILABLE OPTIONS 2.1 Severity of 0 to 100% line break located downstream of the E41-F003 valve in the Mini Steam Tunnel. l 2.2 Severity Rate of 0 to 60 minutes f 3.0 TESTED OPTIONS ,
I 3.1 MALFUNCTION NUMBER.:146 3.2 MALFUNCTION SYMBOL.: MESO 48F 3.3 MALFUNCTION MENU. .:ES ,
3.4 This Malfunction is tested with a severity of 100% and 6 a severity rate of 0 minutes.
i 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. The HPCI System is in standby readiness in ,
accordance with OP-19.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution ,
of 0.5 seconds or less: i 4.2.1 Total Steam Flow............:MSW4111 4.2.2 Total Feedwater Flow........:CFW1REV 4.2.3 Reactor Pressure . . . . . . . . . . . . :NBPITAPT (32) 4.2.4 Mini Steam Tunnel Temp......:HVT5025A I
OR Mini Steam Tunnel Temp......:HVT5025B ;
OR Mini Steam Tunnel Temp......:HVT5025C OR Mini Steam Tunnel Temp......:HVT5025D ,
4.2.5 Reactor Building Exh Plenum.:HVTRBPLM j 4.2.6 South RHR Sump Level........:WDLO800S !
4.2.7 HPCI Room Sump Level........:WDLO900S SSP PTAMA149 REV 0 t
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t 5.0 TEST DURATION :
5.1 The simulator will be placed in the FREEZE mode after 10
- minutes has elapsed or unit conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:1/10/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. i NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING.
JUSTIFICATION.
NONE i
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l PERFORMANCE TEST ABSTRACI ;
PTA-MA-150 '
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE' ,
1.1 STP-MA-150, LPRM Bypass 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (21) Nuclear Instrumentation Failures.
2.O AVAILABLE OPTIONS 2.1 Select any of 93 LPRM operate switches' to the Bypass-postion. The 31 LPRMs in APRMs C & D are not selectable.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:099 3.2 MALFUNCTION SYMBOL.:MNIO54F 3.3 MALFUNCTION MENU...:NI 3.4 This malfunction is tested to verify LPRM bypass capability and APRM Trip /Inop logic for < 11 LPRM inputs.
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. ;
4.2 A recording device is setup to recor'd the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 APRM A............:NISAMTR(1) 4.2.2 APRM B . . . . . . . . . . . . : NISAMTR ( 2 )
4.2.3 APRM C . . . . . . . . . . . . : NISAMTR ( 3 )
4.2.4 APRM D . . . . . . . . . . . . : NIS AMTR (4 )
4.2.5 APRM E............:NISAMTR(5) 4.2.6 APRM F . . . . . . . . . . . . : NISAMTR ( 6 )
5.0 TEST DURATION 5.1 The recording device will be stopped after the effects of the malfunction have stabilized.
6.0 BASE LINE DATA ;
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:1/11/94 ,
SSP PTAMA150 REV 1
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. NONE I
90 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING l JUSTIFICATION. i.
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PERFORMANCE TEST ABSTRACT. .;
PTA-MA-151 i
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 'l 1.1 STP-MA-151', Recirculation Pump Seal #1 Fails 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, !
(1) Loss Of Coolant (b)- inside and outside - Primary containment (c)large and small reactor coolant breaks
)
2.0 AVAI GNii t CPfIONS i 2.1 Severity of 0 to 100% #1 Seal Failure.
2.2 Severity Rate of 0 to 60 minutes ,
i 2.3 This Malfunction allows selection of Recirc Pump 2A or ;
2B. 'j 3.0 TESTED OPTIONS l t
3.1 MALFUNCTION NUMBER..:121 l 3.2 MALFUNCTION SYMBOL..:MRC007F !
3.3 MALFUNCTION MENU....:RC l 3.4 SELECTED RECIRC PUMP: A i 3.5 This Malfunction is tested with a severity of 100% and i a severits rate of 0 minutes.
~
i 4.0 INITIAL CONDITIONS j I
4.1 The simulator is operating at approximately 100% steady i
'I state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution i of 0.5 seconds or less:
3.2.1 2A Recirc Pump #2 Seal Pressure. . :NBPSEALS (1) f i
SE 2B Recirc Pump #2 Seal Pressure. . :NBPSEALS (3) 3.2.2 2A Recirc Pump #1 Seal Pressure. . :NBPSEALS (2)
QR 2B Recirc Pump #1 Seal Pressure. . :NBPSEALS (4) 3.2.3 2A Recirc Pump Seal-Leak Off.....:RCWINSL(1)
QR 2B Recirc Pump Seal Leak Off.. ..:RCHINSL(2) 5.0 TEST DURATION l 5.1 The recording device will be stopped after 10 minutes has f elapsed or unit conditions have stabilized. j 1
SSP f PTAMA151 REV 0 )
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I 6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power t Plant Training Simulator, latest Revision. !
7.O DATE PERFORMED:3/3/92 ___
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. <
NOTE 9
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE 1
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1 SSP PTAMA151 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-152 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-152, Manual Scram Defeat 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, ,
(23) Passive malfunctions in systems such as engineered i safety features, emergency feedwater systems. ;
2.0 AVAILABLE OPTIONS i
NONE 3.0 TESTED OPTIONS l 3.1 MALFUNCTION NUMBER.:111 3.2 MALFUNCTION SYMBOL.:MRP006F 3.3 MALFUNCTION MENU...:RP 40 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. ;
i 5.O TEST DURATION ,
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5.1 The simualtor will be placed in thb FREEZE mode after depressing the Manual Scram Push-buttons. ;
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. j 7.O DATE PERFORMED:3/3/92 f i
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR !
PLANNED, AND ASSOCIATED DATES. !
1 NONE i
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SSP ,
PTAMA152 REV O f
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING ;
JUSTIFICATION. i
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- NONE
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PTAMA152 REV 0 i
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PERFORMANCE TEST ABSTRACT !
PTA-MA-153 i
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- 1. 0 ' PROCEDURE TITLE / ANSI 3.5 REFERENCE- l 1.1 STP-MA-153, Recirculation Pump Seal #2 Fails 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, l (1) Loss- Of Coolant (b) inside and outside Primary ;
containment (c)large and small reactor coolant breaks j l
2.0 ~AVAILABLE OPTIONS !
2 '.1 Severity of 0 to 100% #1 Seal Failure. f 2.2 Severity Rate of 0 to 60 minutes {
i 2.3 This Malfunction allows selection of Recirc Pump 2A-or {
2B. !
3.0 TESTED OPTIONS i I
3.1 MALFUNCTION NUMBER..:123 f 3.2 MALFUNCTION SYMBOL..:MRC009F i 3.3 MALFUNCTION MENU....:RC
- 3.4 SELECTED RECIRC PUMP: A '
3.5 This Malfunction is tested with a severity of 100% and j a severity rate of 0 minutes. !
4.0 INITIAL CONDITIONS I 4.1 The simulator is operating at approximately 100% steady state power. ,
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
3.2.1 2A Recira Pump #2 Seal Pressure. . :NBPSEALS (1)
QR j 2B Recirc Fump #2 Seal Pressure. . :NBPSEALS (3) ;
3.2.2 2A Recirc Pump #1 Seal Pressure..:NBPSEALS(2) !
QE 2B Recirc Pump #1 Seal Pressure. . :NBPSEALS (4) 3.2.3 2A Recirc Pump Seal Leak Off.....:RCWINSL(1) l QE 2B Recirc Pump Seal Leak Off.....:RCWINSL(2) 3.2.4 2A Recirc Pump Outer Seal Leakage:RCWOTSL(1) )
2B l 2B Recirc Pump Outer Seal Leakage:RCWOTSL(2) j SSP PTAMA153 REV 0
5.O TEST DURATION 5.1 The recording device will be stopped after 10 minutes has ,
- elapsed or unit conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. ,
7.O DATE PERFORMED:3/3/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ;
FONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. ,
NONE I i
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l PERFORMANCE TEST ABSTRACT PTA-MA-153 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE ,
1.1. STP-MA-153, Recirculation. Pump-Seal _#2 Fails' ;
i 1.2 . ANSI /ANS 3.5-1985, Section 3.1.2 Plant Malfunctions, ;
(1) Loss - Of Coolant (b) inside- and outside Primary containment (c)large and sma11' reactor coolant. breaks .
2.0 AVAILABLE OPTIONS {
2.1 Severity of 0 to 100% #1 Seal Failure.
t 2.2 Severity Rate of 0 to 60 minutes 2.3 This Malfunction allows selection of Recirc Pump 2A or l 2B. :
3.O TESTED OPTIONS -l t
3.1 MALFUNCTION NUMBER;.:123 !
3.2 MALFUNCTION SYMBOL..:MRC009F 3.3 MALFUNCTION MENU....:RC 3.4 SELECTED RECIRC PUMP: B i 3.5 This Malfunction is tested with a severity of 100% and a severity rate of 0 minutes. t 4.O INITIAL CONDITIONS 4.1 The simulator _is operating at approximately 100% steady f state power. j t
4.2 A recording device is setup to record the following test j parameters simultaneously versus time with a resolution l of 0.5 seconds or less: I 3.2.1 2A Recirc Pump #2 Seal Pressure. . :NBPSEALS (1)
M ;
2B Recirc Puttp #2 Seal Pressure. . :NBPSEALS (3) -:
3.2.2 2A Recirc Pump #1 Seal Pressure..:NBPSEALS(2) !
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2B Recirc Pump #1 Seal Pressure. . :NBPSEALS (4) f 3.2.3 2A Recirc Pump Seal Leak Off.....:RCWINSL(1) -(
M i 2B Recire Pump Seal Leak Off.....:RCWINSL(2) [
3.2.4 2A Recirc Pump Outer Seal Leakage:RCWOTSL(1) i M
2B Recirc Pump Outer Seal Leakage:RCWOTSL(2)
SSP !
PTAMA153 REV 0 l 5
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5.0 TEST DURATION !
5.1 The recording device will be stopped after 10 minutes has e elapsed or unit conditions have stabilized.
6.0 BASE LINE DATA >
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:5/22/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR -
PLANNED, AND ASSOCIATED DATES.
NONE l
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9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. .
1 NONE I
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PERFORMANCE TEST ABSTRACT PTA-MA-151 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-154, RECIRC PUMP MG SET SCOOP TUBE FAILURE 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (17) Failure in automatic control system (s) that affect reactivity and core heat removal AEQ (22) Process *
' instrumentation, alarms, and control system failures.
2.0 AVAILABLE OPTIONS 2.1 This Malfunction allows selection of either A or B Recirc MG Set Scoop Tube. -
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:144 !
3.2 MALFUNCTION SYMBOL...:MRCO21F 3.3 MALFUNCTION MENU.....:RC 3.4 SELECTED RECIRC PUMP.: v2A or 2B 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. Select and activate this malfunction.
Manually trip one of the RFPs to actuate a Speed Limiter >
- 2 Recirc Pump Runback.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A Recirculation Pump Flow....:NBWFLOW(10) 4.2.2 2B Recirculation Pump Flow. . . . :NBWFLOW (11) 5.0 TEST DURATION 5.1 The recording device will be stopped af ter the af fects of ,
the malfunction have stabilized.
6.0 BASE LINE DATA l I
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:6/13/93 i SSP PTAMA154 REV 0
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l 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, ;NCLUDING JUSTIFICATION.
NONE t
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' PERFORMANCE TEST ABSTRACT l PTA-MA-154
.l 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE l l
1.1 STP-MA-154, RECIRC PUMP MG SET SCOOP TUBE FAILURE !
1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (17) Failure in automatic control system (s) that' affect l reactivity and core heat removal AND (22) Process- i instrumentation, alarms, and control' system failures. -l 2.O AVAILABLE OPTIONS l 2.1 This Malfunction allows selection of either A or B Recirc j
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3.0 TESTED OPTIONS .
l 3.1 MALFUNCTION NUMBER...:144 i 3.2 MALFUNCTION SYMBOL...:MRC021F !
3.3 MALFUNCTION MENU.....:RC !
3.4 SELECTED RECIRC PUMP.: 2A orI2B) ~- l 4.0 INITIAL CONDITIONS }
i 4.1 The simulator is operating at approximately.100% steady .!
state power. Select and activate this malfunction. j Manually trip one of the RFPs to actuate a Speed Limiter j
- 2 Recirc Pump Runback. 'l 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A Recirculation Pump Flow....:NBWFLOW(10) 4.2.2 2B Recirculation Pump Flow....:NBWFLOW(11) 5.0 TEST DURATION l t
5.1 The recording device will be stopped after the affects of .i the malfunction have stabilized. {
1 6.O BASE LINE DATA j 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power !
Plant Training Simulator, latest Revision. l
- 7.0 DATE PERFORMED:1/10/94 l
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SSP l PTAMA154 REV O {
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8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE ,
i 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING ;
JUSTIFICATION. t NONE i
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1 PERFORMANCE TEST ABSTRACT PTA-MA-155 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE l 1.1 STP-MA-155, RWCU Resin Injection Into Reactor Vessel i 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (non-specific) ;
t 2.0 AVAILABLE OPTIONS t NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:149 3.2 MALFUNCTION SYMBOL.:MRWOO7F l
3.3 MALFUNCTION MENU...:RW i
4.0 INITIAL CONDITIONS ,
4.1 The simulator is operating at approximately 100% steady state power.
4.2 A recording device is setup to record the following test t parameters simultaneously versus time with a resolution of 0.5 seconds or less: ,
3.2.1 RWCU A F/D Effluent Conductivity. . :RWS0600 (1) ;
3.2.2 RWCU B F/D Effluent Conductivity..:RWS0600(2) 3.2.3 RWCU System Influent Conductivity.:RWS0500 '
3.2.4 Activity at MSL Rad Detector A....:RMPRMMSL 3.2.5 Activity at SJAE Rad Detector A...:RMPRMCOG i
5.0 TEST DURATION The recording device will be stopped after ten minutes has elapsed or the appropriate effects of the malfunction have occurred. ji 6.0 BASE LINE DATA i 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. ,
SSP PTAMA155 REV O !
7.O DATE PERFORMED:12/13/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA155 REV 0
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. l PERFORMANCE TEST ABSTRACT l PTA-MA-164 l
'1.0' PROCEDURE TITLE / ANSI 3.5 REFERENCE I
1.1 STP-MA-164, MSL Rad Monitor Fails Downscale f i
I 1.2 ANSI /ANS.3.5 1985, Section 3.1.2 . Plant Malfunctions, (22) Process instrumentation, alarms,: and control system i failures.
2.0 AVAILABLE OPTIONS ;
2.1 This malfunction allows selection of-A, B, C or D Main !
Steam Line NUMAC Radiation Monitor (s).
3.0- TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:164 3.2 MALFUNCTION SYMBOL.:MRM001F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...: A 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously.versus time with a resolution of 0.5 seconds or less:
4.2.1 MSL Rad Mon Recdr Channel A/C.:G5B01G2G 4.2.2 MSL Rad Mon.Recdr Channel'B/D.:G5B01G1G 4.2.3 MSL NUMAC Rad Mon A...........:G9501G1G 4.2.4 MSL NUMAC Rad Mon B...........:G9D01G1G 4.2.5 MSL NUMAC Rad Mon C...........:G9M01G1G 4.2.6 MSL NUMAC Rad Mon D...........:G9V01G1G' 4.2.7 MSL Rad Det Activity A........:RMPRMMSL(1) 4 . 2 . 8, MSL Rad Det Activity B........:RMPRMMSL(2) 4.2.9 MSL Rad Det Activity C. . . . . . . . :RMPRMMSL (3)
- 4. 2.10 MSL Rad Det Activity D. . . . . . . . :RMPRMMSL (4) 5.0- TEST DURATION 5.1 The recording device will be stopped af ter'the ef fects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA164 REV O
. i Plant Training Simulator,' latest Revision.
7.0 DATE PERFORMED:12/4/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE Y
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. !
NONE 1
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SSP PTAMA164 REV O i
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PERFORMANCE TEST ABSTRACT PTA-MA-164 i
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-164, MSL Rad Monitor Fails Downscale 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures. ,
2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of A, B, C or D Main Steam Line NUMAC Radiation Monitor (s).
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:164 3.2 MALFUNCTION SYMBOL.:MRM001F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...: D 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 MSL Rad Mon Recdr Channel A/C.:G5B01G2G 4.2.2 MSL Rad Mon Recdr Channel B/D.:G5B01G1G 4.2.3 MSL NUMAC Rad Mon A...........:G9501G1G 4.2.4 MSL NUMAC Rad Mon B...........:G9D01G1G l 4.2.5 MSL NUMAC Rad Mon C...........:G9M01G1G 4.2.6 MSL NUMAC Rad Mon D...........:G9V01G1G 4.2.7 MSL Rad Det Activity A........:RMPRMMSL(1) 4.2.8 MSL Rad Det Activity B. . . . . . . . :RMPRMMSL (2) 4.2.9 MSL Rad Det Activity C. . . . . . . . : RMPRMMSL (3 )
- 4. 2.10 MSL Rad Det Activity D. . . . . . . . : RMPRMMSL (4 )
5.O TEST DURATION 5.1 The recording device will be stopped af ter the effects of i the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA164 REV 0
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Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:03/31/93 {
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE ,
l 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING :
JUSTIFICATION.
NONE i
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SSP i PTAMA164 REV O ,
PERFORMANCE TEST ABSTRACT PTA-MA-167 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-167, MSIV Failure To Auto Close >
- 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, L (23) Passive malfunctions in systems such as engineered safety features, emergency feedwater systems.
2.0 AVAILABLE OPTIONS NONE - Malfunction #167 is set active and then the Main Condenser Vacuum Breakers are opened. At 10" Hg a Group 1 isolation signal is generated.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER..:167 3.2 MALFUNCTION SYMBOL..: MMS 006F 3.3 MALFUNCTION MENU....:MS 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Main Condenser Vacuum...:CNP2AHG 4.2.2 Inboard MSIV F022A......:VANB22A '
4.2.3 Inboard MSIV F022B......:VANB22B 4.2.4 Inboard MSIV F022C......:VANB22C 4.2.5 Inboard MSIV F022D......:VANB22D 4.2.6 Outboard MSIV F028A.....:VANB28A 4.2.7 Outboard MSIV F028B.....:VANB28B 4.2.8 Outboard MSIV F028C.....:VANB28C 4.2.9 Outboard MSIV F028D.....:VANB28D 5.0 TEST DURATION ;
5.1 The recording device will be stopped af ter 10 minutes has elapsed or unit conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA167 REV O
7.0 DATE PERFORMED: 3 /4 /92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE !
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE I
t t
c 1
t l
SSP PTAMA167 REV 0
F l
PERFORMANCE TEST ABSTRACT PTA-MA-182 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-182, Loss Of Turbine Bearing Oil Pressure 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (15) Turbine Trip.
2.O AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:182 3.2 MALFUNCTION SYMBOL.: MMS 023F 3.3 MALFUNCTION MENU...:MS 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady '
state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
3.2.1 Loss Of Turbine Bearing Oil Pressure..:G5A30G12 5.0 TEST DURATION 5.1 The recording device will be stopped af ter the effects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:5/22/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR 3 PLANNED, AND ASSOCIATED DATES. ;
NONE l
1 SSP !
PTAMA182 REV 0 l l
1 l
i i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING i JUSTIFICATION. ;
i NONE !
I 1
i i
h
'l i
t i
I I
I f
L i
5 h
r t
f SSP ;
PTAMA182 REV O I i
i i
3'; <d;
' Gdd !
! 41 !
vf/ -
l 1 PERFORMANCE TEST' ABSTRACT l PTA-MA-188 l 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE {
1.1 STP-MA-188, RWCU Break In HTX Room :
1.2 ANSI /ANS : .51985, Section 3.1.2 Plant Malfunctions, - (1). l Loss Of- Coolant (B) inside and outside Primary ;
containment l
2.O AVAILABLE OPTIONS '
i
?
2.1 Severity of 0 to 100% line break, located downstream of l the Regenerative Heat Exchanger. (100% line rupture = !
1.152 E' lbm/hr) l
! 2.2 Severity Rate of 0 to 60 minutes l El 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:188 {
3.2 MALFUNCTION SYMBOL.:MRWD12F t 3.3 MALFUNCTION MENU...:RW i 3.4 This Malfunction is tested with a severity of 100% and j a severity rate of 0 minutes.
4.0 INITIAL CONDITIONS' !
4.1 The simulator is operating at approximately 100% power.
The.RWCU System'is in service in accordance with OP-14. ,
4.2 A recording device is setup to record the following l test parameters simultaneously versus time-with a .;
resolution of 0.5 seconds or less-4.2.1 RWCU Pump Flow....................:RWF0200 l 4.2.2 RWCU Filter Demineralizer A Flow. . :RWF0501(1) ;
4.2.3 RWCU Filter Demineralizer .B Flow. . :RWF0501(2) '!
4.2.4 Non-Regen Htx Otlt/Filt Init Temp.:RWT0500 l 4.2.5 RWCU Htx Room Temperature.........:HVT3016E ;
QE '
RWCU Htx Room Temperature.........:HVT3016F i 4.2.6 South RHR Sump Level..............:WDLO800S :
4.2.7 South Core Spray Sump Level.......:WDL1000S I 5.0 TEST DURATION l The recording device will be stopped after 10 minutes has !
elapsed or the effects of the malfunction have stabilized.
SSP i PTAMA188 REV 0 l 1
I l
(
i
6.0 BASE LINE DATA I l
Malfunction Cause and Effect for Brunswick Unit 2 Power 6.1 Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:1/11/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
I NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE ;
1 i
l r
I 1
SSP !
PTAMA188 REV O l
, i -
'{
. PERFORMANCE TEST ABSTRACT +
PTA-MA-231 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE-1.1 STP-MA-231, RWCU Break In Triangle Room 77' ,
={
'1.2 ANSI /ANS. 3.5 1985, Section 3.1.2 Plant Malfunctions, !
(1) Loss Of Coolant -(b). inside and outside ' Primary i Containment :
I 2.0 AVAILABLE OPTIONS :
2.1 Severity of 0 to 100% line break, located downstream of-the G31-F004 valve.
2.2 Severity Rate of 0 to 60 minutes ,
3.0 TESTED OPTIONS i
3.1 MALFUNCTION NUMBER.:231 !
3.2 MALFUNCTION SYMBOL.:MRWO13F 3.3 MALFUNCTION MENU...:RW [
3.4 This Malfunction is tested with a severity of 100% and' l
a severity rate of 0 minutes.
4.0 -INITIAL CONDITIONS ,
i 4.1 The simulator is operating at approximately 100% steady. ,
state power. The RWCU System is in operation in !
accordance.with OP-14.
4.2 A recording device is. setup to record the following [
test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
i 4.2.1 RWCU Pump Flow..............:RWF0200 4.2.2 RWCU Filter Demin 2A Flow. . . :RWF0501(1) 4.2.3 RWCU Filter Demin 2B Flow. . . :RWF0501(2) -j 4.2.4 Reactor Bldg 50' Area Temp..:HVT25766 'j 4.2.5 South RHR Sump Level........:WDLO800S !
4.2.6 South Core Spray Sump Level.:WDL1000S i
.l ,
l 5.0 TEST DURATION 5 -.1 The recording device will be stopped after 10 minutes !
has elapsed or unit conditions have stabilized. l 1
I SSP PTAMA231 REV 0 l
i
- l 6.O BASE LINE DATA j 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power
- Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:3/4/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA231 REV 0 t
4 PERFORMANCE TEST ~ ABSTRACT PTA-MA-232 T
1.0 -PROCEDURE TITLE / ANSI.3.5 REFERENCE 1.1 STP-MA-232, RWCU Break In Return Line 20'-
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 . Plant Malfunctions, (1) Loss . Of Coolant (b) inside and outside Primary 5 Containment 2.0 AVAILABLE OPTIONS 2.1 Severity of 0 to 100% line break, located downstream of G31-FT-N041 and upstream of G31-F042 in the 20' floor area.
2.2 Severity Rate of 0 to 60 minutes 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:232 3.2 MALFUNCTION SYMBOL.:MRWO14F 3.3 MALFUNCTION MENU...:RW 3.4 This Malfunction is tested with a severity of 100% and a severity rate of 0 minutes.
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. The RWCU System is in operation in accordance with OP-14.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 RWCU Pump Flow..............:RWF0200 ,
4.2.2 RWCU Filter Demin 2A Flow. . . :RWF0501(1) 4.2.3 RWCU Filter Demin 2B Flow...:RWF0501(2) l 4.2.4 Non-Regen Htx Outlet Temp...:RWT0500 l Reactor Bldg 20' Area Temp..:HVT25765 l 4.2.5 4.2.6 South Core Spray Sump Level.:WDL1000S i 5.0 TEST DURATION 5.1 The recording device will be stopped after 10 minutes l has elapsed or unit conditions have stabilized.
l SSP PTAMA232 REV 0 1
im i
i 6.0 BASE LINE DATA i
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. .'
7.O DATE PERFORMED: 3 /4 /92 I
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ,
NONE l
t b
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE l
1 I
l i
l 1
SSP PTAMA232 REV O ,
i t
. . .. _ .. _. . -, - . _ _ _ . _ - . _ .m _ . _ _ _ _ _ . . .
I u !
, %c % ; -
i
4 J ;
? ,
'l PERFORMANCE TEST ABSTRACT. f PTA-MA-250 :t i
1.0 PROCEDURE TITLE /ANSIf3.5 REFERENCE ~ !
1.1 STP-MA-250,. RBCCW High Radiation 1.2 ANSI /ANS 3. 5 1985, Section 3.1.2 ~ Plant Malfunctions, (8)
Loss of component cooling system or cooling to individual j
. components.
2.O AVAILABLE OPTIONS i
.. p 2.1 Severity, of 0- to 100% RWCU Non-Regenerative Heat Exchanger tube leak which causes the RWCU water to flow t into the RBCCW System.
2.2 Severity Rate of 0 to 60 minutes 3.0 TESTED OPTIONS }
3.1 MALFUNCTION NUMBER.:250 1 3.2 MALFUNCTION SYMBOL.:MRWO11F 3.3 MALFUNCTION MENU...:RW I
3.4 This Malfunction is tested with a1 severity of 100% and -l a severity race of 0 minutes.
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady-state power. j 4.2 A recording device is setup to record the following l test parameters simultaneously versus time with a j recolution of 0.5 seconds or less: 4 3.2.1 RBCCW Surge Tank Level...........:RBLO100 ;
3.2.2 RWCU li Leak Flow.................:RWFLEAK l 3.2.3 RBCCW Liguid Process Rad Monitor.:RMPRMRBC j i
5.0 TEST DURATION 5.1 The recording device will be stopped after 10 minutes j has elapsed or unit conditions have stabilized. j 6.0 BASE LINE DATA l
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power !
Plant Training Simulator, latest Revision.
SSP PTAMA250 REV O I
l I
7.0 DATE PERFORMED: 3 /4 /92 ,
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE I
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING .
JUSTIFICATION. ;
NONE P
f i
i r
t i
I t
i t
i i
f J
l SSP >
I PTAMA250 REV 0 i
\
r
. PERFORMANCE TEST ABSTRACT PTA-MA-251 6 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-251, RBCCW Htx/ Service Water Tube Leak 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (8) ;
Loss of component cooling system or cooling to individual components. ,
i 2.0 AVAILABLE OPTIONS Severity of 0 to 100 gpm at rated A P due to RBCCW 2A
~
2.1 Heat Exchanger tube failure.
2.2 Severity Rate of 0 to 60 minutes 3.O TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:251 3.2 MALFUNCTION SYMBOL.:MCWOO4F 3.3 MALFUNCTION MENU...:CW 3.4 This Malfunction is tested with a severity of 100 gpm and a severity rate of 0 minutes.
4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. Malfunction 250 (RBBCW - High Rad) will be activated at 10% Severity to add radioactivity to RBCCW for this test.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution !
of 0.5 seconds or less:
4.2.1 RBCCW Surge Tank Level........:RBLO100 4.2.2 RBCCW Pressure Near HX. . . . . . . . :RBP0102 (2) 4.2.3 Service Water Pressure Near HX:SWP0100(7) 4.2.4 RBCCW Liquid Process Rad Mon..:RMPRMRBC 4.2.5 SW Liguid Process Rad Monitor.:RMRPMSWD 5.O TEST DURATION 5.1 The recording device will be stopped af ter l') minutes has elapsed or unit conditions have stabilired. j i
SSP '
PTAMA251 REV 1 i
i
{
i j
+ i
\
t 6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power
- Plant Training Simulator, latest Revision. l 7.0 DATE PERFORMED: 3 /4 /92 ,
8.0- DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ;
NONE h
t 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING ;
JUSTIFICATION. ,
NONE ;
W SSP ,
PTAMA251 REV 1
PERFORMANCE TEST ABSTRACT ,
PTA-MA-264 ;
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE .
1.1 STP-MA-264, HPCI Eyraulic System Failure !
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process Instrumentation, Alarms and Control System !
Falures (23) Passive malfunctions in systems such as engineered safety features, emergency feedwater systems.
.2.O AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS ;
3.1 MALFUNCTION NUMBER.:264 3.2 MALFUNCTION SYMBOL.:MES016F '
3.3 MALFUNCTION MENU...:ES 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power. Initiate an automatic start signal from low reactor water or high drywell pressure. :
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less: ,
4.2.1 HPCI Hydraulic System Pressure: TAP 7730 4.2.2 HPCI Turbine Speed. . . . . . . . . . . . : TMS6 6 6 0S (4 ) .
4.2.3 HPCI Pump Discharge Pressure..:HPP0003 t I
5.0 TEST DURATION 5.1 The recording device will be stopped after 10 minutes has elapsed or unit conditions have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP .
PTAMA264 REV O P
j
L-
~
t 7.0 DATE ' PERFORMED: 3 /4 /92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. t
- l NONE (
)
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE I
l f
i t
L i
5 h
r SSP )
TAMA2 64 REV O ;
l
9 PERFORMANCE TEST ABSTRACT PTA-MA-268 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE l I
1.1 STP-MA-268, RCIC Turbine Trip 1.2 ANSI /ANS 3.5- 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures. I 2.0 AVAILABLE OPTIONS NONE '
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:268 3.2 MALFUNCi!ON SYMBOL.:MES027F 3.3 MALFUNCTION MENU...:ES 4.0 INITIAL CONDITIONS 4.1 The simulator is operating with the RCIC System in !
service injecting full flow to the reactor vessel, in accordance with OP-16. ,
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 RCIC Pump Flow...............:RJWOOO2 4.2.2 RCIC Pump Discharge Pressure.:RJP0002 :
1 5.0 TEST DURATION 5.1 The recording device will be stopped after the effects of l the malfunction have stabilized.
l l
6.0 BASE LINE DATA j 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. j SSP PTAMA268 REV O I i
R 7.O DATE PERFORMED:1/11/94 1
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR l
. PLANNED, AND ASSOCIATED DATES. ;
NONE t
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING +
JUSTIFICATION.
NONE i i
i i
t
?
)
?
SSP .
PTAMA268 REV O !
i
L L
PERFORMANCE TEST ABSTRACT PTA-MA-271
+ 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-271, RCIC Inadvertent Start 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in automatic control system (s) that affect reactivity and core heat removal (22) Process instrumentation, alarms, and control system failures.
.2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:271 3.2 MALFUNCTION SYMBOL.:MES022F 3.3 MALFUNCTION MENU...:ES 4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Reactor Power (APRM)..............:NIJAPRM 4.2.2 Reactor Pressure (800 to 1100) . . . . :NBPITAPT(32) 4.2.3 Reactor Water Level (150 to 210") . :IARXLVL 4.2.4 RCIC Pump Discharge Pressure......:RJP0002 4.2.5 RCIC Pump Discharge Flow..........:RJWOOO2 4.2.6 RCIC Turbine Speed . . . . . . . . . . . . . . . : TMS6 6 6 0S (3 )
5.0 TEST DURATION 5.1 The recording device will be stopped af ter the effects of the malfunction have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:1/11/94 SSP PTAMA271 REV 0
h 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
'NONE l
P l
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE ,
t i
, SSP PTAMA271 REV 0 I
G'i '
{
}
' PERFORMANCE TEST ABSTRACT f PTA-MA-275 .)
l 5
< 1.0. PROCEDURE TITLE / ANSI 3.5 REFERENCE i
1.1 STP-MA-275, RCIC INJECTION VALVE OVERLOAD j 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, !
(17) Failure in automatic control system (s) that affect i reactivity and core heat removal.
2.0 AVAILABLE OPTIONS r i
NONE 3.0 TESTED OPTIONS {
3.1 MALFUNCTION NUMBER.:275 3.2 MALFUNCTION SYMBOL.:MES026F 3.3 MALFUNCTION MENU...:ES I
4.0 INITIAL CONDITIONS ,
4.1 The simulator is operating at approximately 100% steady i state reactor power. The malfunction is selected and set ;
active. Initiate a small line LOCA of sufficient severity-to cause reactor level to decrease and reactor pressure to remain relatively constant.
4.2 A recording device is setup to record the following test i parameters simultaneously versus time with a resolution i of-0.5 seconds or less: l 4.2.1 RCIC Pump Flow...............:RJW0002- f 4.2.2 RCIC Turbine Speed. . . . . . . . . . . :TMS6660S (3 ) !
4.2.3 Reactor Water Level..........:NBLEVELT(5) i 4.2.4 Reactor Pressure. . . . . . . . . . . . . :NBPITAPT (31) l 5.O TEST DURATION f 5.1 The recording device will be stopped af ter the effects of <
the malfunction have stabilized. i i
r 6.O BASE LINE DATA i
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training simulator, latest Revision.
I 7.0 DATE PERFORMED:1/11/94 t i
SSP PTAMA275 REV 1 i
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
+ NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA275 REV 1
p
, s.
PERFORMANCE TEST ABSTRACT PTA-MA-276 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-276, RHR INJECTION VALVE F015 STUCK CLOSED 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in automatic control system (s) that affect reactivity and core heat removal.
.2.0 AVAILABLE OPTIONS ,
2.1 Upon receipt of an automatic initiation signal the Ell-F015A (B) attempts to OPEN, mechanical binding causes the valve motor to thermal overload preventing valve movement. This malfunction is passive until a RHR System initiation signal is received.
2.2 This malfunction allows selection of E11-F015A (Loop I) or E11-F015B (Loop II) RHR Injection Valve.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:276 3.2 MALFUNCTION SYMBOL.:MRH001F 3.3 14ALFrJNCTION MENU. . . :RH 3.4 SELECTED RHR LOOP..: LOOP I 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power. The mrtlfunction is selected and. set active. A large line breeK LOCA is then activated.
5.O TEST DURATION 5.1 The test will be stopped after the affects, of the ;
malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest revision.
SSP PTAMA276 REV 0 l
7.0 DATE PERFORMED:6/13/93 ,
f 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR !
PLANNED, AND ASSOCIATED DATES.
- w NONE ,
t
+
?
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING j JUSTIFICATION.
NONE i
t I
i I
i l
f f
I
(
SSP PTAMA276 REV 0 1
l 1
l
'I-7
- i PERFORMANCE TEST ABSTRACT i
PTA-MA-276 l
1.0 PROCEDURE TITLE / ANSI 3'.5 REFERENCE l
-1.1- STP-MA-276,.RHR INJECTION VALVE F015 STUCK' CLOSED. f l
ANSI /ANS 3.5 1985, Section . 3.1.2 Plant Malfunctions, '
1.2 (17) Failure in automatic control; system (s) that affect l reactivity and core heat removal. ,
i 2.0 AVAILABLE OPTIONS t
2.1 Upon receipt of an automatic initiation signal the Ell- !
F015A (B) attempts to OPEN, mechanical binding causes the !
valve motor to thermal overload preventing valve movement. This malfunction is passive until a RHR System initiation signal is received.
2.2 This malfunction allows selection of E11-F015A (Loop I) ,
or E11-F015B . (Loop II) RHR Injection Valve. [
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:276 3.2 MALFUNCTION SYMBOL.:MRH001F
r 4.1 The simulator is operating at approximately 100% steady j state reactor power. The malfunction is selected and set !
active. A large line break LOCA is then activated. ;
5.0 TEST DURATION 5.1 The test will be stopped after the affects of the .i malfunction have stabilized.
I 6.O BASE LINE DATA !
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power i Plant Training Simulator, latest revision. !
SSP PTAMA276 REV O )
4 7.0 DATE PERFORMED:6/13/93 1 I
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR !
PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE B
e P
h V
SSP PTAMA276 REV 0
t PERFORMANCE TEST ABSTRACT PTA-MA-292 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-292, RHR HEAT EXCHANGER BYPASS VALVE TRIP 1.2 ANSI /ANS 3.5 1985, Sectic 3.1.2 Plant Malfunctions, (17) Failure in automatic control system (s) that affect '
reactivity and core heat removal.
2.0 AVAILABLE OPTIONS i 2.1 As the operator attempts to CLOSE the RHR Heat Exchanger '
Bypass Valve, E11-F048A(B) , mechanical binding causes the valve motor to thermal overload preventing valve ;
movement. ,
2.2 This malfunction allows selection of E11-F048A (Loop I) or E11-F048B (Loop II) RHR Heat Exchanger Bypass valve.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:292 ,
3.2 MALFUNCTION SYMBOL.:MRH011F 3.3 MALFUNCTION MENU...:RH 3.4 SELECTED RHR VALVE.:I&II 4.O INITIAL CONDITIONS 4.1 Any plant condition requiring the operator to CLOSE the l RHR Heat Exchanger Bypass Valve, E11-F048A(B).
i 5.O TEST DURATION 5.1 The test will be stopped after the affects of the malfunction have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest revision.
SSP PTAMA292 REV 0 l
l
7.O DATE PERFORMED:6/13/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PIANNED, AND ASSOCIATED DATES.
NONE -
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE h
SSP ,
PTAMA292 REV 0
PERFORMANCE TEST ABSTRACT ;
PTA-MA-298 9 7 1.0- PROCEDURE TITLE / ANSI 3.5 REFERENCE
.. i 1.1 ETP-MA-298, AUTO VOLTAGE REGULATOR FAILURE l 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3) Loss or Degraded Electrical Power to the Station and (22) Process instrumentation, alarms, and control system :
failures.
2.0 AVAILABLE OPTIONS 2.1 NONE. An electrical Fault in the Voltage Regulator results in a trip to Manual voltage regulation.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:298 '
3.2 MALFUNCTION SYMBOL.:MEE002F 3.3 MALFUNCTION MENU...:EE 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% Steady State power. ,
5.0 TEST DURATION 7.4 The test will be stopped after the affects of the malfunction have stabilized.
6.O BASE LINE DATA >
6.3 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:6/13/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ;
NONE SSP PTAMA298 REV 0
4 l
i 9.0 EXCEPTIONS TAKEN AS A RESULT OF. TEST PERFORMANCE, INCLUDING JUSTIFICATION. 3 NONE l I
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PTAMA298 REV O !
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l
r PERFORMANCE TEST ABSTRACT PTA-MA-304 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE j 1.1 STP-MA-304, GRID LOAD INCREASE ,
1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3) Loss or Degraded Electrical Power to the Station ,
- a. loss of off-site power 2.0 AVAILABLE OPTIONS 2.1 NONE. The load increase is due to the partial collapse of the grid resulting from high usage and loss of a major generating station.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:304 3.2 MALFUNCTION SYMBOL.:MEE008F 3.3 MALFUNCTION MENU...:EE 4.0 INITIAL CONDITIONS
- 4.1 The simulator is operating at approximately 100% steady state power. >
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 System Frequency...........:EETEST03 4.2.2 System Voltage.............:G7102G18 [
4.2.3 Generator MVARs............:EGJ1201G -
5.O TEST DURATION 5.1 The recording device will be stopped after unit [
conditions have stabilized. ,
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA304 REV O
7.0 DATE PERFORMED:6/13/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ,
NONE i e
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE i
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5 i
SSP PTAMA304 REV O I
1
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-PERFORMANCE TEST ABSTRACT PTA-MA-306 l i
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE
'{ '
1.1 STP-MA-306, 230KV TRANSMISSION LINE TRIP i
1.2' ANSI /ANS 3.5 1985, Section 3.1.2,. Plant Malfunctions, l (3) Loss or Degraded Electrical Power.to.the Station l
2.0 AVAILABLE OPTIONS j 2.1 NONE. A Zone 1 fault is detected on the 230 KV Whiteville .
line resulting in PCB 31A and B' trips. .;
3.0 TESTED OPTIONS :
i 3.1 MALFUNCTION NUMBER.:306 l 3.2 MALFUNCTION SYMBOL.:MEE010F 3.3 MALFUNCTION MENU...:EE 4.0 INITIAL CONDITIONS !
i 4.1 The simulator is operating at approximately 100% steady i state power.
4.2 A recording device.is setup to record the following test parameters simultaneously versus time with a :
resolution of 0.5 seconds or less: ,
4.2.1 Status of PCB 31A. . . . . . . . . . :ELZ1703G (1) i 4.2.2 Status of PCB 31B. . . . . . . . . . :ELZ1703G (2) !
5.0 TEST DURATION {
5.1 The recording device will be stopped after unit ,
conditions have stabilized.
i 6.0 BASE LINE DATA !
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. ;
i 7.0 DATE PERFORMED:1/10/93 ,
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR .
PLANNED, AND ASSOCIATED DATES. ;
NONE ;
SSP PTAMA306 REV O i
l i
I
- \
I I
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING ,
JUSTIFICATION. .
NONE I e
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SSP -
PTAMA306 REV 0 !
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PERFORMANCE TEST ABSTRACT '
PTA-MA-309 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-309, MAIN TRANSFORMER COOLING SYSTEM FAILURE l Plant Malfunctions, !
1.2 ANSI /ANS 3.5 1985, Section 3.1.2, (3) Loss or Degraded Electrical Power to the Station and ,
(8) Loss of Component Cooling System or ' cooling to ,
individual components i
.2.O AVAILABLE OPTIONS ,
2.1 NONE. A phase to phase short on Main Transformer Fan Bank No. 1 results in a loss of the running coolers. The Main r transformer motor coolers normal power supply is fron MCC l 2TC through HB3 circuits 8, 10 and 14.
f 3.0 TESTED OPTIONS t
3.1 MALFUNCTION NUMBER.:309 [
3.2 MALFUNCTION SYMBOL.:MEE012F :
3.3 MALFUNCTION MENU...:EE :)
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100%_ steady state power.
4.2 A recording device is setup to record the following :
test parameters simultaneously versus time with a j resolution of 0.5 seconds or less:
I 4.2.1 Main xformer Cooling Sys Fan Bank 1..:EGZO204G 5.0 TEST DURATION 'l 5.1 The recording device will be stopped after unit conditions have stabilized.
l 6.0 BASE LINE DATA ,
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. f f
i SSP PTAMA309 REV 0 l i
6
J
'7.0 DATE PERFORMED:6/13/93 :
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR-PLANNED, AND ASSOCIATED DATES.
NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE t
SSP PTAMA309 REV 0 1
m g m - x w Maa A n, m b+a14 is 4g A c .
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PERFORMANCE TEST ABSTRACT !
PTA-MA-328 l
-1.0 PROCEDURE TITLE / ANSI'3.5 REFERENCE
'1.1 STP-MA-328, Small Recirculation Pump : A Suction Line >
Rupture i 1.2 ANSI /ANS 3.5-1985, Section 3.1.2 Plant' Malfunctions, i (1) Loss Of Coolant (b) inside and outside Primary- l Containment (c)large and small reactor coolant breaks- ,
2.0' AVAILABLE OPTIONS I i
2.1 Severity of 0 to 100% line~ break, located.between the Recirc Suction Valve (B21-F023A) and the Reactor Vessel. ,
(100% line breakL= .429 ft 8) I i
2.2 Severity Rate of 0 to 60 minutes 3.0 TESTED OPTIONS !
3.1 MALFUNCTION NUMBER.:328 l 3.2 MALFUNCTION SYMBOL.:MNB009F I 3.3 MALFUNCTION MENU...:NB j 3.4 This Malfunction is tested with a severity of 100% and 1
a severity rate of 0 minutes.
4.0 ' INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady ,
state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with'a resolution ;
of 0.5 seconds or less:
NOTE: Reactor Water Levels, NBLEVEL (5) and (7) , are displayed in feet.
3.2.1 2A Recirculation Pump Flow. . . . . . . . :NBWFLOW (10) _
3.2.2 2B Recirculation Pump Flow. . . . . . . . :NBWFLOW (11) '!
3.2.3 Drywell Pressure..................: CAP 0010 l 3.2.4 Reactor Water Level (0 to 210") . . . :NBLEVELT(5) ;
3.2.5 Reactor Water Level (-150 to 150") :NBLEVELT(7) :
3.2.6 Reactor Pressure (0 to 1500) . . . . . . :NBPITAPT (31) !
3.2.7 Total' Core Flow...................:NBWFLOW(7). ;
3.2.8 Suppression Pool Temperature......: CAT 2120 !
3.2.9 Suppression Chamber Pressure......: CAP 0020 _j 1
SSP j PTAMA328 REV O !
5.0 TEST DURATION The recording device will be stopped after the low pressure ECCS has initiated and the core has been
- effectively flooded.
6.0 BASE LINE DATA Malfunction Cause and Effect for Brunswick Unit 2 Power Plant !
Training Simulator, latest Revision.
7.O DATE PERFORMED:12/4 /92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING :
JUSTIFICATION.
NONE f
t L
k 1
SSP PTAMA32B REV 0
P_ERFORMANCE TEST ABSTRACT t PTA-MA-354 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE I 1.1 STP-MA-354, 2D AIR COMPRESSOR FAILS TO LOAD 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (2) Loss of Instrument Air to the extent that the whole system or individual headers can lose pressure and affect l the plant's static or dynamic performance.
2.O AVAILABLE OPTIONS 2.1 NONE. Mechanical failure of the 2D Air Compressor unloadia.y solenoid valve circuit.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:354 3.2 MALFUNCTION SYMBOL.:MAIOOSF 3.3 MALFUNCTION MENU...:AI 4.O INITIAL CONDITIONS 4.1 The simulator is operating at approicimately 100% steady ;
state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a i resolution of 0.5 seconds or less:
i 3.2.1 Instrument Air Receiver Pressure....:AIP0600T ,
5.O TEST DURATION t 5.1 The recording device will be stopped after unit conditions have stabilized. !
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power l Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:6/13/93 :
SSP PTAMA354 REV 0 -
l l
. l 8.0 DEFICIENCIES FOUND DURING TESTING,. CORRECTIVE ACTION TAKEN OR !
PLANNED, AND ASSOCIATED DATES.
NONE i
EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING !
9.0 JUSTIFICATION. 7 NONE i
i i
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i SSP r
! PTAMA354 REV O ,
I i
PERFORMANCE TEST ABSTRACT PTA-MA-361 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE ,
1.1 STP-MA-361, Rx Bldg Vent Mon Fails Downscale -
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures.
L 2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of either A and/or B Reactor Building Ventilation Monitor. ,
3.O TESTED OPTIONS ,
3.1 MALFUNCTION NUMBER.:361 3.2 MALFUNCTION SYMBOL.:MRM003F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...: A i
4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 10GP: 9teady ;
state reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Rx Bldg Vent Recorder Channel A.....:G5B25G1G 4.2.2 Rx Bldg Vent Recorder Channel B.....:G5B25G2G 4.2.3 Rx Bldg Vent Indicator A (P606).....:G9602G1G ,
4.2.4 Rx Bldg Vent Indicator B (P606).....:G9N02G1G i 4.2.5 Rx Bldg Vent Detector Activity A....:RMPRMBVA 4.2.6 Rx Bldg Vent Detector Activity B....:RMPRMBVB 5.O TEST DURATION ,
5.1 The recording device will be stopped after the ef fects of the malfunction have stabilized.
6.O BASE LINE DATA :
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power '
Plant Training Simulator, latest Revision.
i SSP PTAMA361 REV 0 '
l 1
4 7.0 DATE PERFORMED:12/4 /92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR
- PLANNED, AND ASSOCIATED DATES.
NONE
?
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE I
t 6
5 t
t SSP PTAMA361 REV 0
9 PERFORMANCE TEST ABSTRACI PTA-MA-362 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-362, Rx Bldg Vent Mon Fails Upscale 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures.
I 2.0 AVAILABLE OPTIONS
}
l 2.1 This malfunction allows selection of either A and/or B f Reactor Building Ventilation Monitor.
I 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:362 3.2 MALFUNCTION SYMBOL.:MRM004F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...: A 4.O INITIAL CONDITIONS 4.1 The simulator is operating at 100% reactor power.
4.2 CAC-AT-4409 & 4410 are in service monitoring DW H2/02 concentration (the system power switches are in " STANDBY"
& "ON").
4.3 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.3.1 Rx Bldg Vent Recorder Channel A.....:G5B25G1G 4.3.2 Rx Bldg Vent Recorder Channel B.....:G5B25G2G 4.3.3 Rx Bldg Vent Indicator A (P606) . . . . . :G9602G1G 4.3.4 Rx Bldg Vent Indicator B (P606).....:G9N02G1G 4.3.5 Rx Bldg Vent Detector Activity A....:RMPRMBVA 4.3.6 Rx Bldg Vent Detector Activity B....:RMPRMBVB 5.O TEST DURATION 5.1 The recording device will be stopped af ter the ef fects of i the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA362 REV 1 1
t Plant Training Simulator, latest Revision. ,
7.0 DATE PERFORMED:12/4/92 i 8.0 DET1.:IENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR l PLANNED, AND ASSOCIATED DATES.
NONE i
t 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING i JUSTIFICATION.
NONE t
1 P
SSP PTAMA362 REV 1 l
i i
_________________________________________.____f
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PERFORMANCE TEST ABSTRACT PTA-MA-362 1
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE ,
1.1 STP-MA-362, Rx Bldg Vent Mon Fails Upscale 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, n.d control system failures.
2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of either A and/or B i Reactor Building Ventilation Monitor.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:362 3.2 MALFUNCTION SYMBOL.:MRM004F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...: B 4.O INITIAL CONDITIONS 4.1 The simulator is operating at 100% reactor power.
4.2 CAC-AT-4409 & 4410 are in service monitoring DW H2/02 concentration (the systen power switches are in " STANDBY"
& "ON"). ;
4.3 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less: ,
4.3.1 Rx Bldg Vent Recorder Channel A.....:G5B25G1G 4.3.2 Rx Bldg Vent Recorder Channel B.....:G5B25G2G 4.3.3 Rx Bldg Vent Indicator A (P606).....:G9602G1G 4.3.4 Rx Bldg Vent Indicator B (P606).....:G9N02G1G 4.3.5 Rx Bldg Vent Detector Activity A....:RMPRMBVA 4.3.6 Rx Bldg Vent Detector Activity B....:RMPRMBVB 5.0 TEST DURATION ,
5.1 The recording device will be stopped af ter .the ef fects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA362 REV 1 t
- i
)
Plant Training Simulator, latest Revision. !
7.0 DATE PERFORMED:5/13/93 i
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. 1 NONE i
i l
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING -
JUSTIFICATION.
NONE l i
1 i
c i
I I
SSP PTAMA362 REV 1 l
1
s; I PERFORMANCE TEST ABSTRACT PTA-MA-369 g i
P 1.0 PROCEDURE. TITLE / ANSI 3.5 REFERENCE [
1.1 STP-MA-369,'SBGT INADVERTENT' START. l.
1.2 : ANSI /ANS 3.5 1985, Section 3.1.2 . Plant Malfunctions, :!
(22) Process instrumentation, - alarms, and control system i failures. i
.2.O AVAILABLE' OPTIONS i 2.1 This n alfunction allows selection of either 2A and/or ~ 2B SBGT Train.
l 3.0 TESTED OPTIONS j I
3.1 MALFUNCTION NUMBER.:369 !
3.2 MALFUNCTION SYMBOL.:MCA011F l 3.3 MALFUNCTION MENU...:CA' !
3.4 SELECTED SBGT-Train: A j ;
4.0 INITIAL CONDITIONS q l
4.1 The simulator is operating at approximately 100% steady i state reactor power. .;
4.2 A recording' device is setup to record the following j test parameters simultaneously versus' time with a !
resolution of 0.5 seconds or less: j 4.2.1 2A SBGT Train Flow...:CAWSBGTA. !
' 4.2.2 2B SBGT Train Flow...:CAWSBGTB I
5.0 TEST DURATION i 4
5.1 The recording device will be stopped af ter the effects of i the malfunction have stabilized. ]
i 6.O BASE LINE DATA f
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. i t
, SSP !
PTAMA369 REV 0 l i
i s ex., . , , -e - .. - , . . , , - . . - - - -
-7.O DATE PERFORMED:6/13/93 ,
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE t
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING l JUSTIFICATION.
NONE i
i r
v 5
i I
i i
f I
i SSP i PTAMA369 REV 0 l
i
^
PERFORMANCE TEST ABSTRACT PTA-MA-369 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE j 1.1 STP-MA-369, SBGT INADVERTENT START !
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system i failures. j 2.0 AVAILABLE OPTIONS ,
2.1 This malfunction allows selection of either 2A and/or 2B SBGT Train 4
3.0 TESTED OPTIONS !
3.1 MALFUNCTION NUMBER.:369 3.2 MALFUNCTION SYMBOL.:MCA011F 3.3 MALFUNCTION MENU...:CA 3.4 SELECTED SBGT Train: B ;
i 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
4.2 A recording device is setup to record the following ,
test parameters simultaneously versus time with a ,
resolution of 0.5 seconds or less:
4.2.1 2A SBGT Train Flow...:CAWSBGTA 4.2.2 2B SBGT Train Flow...:CAWSBGTB ,
5.O TEST DURATION 5.1 The recording device will be stopped af ter the effects of the malfunction have stabilized.
6.O BASE LINE DATA i
i 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. ;
SSP ,
PTAMh369 REV O
r- 7 i
l i
7.O DATE PERFORMED:6/13/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED,.AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TECT PERFORMANCE, INCLUDING JUSTIFICATION.
NONE 9
SSP PTAMA369 REV O ,
f
}
e PERFORMANCE TEST ABSTRACT PTA-MA-399 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-399, MSL Rad Monitor Fails Upscale 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures.
2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of A, B, C or D Main Steam Line NUMAC Radiation Monitor (s).
3.0 TESTED OPTIONS .
3.1 MALFUNCTION NUMBER.:399 3.2 MALFUNCTION SYMBOL.:MRM010F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...: A 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 MSL Rad Mon Recdr Channel A/C.:G5B01G2G 4.2.2 MSL Rad Mon Recdr Channel B/D.:G5B01G1G 4.2.3 MSL NUMAC Rad Mon A...........:G9501G1G 4.2.4 MSL NUMAC Rad Mon B...........:G9D01G1G N-1 4.2.5 MSL NUMAC Rad Mon C...........:G9M01G1G N-1 4.2.6 MSL NUMAC Rad Mon D...........:G9V01G1G 4.2.7 MSL Rad Det Activity A........:RMPRMMSL(1) 4.2.8 MSL Rad Det Activity B........:RMPRMMSL(2) 4.2.9 MSL Rad Det Activity C. . . . . . . . : RMPRMMSL (3)
- 4. 2.10 MSL Rad Det Activity D. . . . . . . . :RMPRMMSL (4 )
i 5.O TEST DURATION 5.1 The recording device will be stopped af ter the effects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA399 REV O
O Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:12/5/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE l
9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE l
I t
l r
SSP PTAMA399 REV 0 .
-(
PERFORMANCE TEST ABSTRACT PTA-MA-399 i
. 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE ,
1.1 STP-MA-399, MSL Rad Monitor Fails Upscale 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system failures.
2.0 AVAILABLE OPTIONS .
2.1 This malfunction allows selection of A, B, C or D Main Steam Line NUMAC Radiation Monitor (s).
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:399 3.2 MALFUNCTION SYMBOL.:MRM010F 3.3 MALFUNCTION MENU...:RM 3.4 SELECTED MONITOR...:C 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state reactor power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 MSL Rad Mon Recdr Channel A/C.:G5B01G2G 4.2.2 MSL Rad Mon Recdr Channel B/D.:G5B01G1G 4.2.3 MSL NUMAC Rad Mon A...........:G9501G1G 4.2.4 MSL NUMAC Rad Mon B...........:G9D01G1G N-1 4.2.5 MSL NUMAC Rad Mon C...........:G9M01G1G N-1 4.2.6 MSL NUMAC Rad Mon D...........:G9V01G1G 4.2.7 MSL Rad Det Activity A........:RMPRMMSL(1) 4.2.8 MSL Rad Det Activity B........:RMPRMMSL(2) 4.2.9 MSL Rad Det Activity C........:RMPRMMSL(3)
- 4. 2.10 MSL Rad Det Activity D. . . . . . . . :RMPRMMSL (4 )
5.0 TEST DURATION 5.1 The recording device will be stopped af ter the effects of the malfunction have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA399 REV O
. i l
l Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:1/10/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE i
t t
L SSP PTAMA399 REV 0 ,
t
PERFORMANCE TEST ABSTRACT PTA-MA-403 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-403, C32-FT-N002 (FEED FLOW) FAILURE 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control system ,
failures.
2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of either C32-FT-N002A and/or N002B with a Severity of 0 to 100% and Severity Rate of 0 to 60 minutes.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:403 3.2 MALFUNCTION SYMBOL...:MCF043F 3.3 MALFUNCTION MENU.....:CF 3.4 SELECTED TRANSMITTER.: A 3.5 This malfunction was tested with a Severity of 0% and 100%.
4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady ;
state reactor power.
l 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Indicated Total Feedwater Flow...:XFD0103G 4.2.2 Feedwater Flow Line A............:CFW1REAT 4.2.3 Feedwater Flow Line B............:CFW1REBT 4.2.4 Reactor Water Level..............:IARXLVL i
5.O TEST DURATION 5.1 The recording device will be stopped af ter the ef fects of the malfunction have stabilized. l 6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA403 REV 0 r
i
- l 7.0 DATE PERFORMED:6/15/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OF
- PLANNED, AND ASSOCIATED DATES.
NONE 4
t 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA403 REV O
if !
~ v i
PERFORMANCE TEST ABSTRACT l PTA-MA-403 ,
j l
1.0 PROCEDURE. TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-403, C32-FT-N002 (FEED FLOW) FAILURE 1.2 ANSI /ANS 3.5'1985, Section ' 3.1.2 Plant Malfunctions,-
.(22) Process instrumentation, alarms, and control system .
failures.
2.0 AVAILABLE OPTIONS s
2.1 This malfunction allows selection of either C32-FT-N002A' and/or N002L with a Severity of 0 to 100% and Severity-Rate of 0 to 60 minutes.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:403 ;
3.2 MALFUNCTION SYMBOL...:MCF043F 3.3 MALFUNCTION MENU.....:CF :
3.4 SELECTED TRANSMITTER.: B
{
3.5 This malfunction was tested with a Severity of 0% and 100%. .;
L 4.0 INITIAL CONDITIONS !
f 4.1 The simulator is operating at approximately 100% steady state reactor power. i 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a i resolution of 0.5 seconds or less: i 4.2.1 Indicated Total Feedwater Flow...:XFD0103G -!'
4.2.2 Feedwater Flow Line A............:CFW1REAT 4.2.3 Feedwater Flow Line B............:CFW1REBT !
4.2.4 Reactor Water Level..............:IARXLVL 5.0 TEST DURATION _
i 5.1 The recording device will be stopped after the effects of
.the malfunction have stabilized. !
6.0 BASE LINE DATA I i
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power l Plant Training Simulator, latest Revision. l I
SSP 1 PTAMA403 REV O 1
1
_______________J
4 7.0 DATE PERFORMED:6/15/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE L
l 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING .
JUSTIFICATION.
NONE t
f SSP PTAMA403 REV O I
1
..s j i
~
i PERFORMANCE TEST ABSTRACT {
PTA-MA-405 j 1.0 . PROCEDURE TITLE / ANSI 3.5 REFERENCE ~ i
.l 1.1 STP-MA-405,. BROKEN DOWNCOMER QUADRANT ONE l i
1.2 ~ ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, ,
(23). Passive malfunction in systems, such as engineered l safetyLfeatures, emergency feedwater systems.
2.0. AVAILABLE OPTIONS .,
?
2.1 Chugging causes severe stress at the junc_ tion of the l downcomer and the vent header which results in a :
downcomer header rupture. This malfunction is passive :
until a RHR System initiation signal is received.
i 2.2 This malfunction is tested with a Severity of 100% and a Severity Rate of 0 minutes. ;j 3.0 TESTED OPTIONS j 3.1 MALFUNCTION NUMBER.:405 .f 3.2 MALFUNCTION SYMBOL.:MCA017F !
3.3 MALFUNCTION MENU...:CA 4.O INITIAL CONDITIONS .
4.1 The simulator is operating at approximately 100% steady I I
state reactor power. Select this malfunction, set active and then initiate a large line break LOCA. ;
)
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less: -l 4.2.1 Drywell Pressure..........: CAP 0010 l 4.2.2 Suppression Pool Pressure.: CAP 0020 !
4.2.3 Suppression Pool Level....:CALO12F l 5.0 TEST DURATION .
5.1 The recording device will be stopped af ter 10 minutes has i elapsed or unit conditions have stabilized.
6.O BASE LINE DATA !
i 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power l Plant Training Simulator, latect Revision. j I
SSP +
PTAMA405 REV O !
b l
i
, ., - - , , ,, . , , . . . . , , , , , - , , . ,, , c - , - - - ,
A 1
7.O DATE PERFORMED:6/15/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR
- PLANNED, AND ASSOCIATED DATES.
NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. ,
NONE l
L SSP i PTAMA405 REV 0 -
l l
~
.- l
.i PERFORMANCE TEST ABSTRACT >
PTA-MA-406 j
- 1. 0. PROCEDURE TITLE / ANSI-3.5 REFERENCE l l'.1 STP-MA-406, SRV-Tailpipe Rupture l
\
1.2 ANSI /ANS 3.5 1985,_Section 3.1.2, Plant Malfunctions,. !
(23) Passive malfunction in systems, such as engineered !
safety features, emergency feedwater systems.
2 .' O AVAILABLE-OPTIONS !
2.1 The SRV vacuum breaker failed closed during the last operation resulting in water being drawnL up into the tail i pipe. When the SRV is opened, a water hammer occurs !
which results in a tail pipe . rupture above' the !
Suppression Pool water level. j 2.2 This malfunction allows selection of either SRV B,E, or F.
NOTE: This malfunction is passive until the selected SRV is opened.
l 3.0 TESTED OPTIONS i i
3.1 MALFUNCTION NUMBER.:406 i 3.2 MALFUNCTION SYMBOL.:MCA018F f 3.3 MALFUNCTION MENU...:CA :
3.4 Selected SRV....B.E.F ;
4.0 INITIAL CONDITIONS I i
4.1 The simulator is operating at approximately 100% steady i state reactor power. Select this malfunction, set active !
and then open the selected SRV. l 4.2 A recording device is setup to record the following l test parameters simultaneously versus time with a resolution of 0.5 seconds or less-
{
4.2.1 Total Steam Flow...............:MSW4111: '!
4.2.2 Suppression Pool Temperature...: CAT 2120 l 4.2.3 Suppression Chamber Pressure...: CAP 0020 l 4.2.4 Drywell Pressure...............: CAP 0010 ~l 5.0 TEST DURATION fi 5.1 The recording device will be stopped after 10 minutes has j elapsed or unit conditions have stabilized. t i
-SSP !
PTAMA406 REV 1 I l
i i
4 6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power.
Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:9/23/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA406 REV 1
r-L PERFORMANCE TEST ABSTRACT PTA-MA-409 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-409, STATION BLACKOUT 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, <
(3) Loss or Degraded Electrical Power to the Station !
- a. loss of off-site power !
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:409 3.2 MALFUNCTION SYMBOL.:MEE031F 3.3 MALFUNCTION MENU...:EE 4.0 INITIAL CONDITIONS :
4.1 The simulator is operating at approximately 100% steady ,
state power.
4.2 A recording device is setup to record the following ,
test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 Unit 1 AC Power...............:U1ACPWR 4.2.2 230 KV Bus 2A Voltage.........:EDV0403G 4.2.3 230 KV Bus 2B Voltage.........:EDV0610G 4.2.4 Main Generator Output Voltage.:EGVGVKV 4.2.5 4 KV Bus 2B Voltage...........:EDV0104G 4.2.6 4 KV Bus 2C Voltage ..........:EDV0203G ,
4.2.7 4 KV Bus 2D Voltage...........:EDV0204G ;
4.2.8 4 KV Bus El Voltage...........:EDV0304G 4.2.9 4 KV Bus E2 Voltage...........:EDV0306G 4.2.10 4 KV Bus E3 Voltage...........:EDV0301G 4.2.11 4 KV Bus E4 Voltage...........:EDV0208G 5.O TEST DURATION 5.1 The recording device will be stopped after the Diesel Generators are connected to the Emergency Buses and the reactor is in a safe condition.
6.0 BASE LINE DATA i 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA409 REV 0 l
1
Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:12/5/92
- 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. ,
NONE l
i SSP PTAMA409 REV 0 l
r a
o PERFORMANCE TEST ABSTRACT-PTA-MA-410 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-410, HPCI. Failure-To Auto Start.
1.2 ANSI /ANS 3.5 1985, Section 3.1.2.- Plant Malfunctions, (17) Failure in automatic control system (s) that-affect reactivity 'and core heat removal (22) Process instrumentation, alarms, and control system failures.
'2.0 AVAILABLE OPTIONS NONE 3.O TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:410 3.2 MALFUNCTION SYMBOL.: MESO 40F 3.3 MALFUNCTION MENU...:ES 4.O INITIAL CONDITIONS 4.1 The simulator.is operating at approximately.100% steady state power. RCIC System is INOP. Set malfunction #410!
active. Initiate a small break LOCA of sufficient severity to cause reactor level to decrease, Drywell pressure to increase and reactor pressure to remain relatively constant.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
NOTE: Reactor Water Levels, NBLEVEL (5) is displayed in feet.
4 2.1 Rx Water Level (0 to 210") . . . :NBLEVELT (5) 4.2.2 Drywell Pressure.............: CAP 0010 4.2.3 HPCI Turbine Speed. . . . . . . . . . . :TMS6660S (4) 4.2.4 HPCI Pump Discharge Pressure.:HPP0003 5.0 TEST DURATION The recording device will be stopped af ter water level and D/W pressure have exceeded the auto start set points and HPCI did not initiate.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power SSP PTAMA410 REV O
Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:12/5/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR '
PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORM 7.NCE, INCLUDING JUSTIFICATION.
NONE f
l i
l I
k i
r f
I SSP PTAMA410 REV O i
l i
PERFORMANCE TEST ABSTRACT PTA-MA-411 j 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE l
- I 1.1 STP-MA-411, RCIC Failure To Auto Start l t
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in automatic control system (s) that affect reactivity and core heat removal (22) Process !
instrumentation, alarms, and control system failures. !
2.0 AVAILABLE OPTIONS i l
NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:411 3.2 MALFUNCTION SYMBOL.: MESO 41F 3.3 MALFUNCTION MENU...:ES l 4.0 INITIAL CONDITIONS j
?
4.1 The simulator is operating at approximately 100% steady 1 state power. HPCI System is INOP. Set malfunction #411 I active. Initiate a small break LOCA of sufficient ,
severity to cause reactor level to decrease and reactor pressure to remain relatively constant.
- 4.2 A recording device is setup to record the following test !
parameters simultaneously versus time with a resolution of 0.5 seconds or less:
NOTE: Reactor Water Levels, NBLEVEL (5) is displayed in feet. [
4.2.1 Rx Water Level (0 to 210 ") . . . :NBLEVELT ( 5) !
4.2.2 RCIC Turbine Speed. . . . . . . . . . . :TMS666 0S (3 ) [
4.2.3 RCIC Pump Discharge Pressure.:RJP0002 I 5.0 TEST DURATION The recording device will be stopped af ter water level has exceeded the auto start set point and RCIC did not initiate. !
6.0 BASE LINE DATA j 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. !
l 7.0 DATE PERFORMED:1/10/94 SSP !
PTAMA411 REV O l
I 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE i
i 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. j NONE !
t I
i i
l SSP .
PTAMA411 REV 0 :,
. ..~ - . . - .- .- . .. ~- . . .-
2 l 1 , .
., .i l
PERFORMANCE TEST ABSTRACT t
'PTA-MA-412 !
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE l
-1.1' STP-MA-412, Core Spray Failure To Auto Start j i
'1.2 ANSI /ANS 3.5 1985, Section 3.1.2. Plant Malfunctions, !
(17) Failure in automatic control system (s) that affect i reactivity and core heat removal (22) Process l instrumentation, alarms, and control system failures. ;
2.0 AVAILABLE OPTIONS. ,
This malfunction allows selection of either 2A and/or 2B Core Spray Pump.
3.0 TESTED OPTIONS l f
3.1 MALFUNCTION NUMBER.:412 ;
3.2 MALFUNCTION SYMBOL.: MESO 43F i 3.3 MALFUNCTION MENU...:ES 3.4 SELECTED LOOP......: A 4.0 INITIAL CONDITIONS l 4.1 The simulator is operating at approximately 100% steady )
state power. Set. malfunction #412 active. Initiate a 'l LOCA of sufficient severity to caus'e reactor level'and l pressure to decrease.- l 4.2 A recording device is setup to record the following test :
parameters simultaneously versus time with a resolution l of 0.5 seconds or less.
i NOTE: Reactor Water Levels, NBLEVEL (5) is displayed in feet. {
i 4.2.1 . Reactor Water Level ( 0 to 210 " ) . . . . : NBLEVELT ( 5 ) }
4.2.2 Drywell Pressure...................: CAP 0010 !
I 4.2.3 Reactor Pressure...................:NBPREGI 4.2.4 2A Core Spray Injection Flow.......:CSW0002 f 4.2.5 2B Core Spray Injection Flow.......:CSWOO22 l f
5.O TEST DURATION i
The recording device will be stopped after water level and/or i' D/W pressure and reactor pressure has exceeded the auto start set point and Core Spray did not initiate.
4 6.O BASE LINE DATA i
.l SSP l PTAMA412 REV O ;
l l
l I
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision. l 7.0 DATE PERFORMED:12/5/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR '
PLANNED, AND ASSOCIATED DATES.
NONE 1
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE b
p D
h SSP PTAMA412 REV 0 L
PERFORMANCE TEST ABSTRACT PTA-MA-413
- 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-413, RHR Failure To Auto Start 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (17) Failure in automatic control system (s) that affect reactivity and core heat removal (22) Process instrumentation, alarms, and control system failures.
2.0 AVAILABLE OPTIONS This malfunction allows selection of either Loop I and /or Loop II. l 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:413 3.2 MALFUNCTION SYMBOL.: MESO 45F 3.3 MALFUNCTION MENU...:ES 3.4 SELECTED LOOP......: A 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
1 l 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
NOTE: Rx Water Level, NBLEVELT(5) , is displayed in feet.
3.2.1 Reactor Water Level (0 to 210) . . . :NBLEVELT (5) 3.2.2 Drywell Pressure.................: CAP 0010 3.2.3 Reactor Pressure.................:NBPREGI 3.2.4 Loop I RHR/LPCI Injection Flow. . . :RHWOO32 (1) !
3.2.5 Loop II RHR/LPCI Injection Flow. . :RHWOO32 (2) 5.0 TEST DURATION The recording device will be stopped af ter water level and/or Drywell pressure and reactor pressure have exceeded the auto start set point and the RHR System did not initiate.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP l
PTAMA413 REV O 1
l
7.O DATE PERFORMED:12/13/92 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR
- PLANNED, AND ASSOCIATED DATES.
NONE 9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA413 REV 0
.o PERFORMANCE TEST ABSTRACT PTA-MA-415 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-415, #3 DG AUTO VOLTAGE REGULATOR TRIP 1.2 ANSI /ANS 3.5 1985, Section 3.1. 2, Plant Malfunctions, (3)
Loss or Degraded Electrical Power to the Station c. loss of emergency generators; and (22) Process ,
Instrumentation, Alarms, and Control System Failures.
2.0 AVAILABLE OPTIONS L NONE l
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMEER...:415 3.2 MALFUNCTION SYMBOL...:MDG016F 3.3 MALFUNCTION MENU.....:DG 4.0 INITIAL CONDITIONS ,
4.1 The simulator is in operation at. approximately 100%
steady state reactor power. Manually OPEN the !
Master / Slave breaker from 2D to E3. Allow the #3 D/G to Automatically start and energize Bus E3.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
I 4.2.1 4 KV Bus E3 Voltage....:EDV0301G 4.2.2 DG #3 Terminal Voltage. :EEV2601G (1,1) l l
5.0 TEST DURATION 5.1 The recording device will be stopped after unit i conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP ,
PTAMA415 REV 0 j i
l
- c. .
7.0 DATE PERFORMED:2/11/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA415 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-416 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-416, DG #4 AUTO VOLTAGE REGULATOR TRIP 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3)
Loss or Degraded Electrical Power to the Station c. loss of emergency generators; and (22) Process Instrumentation, Alarms, and Control System Failures.
2.0 AVAILABLE OPTIONS NONE 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:416 3.2 MALFUNCTION SYMBOL...:MDG017F 3.3 MALFUNCTION MENU.....:DG 4.O INITIAL CONDITIONS 4.1 The simulator is in operation at approximately 100%
steady state reactor power. Manually OPEN the Master / Slave breaker from 2C to E4. Allow the #4 D/G to Automatically start and energize Bus E4.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 4 KV Bus E4 Voltage....:EDV0208G 4.2.2 DG #4 Terminal Voltage.:EEV2601G(2,1) 5.0 TEST DURA"/ ION 5.1 The recording device will be stopped after unit conditions have stabilized.
6.O BASE LINE DATA i
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power l Plant Training Simulator, latest Revision.
SSP PTAMA416 REV 0 i
d 4
7.0 DATE PERFORMED:2/11/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ;
NONE i
l 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. ;
NONE T
6 r
i i
SSP PTAMA416 REV O
, i
- c1 I I
i PERFORMANCE TEST ABSTRACT l PTA-MA-417
.1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE j 1.1 STP-MA-417, DG AUTO. VOLTAGE REGULATOR FAILS HIGH 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3) ,
Loss or Degraded Electrical Power to the Station c. loss {
of emergency generators; and (22) Process j Instrumentation, Alarms, and Control System Failures. '!
i 2.0 AVAILABLE OPTIONS !
i 2.1 This Malfunction causes the selected Diesel Generator !
Auto Voltage Regulator.setpoint to increase at a fixed !
rate of it /' minute up to a maximum of 110% of rated !
voltage (4576 volts) . :
I 2.2 This malfunction allows selection of either #3 or #4 Diesel Generator. i l
3.O TESTED OPTIONS !
3.1 MALFUNCTION NUMBER...:417 3.2 MALFUNCTION SYMBOL...:MDG020F ;
3.3 MALFUNCTION MENU.....:DG 3.4 SELECTED MALFUNCTION.: #3 .i y ,
4.O INITIAL CONDITIONS l 4.1 The simulator is in operation at approximately 100% !
steady state reactor power with the selected D/G in !
Automatic Voltage Regulation, loaded and operating in !
parallel with the system. j
+
4.2 A recording device is setup to record the following ,
test parameters simultaneously versus time with a -!
resolution of 0.5 seconds or less- t 4.2.1 4 KV Bus E3 Voltage....:EDV0301G !
OR +
4 KV Bus E4 Voltage....:EDV0208G l 4.2.2 DG #3 Reactive Power...:EEJ2804G(1,1) !
OR l
DG #4 Reactive Power...:EEJ2804G(2,1) !
4.2.3 DG #3 Field Voltage....:EEV1801G(1,1) l OR t DG #4 Field Voltage. . . . :EEV1801G (2,1) !
4.2.4 DG #3 Terminal Voltage.:EEV2601G(1,1) !
OR l
SSP .!
PTAMA417 REV 0 !
l l
l
, .- . . . . - . . - . . . . - . . . ~ .. -
DG #4' Terminal _ Voltage.1EEV2601G (2,1) l DG #3 Armature Current.:EEI2801G(1,1) i 4.2.5 OR
- DG #4 Armature Current. :EEI2801G (2,1) f DG #3 Kilowatt Output..:EEJ2803G(1,1). i 4.2.6 OR .
l DG #4 Kilowatt Output. . :EEJ2803G (2,1). j 5.O TEST DURATION stopped after unit ;
5.1 The recording device will. be conditions have stabilized.
+
l 6.O BASE LINE DATA 6.1 Malfunction.Cause and Effect for Brunswick Unit'2 Power Plant Training Simulator, latest Revision. ;
?
7.0 DATE PERFORMED:2/9/93 1
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR l PLANNED, AND ASSOCIATED DATES. j NONE l
t c
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING !
JUSTIFICATION. i NONE _
i SSP !
PTAMA417 REV 0 i i
l i
=.
I .[
- e. ,
.)
PERFORMANCE TEST ABSTRACT l r
PTA-MA-417 l 7 1.O PROCEDURE TITLE / ANSI 3.5-REFERENCE 1.1- STP-MA-417, DG AUTO VOLTAGE REGULATOR FAILS HIGH !
1.2
~
ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions,'(3) !
Loss or Degraded Electrical Power to the Station c. loss :l of . emergency generators; and (22) Process Instrumentation, Alarms, and Control System Failures. j 2.0 AVAILABLE OPTIONS 2.1 This Malfunction causes the selected Diesel Generator.
Auto Voltage Regulator setpoint to increase at a fixed rate of 1% / minute up to a maximum of 110% of rated !
voltage - (4576 volts) . !
2.2 This malfunction allows selection of either #3 or #4 i Diesel Generator. f 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:417 3.2 MALFUNCTION SYMBOL...:MDG020F '
l 3.3 MALFUNCTION MENU.....:DG 3.4 SELECTED MALFUNCTION.: #4
.l 4.0 INITIAL CONDITIONS !
l 4.1 The simulator is in operation at approximately 100% i steady state reactor power with the selected D/G in ;
Automatic Voltage Regulation, loaded and operating in parallel with the system.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a i
resolution of 0.5 seconds or less: !
4.2.1 4 KV Bus E3 Voltage....:EDV0301G t OR ;
4 KV Bus E4 Voltage....:EDV0'IP83 4.2.2 DG #3 Reactive Power...:EEJ23L4Grl,1)
OR DG #4 Reactive Power. . . :EEJ2804G (2,1) 4 4.2.3 DG #3 Field Voltage....:EEV1801G(1,1) I OR I DG #4 Field Voltage. . . . :EEV1801G (2,1) l 4 2.4 DG #3 Terminal Voltage.:EEV2601G(1,1) I OR !
l SSP PTAMA417 REV 0
DG #4 Terminal Voltage.:EEV2601G(2,1) 4.2.5 DG #3 Armature Current. :EEI2801G (1,1)
OR DG #4 Armature Current. :EEI2801G(2,1) 4.2.6 DG #3 Kilowatt Output..:EEJ2803G(1,1)
OR DG #4 Kilowatt Output..:EEJ2803G(2,1) 5.0 TEST DURATION 5.1 The recording device will be stopped after unit conditions have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:2/9/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA417 REV 0
- - . . . .. . - ~ _ - . . .
'I
., e r
. l PERFORMANCE TEST ABSTRACT 'f PTA-MA-418 6 t
1.0 PROCEDURE. TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-418, DG AUTO VOLTAGE REGULATOR FAILS LOW !
1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3)
Loss or Degraded Electrical Power to the Station c. loss of emergency generators; and' (22) Process '
Instrumentation, Alarms, and Control System Failures. l.
-2.0 AVAILABLE OPTIONS {
i 2.1 This Malfunction causes the selected Diesel Generator.-
Auto Voltage Regulator setpoint to decrease at a fixed l rate of 1% / minute down to a minimum of 90% of rated I voltage -(3744 volts) . }
t 2.2 This malfunction allows selection of either #3 or #4 Diesel Generator, j 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:418 l 3.2 MALFUNCTION SYMBOL...:MDG021F l 3.3 MALFUNCTION MENU.....:DG -
3.4 SELECTED MALFUNCTION.: #3 4.0 INITIAL CONDITIONS 4.1 The simulator is in operation at approximately 100% .
steady state reactor power with the selected D/G in l Automatic Voltage Regulation, loaded and operating in parallel with the system.
4.2 A recording device is setup to record the follow.ing test parameters simultaneously versus time with a resolution of 0.5 seconds or less: -
4.2.1 4 KV Bus E3 Voltage....:EDV0301G ,
OR t 4 KV Bus E4 Voltage....:EDV0208G !
4.2.2 DG #3 Reactive Power. . . :EEJ2804G (1,1)
OR '
DG #4 Reactive Power. . . :EEJ2804G (2,1) '
4.2.3 DG #3 Field Voltage....:EEV1801G(1,1) ,
OR DG #4 Field Voltage. . . . :EEV1801G (2,1) .
4.2.4 DG #3 Terminal Voltage. :EEV2601G (1,1)
l l
I
J 1
f DG #4 Terminal Voltage. :EEV2601G(2,1)
-t 4.2.5l DG #3_. Armature Current.:EEI2801G(1,1)
OR~
< DG #4 ' Armature Current. :EEI2801G (2,1) .
4.2.6 DG #3 Kilowatt Output..:EEJ2803G(1,1) , '!
OR DG #4 Kilowatt Output. . :EEJ2803G(2,1) i 5.0 TEST DURATION- i 5.1 The recording device will be stopped after unit l conditions have' stabilized. -t 6.0 BASE LINE DATA ,.
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training-Simulator, latest Revision.
7.0 DATE PERFORMED:2/9/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
5 NONE .
t 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION. !
NONE i
t SSP PTAMA418 REV 0
=-* wp g ---m1-m -% , ++,,e.e y w m
s F.ERfORMANCE TEST ABSTRACT PTA-MA-418 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-418, DG AUTO VOLTAGE REGULATOR FAILS LOW 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3)
Loss or Degraded Electrical Power to the Station c. loss of emergency generators; and (22) . Process Instrumentation, Alarms, and Control System Failures.
2.0 AVAILABLE OPTIONS 2.1 This Malfunction causes the selected Diesel Generator Auto Voltage Regulator setpoint to decrease at a fixed rate of 1% / minute down to a minimum of 90% of rated voltage (3744 volts).
2.2 This malfunction allows selection of either #3 or #4 Diesel Generator.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:418 3.2 MALFUNCTION SYMBOL...:MDG021F 3.3 MALFUNCTION MENU.....:DG 3.4 SELECTED MALFUNCTION.: #4 D/G 4.O INITIAL CONDITIONS 4.1 The simulator is in operation at approximately 100%
steady state reactor power with the selected D/G in Automatic Voltage Regulation, loaded and operating in parallel with the system.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 4 KV Bus E3 Voltage....:EDV0301G OR 4 KV Bus E4 Voltage....:EDV0208G 4.2.2 DG #3 Reactive Power. . . :EEJ2804G (1,1)
OR DG #4 Reactive Power. . . :EEJ2804G (2,1) ,
4.2.3 DG #3 Field Voltage....:EEV1801G(1,1)
OR DG #4 Field Voltage . . . . :EEV18 01G (2,1) 4.2.4 DG #3 Terminal Voltage.:EEV2601G(1,1)
4 DG #4 Terminal Voltage. :EEV2601G (2,1) 4.2.5 DG #3 Armature Current.:EEI2801G(1,1)
OR DG #4 Armature Current. :EEI2801G (2,1) 4.2.6 DG #3 Kilowatt Output..:EEJ2803G(1,1)
OR DG #4 Kilow&tt Output. . :EEJ2803G (2,1) 5.0 TEST DURATION 5.1 The recording device will be stopped after unit conditions have stabilized.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.0 DATE PERFORMED:2/9/93 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE SSP PTAMA418 REV 0
PERFORMANCE TEST ABSTRACT PTA-MA-419 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-419, DG DIFFERENTIAL FAULT 1.2 ANSI /ANS 3.5 1985, Section 3.1.2, Plant Malfunctions, (3)
Loss or Degraded Electrical Power to the Station c. loss of emergency generators.
2.0 AVAILABLE OPTIONS 2.1 This malfunction allows selection of #1, #2, #3 or #4 Diesel Generator.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER...:419 3.2 MALFUNCTION SYMBOL...:MDG024F 3.3 MALFUNCTION MENU.....:DG 3.4 SELECTED DG..........:1.2.3 &4 4.O INITIAL CONDITIONS 4.1 The simulator is in operation at approximately 100%
steady state reactor power with the Diesel Generator running at rated frequency and voltage separated from the grid.
4.2 A recording device is setup to record the following '
test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.3 DG #1 Field Voltage....:EEV1801G(1,2)
OR DG #2 Field Voltage . . . . :EEV1801G (2,2)
OR DG #3 Field Voltage. . . . :EEV1801G (1,1)
OR DG #4 Field Voltage. . . . :EEV1801G (2,1) 4.2.4 DG #1 Terminal Voltage.:EEV2601G(1,2)
OR DG #2 Terminal Voltage. :EEV2601G (2,2)
OR DG #3 Terminal Voltage. :EEV2601G (1,1)
i l
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.l
.; 1 l
DG #4 Terminal. Voltage. :EEV2601G (2,1)
, 4.2.3 DG _ #1 Field Current . . . . :EEI1801S (1,2) i OR l DG #2 Field Current . . . . :EEI1801S (2,2) . l OR l DG #3 Field Current....:EEI1801S(1,1) !
OR IX3 #4 ' Field Current. . . . :EEI1801S (2,1) 5.0 TEST DURATION 5.1 The recording . device. will be stopped after unito conditions have stabilized.
'6 . 0 - BASE LINE DATA l 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power [
Plant Training Simulator, latest. Revision. I i
7.0 DATE PERFORMED:2/11/93 !
i 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN.OR !
PLANNED, AND ASSOCIATED DATES. j l
NONE- l f
i i
s.
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING' i JUSTIFICATION. !
e NONE '[
I t
l l-I i
SSP j PTAMA419 REV O ;
e !
PERFORMANCE TEST ABSTRACT PTA-MA-421 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-421, Isolation Of Condensing Pot D004A >
1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control systems failures. '
2.0 AVAILABLE OPTIONS i NONE This malfunction simulates the manual isolation valve .
V40F on penetration X53F being manually closed. !
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:421 3.2 MALFUNCTION SYMBOL.:MNB012F 3.3 MALFUNCTION MENU...:NB 4.O INITIAL CONDITIONS ,
4.1 The simulator is operating at approximately 100% reactor power with CRD system in normal lineup. ;
5.O TEST DURATION l I
5.1 The simulator will be placed in FREEZE af ter the Cause &
Effect has been verified.
6.0 BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:8/1/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE SSP PTAMA421 REV 0 ;
r 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION, ;
NONE ,
I 6
h p
6 0
e l
l i
i SSP PTAMA421 REV O
PERFORMANCE TEST ABSTRACT PTA-MA-422 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-422, Isolation Of Condensing Pot D004B 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (22) Process instrumentation, alarms, and control systems failures.
2.0 AVAILABLE OPTIONS NONE This malfunction simulates the manual isolation valve V51 on penetration X69D being manually closed.
3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:422 3.2 MALFUNCTION SYMBOL.:MNB013F 3.3 MALFUNCTION MENU ..:NB 4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% reactor power with CRD system in normal lineup.
5.0 TEST DURATION 5.1 The simulator will be placed in FREEZE after the Cause &
Effect has been verified.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
7.O DATE PERFORMED:8/1/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE SSP PTAMA422 REV 0
t o .
I 9.0' EXCEPTIONS TAKEN AS A_ RESULT OF TEST PERFORMANCE, INCLUDING t JUSTIFICATION. I
. NONE f r f I
i t
i t
b I
i f
I SSP PTAMA422 REV O l
i l
-\
l PERFORMANCE TEST ABSTRACT PTA-MA-423 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE f 1.1 STP-MA-423, CW Screen Hj Delta P $
i 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (5) {
Loss of condenser vacuum including loss of condenser level control. !
i 2.0 AVAILABLE OPTIONS :
2.1 Selectable to any one of four CW intake screens, 2A, 2B, !
2C, or 2D. i 2.2 Severity Rate of 1 to 60 minutes j 3.0 TESTED OPTIONS ;
3.1 MALFUNCTION NUMBER.:423 ;
3.2 MALFUNCTION SYMBOL.:MCWO15F, MCW016F, MCWO17F, MCWO18F 3.3 MALFUNCTION MENU...:CW ;
3.4 Component Selected..................A '
3.4 This .ialfunction is tested with a severity rate of I minute.
4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady j state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution !
of 0.5 seconds or less:
4.2.1 2 A CW INTAKE FLOW . . . . . . . . . . . . . . . : CWWTIKP (1) 4.2.2 2B CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (2 )
4.2.3 2 C CW INTAKE FLOW . . . . . . . . . . . . . . . : CWWTIKP ( 3 )
4.2.4 2D CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (4 )
4.2.5 2A CONDENSER VACUUM.............:CNP2AHG 5.0 TEST DURATION 5.1 The recording device will be stopped af ter 10 minutes or unit conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA423 REV O
7.O DATE PERFORMED:8/1/94 8.0 DEFICIENCIES'FOUNE DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE i
t SSP ,
PTAMA423 REV O
PERFORMANCE TEST ABSTRACT PTA-MA-423 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-423, CW Screen Hi Delta P 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (5)
Loss of condenser vacuum including loss of condenser level control.
2.0 AVAILABLE OPTIONS 2.1 Selectable to any one of four CW intake screens, 2A, 2B, 2C, or 2D.
2.2 Severity Rate.of 1 to 60 minutes 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:423 3.2 MALFUNCTION SYMBOL.:MCWO15F, MCW016F, MCWO17F, MCWO18F 3.3 MALFUNCTION MENU...:CW 3.4 Component Selected..................B 3.4 This Malfunction is tested with a severity rate of 1 minute.
4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (1) 4.2.2 2B CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (2 )
4.2.3 2 C CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (3 )
4.2.4 2D CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (4 )
4.2.5 2A CONDENSER VACUUM.............:CNP2AHG 5.O TEST DURATION 5.1 The recording device will be stopped after 10 minutes or unit conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
SSP PTAMA423 REV O
er 7.0 DATE PERFORMED:8/1/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR l PLANNED, AND ASSOCIATED DATES. l l
NONE ,
t i
i i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMA.NCE, INCLUDING !
JUSTIFICATION. j NONE I
i i
i i
i
(
I i
SSP PTAMA423 REV 0
PERFORMANCE TEST ABSTRACT i PTA-MA-423 ,
1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE ;
1.1 STP-MA-423, CW Screen Hi Delta P 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (5)
Loss of condenser vacuum including loss of condenser !
level control.
2.0 AVAILABLE OPTIONS ;
1 2.1 Selectable to any one of four CW intake screens, 2A, 2B, !
2C, or 2D.
2.2 Severity Rate of 1 to 60 minutes i 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:423 3.2 MALFUNCTION SYMBOL.:MCWO15F, MCW0l6F, MCWO17F, MCWO18F '
3.3 MALFUNCTION MENU...:CW 3.4 Component Selected..................C This Malfunction is tested with a severity rate of 1 l 3.4 minute, i 4.0 INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
p 4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2 A CW INTAKE FLOW . . . . . . . . . . . . . . . : CWWTIKP (1) 4.2.2 2B CW INTAKE FLOW........ ......:CWWTIKP(2) '
4.2.3 2 C CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (3 )
4.2.4 2D CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (4 ) '
4.2.5 2A CONDENSER VACUUM.............:CNP2AHG 5.0 TEST DURATION 5.1 The recording device will be stopped after 10 minutes or unit conditions have stabilized.
6.O BASE LINE DATA i
6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision.
l SSP PTAMA423 2tEV 0
7.O DATE PERFORMED:8/1/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE l
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING ,
JUSTIFICATION.
NONE i
I r
I SSP ,
PTAMA423 REV O l
i l
l l l
O PERFORMANCE TEST ABSTRACT PTA-MA-423 1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MA-423, CW Screen Hi Delta P 1.2 ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (5)
Loss of condenser vacuum including loss of condenser level control.
2.0 AVAILABLE OPTIONS 2.1 Selectable to any one of four CW intake screens, 2A, 2B, 2C, or 2D.
2.2 Severity Rate of 1 to 60 minutes 3.O TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:423 3.2 MALFUNCTION SYMBOL.:MCWO15F, MCW016F, MCWO17F, MCWO18F 3.3 MALFUNCTION MENU...:CW 3.4 Component Selected..................D 3.4 This Malfunction is tested with a severity rate of 1 minute.
4.O INITIAL CONDITIONS 4.1 The simulator is operating at approximately 100% steady state power.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2 A CW INTAKE FLOW . . . . . . . . . . . . . . . : CWWTIKP (1) 4.2.2 2B CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (2 )
4.2.3 2 C CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (3 )
4.2.4 2D CW INTAKE FLOW. . . . . . . . . . . . . . . : CWWTIKP (4 )
4.2.5 2A CONDENSER VACUUM.............:CNP2AHG 5.O TEST DURATION 5.1 The recording device will be stopped after 10 minutes or unit conditions have stabilized.
6.O BASE LINE DATA 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power Plant Training Simulator, latest Revision, f
SSP PTAMA423 REV 0
d 7.O DATE PERFORMED:8/1/94 8.0 DEF2CIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NG.TE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE ;
r f
l SSP PTAMA423 REV 0 I
1
r'
.o:
p PERFORMANCE TEST ABSTRACT PTA-MA-424
~
1.0 . PROCEDURE' TITLE /AN'SI'3.5 REFERENCE.
.1.1 STP-MA-424, RHR Suction Strainer Clogging 1.2~. ANSI /ANS 3.5 1985, Section 3.1.2 Plant Malfunctions, (7)
Loss of shutdown ' cooling, (23) Passive malfunctions ~in systems, such as engineered' safety features, emergency feedwater systems.
2.3 AVAILABLE OPTIONS 2.1 Selectable to A or B loop suction filter.
2.2 Severity of 50% to 80% plugging of suction filter.
2.3 Severity Rate of 0 to 60 minutes 3.0 TESTED OPTIONS 3.1 MALFUNCTION NUMBER.:424 3.2 MALFUNCTION SYMBOL.:MRH018F,MRH019F 3.3 MALFUNCTION MENU...:RH 3.4 Component Selected .............A 3.5 This Malfunction is tested with a severity of 80% and a severity rate of 0 minute.
4.O INITIAL CONDITIONS 4.1 he simulator is operating with A(B) loop of RHR in cuppression pool cooling.
4.2 A recording device is setup to record the following test parameters simultaneously versus time with a resolution of 0.5 seconds or less:
4.2.1 2A RHR Pump Suction Pressure..:RHP0030(1) 4.2.2 2B RHR Pump Suction Pressure. . :RHP0030 (2) 4.2.3 2C RHR Pump Suction Pressure. . :RHP0030 (3) 4.2.4 2D RHR Pump Suction Pressure. . :RHP0030 (4) 4.3.5 RHR Loop A Flow . . . . . . . . . . . . . . . : RHWO O 3 2 ( 1 )
4.3.6 RHR Loop B Flow . . . . . . . . . . . . . . . : RHWO O3 2 (2 )
4.3.7 2A RHR Pump Discharge Pressure:RHP0016 (1) 4.3.8 2B RHR Pump Discharge Pressure:RHP0016 (2) 4.3.9 2C RHR Pump Discharge Pressure:RHP0016 (3) 4.3.10 2D RHR Pump Discharge Pressure:RHP0016 (4) 5.0 TEST DURATION SSP PTAMA424 REV 1
i 5.1 The recording device will be stopped after 10 minutes or :
unit conditions have stabilized.
6.0 BASE LINE DATA j 6.1 Malfunction Cause and Effect for Brunswick Unit 2 Power i Plant Training Simulator, latest Revision. '
7.0 DATE PERFORMED:9/26/94 i
~I 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE __
i E
i I
k i
SSP PTAMA424 REV 1
O Q:
PERFORMANCE TEST ABSTRACT PTA-MV-747 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MV-747 , MAIN STACK RADIATION MONITORING SYSTEM CHANNEL FUNCTIONAL TEST 1.2 PT-04.1.2 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, (10) Operator conducted surveillance testing on safety related equipment or systems.
2.0 AVAILABLE OPTIONS 2.1 N/A 3.0 TESTED OPTIONS 3.1 N/A 4.O INITIAL CONDITIONS 4.1 IC 11 5.0 TEST DURATION 5.1 1 HR.
6.O BASE LINE DATA 6.1 PT 4.1.2 COMPLETED 12/5/93 ON UNIT 2 SSP PTAMV700 REV 1
7.0 DATE PERFORMED:2/4/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR
- PLANNED, AND ASSOCIATED DATES.
NONE 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE. INCLUDING JUSTIFICATION. ,
NONE O
)
e 9
f i
SSP PTAMV700 REV 1
PERFORMANCE TEST ABSTRACT PTA-MV-748 1.O PROCEDURE TITLE / ANSI 3.5' REFERENCE 1.1 STP-MV-748 , TURBINE BUILDING EXHAUST VENT RADIATION MONITOR FUNCTIONAL TEST 1.2 PT-04.2.1 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, (10) Operator conducted surveillance testing on safety related equipment or systems.
2.0 AVAILABLE OPTIONS 2.1 NONE 3.0 TESTED OPTIONS 3.1 NONE ,
i 4.O INITIAL CONDITIONS 4.1 IC-02 5.0 TEST DURATION 5.1 1 HR 6.O BASE LINE DATA 6.1 PT 4.2.1 PERFORMED 1/7/94 ON UNIT 2 SSP PTAMV700 REV 1 i
7.0 DATE PERFORMED:2/7/94 ,
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 9.O EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING JUSTIFICATION.
NONE ,
'9 m.W
)-
k i
r SSP PTAMV700 REV 1 I
L
i
. i PERFORMANCE TEST ABSTRACT !
PTA-MV-749 l
'1.O PROCEDURE TITLE / ANSI 3.5 REFERENCE .;
1.1 STP MV-749 , RX BUILDING VENT EXHAUST MONITORING ,
SYSTEM FUNCTIONAL TEST l P
1.2 PT-04.1.1 ;
i 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant !
Evolutions, (10) Operator conducted surveillance testing. ;
.on safety related equipment or systems.
l 2.0 -AVAILABLE OPTIONS 2.1 NONE j 3.O TESTED OPTIONS j i
3.1 NONE {
I i
4.0 INITIAL CONDITIONS !
4.1 IC-11 l i
l l
l I
5.0 TEST DURATION 5.1 1.5 HR ,
i i
i 6.O BASE LINE DATA 6.1 PT 4.1.1 !
SSP PTAMV700 REV 1
+ -
7.O DATE PERFORMED:2/3/94 8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES. ,
NONE
?
i 9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING l JUSTIFICATION. ;
NONE e
f i
4 SSP PTAMV700 REV 1
i, e
PERFORMANCE TEST ABSTRACT PTA-MV-750 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MV-21Q_ , RHR SERVICE WATER SYSTEM OPERABILITY TEST-LOOP A 1.2 PT-08.1.4A 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, (10) Operator conducted surveillance testing on safety related equipment or systems.
2.0 AVAILABLE OPTIONS 2.1 N/A 3.0 TESTED OPTIONS 3.1 N/A 4.0 INITIAL CONDITIONS 4.1 IC-11 r
5.0 TEST DURATION 5.1 1.5 6.0 BASE LINE DATA 6.1 OPT 8.1.4A PERFORMED ON UNIT 2 12/16/93 1
l l
SSP PTAMV700 REV 1 l
\
7.0 DATE PERFORMED:1/28/94 l
?
8.0 DEFICIENCIES FOUND DURING TESTING, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE i
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST PERFORMANCE, INCLUDING
+
JUSTIFICATION.
NONE ,
t I
i L
P SSP PTAMV700 REV 1 +
PERFORMANCE TEST ABSTRACT PTA-MV-751 1.0 PROCEDURE TITLE / ANSI 3.5 REFERENCE 1.1 STP-MV-751. , RHR SERVICE WATER SYSTEM OPERABILITY TEST-LOOP B 1.2 PT-08.1.4B 1.3 ANSI /ANS 3.5 1985, Section 3.1.1 Normal Plant Evolutions, (10) Operator conducted surveillance testing on safety related equipment or systems.
2.0 AVAILABLE OPTIONS 2.1 N/A 3.0 TESTED OPTIONS 3.1 N/A 4.O INITIAL CONDITIONS 4.1 IC-11 5.0 TEST DURATION 5.1 1.5 HR 6.0 BASE LINE DATA 6.1 PT 8.1.4B PERFORMED ON UNIT 2 10/21/93 SSP PTAMV700 REV 1
r e
7.0 DATE PERFORMED:1/28/94 8.0 DEFICIENCIES FOUND DURING TESTIiM, CORRECTIVE ACTION TAKEN OR PLANNED, AND ASSOCIATED DATES.
NONE 1
9.0 EXCEPTIONS TAKEN AS A RESULT OF TEST FERFORMANCE, INCLUDING JUSTIFICATION.
NONE t'
h SSP PTAMV700 REV 1
l
. 1
' el ATTACHMENT 5 q BRUNSWICK CERTIFICATION TEST PLAN The following Simulator Test Procedures should be performed with a frequency of Once Per Calendar Years I. SIMULATOR OPEftATING LIMITS TEST STP-OL 001 Simulator Operating Limits Test (4.3)
II. COMPUTER REAL TIME TEST STP-RT-001 Simulator Real Time Test { Appendix A A3. (1) )
III. STEADY STATE STP-SS-002 50% Power. Steady State Comparison (4.1L '
STP-SS-003 75% Power- Steady State Comparison 14 .1, STP-SS-004 100% Power-Steady State Comparison (4.1; IV.NOPJMAL PLANT EVOLUTIONS STP-MV-100 GP-01 & GP-02 Plant Startup-Cold Shutdown To Hot Standby 3.1.1 (1)&(5))
STP-MV-200 GP-03 Unit Startup And Synchronization 3.1.1 (2) , (3) &(4))
STP-MV-300 GP-04 Increasing Turbine Load to Rated Power 3.1.1 (2)&(6)}
STP-MV-400 GP-05 Unit Shutdown-Rated Power To Cold Shutdown 3.1.1 (8)) .
STP-MV-500 COP-01 (4)
STP-HV-600 Rx Trip Core Followed By Performance Cecovery Testing To Hot Standby { 3.1.1 3.1.1 (9)))
STP-MV-601 PT-01.8D Thermal Power Calculation 6 STP-MV-602 PT-14.3.1 & U2 Cycle Mgt Report In Sequence Critical Shutdown Margin Calculation STP-MV-603 PT-01.11 Core Performance Parameter Check STP-MV-604 PT-50.2 SRM/IRM/APRM Overlap Determination ,
STP-HV-605 PT-14.5.2 Reactivity Anomaly Check STP-MV-606 Flux Response To Control Rod Movement STP-MV-607 Core Power Response To Voids STP-MV-700 Operator Conducted Surveillances (PT Guideline){3.1.1 (10))
STP-MV-701 OPT-01.1.6 RPS Manual Scram i f
STP-HV-702 OPT-18.4 One Rod-Out Interlock Operability Test STP-MV-703 OPT-01.10 IRM Detector Position Rod Block Function STP-MV-704 OPT-01.14a Equipment and Instrument Channel Check [
STP.MV-705 OPT-01.14b Equipment and Instrument Channel Check STP-MV-706 OPT-02.3.1 Suppression Chamber To Drywell Vacuum Breaker Operability 1 STP-MV-707 OPT-02.3.2 Reactor Building To Suppression Chamber Vacuum Breaker and Valve Operability STP-MV-708 OPT-03.1.21 Reactor Recirculation Valves Operability i STP-MV-709 OPT-04.1.8 Off Gas System Automatic Isolation Operability Check [
STP-MV-710 OPT-07.1,la Core Spray Injection Check Valve Operability Test-Loop A STP-MV-711 OPT-07.1.1b Core Spray Injection Check Valve Operability Test-Loop B 'i 6
STP-MV-712 CPT-07.2.4a Core Spray System Operability Test-Loop A STP-MV 713 OPT-07.2.4b Core Spray System Operability Test-Loop B STP-MV-714 OPT-08.0 LPCI/RHR System Valve Operability Test STP-HV-715 OPT-08.0a LPCI/RHR Loop A Check Valve Operability Test STP-MV-716 OPT-08.0b LPCI/RHR Loop B Check Valve Operability Test STP MV-717 OPT-08.2.2b LPCI/RHR System Operability Test Loop B -i STP-MV-718 OPT-08.2.2c LPCI/RHR System Operability Test Loop A ;
STP-MV-719 OPT-09.2 HPCI System Operability Test i.
STP-MV-720 OPT-09.3 HPCI System 165 PSIG Flow Test STP-MV-721 OPT-10.1.1 RCIC System Operability Test-Flow Requirements at 1000 PSIG STP-MV-722 OPT-10.1.3 RCIC System Operability Test-Flow Rates at 150 PSIG STP-MV-723 OPT-11.1.2 ADS and SRV Operability Test STP-HV-724 OPT-11.3 Drywell Drains System Valve Operability Test STP MV-725 OPT 12.2C # 3 Diesel Generator Monthly Load Test STP-MV-726 OPT-12.2D # 4 Diesel Generator Monthly Load Test STP-MV-727 OPT-13.1 Reactor Recirculation Jet Pump Operability STP-MV-728 OPT-14.0 Control Rod Drive System Valve Operability Test STP-MV-729 OPT-14.1 Control Rod Operability Check I
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- e ATTACHMENT 5 cont. I IV. NORMAL PLANT EVOLUTIONS (con't)
STP MV 730- OPT-14.1A Control Rod Coupling Check and CRD Test i STP-MV-731 O P'.*- 14 . 6 Reactor Water Clean-up System Operability Test i STP-MV-732 OPT-15.4A Secondary Containment Isolation Operability i STP-MV-733 OPT-15.7 Standby Gas Treatment System Operability Test i STP-MV-734' OPT-16.1 CAD System Component Test !
STP-MV-735 OPT-16.1.1 CAC System Valve Operability ,
STP-MV-736 OPT-16.2 Primary Containment Volumetric Average Temperature i STP-MV-737 OPT-22.2 Reactor Building Closed Cooling Water Valve Operability Test !
STP-MV-738 CPT-24.0 Service Water Valve Lineup Verification l STP-MV-739 OPT-24.1.2 Miscellaneous Service Water Valve Operability ?
STP-MV 740 OPT-25.1 NSSS Main Steam and Feedwater Isolation Valve Operability Test STP-MV-741 '0PT-25.4 NSSS Main Steam Drain Valve Operability STP-MV-742 OPT-31.6 Backup N, Supply to Drywell Valve Operability Test !
STP-MV-744 2PT-01.6.2-2 RWM Operability l STP-MV-745 2PT-16.0+2 Containment Atmosphere Monitoring System Valve Operability '?
STP-MV-746 2PT-24.1-2 Service Water Pump and Discharge Valve Operability i STP-MV-747 OPT-04.1.2 Main Stack Radiation Monitoring System Channel Functional Test !
STP-MV-748 OPT-04.2.1 Turbine Building Exhaust Vent Radiation Monitor Channel Functional Test t STP-MV-749 OPT-04.1.1 Reactor Building Vent Exhaust Monitoring System Functional Test -
STP-MV 750 OPT-08.1.4A RHR Service Water System Operability Test - Loop A I STP-MV-751 OPT-08.1.4B RHH Service Water System Operability Test - Loop B i V. TRANSIENTS STP-TN-001 Manual Scram (Appendix B Bl.2) l STP-TN-002 Simultaneous Trip All Feedwater Pumps (Appendix B Bl.2) :
I STP-TN-003 Simultaneous Closure Of All MSIV's (Appendix B Bl.2)
STP-TN-004 Simultaneous Trip Of Both Recirc. Pumps (Appendix B B1.2)
STP-TN-005 Single Recirc Pump Trip (Appendix B Bl.2) !
STP-TN-006 Turbine Trip Does not result in an immediate Rx SCRAM (Unit 2) (Appendix B Bl.2) [
^
STP-TN-006.1 Turbine Trip Does not result in an immediate Rx SCRAM (Unit 1) (Appendix B Bl.2)
STP-TN 007 Max Rate Power Ramp-Recire. Flow Controller in Manual.(100%-75%-100t) (Appendix B Bl.2)
STP-TN-008 DB LOCA in Conjunction with Loss OF Off-sue-power (Appendix B Bl.2)
STP-TN-009 Maximum Size Unisolable MSL Rupture (Appendix B Bl.2) ,
STP-TN+010 MSIV Closure With 1 Stuck Open SRV With High Pressure ECCS Inhibited (Appendix B Bl.2) i STP-TN-011 Inadvertent HPCI Initiation (Appendix A A3.3) l h
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i ATTACHMENT 5 cont. )
i The following Malfunction Simulator Test Procedures should be performed once every four years: 1 l
VI. MALFUNCTIONS - YEAR ONE (1) )
i Malf Severity Test Sys Num. Description' Severity Rate ANSI /ANS 3.5 Ref, l
j STP-MA-001 NB 140 RECIRC PUMP A SUCTION LINE RUPTURE 0-100% 0-60 min. 3.1.2 (1) (b) & (c)
STP-MA 008 MS 154 MSL D BREAK IN STEAM TUNNEL 0-100% 0-60 min. 3.1.2 (1) (b)&(c) (20) l STP-MA-012 AI 349 INSTR AIR RUPT DNSTR OF DRYERS 0-100% 0-60 min. 3.1.2 (2) l STP-MA-021 DG 311 LOSS OF SUBSTATION E8 NONE NONE 3.1.2 (3)b i STP-MA-028 EE 395 INDIVIDUAL BUS FAILURES (PARTIAL) NONE NONE 3.1.2 (3) d i STP-MA-031 EE 345 LOSS OF 4160V BUS NONE NONE 3.1.2 (3)d !
STP-MA-035 RC 115 RECRC PMP MG SET FLD FKR TRIP NONE NONE 3.1.2 (4) I STP MA-041 CW 247 NUC SW HDR RUPTURE 0-100% 0-60 min. 3.1.2 (6) !
STP-MA-042 CA 255 LOSS OF RBCCW TO DW CO LERS NONE NONE 3.1.2 (8) -- i STP-MA-054 CF 212 COND XFER SYS RUPTURE NONE NONE 3.1.2 (5) l STP-MA-055 CN 190 LOSS OF CONDENSER VACSUM 0- +10K 0-60 min. 3.1.2 (5) l STP-MA-062 RH 284 RHR PUMP TRIP NONE NONE 3.1.2 (7) ,
STP-MA-063 CF 200 CONDENSATE PUMP SHEARED SHAFT NONE NONE 3.1.2 (9)
STP-MA-065 CF 206 COND BSTR PMP SHEARED SHAFT NONE NONE 3.1.2 (9)
STP-MA-071 CF 221 FEEDWATER PUMP SHEARED SHAFT NONE NONE 3.1.2 (9)
STP-MA-088 RD 001 CONTROL ROD SLOW INSERTION DRIFT NONE NONE 3.1.2 (12)c I STP-MA-090 XX 012 & 016 CONTROL ROD DROP NONE NONE 3.1.2 (12) d l STP-MA-091 RD 017 CRD FCV 'A' FAILS CLOSED NONE NONE 3.1.2 (13) l STP-MA-099 MS 169 MAIN TURBINE TRIP (Unit 2) NONE NONE 3.1.2 (15) i STP-MA-099.1 MS 169 MAIN TURBINE TRIP (Unit 1) NONE NONE 3.1.2 (15) i STP-MA-103 ES 269 RCIC TURBINE SPEED CONTROL FAILURE NONE NONE 3.1.2 (17) & (22) '
STP-MA-105 RP 045 SPURIOUS SCRAM NONE NONE 3.1.2 (19)
STP-MA 108 NI 130 REC /APRM FLOW INST FAILS DNSCL NONE NONE 3.1.2 (21) & (22)
STP-MA-109 NI 046 SRM FAILS HI NONE NONE 3.1.2 (21) & (22) !
STP-MA 112 NI 058 IRM FAILS HI NONE NONE '3.1.2 (21) & (22) !
STP-MA-115 NI 076 APRM FAILS HI NONE NONE 3.1.2 (21) & (22) f STP-MA-118 NI 092 LPRM FAILS HIGH NONE NONE 3.1.2 (21) & (22) i STP-MA-126 NB 236 RX LVL XMITTER B21-N004 FAILS NONE NONE 3.1.2 (22)
STP-MA-127 DG 320 DG AUTO START FAILURE NONE NONE 3.1.2 (23) -
STP-MA-128 ES 113 ADS LOGIC FAILURE NONE NONE 3.1.2 (23) & (22) !
STP-MA-130 ES 261 HPCI LOGIC BUS A AUTO START FAILS NONE NONE 3.1.2 (23) !
STP MA 136 MS 162 EHC PRESSURE REGULATOR FAILS HIGH NONE NONE 3.1.2 (25) & (22) :
STP MA-141 MS 181 ALL TURB BYP VLVS FAIL OPEN NONE NONE 3.1.2 (25) l STP-MA-147 CF 147 FEEDWATER LINE BREAK IN DRYWELL 0-100% 0-60 min. 3.1.2 (20) l STP-MA-152 RP 111 MANUAL SCRAM DEFEAT NONE NONE 3.1.2 (23) ;
STP-MA-231 RW 231 RWCU BREAK IN TRIANGLE ROOM 77* 0-100% 0-60 min. 3.1.2 (1) (b) i STP-MA-264 ES 264 HPCI HYDRAULIC SYSTEM FAILURE NONE NONE 3.1.2 (22) l STP-MA-276 RH 276 RHR INJ VALVE F015 STUCK CLOSED NONE NONE 3.1.2 (17)
STP-MA-292 RH 292 RHR HEAT EXCHANGER BYPASS VALVE TRIP NONE NONE 3.1.2 (17)
'STP-MA-298 EE 298 AUTO VOLTAGE REGULATOR FAILURE NONE NONE 3.1.2 (3) & (22)
STP-MA-309 EE 309 MAIN XFORMER COOLING SYSTEM FAILURE NONE NONE 3.1.2 (3) k (8)
STP-MA-409 EE 409 STATION BLACKOUT NONE NONE 3.1.2 (3)
STP-MA-415 DG 415 DG #3 AVR TRIP NONE NONE 3.1.2 (3)c & (22) l STP MA-416 DG 416 DG #4 AVR TRIP NONE NONE 3.1.2 (3)c & (22) i STP-MA-425 MS 425 EHC FAILS TO AUTO START NONE NONE 3.1.2 (25) i i
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ATTACHMENT 5 cont.
VI. MALFUNCTIONS - YEAP TWO (2)
Malf Severity Test Sys Num. Description Severity Rate ANSI /ANS 3.5 Ref.
STP-MA-002 NB 141 RECIRC PUMP A DISCH LINE RUPTURE 0-100% 0-60 min. 3.1.2 (1) (b) & f c)
STP-MA-009 MS 155 MSL D BREAK IN TURBINE BLDG 0-100% 0-60 min. 3.1.2 (1) (b) & (c) ; (20)
STP-MA-013 AI 365 SERVICE AIR RUPTURE NONE NONE 3.1.2 (2)
STP-MA-025 DG 331 DG #4 GOVERNOR FAILURE HIGH NONE NONE 3.1.2 (3)c STP-MA-026 EE 297 MAIN XFMR SUD PRESS DEV ACTUATES NONE NONE 3.1.2 (3 ) d STP-MA-026 EE 395 INDIVIDUAL BUS FAILURES (PARTIAL) NONE NONE 3.1.2 (3)d STP-MA-032 DG 333 UPS FAILURE NONE NONE 3.1.2 (3)e STP-MA-036 RC 117 RECRC PMP MG SET BUS BKR TRIP NONE NONE 3.1.2 (4)
STP-MA-043 CW 252 TBCCW HX PLUGGED 0-100% 0-60 min. 3.1.2 (6)
STP MA-050 XY 317 STATOR CLG TEMP CONTROLLER FAILS NONE NONE 3.1.2 (8) & (22)
STP-MA-051 MS 191 MTLO TEMP CNTRLR FAILS NONE NONE 3.1.2 (B) & (22)
STP MA-053 CF 194 H/W REJ VLV FAILS CLOSED NONE NONE 3.1.2 (5) & (22)
STP-MA-057 CN 242 CW PMP DISC VLV FAILS CLOSED NONE NONE 3.1.2 (5)
STP-MA-061 CW 286 RHR SW PUMP BREAKER FAULT NONE NONE 3.1.2 (7)
STP MA-068 CF 216 LP FW HEATER 2B TUBE LEAK 0-500,000 0-60 min. 3.1.2 (9)
STP-MA-077 CF 234 RFP LOW SUCTION PRESS NONE NONE 3.1.2 (9)
STP-MA-083 RP 108 RPS M.G. SET TRIP NONE NONE 3.1.2 (11)
STP-MA-087 RD 005 CONTROL ROD WITHDRAWAL DRIFT NONE NONE 3.1.2 (12)c STP-MA-092 RD 018 CRD PUMP SUCTION FILTER PLUGGED NONE NONE 3.1.2 (13)
STP-MA-094 RD 398 RWM LOSS OF POWER NONE NONE 3.1.2 (13)
STP-MA-100 EE 299 MAIN GENERATOR TRIP NONE NONE 3.1.2 (16)
STP-MA-102 ES 263 HPCI INVERTER FAILURE NONE NONE 3.1.2 (17)
STP-MA-107 NI 103 SRM/IRM DRIVE MTR POWER FAILURE NONE NONE 3.1.2 (21)
STP-MA-110 NI 047 SRM FAILS HI NONE NONE 3.1.2 (21) & (22)
STP-MA-114 NI 059 IRM FAILS AS IS NONE NONE 3.1.2 (21)
STP-MA-119 NI 093 LPRM FAILS LOW NONE NONE 3.1.2 (21) & (22)
STP-MA-122 NI 100 SRM CH A STUCK DETECTOR NONE NONE 3.1.2 (21)
STP-MA-131 ES 267 RCIC LOGIC BUS B AUTO START FAILS NONE NONE 3.1.2 (23)
STP-MA-137 MS 163 EHC PRESSURE REGULATOR FAILS LOW NONE NONE 3.1.2 (25) & (22)
STP-MA-132 XY 393 DEFEAT OF GROUP 2 ISOLATION LOGIC NONE NONE 3.1.2 (23)
STP MA-145 ES 156 ADS VALVE FAILS OPEN NONE NONE 3.1.2 (1) (d)
STP-MA-148 ES 138 HPCI STEAM BRK HPCI ROOM 0-100% 0-60 min. 3.1.2 (1) (B) ; (C) & l20)
STP-MA-151 RC 121 RECIRC PUMP #1 SEAL FAILURE 0-100% 0 60 min. 3.1.2 (1) (B) & (C)
STP-MA-155 RW 149 RWCU RESIN INJECTION INTO RX VESSEL NONE NONE 3.1.2 (NON-SPECIFIC)
STP-MA-167 MS 167 MSIV FAILURE TO AUTO CLOSE NONE NONE 3.1.2 (23)
STP-MA-304 EE 304 GRID LOAD INCREASE NONE NONE 3.1.2 (3)
STP MA-354 AI 354 2D AIR COMP FAILS TO LOAD NONE NONE 3.1.2 (2)
STP-MA-361 RM 361 RX BLD VENT MONITOR FAILS DOWNSCALE NONE NONE 3.1.2 (22)
STP-MA-369 CA 369 SBGT INADVERTENT START NONE NONE 3.1.2 (22)
STP-MA-403 CF 403 C32-FTN002 (Feed Flow) Failure 0-100% 0-60 min. 3.1.2 (22)
STP-MA-410 ES 410 HPCI Auto Start Failure NONE NONE 3.1.2 (17) & (22)
STP-MA-413 ES 413 RHR Failure to Auto Start NONE NONE 3.1.2 (17) & (22)
STP-MA-417 DG 417 DG AVR FAILS HIGH NONE NONE 3.1.2 (3)c & (22)
STP-MA-421 NB 421 ISOLATION OF CONDENSING POT D004A NONE NONE 3.1.2 (22)
T ATTACHMENT 5 cont.
VI, t<ALFUNCTIONS - YEAP FOUR f4)
Malf Severity Test Sys Num. Description Severity Rate ANSI /ANS 3.5 Ref.
STP-MA-004 NB 153 MSL D BRK BEFORE FLOW RESTRICTOR 0-100% 0-60 min. 3.1.2 (1) (b) & (c) i (20)
STP-MA 005 RC 335 RECIRC PUMP A DUAL SEAL FAILURE NONE NONE 3.1.2 (1) (b) & (c)
STP-MA 010 ES 159/160 SRV NOT PROPERLY SEATED NONE NONE 3.1.2 (1) (d)
STP-MA-016 RD 114 LOSS OF CNTRL AIR TO THE SCRAM VLVS 0-100% 0-60 min 3.1.2 (2)
STP-MA-020 EE 338 UNIT 2 SAT RELAY FAILURE NONE NONE 3.1.2 (3)a STP-MA-023 DG 326 DG OUTPUT BREAKER TRIP NONE NONE 3.1.2 (3)c STP MA-027 EE 301 4KV COMMON BUS B TRIP NONE NONE 3.1.2 (3)d STP-MA-028 EE 395 INDIVIDUAL BUS FAILURES (PARTIAL) NONE NONE 3.1.2 (3)d STP-MA-038 RC 132 RECRC MG SET COOLING WATER LOSS NONE NONE 3.1.2 (B)
STP-MA-039 CN 246 TOTAL LOSS OF CW PUMP SEAL WATER NONE NONE 3.1.2 (5) & (8)
STP-MA-044 CW 381 TBCCW HX DISCH HDR RUPTURE 0-100% 0-60 min. 3.1.2 (6)
STP MA-047 RD 019 CRD DRIVE WATER FILTER PLUGGED NONE NONE 3.1.2 (8) & (13)
STP-MA-048 RW 151 RWCU N/R HX HI OUTLET TEMP NONE NONE 3.1.2 (8)
STP-MA-049 XY 314 GEN H2 CLG TCV FAILS CLOSED NONE NONE 3.1.2 (8) & (22)
STP-MA-052 CF 193 H/W MAKE-UP VLV FAILS CLOSED NONE NONE 3.1.2 (5) & (22)
STP-MA-060 MS 189 TURB STEAM SEAL REG FAILS CLOSED NONE NONE 3.1.2 (5)
STP-MA-070 CF 218 HP FW HEATER 4B TUBE LEAK 0-920,000 0-60 min. 3.1.2 (9)
STP MA-072 CF 223 RFP 2A LUBE OIL LEAK 1000 gal. 30 min. 3.1.2 (9)
STP-MA-076 CF 233 S/U LVL CONT VLV FAILS CLOSED NONE NONE 3.1.2 (9)
STP-MA-084 RP 112 RPS SCRAM GROUP BLOWN FUSE NONE NONE 3.1.2 (11)
STP MA-086 RD 016 CONTROL ROD UNCOUPLED NONE NONE 3.1.2 (12)b STP-MA-097 RD 044 ROD MOTION TIMER FAILURE NONE NONE 3.1.2 (13) & (22) l
{ STP-MA-117 NI 078 APRM FAILS AS IS NONE NONE 3.1.2 (21)
STP-MA-120 NI 094 LPRM FAILS AS IS NONE NONE 3.1.2 (21)
STP MA-123 NI 101 IRM STUCK DETECTOR NONE NONE 3.1.2 (21)
STP-MA-124 NI 104 SRM/IRM OVERLAP INCORRECT NONE NONE 3.1.2 (21)
STP-MA-129 ES 392 HPCI INJECT VLV FAILS TO AUTO OPEN NONE NONE 3.1.2 (23)
STP+MA-134 RP 382 ATWS NONE NONE 3.1.1 (24)
STP-MA-135 SP 110 AUTO SCRAM DEFEAT NONE NONE 3.1.2 (24)
STP-MA-140 MS 180A TURB BPV #1 FAILS CLOSED NONE NONE 3.1.2 (25)
STP-MA-142 MS 181A ALL TURB BYP VLVS FAIL CLOSED NONE NONE 3.1.2 125)
STP-MA-144 CA 357 DW CLG FAN FAILURE NONE NONE 3.1.2 (8)
STP-MA 149 ES 146 HPCI STM LINE BREAK-MINI STEAM TUNNEL 0-100% 0-60 min. 3.1.2 (1) (b) ; (c) & (20)
STP-MA-150 NI 099 LPRM BYPASS NONE NONE 3.1.2 (21)
STP-MA-154 RC 144 RECIRC PUMP MG SET SCOOP TUBE FAILURE NONE NONE 3.1.2 (17) & (22)
STP-MA-188 RW 188 RWCU BREAK IN HTX ROOM 0-100% 0-60 min. 3.1.2 (1) (b)
STP-MA-271 ES 271 RCIC INADVERTENT START NONE NONE 3.1.2 (17) & (22)
STP-MA-268 ES 268 RCIC TURB1NE TRIP NONE NONE 3.1.2 (22)
STP-MA-275 ES 275 RCIC INJECTION VALVE OVERLOAD NONE NONE 3.1.2 (17)
STP MA-306 EE 306 230KV TRANSMISSION LINE TRIP NONE NONE 3.1.2 (3)
LTP-MA-399 RM 399 MSL RAD MONITOR FAILS UPSCALE NONE NONE 3.1.2 (22)
STP-MA-406 CA 406 SRV TAILPIPE RUPTURE NONE NONE 3.1.2 (23)
STP-MA-411 ES 411 RCIC FAIL TO AUTO START NONE NONE 3.1.2 (17) & (22)
STP-MA-419 DG 419 DG DIFFERENTIAL FAULT NONE NONE 3.1.2 (3)c STP-MA-423 CW 423 CW SCREEN HI DELTA P NONE 1-60 min 3.1.2 (5)
STP-MA-424 RH 424 RHR SUCTION STRAINER CLOGGING 50-80% 0-60 min 3.1.2 (7) & (23)
)
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ATTACHMENT 5 cont.
VI. Y,ALFUNCTIONS - YEAR THPEE (3)
Malf Severity Test Sys Hum. Description Severity Rate ANSI /ANS 3.5 Ref.
==
STP-MA-006 ES 274 RCIC STEAM BREAK - SOUTH RHR NONE NONE 3.1.2 (1) (b) & (c)
STP-MA-011 ES 161 SRV B21-F013E SETPT DRIFT LOW NONE NONE 3.1.2 (1) (d)
STP-MA-017 Al 368 PNEUMATIC LEAK IN THE DRYWELL 0-100 cfm 0-60 min. 3.1.2 (2)
STP-MA-018 EE 305 LOSS OF OFF-SITE POWER NONE NONE 3.1.2 (3)a STP-MA-022 DG 334 LOSS OF SUBSTATION E7 NONE NONE 3.1.2 (3)b STP-MA-024 DG 330 DG #3 GOVERNOR FAILURE LOW NONE NONE 3.1.2 (3)c & (22)
STP MA-028 Eg 395 INDIVIDUAL BUS FAILURES (PARTIAL) NONE NONE 3.1.2 (3)d STP-MA-033 EE 336 LOSS OF 250V DC BUS A NONE NONE 3.1.2 (3)e
'STP-MA-037 RC 126 RECRC PMP SHAFT SEIZURE NONE NONE 3.1.2 (4)
STP-MA-040 CW 248 CONV SW HDR RUPTURE 0-100% 0-60 min. 3.1.2 (6)
STP-MA-045 MS 173 EXH HOOD SPR VLV FAILS CLOSED FIXED 5-50 min. 3.1.2 (8)
STP-MA-046 CW 249 RBCCW PUMP SUCT HDR RUPTURE 0-100% 0-60 min. 3.1.2 (6)
STP-MA-059 CN 324 LOSS OF SJAE NONE NONE 3.1.2 (5)
STP-MA-064 CF 203 CONDENSATE PUMP LOCKED ROTOR NONE NONE 3.1.2 (9)
STP-MA-073 CF 224 RFP 2B TURBINE OVERSPEED NONE NONE 3.1.2 (9)
STP-MA-080 CF 239 RFP MIN FLOW VLV FAILS OPEN NONE NONE 3.1.2 (9)
STP-MA-081 ZZ 234,261,267 LOSS OF ALL FEEDWATER-NORMAL AND EM NONE NONE 3.1.2 (10)
STP-MA-082 RP 107 RPS CHANNEL A FAILURE NONE NONE 3.1.2 (11)
STP MA*005 RD 012 STUCK CONTROL ROD NONE NONE 3.1.2 (12)a STP MA-089 RD 031 CONTROL ROD FAST INSERTION DRIFT NONE NONE 3.1.2 (12) c STP-MA-095 RD 042 ROD BLOCK MONITOR A FAILS DNSCL NONE NONE 3.1.2 (13) & (22)
STP-MA-098 NB 143 FUEL FAILURE 0-100% 0-60 min. 3.1.2 (14)
STP-MA-101 ES 259 CS VALVE F005 FAILS TO OPEN NONE NONE 3.1.2 (17)
STP-MA-106 CF 225 FW HTR #5 OUTLET LINE RUPTURE 0-100% 0-60 min. 3.1.2 (20)
STP-MA-ill NI 048 SRM FAILS AS IS NONE NONE 3.1.2 (21)
STP-MA-113 NI 061 IRM FAILS LO NONE NONE 3.1.2 (21) & (22)
STP-MA-116 NI 077 APRM FAILS LO NONE NONE 3.1.2 (21) & (22)
STP-MA-121 NI 098 LPRM ERRATIC OPERATION NONE NONE 3.1.2 (21)
STP-MA-125 NI 105 APRM C INCONSISTENT WITH OTHERS NONE NONE 3.1.2 (21)
STP MA-133 RH 296 S/D CLNG HI RX PRESS PERM FAILS NONE NONE 3.1.2 (23) & (22)
STP-MA-13B MS 168 EHC PRESSURE REGULATOR OSCILLATION NONE NONE 3.1.2 (25) & (22)
STP-MA-139 MS 180 TURB BPV #1 FAILS OPEN NONE NONE 3.1.2 (25)
STP-MA-143 CA 350 DW CLG FAN DAMPER FAILURE NONE NONE 3.1,2 (8)
STP-MA-153 RC 123 RECIRC PUMP SEAL #2 FAILS 0-100% 0-60 min. 3.1.2 (1) (b) & (c)
STP MA-164 RM 164 MSL RAD MONITOR FAILS DOWNSCALE NONE NONE 3.1.2 (22)
STP- MA- 18 2 MS 182 LOSS OF TURBINE BEARING OIL PRESSURE NONE NONE 3.1.2 (15)
STP-MA-232 RW 232 RWCU BREAK IN RETURN LINE 20' 0-100% 0-60 min. 3.1.2 (1) (b)
STP-MA-250 RW 250 RBCCW HIGH RADIATION NONE NONE 3.1.2 (8)
STP-MA-251 CW 251 RBCCW HX/SW TUBE LEAK NONE NONE 3.1.2 (8)
STP-MA-328 NB 328 SMALL RECIRC SUCTION LINE RUPTURE 0-100% 0-60 min. 3.1.2 (1) (b) & (c)
STP-MA-362 RM 362 RX BLDG VENT MONITOR FAILS UPSCALE NONE NONE 3.1.2 (22)
STP-MA-405 CA 405 BROKEN DOWNCOMER QUADRANT 1 0-100% 0-60 min. 3.1.2 (23)
STP-MA-412 ES 412 CORE SPRAY FAILURE TO AUTO START NONE NONE 3.1.2 (17) & (22)
STP-MA-418 DG 418 DG AVR FAILS LOW NONE NONE 3.1.2 (3)c & (22)
STP-MA-422 NB 422 ISOLATION OF CONDENSING POT D004B NONE NONE 3.1.2 (22)
?
( . *4 i ENCLOSURE .3 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2
. l DOCKET NOS. 50-325 AND 50-324 i LICENSE NOS. DPR-71 AND DPR-62 CERTIFICATION OF SIMULATOR FACILITIES LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Carolina Power & Light l
' Company (CP&L) in this document. Any other actions discussed in the submittal represent !
- ' intended or planned actions by CP&L. They are described to the NRC for the NRCs information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs at the Brunswick Nuclear Plant of any questions regarding this document or any associated regulatory commitments. j 1
Commitment (s) Committed a
date or !
outage t Complete annual test requirements for 1995,1996,1997,1998 in accordance with the certification plan. I 12/31/98 l
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3
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