ML20206P536
| ML20206P536 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/05/1999 |
| From: | White R DUKE POWER CO. |
| To: | NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9901120144 | |
| Download: ML20206P536 (15) | |
Text
..
A LYk? $$c5, hr L 8 kg, McGuire Nuclear Station a rw % o,,
12700 llagers Ferry Road Huntersville. NC 28078-9340 (704) 875-4100 January 5,1999 TO:
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Document Control Washington, D. C. 20555 FROM:
Ronnie B. White, Jr.
Manager, McGuire Training
SUBJECT:
McGuire Simulator Four Year Report This report is submitted as the Four Year Repert for the McGuire Nuclear Station Unit One Simulator in accordance with 10CFR55.45 b.5.ii and b.5.vi. Form 474's are included for each McGuire Unit. The required information is included in the form of attachments to this letter as follows:
ATTACHMENT 1.0 1995-1998 SIMULATOR TEST FAILURES ATTACHMENT 2.0 1995-1998 ANNUAL SIMULATOR TESTS AND COMPLETION DATES ATTACHMENT 3.0 1999-2000 FOUR YEAR TESTING SCHEDULE If there are any questions concerning this report, please feel free to call or write:
Terry S. Tessnear Sr. Technical Specialist, McGuire Simulator Support McGuire Nuclear Station 13339 Hagers Ferry Road Huntersville, N. C. 28078 Phone: (704) 875-5033 Thank you for your attention in this matter.
_ f. &
- /
Ronnie B. White, Jr.
TST:nte y
Cc:
H.B. Barron E.M. Geddie j
A.S. Bhatnagar C.A. Orton D.J. Taylor Frank Collins (NRC) 9901120144 990105 PDR ADOCK 05000369 P
PDR _
l l
NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0Y OM8: No. 31504138 EXPT;,ES:08/31/2001 (8 880 Estmated borden per response to comply we this mandat mformabon coincnon request 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> The mformanon a used to certdy a s.mo tion facelety Forward Comments regardmg burden esbmate k) the Records Mana ement Branch (T4 F33). U S SIMULATION FACILITY CERTIFICATION
%"E*L"s */"'*"W*"0",'W"@""JCa%n'eL Bk',3*s*aan~M e
+
2rXC3 N sn con collechon does not display a cunency valed OMB control number, the NR.C m,.ay not.c.onduct or sponsor, and a person a not requered to respond to, bie in% rio com.ce INSTLUCTIONS: The form is to be flied for inabal certmcahon, racertMcanon (if sewsred), and for any change b a simulanon facsisty performance tesong pian made after escal submittal of such a pian p,
no me eno.nwoon.nd cn.a me.w,wn.. hos to md ais reason fo, soi-tai FACluTY DOCKET NUMBER McGuire Nuclear Station Unit One 64-369 LEENSEE DATE Duke Power Company 01/05/99 The IG to cerbfy that i The atee named facehty licensee a usmg a samulebon facelsty consonng solely of a planteeterenced sunulator that meets the requirements of 10 CFR 55 45 2 Documentabon a eelable lor NRC renew an accordance wo 10 CFR 55 45(b) 3 TNs semulabon facsMy meets the guadance contamed in ANSIIANS 3 51965 or ANSVANS 3 S1993, as endorsed by NRC Regulatory Guide 1149 N there a e any EXCEPTIONS to the certifbcanon of the stem, CHECK HERE [ ] and desenbe fully on addebonal pages as necessary NJ.ME (a other denbfcabon) AND LOCATION OF SIMULATION FACILITY.
McGuire Nuclear Power Plant Operator Training Simulator at MCGuire Training Center 133339 Hagers Ferry Road Huntersville, N.
C.
28078 SsMULATION FACluTY PERFORMANCE TEST ABSTRACTS ATTACHED. (Forpehmence aests cornf.csed > me pened andmg we me dele of mse carefce6on)
DEScr.lPTION OF PERFORMANCE TESTING COMPLETED. Mitmen addebanetpages es necessary and den 64 me dern descnpean bemp conenued)
SIMULATION FACLITY PERFORMANCE TESTING SCHEDULE ATTACHED. (For me condtzf of epsrowneWy 25 percent of pehmence tests peryear b me hatoerpenod commenceg we me dele of mse carbicaban )
DESCRIPTION OF PERFORMANCE TESTING TO BE CONDUCTED (AttacA eddibcmetpages as necessa y and den 64 me elem descriphon besng con 6nued)
PERFORMANCE TESTING PLAN CHANGE (For any modofcehon 80 e perkmence heshng pJen submrtled on a prevoous certsticebon)
MSCTJPTION OF PERT:ORMANCE TESTING PLAN CHANGE Mirach addihorulpages as necessay and den 64 me dem descripton besng con 6nued)
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LECERTIFsCATION (Descnbe carecbve echons leken, ettech resu ts of cornpJesed pakmence les6ng m eccordance we 10 CFR SS dS(b)(S)(v)
X en.cn oddafonespages as necessay and noney me nem desenpson se,ng canonued) l Any falso statement or omissen m thes document, meludmg attachments, may be sub oct to cMI and enmmal sanchons I certdy under penalty of pequry that the mformaton m the document and l
attachments a vue and correct SIGNATURE - AUTHORIZED REPRESENTATIVE TITLE DATE
- )dOMC,[
Manager, MCGuire Training 01/05/99 l
In accordance we to CFR 55 5. Communcaoona, the form shall be submatted to the NRC as follows BY Mall ADORESSED TO DIRECTOR. OFFICE OF NUCLEAR REACTOR REGULATION SY DELNERY IN PERSON ONE WNITE FLINT NORTH U.S. NUCLEAR REQUL.ATORY COMMISSION TO THE NRC OFFICE A7.
11555 ROCKylLLE PlKE WASHINGTON, DC 20SS5M1 ROCMVILLE, MO NRC FORM 474 (&1996)
PRINTED ON RECYCLED PAPER
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i-I NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROYED 1Y OMB. NO. 31504138 EX7CES. 08/31/2001 IO' *)
Esnmated burden per response ta comply with trus manda mformanon collecton request 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> The mformanon is used to cerufy a sarnu tion facey Forward Comments regaroing burden eshmate to the Records M ment Branch (T4 F33), V $
i l
SIMULATION FACILITY CERTIFICATION 2' "7""""(3TJAI"a*n"TO.Simeni.ed Bdon*s*d'A*22 L
i 20503 e an anon collecnon does not despier a currently valid OMB contros number.
l the NRC may not conduct or sponsor, and a person es not required to respond to. the m*armetion coem INSTRUCTIONS: The form e to be Blod for eribal certficaban, recerbhcanon (# requred), and har any change to a simulabon facildy pe#,'ormance tesbng plan made after meal submittal of such a otan Panvio, the h9towmo en6cmedon and checli the sporopnete bow to indica'e reason be submeal FACILfTY DOCKET NUMBER McGuire Nuclear Station Unit Two so 370 UCENSEE DATE Duke Power Company 01/05/99 The es to cerufy that i The above named facdsty bcensee is usmg a simulaban facdity consistmo solely of a piant-referenced tumulator that meets the requirements of 10 CFR 55 45.
2 Docuenentabon as available for NPO review m accordance with 10 CFR 55 45(b).
3 TNs simutaban facddy meets the guidance contained m ANSVANS 3 51955 or ANSt/ANS 3 51903, as endorsed by NRC Regulatory Guide 1149 N there are any EXCEPTIONS to the certshcanon of this stem, CHECK HERE [ ] and desenbe fully on additional pages as necessary NAME ter omer mientdicebon) AND LOCATION OF SIMULATION FACluTY.
McGuire Nuclear Power Plant Operator Training Simulator at McGuire Training Center 133339 Hagers Ferry Road Huntersville, N.
C.
28078 SIMULAT10N FACluTY PERFORMANCE TEST ABSTRACTS ATTACHED (For perfbrmance aests conducted m me pened andmg wsm me dele of rus certencateri)
DESCR;PT10N OF PERFORMANCE TESTING COMPLETED (Attach oddebonelpeges as necessary and odontr& ne nom descrophon beme conhnued )
SIMULAT10N F ACluTY PERFORMANCE TESTING SCHEDULE ATTACHED (Fbr me conduct of apprtmsmeholy 25 percent ofperibrmance aests per year Ibr me keteer panod commenceg anh me date of mes certencebon)
DESCRtPT)ON OF PERFORMANCE TEST 1NG TO BE CONDUCTED (Altech eddobonelpages es necessary and nienkfy be noen descriptoon bonne conhnved)
PERFORMANCE TESTING PLAN CHANGE. (For any eiaddice6cn k2 e pe1brmance aestng pJan submined on a prevsous certificecon)
DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (Anoch addrbonalpages as necessary and nienkfy me nom tiescr1 phon bonng conbnved)
RECERTIFICAT10N (Describe correcbve acfsons askett anoch results of compJeded parkrmance lesbag in acccrtience wrm 50 CFR 55 #5(b)(5)(V)
X (Altech eddrhonetpages es necessary and aienky the Rom descripton beeng conbaued)
Any false statement or omass.on m this document, meludmg attachments, may be subject to cMI and enmmel sanctons I certify under penalty of perjury that the mformabon m this document and attachments e true and correct SIGNATURE - AUTHOR 2ED REPRESENTATIVE TITLE DATE
)8 p
Manager, MCGuire Training 01/05/99 in accordance weth 10 CFR 55 5, Cr.-
Z,s. this form shall be submitted to the NRC as follows 9Y Mall ADDRESSED TO DIRECTOR, OFFICE OF NUCLEAR REACTOR REQULATION BY DELIVERY IN PERSON ONE WHITE FUNT NORTH U.S. NUCLEAR REQULATORf COMMISSION TO THE NRC OFFCE AT.
11555 ROCKYILLE PIKE WASHINGTON, DC 20S$54001 ROCKVILLE, MO NRC FORM 474 @1998)
PRINTED ON RECYCLED PAPER ~
,,,_m J2 b
l ATTACHMENT 1 1995 - 1998 SIMULATOR TEST FAILURES
)
ATTACHMENT 1 1995 -1998 SIMULATOR TEST FAILURES Four Simulator Tests have failed during this report period.
Simulator Work Requests (WR) or Simulator Deficiency Reports (SDR) have been written for each of these to correct the problem associated with them. The only Simulator Test failure that has not been resolved is associated with the computer Real Time Test. This problem cannot be corrected with the current Gould MPX Operating System Running on an RSX Computer.
Simulator Computer / Instructor System Replacement is in progress and is scheduled to be completed / ready for training on 3/15/99.
The new Simulator Computer System will be a PC Based on NT 4.0/
RNI Technologies OpenSim.
YEAR TEST NAME WR / SDR DISCREPANCY DESCRIPTION 1996 Dropped Rod (IRE 6)
CRF-0004 Flux Tilt Effects On Power Range Detectors Was not being shown Correctly.
1997 Steady State Power, EOA-0090 Miscellaneous Parameters Heat Balance Check out of tolerance due to S/G Replacement.
1997 Steady State Power, EOA-0090 Miscellaneous Parameters Critical and Non-out of tolerance due to Critical Parameters S/G Replacement.
Check 1997 Computer Real Time SDR Simulator Duty Cycle Spec Test 9800001 exceeded during peak of LB Loca w/ Blackout Trans-ient.
1998 Computer Real Time SDR Simulator Duty Cycle Spec Test 9800001 exceeded during peak of LB Loca w/ Blackout Trans-ient.
e t
ATTACHMENT 2 1995 - 1998 ANNUAL SIMULATOR TESTS AND COMPLETION DATES l
l
ATTACHMENT 2 1995 ANNUAL SIMULATOR TESTS AND COMPLETION DATES Transients Cygoletion Date 1.
SG Tube Rupture 12/12/95 2.
Large Break Loca 07/25/95 3.
Small Break Loca 10/11/95 4.
Loss Of Offsite Power 11/27/95 5.
Single NC Pump Trip 11/02/95 6.
Loss Of Main Feedwater 11/15/95 7.
Loss Of All Feedwater 10/12/95 8.
Dropped Rod 07/19/95 9.
Load Rejection 07/27/95 10.
Pzr Porv Failure 08/02/95 11.
Reactor Trip 11/02/95 12.
Steam Line Break 11/30/95 13.
Feedwater Line Break 11/30/95 14.
Small Break LOCA/ICC 10/11/95 16.
SG Tube Rupture /SM Porv Failure 12/12/95 Malfunctions 1
1.
Charging Line Break Inside Cont (NV-8) 02/07/95 2.
Pressurizer Porv Failure (NC-3) 02/07/95 3.
D/G Trips On Overspeed (DG-4) 02/08/95 4.
Hotwell Level Control Valve Failure (CM-2) 02/08/95 5.
Feedwater Contain. Isol. Vlv Failure (CF-3) 02/08/95 6.
Uncontrolled Rod Motion (IRE-3) 02/08/95 7.
Variable NC System Activity (CH-1) 02/09/95 8.
Pressurizer Spray Valve Failure (ILE-3) 02/09/95 9.
Power Range Detector Failure (ENB-13) 02/13/95 30.
Failure Of CA Pu.np To Start (CA-4) 03/07/95 Steady State Operation 1.
Steady State Power Drift Test 01/11/95 2.
Steady State Power, Heat Balance Check 05/04/95 3.
Steady State Power, Critical and 05/09/95 Noncritical Parameters Check
. Computer Real Time Test 12/27/95
[.,
ATTACHMENT 2 1996 ANNUAL SIMULATOR TESTS AND COMPLETION DATES L
Transients Completion Date 1.
SG Tube Rupture 08/12/96 2.
Large Break Loca 04/25/96 3.
Small Break Loca 04/25/96 4.
Loss Of Offsite Power 08/12/96 5.
S4.ngle NC Pump Trip 08/13/96 6.
Loss Of Main Feedwater 08/15/96 7.
Loss Of All Feedwater 08/15/96 j
8.
Dropped Rod 09/19/96 9.
Load Rejection 08/13/96 10.
Pzr Porv Failure 08/13/96 11.
Reactor Trip 08/13/96 12.
Steam Line Break 08/20/96 13.
Feedwater Line Break 08/20/96 1
14.
Small Break LOCA/ICC 06/04/96 16.
SG Tube Rupture /SM Porv Failure 09/11/96 Malfunctions 1.
Charging Line Leak Outside Containment (NV9) 02/06/96 2.
Instrument Air Leak (VI1) 02/06/96 3.
Loss Of 6.9KV Switchgear (EP5) 02/07/96 4.
RN System Leak (RN1) 02/07/96 5.
Failure Of Phase A Isolation Signal (ISE3) 02/08/96 6.
Dropped Rod (IRE 6) 02/21/96*
7.
Inadvertent Turbine Trip (DEH1) 02/08/96 8.
NV System Letdown Valves Fail (NV20) 02/12/96 9.
Loss Of Intermediate Range Hi Voltage (ENB9) 02/12/96 10.
Failure Of Automatic Reactor Trip (IPE1) 02/13/96 Steady State Operation 1.
Steady State Power Erift Test 02/01/96 2.
Steady State Power, Heat Balance Check 07/17/96 3.
Steady State Power, Critical and 08/13/96 Noncritical Parameters Check Computer Real Time Test 12/31/96
- - Test Failed l
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-.. -. = _ -. _
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I ATTACHMENT 2 i
1997 ANNUAL SIMULATOR TESTS AND COMPLETION DATES l
Transients-Completion Date j
1.
SG Tube Rupture 07/30/97 2.
Large Break Loca/ Cold Leg 07/29/97 3.
Small Break Loca 07/29/97 4.
Loss Of Offsite Power 07/29/97 l
5.
Single NC Pump Trip 07/30/97 6.
Loss Of Main Feedwater 07/28/97 l
7.
Loss Of All Feedwater 07/30/97 8.
Dropped Rod 07/28/97 l
9.
Load Rejection 07/29/97 10.
Pzr Porv Failure 07/28/97 11.
Reactor Trip 07/29/97 12.
Steam Line Break 07/28/97 13.
Feedwater Line Break 07/28/97 j
14.
Small Break LOCA/ICC 07/30/97 16.
Large Break Loca/ Hot Leg 07/30/97 1
Malfunctions 1.
NC System Leak (NC7) 06/25/97 2.
Blackout (EP1) 06/24/97 3.
NCP Trip (NCP1) 06/25/97 4.
ND HX Outlet Or Bypass Vlv Failure (ND5) 06/25/97 5.
Stuck Rod (IRE 10) 06/24/97 L
6.
Improper Bank Overlap (IRE 14) 06/25/97 l
7.
Exciter Breaker Failure (MG2) 06/25/97 l
8.
Main Steam Header Break (SM9) 06/24/97 l
9.
TREF Failure for Rod Control (IR1) 06/25/97 Steady State Operation l
1.
Steady State Power Drift Test 09/15/97 2.
Steady State Power, Heat Balance Check 10/29/97*
l 3.
Steady State Power, Critical and 10/28/97*
l Noncritical Parameters Check l
. Computer Real Time Test 12/29/97*
- - Test Failed 4
i f
ATTACHMENT 2 1998 ANNUAL SIMULATOR TESTS AND COMPLETION DATES Transients Completion Date 1.
SG Tube Rupture 08/12/98 2.
Large Break Loca/ Cold Leg OE/12/98 3.
Small Break Loca 08/12/98
'4.
Loss Of Offsite Power 08/12/98 5.
Single NC Pump Trip 08/14/98 6.
Loss Of Main Feedwater 08/14/98 7.
Loss Of All Feedwater 08/19/98 8.
Dropped Rod 08/14/98 9.
Load Rejection 08/31/98 10.
Pzr Porv Failure 08/17/98 11.
Reactor Trip 08/17/98 12.
Steam Line Break 08/17/98 13.
Feedwater Line Break 08/18/98 14.
Small Break LOCA/ICC 08/18/98 16.
Large Dreak Loca/ Hot Leg 08/18/98 Malfunctions 1.
Steam Generator Tube Leak (SG-1) 07/22/98 2.
Pressurizer Safety Valve Failure (NC-4) 07/22/98 3.
Loss Of 4160V Bus (EP-8) 07/27/98 4.
Loss Of Condenser Vacuum (MT-3) 09/15/98 5.
Various KC System Valve Failures 07/27/98 6.
RCCA Disconnects At Spider Assembly (IRE-8) 07/28/98 7.
Rods Fail TO Move (IRE-9) 07/28/98 8.
Power Mismatch Unit Failure (IR-2) 07/29/98 9.
Feedline Break Outside Containment 07/29/98 10.
Failure Of NI Pump To Start (NI-1) 07/29/98 Steady State Operation 1.
Steady State Power Drift Test 09/15/98 2.
Steady State Power, Heat Balance Check 01/28/98 3.
Steady State Power, Critical and 01/28/98 Noncritical Parameters Check Computer Real Time Test 11/22/98*
- Test Failed
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l ATTACHMENT 3 i
FOUR YEAR TESTING SCHEDULE i
1999 - 2002 l
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I' o
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.______s-I' l
6
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ATTACHMENT 3 i
ANNUAL SIMULATOR TESTING SCHEDULE YEAR 1999 1
l Transients 1.
SG Tube Rupture 2.
Large Break Loca 3.
Small Break Loca 4.
Single NC Pump Trip 6.
Loss Of Main Feedwater 7.
Loss Of All Feedwater 8.
Dropped Rod 9.
Load Rejection 10.
PZr Porv Failure 11.
12.
Steam Line Break l
13.
Feedwater Line Break l
14.
15.
Small Break 'OCA/ICC
[
16.
SC Tube Rup"
- CM Porv Failure l
l Malfunctions l
1.
Charging Line Leak Inside Containment (NV8) 2.
Pressurizer Porv Failure (NC3) 3.
D/G Trips On Overspeed (DG4) l 4.
Hotwell Level Control Failure (CM2) 5.
Feedwater Containment Isolation Valve Failure (CF3) 6.
Uncontrolled Rod Motion (IRE 3) 7.
Variable NC System Activity (CHl) 8.
Pressurizer Spray Valve Failure (ILE3) i 9.
Power Range Detector Failure (ENB13)
L 10.
Failure Of CA Pump To Start (CA4)
Steady State ~ Operation 1.
Steady State Power Drift Test 2.
Steady State Power, Heat Balance Check 3.
Steady State Power, Critical and Noncritical Parameters Check Computer Real Time Test i
f r
r
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i ATTACIOGENT 3 l
ANNUAL SINULATOR TESTING SCHEDULE YEAR 2000 l
l Transients 1.
SG Tube Rupture 2.
Large Break Loca 3.
Small Break Loca 4.
S.
Single NC Pump Trip 6.
Loss Of Main Feedwater 7.
Loss Of All Feedwater 8.
Dropped Rod
(
9.
Load Rejection 10.
Pzr Porv Failure 11.
Reactor Trip 12.
Steam Line Break 13.
Feedwater Line Break 14.
,l' 15.
Small Break LOCA/ICC l
16.
SG Tube Rupture /SM Porv Failure l
Malfunctions Charging Line Leak Outside Containment (NV9) l t.
l 2.
Instrument Air Leak (VIl) 3.
Loss Of 6.9KV Switchgear (EP5) 4 RN System Leak (RN1)
's.
Failure Of Phase A Isolation Signal (ISE3)
C.
Dropped Rod (IRE 6) 7.-
Inadvertent Turbine Trip (DEHl) 8.
NV System Letdown Valves Fail (NV20) 9.
Loss Of Intermediate Range High Voltage (ENB9) 10.
Failure Of Automatic Reactor Trip (IPE1)
. Steady State Operation l
1.
Steady State Power Drift Test 1
2.
Steady State Power, Heat Balance Chuck 3.
Steady State Power, Critical and Noncritical Parameters Check s
Computer Real Time Test 1
e 4
a 4
C ATTACIDENT 3 j
ANNUAL SIMULATOR TESTING SCHEDULE YEAR 2000
/
Transients 1.
SG Tube Rupture 2.
Large Break Loca 3.
Small Break Loca 4.
Single NC Pump Trip 6.
Loss Of Main Feedwater 7.
Loss Of All Feedwater 8.
Dropped Rod 9.
Load Rejection 10.
Pzr Porv Failure 11.
Reactor Trip 12.
Steam Line Break 13.
Feedwater Line Break i
14.
Small Braak LOCA/ICC l
'16.
SG Tube Rupture /SM Porv Failure l
l i
Malfunctions 1.
Charging Line Leak Outside Containment (NV9)
[_i 2.
Instrument Air Leak (VI1) l 3.
Loss Of 6.9KV Switchgear (EP5) l 4.
RN System Leak (RN1) l S.
Failure Of Phase A Isolation Signal (ISE3) 1 l
6.
Dropped Rod (IRE 6) l 7.
Inadvertent Turbine Trip (DEHl)'
8.
NV System Letdown Valves Fail (NV20) 9.
Loss Of Intermediate Range High Voltage (ENB9) 10.
Failure Of Automatic Reactor Trip (IPEl) t Steady State Operation l
1.
Steady State Power Drift Test 2.
Steady State Power, Heat Balance Check 3.
Steady. State Power, Critical and Noncritical Parameters Check Computer Real Time Test i
L
.. _...... _.. _ __._ _. _. _._ _ _ _ _ _. _... ~ _ _.. _.... _ _ -
ATTACHMENT 3 ANNUAL SIMULATOR TESTING SCHEDULE YEAR 2001 Transients 1
1.
SG Tube Rupture I
2.
Large Break Loca 3.
Small Break Loca 4.
Single NC Pump Trip 6.
Loss Of Main Feedwater 7.
Loss Of All Feedwater 8.
Dropped Rod 9.
Load Rejection 10.
Pzr Porv Failure 11.
Reactor Trip 12.
Steam Line Break 13.
Feedwater Line Break
Small Break LOCA/ICC 16.
SG Tube Rupture /SM Porv Failure Malfunctions 1.
NC System Leak (NC7) 2.
Blackout (EP1) 3.
NCP Trip (NCP1) 4.
ND HX Outlet Or Bypass Valve Failure (ND5) 5.
Stuck Rod (IRE 10) 6.
Improper Bank Overlap (IRE 14) 7.
Exciter Breaker Failure (MG2) 8.
Main Steam Header Break (SM9) 9.
TREF Failure - Rod Control (IR1)
Steady State Operation 1.
Steady State Power Drift Test 2.
Steady State Power, Heat Balance Check 3.
Steady State Power, Critical and Noncritical Parameters Check Computer Real Time Test
_ _ -... _ ~. _ _ _... _,
ATTACHNENT 3 ANNUAL SINULATOR TESTING SCHEDULE YEAR 2002 Transients 1.
SG Tube Rupture 2.
Large Break Loca 3.
Small Break Loca 4.
Less Of Offsite Power 5.
Single NC Pump Trip 6.
Loss Of Main Feedwater 7.
Loss Of All Feedwater 8.
Dropped Rod i
9.
Load Rejection i
10.
Pzr Porv Failure l
11.
Reactor Trip 12.
Steam Line Break 13.
Feedwater Line Break 14.
15.
Small Break LOCA/ICC 16.
SG Tube Rupture /SM Porv Failure l
Malfunctions j
1.
Steam Generator Tube Leak (SG1) 2.
Pressurizer Safety Valve Failure (NC4) 3.
Loss Of 4160V Bus (EP8) 4.
Loss Of Condenser Vacuum (MT3) 5.
Various KC System Valve Failures (KC2)
J 6.
RCCA Disconnects At Spider Assembly (IRE 8) 7.
Rods Fail To Move (IRE 9) 8.
Power Mismatch Unit Failure (IR2) 9.
Feedline Break Outside Containment (CF5) 10.
Failure Of NI Pump To Start (NI1) l i
Steady State Operation l
1.
Steady State Power Drift Test l
2.
Steady State Power, Heat Balance Check l
3.
Steady State Power, Critical and l
Noncritical Parameters Check Computer Real Time Test 4
i i
J
,