ML20248B865
| ML20248B865 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/15/1998 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20248B863 | List: |
| References | |
| NUDOCS 9806020006 | |
| Download: ML20248B865 (126) | |
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Table of Contents Section General Statement 1
Unit 2 Form 474 2
- Exceptions
- Software and Hardware Deficiencies 3
- Abstract Summary and Panel Members
- AnnualTests Abstracts
- Year 1 Tests Abstracts
- Year 2 Tests Abstrcets
- Year 3 Tests Abstracts
- Year 4 Tests Abstracts 4
- Peformance Test Schedule
- Changes Since Last Report 5
Unit 1 Form 474 6
- Clarification Statement
- Exceptions l
- Hardware and Environmental Differences
- Operating Procedure Differences L
- Technical Specification Differences 6 020006 980526 DR ADOCK 0 1
Plant E. I. Hatch Docket # 50-321 & 50-366 Southern Nuclear Operating Company The analysis of documents referenced in this submittal was completed prior to 'he date of submittal as listed en NRC Form 474 for each unit. The revision number listed for these documents in the attachments to the submittal and in the documentation retained I
by GPC in support of this submittal are the revision levels used in the Certifications process.
As procedure revisions Technical Specification ammendments, and revisions to other documents used in the certification process occur, they will be reviewed in accordance with the Plant E. I.11atch training department procedures (including the l
Simulator Certification Program) to determine any required action.
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f NRC FORM 474 U.S. NUCLEAR REGULATORY CORAINSSION APPRevue sY case: estL stesetas expeRes: ear:1me Esansass tween per mapanse to campsy won sus m.esamy reamseen aan +an ruwest 120 huws. This scannemen a uses to sunny a esmeseeissessy. Formero commente *& "'u s N esernen to sie trearmenen ons R.esonas t tween SIMULATION FACILITY CERTIFICATION Co"m'." '*= x em Run.aon Pn m (31sootm On.e a Man.e.ne,.
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h one for miy onenOs to e esmdurwi tendsy panormanos teseme pun mado ener mesd euemmai or m.en s. m.,r w FACILITY DOCICET NUMBER E.I. HATCH, Unit 2, Nuclear Power Station so-366 uCENSEE DATE Southern Nuclear Operating Company 5-15-98 Tha m m e wy nt t the move names secety keenese e uenig e annuisson seemey consionne newy or a piensenreness er uisier met meses the requsemeres or 10 CFR 66 46.
- 2. Documeraseen g evadeels for NRC review m encoreence wah 10 CFR 56 46(b) 3 The osnuishen Isoihty meses the pumannos contesned in ANSIIANS 3 6-tee 6 or ANSDANS 3 6-10sJ, se enskueed Isy NRC Repdatory Ouuto 1140 n e e.o y EmCarfiaNs = = os,wc.on a ne =rn CN Cx Nem ( }
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y NAME (or omer assnescason) AND LOCATION OF StauLATION FACluTY.
E.I. Hatch Simulator US 1 North Approx 12 miles North of Baxley, Ga Zip 31515 81h4ULATION FACluTY PERFOR*4ANCE TEST ABSTRACTS ATTACHED (For meermance feet conshdada me ponod eneng use lhe cWe of #bs cere#cason)
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DESCRIPTION OF PERFORMANCE TESTING COMPLETED. (Assen amesoner pges as nessenery ans sesmaqr she som sesenpean assar consnuse)
See Attachment 2: Performance Test Completed SchautATION FACILl" PERFORMANCE TESTING SCHEDULE ATTACHED (For me conmuer of appsommessly 28* ef asntweense asses per yearihr the ibwyear pened g
commenemy wwn she dose of pws comeceson.)
DESCRIPTION OF PERFORIAANCE TESTING TO BE CONDUCTED (Asoca assooner pepse es asonesary one assnefy she mom.sonpean aamp conomme)
See Attachment 3: Performance Test Schedule PERFOftMANCE TESTING PLAN CHANGE. (For any snocMeason lo a pantrmance essenp pien subamenW on a pomous ce*Aceton)
DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (Asoch seasoner pepse as neessesty anc M the dem anscnget, semp consnued)
See Attachment 3: Changes Since Last Report itECERTIFICATION (Desome conusene oceans ashen, aessa resems of casussent poennenos sneeng m.- sum 10 CPR 56 48(b)(5)(v)
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__________N OC Sese64eM EXCEPTIONS 05/15/98 Plant E. I. Ilatch, Unit 2 Docket # 54-366 Southern Nuclear Operating Company b
Pl:nt E. I. Hitch, Unit 2 Docket # $0-366 Southern Nuclear Operating Company 05/15/98 LISTING OF CERTIFICATION EXCEPTIONS I
NO.
TESTS ANSI SPEC TITLE OF EXCEPTION 001 05-01 3.1.2(1)(a)
Loss of Coolant; Si nificant EWE Steam Generator Leaks F
002 05-28 3.1.2(18)
Failure of Reactor Coolant Pressure and Volume Control
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Systems (PWR) j 003 06-07 3.1.1 (7)
Startup, Shutdown and Power Operations with Less Than Full Reactor Coolant Flow 004 06-12 3.1.1(9c)
Core Performance; Reactivity Coefficient Measurements 005 06-13 3.1.1 (9d)
Core Performance; Control Rod Worth Using Permanently Installed Instrumentation 006 06-11 3.1.1 (9b)
Core Performance; Determination of Shutdown Margin 007 07-XX B. l.2.1,2,3 Appendix B: Transient Performance l
008 ALL 3.3.1 Degree of Panel Simulation 009 05-15 3.1.2 (5)
Loss of Condenser Level Control 012 06-15,16, App.B Bl.1 Steady State Performance and 17 i
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PLANT E. I. IIATCil SIMULATOR CERT;FICATION PLAN PAGE 2 TITL E:
CERTIFICATION EXCEI'TIONS REVISION I PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICitTER DATE:01-31-89 l
APPROVED BY: R.S. GR ANTilAM OPERATOR TR AINING SUPERVISOR DATE:12-20-89 EXCEI' TION NUMBER: _QQ1 ANSI SPECIFICATION: 3.1.2(1)(a) TITLE: Loss of Coolant; Significant EWR Steam Generator Leaks (05-01)
EXCElrrION:
Unit One and Unit Two GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant flatch simulator certification process.
JUSTIFICATION:
Plant flatch is a General Electric Boiling Water Reactor (BWR). This requirement is not applicable to the flatch simulator.
PLANT E. I. IIATCil SIMULATOR CERTIFICATION PLAN PAGE 3 TITLE:
CERTIFICATION EXCEPTIONS REVISION 1__
PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICitTER DATE:01-31-89 APPROVED BY: R.S. GR ANTilAM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: 002 ANSISPECIFICATION: 3.1.2(18) TITLE: Failure of Reactor Coolant Pressure and Volume Control Systems (E)y.8)(05-28)
EXCEirTION; Unit One and Unit Two GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant Hatch simulator certification process.
JUSTIFICATION:
Plant Hatch is a General Electric Boiling Water Reactor (BWR). This requirement is not applicable to the flatch simulator.
PLANT E. I. IIATCil SIMULATOR CERTIFICATION PLAN PAGE 4 TITLE:
CERTIFICATION EXCEPTIONS REVISION 1 PERFORMED BY: RUTAN DATE:01-31-89 RIIVIEWED BY: J. RICIITER DATE:01-31-89 APPROVED BY: R.S. GRANTilAM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: 003 ANSI SPECIFICATION: 3.1.1 (7) TITLE: Startup, Shutdown and Power Operations with Less Than Full Reactor Coolant Flow (06-07)
EXCEPTION:
Unit One and Unit Two GPC takes exception to this requirement. This requirement is satisfied by performance of ANSI specifications 3.1.1 (1), (2), (8a) and (8b); ther: fore, this test will not be performed as a separate test.
JUSTIFICATION _;.
Plant liatch is a General Electric Boiling Water Reactor (BWR-4) and can only startup and shutdown with less than full reactor coolant flow. Performance of tests 06-01,06-02,06-08 and 06 09 satisfy the above mentioned ANSI 3.1.1 specifications and will be performed in lieu of this requirement.
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PLANT E.1. IIATCil SIMULATOR CERTIFICATION PLAN PAGE 5 TITLE:
CERTIFICATION EXCEFTIONS REVISION 1 PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICHTER DATE:01-31-89
' APPROVED BY: R.S. GRANTIIAM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 l
EXCEPTION NUMBER: 004 g
ANSI SPECIFICATION: 3.1.1 (9c) TITLE: Core Performance; Reactivity Coefficient Measurements (06-12)
EXCEPTIOli Unit One and Unit Two GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant I!atch simulator certification process.
JilSTIFICATION:
Plant Hatch personnel do not perform this type of testing on the plant nor in the simulator; therefore, this test is considered to be not applicable M Plant flat < h.
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PLANT E.1. IlATCil SIMULATOR CERTIFICATION PLAN PAGE 6 TITLE:
CERTIFICATION EXCEL'TIONS REVISION 1 PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICilTER DATE:01-31-89 APPROVED BY: R.S. GR ANTil AM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: 005 ANSISPECIFICATION: 3.1.1(9d) TITLE: Core Performance; Control Rod Worth Using Permanently Installed Instrumentation (06-13)
EXCEPTION, Unit One and Unit Two GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant flatch simulator certification process.
JUSTIFICATION:
Plant flatch personnel do not perform this type of testing on the plant nor in the simulator; therefore, this test is considered to be not applicable to Plant flatch.
PLANT E.1.11ATCli SIMULATOR CERTIFICATION PLAN PAGE 7 TITLE:
CERTIFICATION EXCEL'TIONS REVISION _1 PERFORMED BY: RUTAN DATE:(1)-3189 REVIEWED BY: J. RICitTER DATE:01-31-89 APPROVED BY: R.S.GRANTilAM OPERATOR TRAINING SUPERV s0R DATE:12-20-89 EXCEPTION NUMBER: _QQ6 ANSI SPECIFICATION: 3.1.1 (910 TITLE: Core Performance; Determination of Shutdown Margin (06-11) i liXCEPTION:
Unit One and Unit Two GPC takes exception to this requirement. There is no Performance Test which will be performed as part of the Plant 11atch simulator certification process.
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JUSTIFICATION:
Reactor Engineering performs the Shutdown Margin Determination at the time ofinitial core criticality by mean of a "In-Sequence Criticality Verification". Reactor Engineering personnel do not utilize the simulator to train on Shutdown Margin Determination; therefore, this test is considered to be not applicable to Plant l
Ilatch.
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PLANT E.1. IIATCli SIMULATOR CERTIFICATION PLAN PAGE 8 TITLE:
CERTIFICATION EXCEfrrlONS REVISION 1 PERFORMED BY: RUTAN DATE:91-31-89 REVIEWED BY: J. RIC11TER DATE:01-31-89 APPROVED BY: R.S. GR ANTil AM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: Q01 ANSI SPECIFICATION: B.1.2.1.2.3 TITLE: Appendix B: Transient Performance (07 XX)
EXCEPTION _;
Unit One and Unit Two This section of Appendix B requires that all Appendix B listed transient tests be recorded with a resolution of 0.5 second or less. GPC takes exception to this requirement of recording at 0.5 second criteria. All transient tests were recorded at 1.0 second intervals.
JUSTIFICATION:
Current data recording capabilities meet the requirement of Section 4.4, Monitoring Capability, of the standard. GPC's recording program has the ability to record at 0.5 second intervals but the plant reference data recording program (Safety Parameter Display System) utilizcs a 1.0 second recording interval. GPC has determined that to better compare plant reference data to simulator response the 1.0 second recording interval was warranted for the following reasons:
1.
System dynamic response time for most parameters is approximately equal to one second. Plant recorders have a typical response time interval of one to five seconds.
2.
System response items that require less than one secorid intervals are logical items (i.e.,
annunciators, setpoint actuations, etc.) that were observed during performance testing. These items are not a part of the plotled information.
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PLANT E. I. II ATCli SIM ULATOR CERTIFICATION PLAN PAGE 9 TITLE:
CERTIFICATION EXCEirrIONS REVISION 1 PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICitTER DATE:01-31-89 APPROVED BY: R.S. GR ANTil AM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: 008 ANSI SPECIFICATION: 3.2.1 TITLE: Degree of Panel Simulation EXCEPTION:
Unit One and Unit Two This section requires that the simulator shall contain sufficient operational panels to provide the control, instrumentation, alarms, and other man-machine interfaces to conduct the normal plant evolutions of 3.1.1 and respond to the malfunctions of 3.1.2. GPC takes exception to this requirement for control room panel features:
PANEL (S) DESCRIITTION OF CONTROL ROOM PANEL FEATURE (REMOTE FUNC. NO.)
P609P611 MSIV Low Vacuum Trip Bypass switches 2A71-S34A,B,C,D (#134)
P662 Condensate Booster Pump Minimum Flow Control Valve Controller (#151)
P662 Reactor Feedwater Pump "A" Minimum Flow Control Valve Controller (#137)
P662 Reactor Feedwater Pump "B" Minimum Flow Control Valve Controller (#200)
P663 EllC Cabinet 400 liz and Electrical Malfunction reset switch (#144)
P621 RCIC valve F022 (Test line to CST) automatic closure bypass link AA-14 (# 235)
P609P611 Reactor Recire. System RPT Breaker Trip Bypass switches (#171,172)
P609P611 Main Turbine Control Valve Testing jumpers (#173 thru 176)
P609P611 Main Turbine Stop Valve Testing jumpers (#258 thru 269)
JUSTIFICATION:
GPC considers the above listed hardware exceptions to be warranted due to the following reasons:
O These panels are not located in the simulator since they are not used frequently enough by the control rcom operator in the course of plant operation tojustify the additional cost to the simulator. On-i the-Job training is considered to be adequate for these items.
0 Each of these panel features are software simulated and controlled by the simulator instructor via remote function operation.
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PLANT E.1. HATCH S!!'ULATOR CERTIFICATION PLAN PAGE 10 TITLE:
CERTIFICATION EXCEPTIONS REVISION 1 PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICHTER DATE:01-31-89 APPROVED BY: R.S. GR ANTHAM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEL' TION NUMBER: (K)9 ANSI SPECIFICATION: 3.1.2 (5) TITLE: Loss of Condenser Vacuum including Ims of Condenser level Control EXCEPTION:
Unit One and Unit Two GPC takes exception to this requirement only with regard to the Loss of Condenser Level Control portion. A Loss of Condenser Level Control test will not be performed as part of the Plant Hatch simulator certification process.
l JUSTIFICATION:
l A failure of the condenser hotwell level control system transient would be slow in developing and would j
cause no major changes in associated plant critical parameters without ample warning and in sufficient time to l
allow for malfunction correction prior to any major plant transient occurring.
There are no JTA tasks selected for training in the simulator associated with condenser hotwell level control system malfunctions; therefore, the 1.oss of Condenser level Control portion of this specification is considered not applicable to Plant Hatch.
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PLANT E.1. IIATCil SIMULATOR CERTIFICATION PLAN PAGE 13 TITLE:
CERTIFICATION EXCEfrTIONS REVISION 1 PERFORMED BY: RUTAN DATE:Qh3h89 REVIEWED BY: J. RICHTER DATE:PI-31-89 APPROVED BY: R.S. GR ANTH AM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: 1 12 ANSI SPECIFICATION: App.B Bl.1 TITLE: Steady State Performance EXCEPTION:
Unit One and Unit Two Appendix B of the Standard requires Reactor Water Cleanup return flow to be a recorded parameter for steady state performance of a minimum of three points over the power range. GPC takes exception to this requirement to the extent there is no Performance Test with a recorded Reactor Water Cleanup return flow as part of the Plant Hatch simulator certification process.
s JUSTIFICATION:
Reactor Water Cleanup return flow is not a parameter that is monitored in the Reference Plant Control Room.
Plant E. I. Ilatch, Unit 2 Docket # 50-366 Southern Nuclear Operating Company 05/15/98 Software and hardware deficiencies noted during the Control Room Environment review and during performance of ANSI 3.1.1 and 3.1.2 testing are listed below. Corrective action for each deficiency is to modify the simulator as necessary to meet the ANSI 3.5 acceptance criteria. Projected dates of completion for each of the deficiencies is also listed below by its Simulator Change Request (SCR) number.
SCR Anticipated Number Completion Software Discrepancies 9606002 12/98 Fission Products lodine, Particulate, and Noble Gas monitors are not modeled 9805002 12/98 Dual Recire pump trip results in a full and immediate reactor scram 9805003 12/98 Main turbine lube oil system controller failure does not trip turbine
Pl:nt F. I. Ilitch, Unit 2 Docket # 50-366 Southern Nuclear Operating Company 05/15/98 ABSTRACTS The Performance Test Lists attached with this submittal provide a cross reference between the title of the performance test, the test number assigned by Georgia Power, and the specific ANSI /ANS 3.5 requirement the test addresses. The Performance Test Abstracts included in this attachment provide a description of the specific tests performed to show compliance with ANSI /ANS 3.5 - 1985 and Regulatory Guide 1.149.
The simulator malfunctions tested for certification are listed on the Performance Test Abstracts.
Malfunctions listed as tested at a particular severity are variable severity malfunctions and specify the severity used for the test. The range of severity available for all variable malfunctions is I to 100 percent. The exact parametric value (e.g.,100 pm) of the tested severity is also listed in the abstract.
F The variable severity malfunctions will also have a specified ramp rate used in the test. The ramp rate is the insertion rate (rate of increase in severity) associated with a variable severity malfunction. The maximum ramp rate available is 1,000 percent per minute.
The baseline data used in the evaluation of simulator response to the test is specified on the abstract. Items typically used for comparison include the Final Safety Analysis Report (FSAR), Reference Plant strip charts, and Safety Parameter Display System (SPDS) tapes. Additionally, an Abnormal Event Analysis was utilized as baseline data for the Unit One evaluation, as applicable. The Abnormal Event Analysis (NEDE - 30156) is a training document developed by the General Electric Company for use in Transient and Accident Analysis traininF. This i
document uses analyses specific to a BWR-4 with steam turbine driven feedwater pumps. These analyses are collected from various sources, including the FSAR, the reload analyses for Plant flatch, the Emergency Procedure I
Guidelines and other related studies. The FSAR data was only used to verify the proper direction of the parameters l
evaluated.
The data collected for each performance test was analyzed by a group ofindividuals knowledgeable of Plant IIntch systems and operations. These individuals are listed on the test abstract as Panel Members and are listed i
below specifying the qualifications of each individual. Differing opinions (if any) expressed by the panel members I
related to the performance of the simulator are also listed on the Performance Test Abstract.
I PANEL MEMBERS LISTED ON TEST ABSTRACTS I
NAMl; POSITION QUALIFICATIONS B. Smith Plant Instructor - Operations Nuclear NRC SRO Instructor Certification (BWR) i Bachelor of Science Nuclear Engineering Technology S. Loesch Senior Engineer i Masters Degree Mechanical Engineering C. Tyre Shift Supervisor SRO License at Plant E.1. Hatch l
E. Jones Plant instructor - Operations Nuclear SRO License at Plant E. I. Ilatch J. Kelley Plant instructor-Operations Nuclear SRO License at Plant E.1. Ilatch l
l PERFORMANCE TESTS COMPLETED 05/ISN8 liant E. I. Ilatch, Unit 2 Docket # 50-366 Southern Nuclear Operating Company l
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WORKSHEET 17-02 PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN PAGE 2 OF 6 W.S. TITLE:
PERFORMANCE TEST SCHEDULE REVISION 1 PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/15/98 APPROVED BY: R.S. GRANTHAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 Annual Operability Test The following operability tests will be conducted annually (Computer Real Time and Simulator Operating Limits Tests and Appendix B - Steady State and Transient Performance Tests):
08-01 Simulator Real Time Test 08-02 Sin.ulator Operating Limits Testing 06-15 Steady State Performance at 25% power 06-16 Steady State Performance at 75% power 06-17 Steady State Performance at 100% rated thermal power and verify stability for 60 minutes 07-01 Transient Performance; Manual scram 07-02 Transient 4*erformance; Simultaneous trip of all feedwater pumps 07-03 Transient Performance; Simultaneous closure of all Main Steam isolation Valves 07-04 Transient Performance; Simultaneous trip of all recirculation pumps 07-05 Transient Performance; Single recirculation pump trip 07-06 Transient Performance; Main turbine trip (from the maximum power level which will not result in an immediate reactor scram) 07-07 Transient Performance; Maximum power ramp (master recire controller in manual) down to approximately 75% and back up to 100%
07-08 Transient Performance; Maximum size reactor coolant system rupture combined with a loss of offsite power 07-09 Transient Performance; Maximum size unisolable main steam line rupture 07-10 Transient Performance; Simultaneous closure of all Main Steam Isolation Valves combined with single stuck open safety / relief valve (inhibit activation of high pressure Emergency Core Cooling Systems)
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L PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
SIMULATOR REAL TIME AND OPERATING LIMITS TEST ABSTRACTS I
PREPARED BY: L Richter DATE: 02/16/98 REVIEWED BY: 1 Richter DATE: 02/16/98 l
SIMULATOR TEST NUMBER: 08-01 TITLE: Simulator Real Time Test ANSI App. A3.1 SECTION A: STEADY STATE REAL TIME TEST Date Tested: 02/16/98 InitialConditions:
Part One - 100% rated power Part Two - 50% rated power Part Three - 25% rated power Evolution Initiator:
At any terminal connected to CCC85A computer start the program " realtime". This program compares model scheduled time to actual model run time. A message is sent to tenninal after five minutes. Message " test is done" is received when results are acceptable. A message "not keeping up with real time" is received when results are not acceptable.
Termination Criteria: Five minutes.
Deficiencies:None Exceptions: None SECTION B: TRANSlENT REAL TIME TEST Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
I Transient Initiator:
l Part One - Malfunction # 87A (Feedwater Pump Trip).
Part Two - Malfunction # 178 (4KV bus 2A fault) and # 179 (4KV bus 2B fault)
Part Three - Malfunction # 161 (Loss of Offsite Power) and # 210 Recirc loop suction break) at 100% severity (DBA LOCA)
Evolution Initiator:
At any terminal connected to CCC85A computer start the program " realtime". This program compares model
. scheduled time to actual model run time. A message is sent to terminal after five minutes. Message " test is done" is received when results are acceptable. A message "not keeping up with real time" is received when results are not acceptable.
l Termination Criteria: Five minutes.
Deficiencies:None Exceptions: None
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PLANI' E. I. IIATCH SIMULATOR CERTIFICATION PLAN TITLE:
SIMULATOR REAL TIME AND OPERATING LIMITS TEST ABSTRACTS PREPARED BY: 1 Richter DATE:02/16/98 REVIEWED BY:1 Richter DATE:02/16/98 SIMULATOR TEST NUMBER: 08-02 TITLE: Simulator Operating Limits Testing ANSI Section 4.3 PART ONE Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient initiator:
Bring Reactor pressure to it's Engineering Limit by any method desired. When Reactor pressure increases to the Engineering Limit (1340 psig), verify the simulator automatically goes into freeze and a message appeau on the computer console. Place the simulator back into the RUN mode and bring reactor pressure above the Model Limit (1425 psig).
Termination Criteria: When Reactor pressure is brought above the Model Limit (1425 psig), the simulator automatically goes into freeze and can not be placed into the RUN mode.
Deficiencies:None Exceptions: None PART TWO Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient Initiator:
Bring Containment Pressure to it's Engineering Limit by any method desired. When Containment Pressure increases to the Engineering Limit (77 psig), verify the simulator automatically goes into freeze and a message appears on the computer console. Place the simulator back into the RUN mode and bring Containment Pressure above the Model Limit (115 psig).
Termination Criteria: When Containment Pressure is brought above the Model Limit (115 psig), the simulator automatically goes into freeze and can not be placed into the RUN mode.
Deficiencies:None Exceptions: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
SIMULATOR REAL TIME AND OPERATING LIMITS TEST ABSTRACTS PREPARED BY:1 Richter DATE:02/16/98 REVIEWED BY:1 Richter DATE:02/16/98 SIMULATOR TEST NUMBER: 08-02 TITLE: Simulator Operating Limits Testing ANSI Section 4.3 PART TIIREE Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient initiator:
Bring Fuel Cladding Temperatures indicating gross fuel failures to it's Engineering Limit by any method desired. When Fuel Cladding Temperatures indicating gross fuel failures increases to the Engineering Limit (2200 0F), verify the simulator automatically goes into freeze and a message appears on the computer console. Place the simulator back into the RUN mode and bring Fuel Cladding Temperatures above the Model Limit (2800 0F).
Termination Criteria: When Fuel Cladding Temperatures are brought above the Model Limit (2800 0F), the simulator automatically goes into freeze and can not be placed into the RUN mode.
Deficiencies:None Exceptions: None PART FOUR Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient Initiator:
Bring Gross Voiding in the Core to it's Engineering Limit by any method desired. When Gross Voiding in the Core increases to the Engineering and Model Limit (-385 inches of Reactor Water Level), verify the simulator automatically goes into freeze and a message appears on the computer console. Attempt to place the simulator back into the RUN mode.
Termination Criteria: After Gross Voiding in the Core has been brought to it's Engineering and Model Limit (-385 inches of Reactor Water Level), the simulator can not be placed into the RUN mode.
Deficiencies:None Exceptions: None 1
PLANT E.1. IIATCII SIMULATOR CERTIFICATION PLAN TITLE:
SIMULATOR REAL TIME AND OPERATING LIMITS TEST ABSTRACTS PREPARED BY: 1 Richter DATE:02/16/98 REVIEWED BY: 1 Richter DATE:02/16/98 SIMULATOR TEST NUMBER: 08-02 TITLE: Simulator Operating Limits Testing ANSI Section 4.3 PART THREE Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient Initiator:
Bring fuel Cladding Temperatures indicating gross fuel failures to it's Engineering Limit by any method desired. When Fuel Cladding Temperatures indicating gross fuel failures increases to the Engineering Limit (2200 0F), verify the simulator automatically goes into freeze and a message appears on the computer console. Place the simulator back into the RUN mode and bring Fuel Cladding Temperatures above the Model Limit (2800 0F).
Termination Criteria: When Fuel Cladding Temperatures are brought above the Model Limit (280 0F), the simulator automatically goes into freeze and can not be placed into the RUN mode.
Deficiencies:None Exceptions: None PART FOUR Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient Htiator:
Bring Gross Voiding in the Core to it's Engineering Limit by any method desired. When Gross Voiding in the Core increases to the Engineering and Model Limit (-385 inches of Reactor Water Level), verify the simulator automatically goes into freeze and a message appears on the computer console. Attempt to place the simulator back into the RUN mode.
Termination Criteria: After Gross Voiding in the Core has been brought to it's Engineering and Model Limit (-385 inches of Reactor Water Level), the simulator can not be placed into the RUN mode.
Deficiencies:None Exceptions: None
PLANT E. I. IIATCil SIMULATOR CERTIFICATION PLAN TITLE:
SIMULATOR REAL TIME AND OPERATING LIMITS TEST ABSTRACTS PREPARED BY: J. Richter DATE: 02/16/98 REVIEWED BY:1. Richter DATE: 02/16/98 SIMULATOR TEST NUMBER: 08-02 TITLE: Simulator Operating Limits Testing ANSI Section 4.3
\\
PART FIVE Date Tested: 02/16/98 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient Initiator:
Bring Suppression Pool High Temperature to it's Engineering Limit by any method desired.
When Suppression Pool liigh Temperature increases to the Engineering Limit (Temperature > Tsat -20 0F), verify the t
simulator automatically goes into freeze and a message appears on the computer console. Place the simulator back into the RUN mode and bring Suppression Pool liigh Temperature to it's Model Limit (Temperature > Tsat -10 0 F).
Termination Criteria: When Suppression Pool High Temperature is brought to it's Model Limit (Temperature > Tsat -10 0 F), the simulator automatically goes into freeze and can not be place into the RUN mode.
Deficiencies:None Exceptions: None
l PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN l
TITLE:
NORMAL AND STEADY STATE TEST ABSTRACT PERFORMANCE TEST NUMBER: 615-1 Date Tested: 4/24/98 TITLE: Steady State Performance 35% power Initial Conditions: 35.8% rated power,39.4% rated core flow, EOL, Equilibrium Xe l
Transient Initiator: Steady State Conditions Termination Criteria: After 5 consecutive OD-3 printouts I minute apart have been collected.
Deficiencies Unit I: None Deficiencies Unit 2: N/A Exceptions Numbers (see attachment A for descr!ptions): 10,12 Unit 1 Baseline Data:
SCR l-88-5 Dated 5/20/88 - A615A 34GO-OPS-005-1S - Attachments 1 & 2 Process Computer Data Collected during 5/28/96 & 11/22/97 startups and data on 12/17-18/97 Unit 2 Haseline Data: N/A Panel Members: B. Smith, C. A. Tyre Differing Opinion: None l
l
PLANT E. I. IIATCII SIMULATOR CERTIFICATION PLAN TITLE:
NORMAL AND STEADY STATE TEST ABSTRACT PERFORMANCE TEST NUMHER: 615-2 Date Tested: 04/24/98 TITLE:
Steady State Performance at 35%
Initial Conditions:
34% rated power,47.9% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Steady State Conditions Termination Criteria: After 5 consecutive OD-3 printouts I minute apart have been collected.
Deficiencies Unit 1: N/A Deficiencies Unit 2: None
\\
Exceptions Numbers (see attachment A for descriptions): 12 Unit 1 Haseline Data: N/A Unit 2 Baseline Data: Tape Dated 3/23/88 - F615A Process Computer Data of 9/15/97, & Dec 17-18,1997 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN
'flTLE:
NORMAL AND STEADY STATE TEST ABSTRACT PERFORMANCE TEST NUMBER: 616-1 Date Tested: 04/24/98 TITLE:
Steady State Performance at 75% power Initial Conditions:
75% rated power,54.4% rated core flow, EOL, Equilibrium Xe i
Transient Initiator:
Steady State Conditions Termination Criteria: After 5 Consecutive OD-3 priatouts 1 minute apart have been collected.
l l-Deficiencies Unit 1. None Deficiencies Unit 2: N/A Exceptions Numbers (see attachment A for descriptions): 10,12 l
1-Unit i Haseline Data: SPDS Tape 500000024, SCR l-86-9 Dated 11/22/86 - A616A -
Process Computer Data Collected during startup on 5/5/96 & 11/23/97 Unit 2 Haseline Data: N/A Panel Members:
B. Smith, C. A. Tyr:
Differing Opinion:
None l
I 1
1 L _ _____-_______ _ ____ -
l PLANT Ea L HATCH SIMULATOR CERTIFICATION PLAN TITLE:
NORMAL AND STEADY STATE TEST ABSTRACT PERFORMANCE TEST NUMHER: 616-2 Date Tested: 04/24/98 TITLE:
Steady State Performance at 75%
i Initial Canditions:
74.7% rated power,56.1% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Steady State Conditions Termination Criteria: After 5 Consecutive OD-3 printouts I minute apart have been collected.
Deficiencies Unit 1: N/A Defic!encies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
12 Unit 1 Baseline Data: N/A Unit 2 Baseline Data: SCR 2-88-5 Dated 4/17/88 - B616A Plant Data Collected on 11/26/95 & 9/15/97 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None j
PLANT E. L IIATCH SIMULATOR CERTIFICATION PLAN TITLE:
NORMAL AND STEADY STATE TEST ABSTRACT PERFORMANCE TEST NUMHER: 617-1 Date Tested: 04/30/98 TITLE:
Steady State Performance at 100% rated thermal power and verify stability for 60 minutes 1
Initial Conditions:
100% rated power,99.5% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Steady State Conditions Termination Criteria: 60 Minutes Deficiencies Unit 1: None Deficiencies Unit 2: N/A Exceptions Numbers (see attachment A for descriptions): 10,12 Unit 1 Baseline Data: SPDS Tape 500000023, SCR l-87-1 Dated 1/1/87 - C617A SPDS Tepe 500000031, SCR l-88-6 Dated 9/4/88 - E617A SCR 1-87-5 Dated 7/23/87
)
Process Computer Data CoJ :cted on 12/8/97 & during startup on 12/15/97 Unit 2 Basel3a: Data: N/A 1
Panel Members:
B. Smith, C. A. Tyre l
Differing Opinion:
None 1
i
PLANT E.1. IIATCII SIMULATOR CERTIFICATION PLAN TITLE:
NORMAL AND STEADY STATE TEST AHSTRACT PERFORMANCE TEST NUMllER: 617-2 Date Tested: 05/01/98 TITLE: Steady State Performance at 100% rated thermal power and verify whility for 60 minutes.
Initial Conditions:
99.9% rated power,96.3% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Steady State Conditions Termination Criteria: 60 minutes Deficiencies Unit 1: N/A Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): 12 Unit I liaseline Data: N/A Unit 2 Ilaseline Data: SPDS Tape 500(XX)027, SCR 2-87-1 Dated I/26/87 SCR 2-88-10 Dated 8/5/88 Plant Data Collected on 12/08/97 & 12/15/97 Panel Members:
II. Smith, C. A. Tyre Differing Opinion:
None
PLANT E. I. IIATCII SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMBER: 701-0 Date Tested: 10/24/97 TITLE: Transient Performance: Manual Scram i
Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe l
Transient Initiator:
Manual Reactor Scram by placing the Reactor Mode Switch to Shutdown l
Termination Criteria:
Reactor Water Level has been restored to above +32 inches and the EllC system j
has stabilized Reactor pressure.
I Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit I Haseline Data:
SPDS Tape 500000024, SCR l-R6-9 Dated i I/22/86 - C701C Scram Report 1-87-4 Stri). Charts - I B21-R613, I B21-623 A, I B31-R614, IC51 -R603 A, 1C32-R607 Strip Charts - 1C32-R608,1C32-R609,1 N40-R903 Unit 2 Baseline Data:
SCR 2-88-5 Dated 4/17/88 l
l l
Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None i
l
l l
l l
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMHER: 702-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Simultaneous trip of all feedwater pumps Initial Conditions:
100% rated power,100% rated core now, EOL, Equilibrium Xe l
Transient Initiator:
Malfunction #87A & 87B (Feedwater pump Trip)
Termination Criteria: Reactor water level restored to above +32 inches by llPCI and RCIC Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit i Haseline Data:
Any SPDS Tape that show a loss of feedwater transient AEA (NEDE - 30156)
FSAR 14.3.4.3 Unit 2 Haseline Data:
SCR 2-88-10 Dated 8/5/88 SCR 2-87-2 Dated 4/22/87; SCR 208806 Dated on 5/27/88 Strip Charts - 2C32-R607,2C32-R609 FSAR 15.1.18 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None 1
l
PLANT E. I. IIATCII SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMBER: 703-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Simultaneous closure of all Main Steam Isolation Valves Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Translent Initiator:
Malfunction #127A 127B,127C, and 127D (MSIVs Fail She0 Termination Criteria: Reactor water level has been restored to above '32 inches.
)
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
AEA ((NEDE-30156);
FSAR 14.3.1.3 SCR l-86-2 Strip Charts - l B31-R614, I N40-R903, I B21-R613, IC51-R601 A. IC32-R608, 1 B21-R623 A,1C32-R609, IC32-R607 Unit 2 Baseline Data:
SPDS Tape - 500000006; SCR 2-86-6 Dated 8/29/86 - B703B SPDS Tape - 500000027; SCR 2-87-1 Dated 1/26/87 - D703B FSAR 15.1.4 Strip Chart 232-R609 Panel Members:
B. Smith, C. A. Tyre l
Differing Opinion:
None l
PLANT E I. HATCII SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMRER: 703-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Simultaneous closure of all Main Steam isolation Valves Initini Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #127A,1278,127C, and 127D (MSIVs Fail Shut)
Termination Criteria: Reactor water level has been restored to above +32 inches.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Haseline Data:
AEA ((NEDE - 30156);
FSAR 14.3.1.3 SCRl-i. '
Strip ' v a - 1 B31-R614, IN40-R903,1 B21-R613, IC51-R603A, IC32-R608, 1B21.c 3 A, IC32-R609, IC32-R607 Unit 2 Haseline Data:
SPDS Tape - 500000006; SCR 2-86-6 Dated 8/29/86 - B703B SPDS Tape - 500000027; SCR 2-87-1 Dated 1/26/87 - D703B FSAR 15.1.4 Strip Chart 232-R609 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None
PLANT E. I. HATCII SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMBER: 704-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Simultaneous trip of all recirculation pumps initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe
)
Transient Initiator:
Malfunctions 37A and 37B (Recirculation Pump Drive Motor Breaker Trip)
\\
Termination Criteria: Reactor feedwater temperature stabilizes Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
FSAR 14.3.5.3 Unit 2 Baseline Data:
FSAR 15.1.22 SCR 2-88-12 Strip Charts - 2C51-R603 A, 2C32-R608, 2B21 -R623 A, 2C32-R609, 2C32-R607 Strip Charts - 2831-R614,2B31-R613 Panel Me:nbers:
B. Smith, C. A. Tyre Differing Opinion:
None
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFC'MANCE TEST ABSTRACT PERFORMANCE TEST NUMBER: 705-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Single recirculation pump trip Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #38(B) (Recirculation Pump Field Breaker Trip)
Termination Criteria: Reactor feedwater temperature stabilizes Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
Strip Charts - IC51-R603A, IC32-R608,1B21-R623A, IC32 R609, IC32-R607 Strip Charts - 1 B31-R614,1 B21-R613 AEA (NEDE - 30156)
Unit 2 Baseline Data:
Strip Charts - 2C51 -R603 A, 2C32-R608, 2B21 -R623 A, 2C32-R609, 2B31-R614 Strip Charts - 2B21-R613,2C32-R607 SCR 2-87-7 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST AHSTRACT PERFORMANCE TEST NUMHER: 706-0 Date Tested: 10/27/97 l
l TITLE:
Main Turbine Trip (From the max powei level which will not result in an immediate Rx scram)
Initial Conditions:
30% rated power,40% rated core flow, MOL, Equilibrium Xe Transient Initiator:
Malfunction #122 (Main Turbine Trip)
TerminaMon Criteria:
Reactor water level restored to above +32 inches by Reactor Feedwater Pumps following a high reactor pressure scram.
Deficiencies Unit 1: None Deficiencies Unit 2: Nr'ne Exceptions Numbers (see attachment A for descriptions): None Unit 1 Haseline Data:
AEA (NEDE - 30156 4.2)
Unit 2 Haseline Data:
Best Estimate Judgment Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None
PLANT E. I. HATCII SIMULATOR CERTIFICATION PLAN TITLE:
NORMAL AND STEADY STATE TEST ABSTRACT PERFORMANCE TEST NUMBER: 707-0 Date Tested: 10/27/97 TITLE:
Transient Performance; Maximum power ramp (master recire controller in manual) down to approximately 75% and back up to 100%
l Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe.
Transient Initiator:
At I minute, reduce the output of the Recire Master Controller output (2B31-R620) to about 48.6% as read on 2B31-R621 A & B (about 30 MV).
l Termination Criteria: Reacar water level has stabilized following the power increase.
l Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Waseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members:
B. Smith, C. A. Tyre i
Differing Opinkm:
None l
1
PLANT E. I. H ATCli SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST AHSTRACT PERFORMANCE TEST NUMBER: 708-1 Date Tested: 10/24/97 T' TLE:
Transient Performance; Maximum size reactor coolant system rupture combined with a loss of offsite power Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malf #210 (Unit 1 DB A LOCA-Recire Suction Double Ended Break) at max. ramp rate with Malf #161 (Loss of Offsite Power).
Termination Criteria: Approximately 5 minutes Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
AEA (NEDE - 30156 11.2,13.4.1)
FSAR 14.4.3 Unit 2 Baseline Data:
Best Estimate Judgment Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None 1
i
PLANT E. L HATCH SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMBER: 708-2 Date Tested: 10/24/97 TITLE:
Transient Performance; Maximum size reactor coolant system rupture combined with a loss of offsite power Initial Conditions:
100% rated power,100% rated core How, EOL, Equilibrium Xe Transient Initia%r:
Malf #35A (Unit 2 DBA LOCA-Recire Discharge Double Ended Break) at max. ramp rate with Malf #161 (Loss of offsite Power)
Termination Criteria: Approximately 5 minutes Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
FSAR 15.L39 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None l
I
PLANT E. I. IIATCII SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMHER: 709-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Maximum size unisolable main steam line rupture Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #123B (Steam Line Break - Complete Severance of the "B" Main Steam Line in the Drywell)
Termination Criteria:
RWL has been raised to above +32" and Low Pressure ECCS are injecting into the Reactor Vessel.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
FSAR 14.4.5 AEA (NEDE 30156 11.2.2.2)
Unit 2 Baseline Data:
FSAR 15.1.40 l
Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None i
l l
)
PLANT E.1. HATCII SIMULATOR CERTIFICATION PLAN TITLE:
TRANSIENT PERFORMANCE TEST ABSTRACT PERFORMANCE TEST NUMBER: 710-0 Date Tested: 10/24/97 TITLE:
Transient Performance; Simultaneous closure of all Main Steam Isolation Valves combined with single stuck open safety / relief valves (inhibit activation of high pressure Emergency Core Cooling Systems)
Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malf #127A,127B,127C & 127D (Outboard MSIVs Fail Shut), Malf # 130A (SRV Fails Open), and Malf #104 (HPCI Turbine Trip)
Termination Criteria:
RWL has been restored to above +32" and pressure increased by CDPs
{
l Deficiencies Unit I: None Deficiencies Unit 2: None 1
l Exceptions Numbers (see attachment A for descriptions): None Unit 1 Baseline Data:
AEA (NEDE 30156, i1.3.6.7, 11.3.6.8) l FSAR 14.3.4.2 j
l I
l Unit 2 Baseline Data:
FSAR 15.1.17 Panel Members:
B. Smith, C. A. Tyre Differing Opinion:
None l
l 1
l l
WORKSHEET 17-02 PLANT E.1. HATCil SIMULATOR CERTIFICATION PLAN PAGE 3 OF 6
+
W.S. TITLE:
PERFORMANCE TEST SCHEDULE REVISION I PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/15/98 APPROVED BY: R.S. GRANTHAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 l
l Performance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the first year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
l l
05-02 Loss of coolant; inside primary containment 05-05 Loss of coolant; Small reactor coolant breaks including demonstration of saturation condition 1
05-07 Loss ofinstrument air to the extent that the whole system or individual headers can lose pressure and affect the plant's static or dynamic perfonnance l
05-2i Loss of protective system channel I'
05-25 Turbine trip 05-26 Generator trip 05-32 Main feed line break inside containment 05-34 Nuclear instrumentation failure (s) 05-38 Reactor pressure control system failure including turbine bypass failure (BWR) 06-04 Reactor trip followed by recovery to rated power; I
l l
y
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 502-0 Date Tested: 09/27/94 TITLE:
Loss of Coolant; inside primary containment initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #48D (Intermediate break in Drywell) at 50% severity (2125 gpm) at a maximum ramp rate.
Termination Criteria:
Low pressure ECCS systems have raised reactor water level above +60 inches.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, S. Loesch l
Differing Opinion: None i
l l
l 4
1 PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 I
PERFORMANCE TEST NUMBER: 505-1 Date Tested: 05/29/95 l
TITLE:
Loss of Coolant; Small reactor coolant breaks including demonstration of saturation condition.
Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator: Malfunction #54 (Coolant Leakage in Drywell-2G31-F001 weld leakage) at 100% severity (30 gpm) at a maximum ramp rate.
I Termination Criteria:
After drywell pressure has increased to 1.0 psig and has been reduced to
<0.5 psig by venting with SBGT system.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Scram Report 1-85-5 Strip Chart data for Drywell, Torus, and SBGT parameters Best Estimate Judgment for other parameters Unit 2 Baseline Data:
All parameters from 000012/13/87 to 2400 on 12/14/87 FSAR 15.1.32 Strip Chart data for Drywell Pressure and SBGT Flow parameters Best Estimate Judgment for other parameters Panel Members: J. Kelley, B. Smith, S. Loesch Differing Opinion: None 2
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 505-2 Date Tested: 09/28/94 TITLE:
Loss of coolant; Small reactor coolant breaks including demonstration of saturation condition Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #215B (Reactor Level Instrument Line "B" Leak - reference leg severance)
Termination Criteria:
Reactor water level has been restored to 32" by HPCI and RCIC Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
{
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
SCR 1-87-1 Unit 2 Baseline Data:
Plant Strip Chart data on initial portion of transient for APRM i
Best Estimate Judgment i
2-88-1 Panel Members: B. Smith, J. Kelley, S. Loesch Differing Opinion: None
l l
['
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN l
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 I
PERFORMANCE TEST NUMBER: 507-0 Date Tested: 09/28/94 l
1 l
TITLE:
Loss of instrument air to the extent that the whole system or individual headers can lose pressure and affect the plant's static or dynamic performance initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe i
Transient initiator: Malfunction #191 (Instrument Air Leakage). This malfunction will cause a total I
loss of service air & nonessentialinstr.
l l
Termination Criteria:
Reactor water level has been restored to above +32 inches l
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment FASR 15.1.28 Panel Members: B. Smith, J. Kelley, S. Loesch Differing Opinion: None
1 PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 521-0 Date Tested: 09/28/94 1
TITLE:
Loss of protective system channel initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #57A (Loss of Normal Power to Reactor Protective Channel)
Termination Criteria:
Malfunction insertion time of 5 minutes Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Strip Charts 1C51-R603A, R603C; 1C32-R607, R608, R609; 1B21-R615 Strip Chart 1B31-R614 Unit 2 Baseline Date:
Strip Charts 2C51-R603A; 2C32-R607, R608, R609; 2B31-R614 Strip Chart 2B21 R615 Panel Members: B. Smith, J. Kelley, S. Loesch j
Differing Opinion: None
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 525-0 Date Tested: 09/30/94 TITLE:
Turbine Trip initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #122 (Turbine Trip)
Termination Criteria:
Reactor water level restored to above +32 inches by the Reactor Feedwater Pumps Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
SPDS Tape 500000023 (A525A), SCR 1-87-1 Strip Charts 1831-R614,1C32-R607,1C32-R608,1C32-R609
)
Strip Charts 1B21-R615,1B21 R623A,1C51-R603A Scram Report 1-88-4 Unit 2 Baseline Data:
Strip Charts 2C51-R603A; 2C32-R608,2B21-R623A,2B21-R615, 2C32-R609 Strip Charts 2C32-R607,2B31-R614 l
Scram Report 2-85-6 l
Panel Members: B. Smith, J. Kelley, S. Loesch l
Differing Opinion: None I
I
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 526-0 Date Tested: 09/30/94 TITLE:
Generator Trip Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #209 (Generator Load Rejection)
Termination Criteria:
Reactor water level restored to above +32 inches by Reactor Feedwater Pumps Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
SPDA Tape 500000026 (A526A)
REF V /
-rh 1 Report 1-88-1 FSAR 14.3.1.1 Strip Charts 1C51 R603A; 1C32-R607, R60E at 9; 1821-R615, R623A; 1B31-R614 Unit 2 Baseline Data:
Scram Report 2-86-4 FSAR 15.1.1 Strip Charts 2C51 R603A; 2C32-R607, R608, R609; 2B31-R614; 2B21-R623A, R615 Penel Members: B. Smith, J. Kelley, S. Loesch Differing Opinion: None
PLANT Eo 1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 532-0 Date Tested: 09/30/94 TITLE:
Main feed line break inside containment initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #229B (Feedwater Line "A" Break inside Containment) at 100%
severity (Double Ended Break) at max ramp rate Termination Criteria:
HPCI has restored reactor water level to above +32 inches Deficiencies Unit 1:
0 0
0 l
0 l
l Deficiencies Unit 2:
0 0
0 f
0 Exceptions Numbers (see attachment A for descriptions):
l Unit 1 Baseline Data:
Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, S. Loesch, J. Kelley Differing Opinion: None l
l l
J
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 534-1 Date Tested: 09/30/94 l
TITLE:
Nuclear instrumentation failure (s) 4 initial Conditions:
Reactor Startup in progress, BOL, Reactor Mode Switch in Startup, 172%F Reactor coolant temperature Transient initiator: Malfunction #3A (SRM Failure - Upscale) and then Malfunction #4C, (SRM Failure - Downscale)
Termination Criteria:
Malfunction #4C has been inserted for 1 minute Deficiencies Unit 1:
0 l
0 0
0 Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Plant Procedures, Drawings and Surveillance Best Estimate Judgment Unit 2 Baseline Data:
Plant Procedures, Drawings and Surveillance Best Estimate Judgment l
Panel Members: B. Smith, S. Loesch, J. Kelley Differing Opinion: None 9
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 534-2 Date Tested: 09/30/94 TITLE:
Nuclear instrumentation failure (s)
Initial Conditions:
Rx Power about 10%, Reactor Startup in progress, BOL, Rx Mode Switch in Startup,925 psig Rx pressure Transient initiator: Malfunction #7A (IRM Failure - Inoperative) and then Malfunction #9C, (IRM Failure - Upscale)
Termination Criteria:
Malfunction #9C has been inserted for 1 minute Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Plant Procedures, Drawings and Surveillance Unit 2 Baseline Data:
Plant Procedures, Drawings and Surveillance Panel Members: B. Smith, S. Loesch, J. Kelley Differing Opinion: None l
l
f I
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN
)
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 534-3 Date Tested: 09/30/94 TITLE:
Nuclear instrumentation failure (s)
Initial Conditions:
100% rated power,100% rated core flow, EOL Equilibrium Xe 1
Transient Initiator: Malfunction #11 A (APRM Failure - Upscale) and then Malfunction #140, (APRM Failure - Inoperative)
Termination Criteria:
After Malfunction #14C response has been verified.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Plant Procedures, Drawings and Surveillance Unit 2 Baseline Data:
Plant Procedures, Drawings and Surveillance i
l Panel Members: B. Smith, J. Kelley, S. Loesch l
Differing Opinion: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 534-4 Date Tested: 09/30/94 l
TITLE:
Nuclear instrumentation failure (s)
Initlai Conditions:
100% rated power,100% rated core flow, EOL Equilibrium Xe Transient initiator: Malfunction #15B (RBM Failure - Upscale) and then Malfunction #17A, (RBM Failure - Inoperative)
I Termination Criteria:
After Malfunction #17A response has been verified.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Plant Procedures, Drawings and Surveillance Best Estimate Judgment Unit 2 Baseline Data:
Plant Procedures, Drawings and Surveillance Best Estimate Judgment Panel Members: B. Smith, S. Loesch, J. Kelley i
Differing Opinion: None
\\
4
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 534 5 Date Tested: 09/30/94 l
TITLE:
Nuclear instrumentation failure (s)
I initial Conditions:
100% rated power,100% rated core flow, EOL Equilibrium Xe Transient initiator: Malfunction #200D (Recirculation Loop Flow Instrument Failure) & then Malfunction #20J, Rev. 0 (LPRM Failure - Downscale) l Termination Criteria:
After Mal function #20J response has been verified.
l Deficiencies Unit 1:
0 I
O O
I l
Deficiencies Unit 2:
0 0
O
)
l Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Plant Procedures, Drawings and Surveillance Best Estimate Judgment Unit 2 Baseline Data:
Plant Procedures, Drawings and Surveillance Best Estimate Judgment I
l l
Panel Members: B. Smith, S. Loesch, J. Kelley i
Differing Opinion: None i
1 PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 I
PERFORMANCE TEST NUMBER: 538-1 Date Tested: 09/30/94 TITLE:
Reactor pressure control system failure including turbine bypass failure (BWR)
Initial Conditions: 75% rated power, MOL Transient initiator: Malfunction #137A (EHC Pressure Regulator Fails High)
Termination Criteria:
Reactor Water Level has been restored to above +32 inches by RCIC and HPCI Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 i
0 I
O O
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
FSAR 14.3.4.1 AEA (NEDE - 30156)
Best Estimate Judgment Unit 2 Baseline Data:
FSAR 15.1.5 j
Best Estimate Judgment I
l Penel Members: B. Smith, S. Loesch, J. Kelley i
Differing Opinion: None i
1 PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 538-2 Date Tested: 09/30/94 l
1 TITLE:
Reactor pressure control system failure including turbine bypass failure (BWR) l Initici Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #138A (EHC Pressure Regulator Fails Low)
Termination Criteria:
Main Generator MWe Stabilized Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
FSAR 15.1.6 Best Estimate Judgment Panel Members: B. Smith, S. Loesch, J. Kelley Differing Opinion: None l
l
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 538-3 Date Tested: 09/30/94 TITLE:
Reactor pressure control system failure including turbine bypass failure (BWR)
\\
Initial Conditions:
100% rated power,100% rated core flow, EOL Transient initiator: Manual Scram with Malfunction #134 (All Bypass Valves Fail Closed)
Termination Criteria:
Low Low Set has actuated and suppression pool temperature begins to l
increase Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, S. Loesch, J. Kelley Diffeting Opinion: None
l l
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 604-0 Date Tested: 10/10/94 TITLE:
Reactor trip followed by recovery to rated power Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Following a Reactor Scram from power, perform a reactor startup per 34GO-OPS-001, " Normal Reactor Startup."
Termination Criteria:
The plant has been returned to rated Reactor Power.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
00 0
8 Unit 1 Baseline Data:
SPDS Tape 500000024 Scram Report 1-86-9 on 11/22/86 (A604A1,2,4,5)
Unit 2 Baseline Data:
34GO-OPS-0012S Data package Sheets 7-42, Rev. 8 Panel Members: B. Smith, S. Loesch, J. Kelley Differing Opinion: None i
e
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 604 1 Date Tested: 12/06/90 TITLE:
Reactor Trip followed by recovery to rated power initial Conditions:
Transient initiator: See page 1, this page is only for 1 interval (mode switch to run to rated power)
Termination Criteria:
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members:
Differing Opinion:
WORKSilEET 17-02 PLANT E.1. IIATCli SIMULATOR CERTIFICATION PLAN PAGE 4 OF 6 W.S. TITLE:
PERFORMANCE TEST SCilEDULE REVISION 1 l
PREPARED BY: C. B Smith DATE: 05/15/98 REVIEWED BY: 1 Richter DATE: 05/15/98 l
APPROVED BY: R.S. GRANTH AM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 l
Performance Tests
\\
i l
The following performance tests will be conducted (in addition to the annual operability tests) in the second year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability 3
Tests):
)
05-03 Loss of coolant; Outside primary containment 05-06 Failure of safety and relief valves 05-08 Loss or degraded electrical power to the station, including loss of offsite power 05-15 Loss of condenser vacuum including loss of condenser level control 05-16 Loss of service water or cooling to individual components 05-22 Control rod failure including stuck rods, uncoupled rods, drifling rods, rod drops, and misaligned rods 05-23 Inability to drive control rods 05-24 Fuel cladding failure resulting in high activity in reactor coolant or off gas and the associated high radiation alarms 05-27 Failure in automatic control system (s) that affect reactivity and core heat removal 06-08 Plant shutdown from rated power to hot standby 06-09 Cooldown to cold shutdown conditions i
l I
L
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 503-1 Date Tested: 04/03/96 TITLE:
Loss of Coolant; Outside Primary Containment initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #52 (Reactor water clean-up system leak on check valve F122) at 5% severity (12.5 gpm) at a max. ramp rate.
Termination Criteria:
Five minutes after malfunction insertion Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, C. A. Tyre, Ed Jones Differing Opinion: None
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
l PERFORMANCE TEST NUMBER: 503-2 Date Tested: 04/03/96 l
TITLE:
Loss of Coolant; Outside Primary Containment i
Initial Conditions: 100% rated power,100% rated coro flow, EOL, Equilibrium Xe i
Transient initiator: Malf. #52 (Rx water clean-up system leak on check valve F122) severity l
increased to 50% (125 gpm) at a max. ramp rate.
I Termination Criteria:
Upon RWCU system isolation I
Deficiencies Unit 1:
0 0
0 0
i Deficiencies Unit 2:
0 l
O 0
0 Exceptions Numbers (see attachment A for descriptions):
)
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment l
Panel Members: B. Smith, J. Kelley, C. A. Tyre, Ed Jones Differing Opinion: None I
l
l PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
l PERFORMANCE TEST NUMBER: 503-3 Date Tested: 04/03/96 l
TITLE:
Loss of Coolant; Outside Primary Containment initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #126 (Steam leak in the turbine building) 1.26%
l Termination Criteria:
Upon PCIS group I isolation (MSIV) closure Deficiencies Unit 1:
0
)
0 O
{
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment
)
Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, Ed Jones Differing Opinion: None I
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 1
PERFORMANCE TEST NUMBER: 506-0 Date Tested: 04/03/96 TITLE:
Failure of safety and relief valves l
1 Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #130-A (Main Steam Relief Valve Fails Full Open)
Termination Criteria:
Suppression Pool water level is increasing with Suppression Pool temperature >100 degrees Deficiencies Unit 1:
0 l
0 0
0 i
Deficiencies Unit 2:
0 0
l 0
0 Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Unit 1 Baseline Data on Strip Charts from 10/23/87 (Event File 87-067)
Unit 2 Baseline Data:
Unit 2 Baseline Data in test file (s) B506A (Event File 88-038).
~
Panel Members: B. Smith, J. Kelley, Ed Jones Differing Opinion: None
PLANT E.1. HATCH SIMUL TGR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 508-0 Date Tested: 04/03/96 TITLE:
Loss or degraded electrical power to the station, including toss of offsite power Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #161 (Loss of Off-Site Power)
Termination Criteria:
Malfunction insertion for 3 minutes Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment l
Panel Members: B. Smith, J. Kelley, Ed Jones Differing Opinion: None l
L _ _ _ __ _ _____ _ _ _______ _____ _ ___ -._ _. - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 515-0 Date Tested: 04/03/96
)
TITLE:
Loss of condenser vacuum including loss of condenser level control 1
(
Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #70 (Circulating Water System Leak) at 100% severity I,100,000 gpm) at a maximum ramp rate.
Termination Criteria:
Reactor water level has been restored to above +32 inches.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Ectimate Judgment Panel Members: B. Smith, C. A. Tyre Differing Opinion: None
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 516-1 Date Tested: 04/04/96 l
TITLE:
Loss of service water or cooling to individual components I
initial Conditions: 10^% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator: Malfunction #678 (Service Water Pump Trip)
Termination Criteria:
Plant Service Water pressure and Flow have returned to normal Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
i Unit 1 Baseline Data:
Best Estimate Judgment i
l Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, Ed Jones Differing Opinion: None l
l I
PLANT E.1. IIATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
i PERFORMANCE TEST NUMBER: 516-2 Date Tested: 04/04/96 TITLE:
Loss of service water or cooling to individual components initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #67A,67C,67D (Service Water Pump Trip)
Termination Criteria:
Reactor water level has been restored to above +32 inches.
l Deficiencies Unit 1:
0 0
0 0
1 Deficiencies Unit 2:
0 0
0 0
l l
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment r
Unit 2 Baseline Data:
Best Estimate Judgment I
Panel Members: B. Smith, J. Kelley, Ed Jones Differing Opinion: None
}
l l
)
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 522-1 Date Tested: 04/08/96 TITLE:
Control Rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and misaligned rods
{
1 Initial Conditions: 52% rated power,55% rated core flow, EOL Transient initiator: Malfunction #22 (Control Rod XX YY Failure - Stuck)
Termhation Criteria:
Stall Flow has been verified in both the insert and withdraw directions Deficiencies Unit 1:
0 0
1 o
0 l
Deficiencies Unit 2:
0 0
O O
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment l
Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, C. A. Tyre l
Differing Opinion: None I
l 4
lr
PLANT E. I. HATCH SIMULATOR CERTlhCATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 522-2 Date Tested: 04/08/P6 TITLE:
Control Rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and misaligned rods initial Conditions: 52% rated power,55% rated core flow, EOL Transient initiator: Malfunction #23 Inserted on the rod selected for Part 1 & removal of Malf #22 after the selected CRD Mech. has been withdrawn Termination Criteria:
Reactor power has stabilized after the control rod drop Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment on Abnormal Event Analysis (NEDE 30156)
Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, C. A. Tyre Differing Opinion: None
PLANT E.1. HATC.H SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 522-3 Date Tested: 05/30/96 i
TITLE:
Control Rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and misaligned rods initial Conditions: 52% rated power,55% rated core flow, EOL Transient initiator: Malfunction #25 (Control Rod XX-YY Failure - Drift In)
Termination Criteric:
The selected control rod has gone to the full in overtravel position after opening the cooling water supply valve.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, C. A. Tyre Differing Opinion: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN 3
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2
)
PERFORMANCE TEST NUMBER: 522-4 Date Tested: 05/30/96 TITLE:
Control Rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and j
misaligned rods initial Conditions: 52% rated power,55% rated core flow, EOL Transient initiator: Malfunction #26 (Control Rod XX-YY Failure - Scram)
Termination Criteria:
Reactor pressure and power have stabilized following the individual rod scram.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley, C. A. Tyre Differing Opinion: None l
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
' MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 523-0 Date Tested: 04/04/96 TITLE:
Inability to drive control rods initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe l
l Transient initiator: With Malfunction #30A (Control Rod Drive System Pump Trip) inserted, attempt j
to move a control rod.
Termination Criteria:
Verification that the control rod will not move.
l Deficiencies Unit 1:
0 l
0 i
0 0
Deficiencies Unit 2:
0 0
)
o 0
Exceptions Numbers (see attachment A for descriptions):
l Unit 1 Baseline Data:
Best Estimate Judgment I
L Unit 2 Baseline Data:
Best Estimate Judgment l
Panel Members: B. Smith, J. Kelley, Ed Jones Differing Opinion: None f
I l
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 524-1 Date Tested: 04/04/96 TITLE:
Fuel cladding failure resulting in high activity in reactor coolant or off gas and the associated high radiation alarms j
initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Malfunction #282A (Fuel Cladding Failure / Gross Fuel Failure) at.225% severity (9 Million R/hr) at a maximum ramp rate.
Termination Criteria:
Retreatment Radiation level increases Deficiencies Unit 1:
9606002 0
0 0
Deficiencies Unit 2:
9606002 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, Ed Jones Differing Opinion: None l
l l
u
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 524-2 Date Tested: 04/04/96 TITLE:
Fuel cladding failure resulting in high activity in reactor coolant or off gas and the associated high radiation alarms Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe l
l Transient initiator: Malfunction #282A (Fuel Cladding Failure / Gross Fuel Failure) at 1.5% severity (9 Million R/hr) at a maximum ramp rate.
f Termination Criteria:
Primary Containment radiation levels stabilize following the scram and PCIS Group i isolation
[
Deficiencies Unit 1:
9606002 0
0 l
0 L
Deficiencies Unit 2:
9606002 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment l
l Unit 2 Baseline Gata:
Best Estimate Judgment l
l l
Panel Members: B. Smith, Ed Jones Differing Opinion: None l
l
L PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN I
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 l
PERFORMANCE TEST NUMBER: 527-0 Date Tested: 04/04/96 TITLE:
Failure in automatic control system (s) that affect reactivity and core heat removal Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe l
1 Transient initiator: Malfunction #103 (HPCI Inadvertent Start-up)
Termination Criteria:
HPCI trip on high reactor water level.
Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment utilizing Abnormal Event Analysis (NEDE 30156)
Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, Ed Jones, J. Kelley Differing Opinion: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 608-0 Date Tested: 04/09/96 TITLE:
Plant shutdown from rated power to hot standby Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator: Shutdown the Reactor Plant to Hot Standby per 34GO-OPS-013-2, Normal Plant Shutdown.
Termination Criteria:
The reactor mode switch has been placed to Startup and Hot Standby position Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, C. A. Tyre Differing Opinion: None I
l 1
l L____________________
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 609-0 Date Tested: 04/22/96 TITLE:
Cooldown to cold shutdown conditions Initial Conditions:
2.7% rated power,18% rated core flow,920 psig reactor pressure, MOL i
I Transient initiator: Perform a Plant Cooldown per 34GO-OPS-013, Plant Cooldown Termination Criteria:
Cold shutdown conditions have been established Deficiencies Unit 1:
0 0
0 0
Deficiencies Unit 2:
0 0
0 0
Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
SCR 1-87-3 1
1 Unit 2 Baseline Data:
SCR 2-87-5 Panel Members: B. Smith, C. A. Tyre Differing Opinion: None l
l j
WORKSiiEET 17-02 PLANT E. I. liATCil SIMULATOR CERTIFICATION PLAN PAGE 5 OF 6 W.S. TITLE:
PERFORMANCE TEST SCilEDULE REVISION 1 l
PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY:1 Richter DATE: 05/15/98 j
i APPROVED BY: R.S. GRANTHAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98
{
l I
I I
Performance Tests I
The following performance tests will be conducted (in addition to the annual operability tests) in the third year following I
certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
05-09 Loss or degraded electrical power to the station, loss of emergency power 05-10 Loss or degraded electrical power to the station, loss of emergency generators 05-11 Loss or degraded electrical power to the station, loss of power to the plant's electrical distribution buses 05-31 Main steam line break outside containment 05-33 Main feed line break outside containment 06-01 Plant startup - cold to hot standby. The starting conditions shall be cold shutdown conditions of l
temperature and pressure. Removal of the reactor vessel head is not a required condition for simulation 06-02 Nuclear startup from hot standby to rated power 06-03 Turbine startup and generator synchronization 06-05 Operations at hot standby 06-06 Load changes 06-10 Core performance testing; lieat Balance L
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PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 509-0 Date Tested: 06/19/97 TITI.E: Loss of Degraded Electrical Power to Station, Loss of Emergency Power Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator:
Malfunction # 182 (4KV Emergency Bus 2E Fault)
Termination Criteria:
Reactor water level has returned to the normal band Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Drawings and Procedures and Best estimate Judgment Unit 2 Baseline Data:
Drawings and Procedures and Best estimate judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None l
)
PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2
?
PERFORMANCE TEST NUMilER: 510 Date Tested: 01/30/97 l
l TITLE: Loss of Degraded Electrical Power to the Station, Loss of Emergency Generators l
1 I
Initial Conditions: 100% rated power,100% rated core flow, Equilibrium Xe
)
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Transient Initiator:
Malfunction # 62C (Diesel Generator Failure to Auto Start),
l Malfunction #184 (4KV Bus 2G Fault) l I
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l Termination Criteria:
Malfunction #184 has been inserted for 5 minutes.
Deficiencies Unit 1: None i
l Deficiencies Unit 2: None l
Exceptions Numbers (see attachment A for descriptions):
l 1
Unit i Haseline Data:
Drawings and Procedures and Best Estimate Judgment Unit 2 Ilaseline Data:
Drawings and Procedures and Best Estimate Judgment j
i Panel Members: B. Smith, J. Kelley Differing Opinion: None r
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PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMIiER: 511-0 Date Tested: 01/31/97 TITLE: loss of degraded electrical power to the station, loss of power to the plant's electrical distribution buses.
Initial Conditions: 100% rated power,100% rated core flow, EOL Equilibrium Xe Transient Initiator:
Malfunction # 201 (less of Vital AC)
Termination Criteria:
Reactor water level restored to above + 32 inches Deficiencies Unit 1:
None Deficiencies Unit 2:
None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Scram Report #1-87-5 Dated 7/23/87 (outdated)
Unit 2 Baseline Data:
Scram Report #2-87-3 Dated 7/26/87 (outdated)
Scram Report #2-87-4 Dated 8/3/87 (outdated)
SPDS Tapes from Loss of Vital AC Dated 7/26/67 or 8/3/87 (outdated)
Panel Members: B. Smith, J. Kelley Differing Opinion: None l
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PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMHER: 531-0 Date Tested: 01/31/97 TITLE: Main steam line break outside containment Initial Conditions: 100% rated power,100% rated core flow, EOL Equilibrium Xe l
Transient Initiator:
Malfunction #126A (Steam Leak in Turbine Building).
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Termination Criteria:
Reactor Water Level restored to above + 32 inches by llPCI.
Deficiencies Unit 1: None l
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Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
(AEA (NEDE-30156)
Unit 2 Haseline Data:
Best Estimate Judgment
]
Panel Members: B. Smith, J. Kelley DifTering Opinion: None i
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l PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMHER: 533-0 Date Tested: 02/06/97 TITLE: Main feed line break outside containment initial Conditions: 100% rated power,100% core flow, EOL Equilibrium Xe.
Transient Initiator:
Malfunction #64 (Feedwater Line "A" Break) at 100% severity at the maximum ramp rate.
Termination Criteria:
Reactor water level has been restored to above +32 inches by RCIC.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment i
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Panel Members: B. Smith, J. Kelley l
l Differing Opinion: None l
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i PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 601-0 Date Tested: 02/03/97 TITLE: Plant startup - Cold to hot standby. The starting conditions shall be cold shutdown conditions of temperature and Pressure. Removal of the reactor vessel head is not a required condition for simulation.
Initlai Conditions:
0% rated power,10% rated core flow, BOL,172 F reactor coolant temperature, Xenon free condition.
Transient Initiator:
Perform a reactor startup per 34GO-OPS-001-2S," Normal Reactor Startup."
Termination Criteria:
After shell and chest warming are complete per 34GO-OPS-001-2S and the plant has been brought to 920 psig.
Deficiencies Unit 1:
None Deficiencies Unit 2:
None Exceptions Numbers (see attachment A for descriptions):
8 Unit 1 Baseline Data:
34GO-OPS-001-2 Data pkg shts 7-28, Rev. 5 34SV-B31-001-2 Data pkg shts 9-10, Rev.1 Unit 2 Baseline Data:
34GO-OPS-001-2 Data pkg shts 7-28, Rev. 5 SPDS Tapes B601 B 1, B601 B2, B601 B3, D601 B;, N601 B3, N601 B4 l
l Tapes dated 3/17/88 to 3/26/88. Also tapes dated 12/9/86 to 12/12/86 34SV-B31-00!-2 Data pkg shts 9-10, Rev. I Panel Members: B. Smith, J. Kelley Differing Opinion: None L
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMHER: 602-0 Date Tested: 02/05/97 l
TITLE: Nuclear startup from hot standby to rated power (920 PSIG TO RATED POWER)
Initial Conditions:
Reactor Critical, BOL,920 psig reactor pressure, shell and chest warming complete, Mode Switch in Startup/Ilot Standby.
1 Transient Initiator:
Perform a reactor startup per 34GO-OPS-001-2S, " Normal Reactor Startup."
a Termination Criteria:
The plant has been brought to rated power Deficiencies Unit 1: None l
Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment 1
Unit 2 Haseline Data:
34GO-OPS-001-2 Data pkg shts 21,28-42 R5 l
SPDS Tape B602A1, D602Al, D602A2, D602A3 l
Tapes dated 3/17/88 to 3/26/88. Also tapes dated 12/9/86 to 12/12/86 i
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l Pant. Members: B. Smith, J. Kelley i
Differing Opinion: None l
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PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN l
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 i
PERFORMANCE TEST NUMHER: 603-0 Date Tested: 02/03/97 l
TITLE: Turbine startup and generator synchronization Initial Conditions:
Reactor Critical, BOL,920 psig reactor pressure, shell and chest warming complete, Mode Switch in Run i
Transient Initiator:
Perform a Main Turbine startup and a Main Generator synchronization per 34GO-OPS-001," Normal Reactor Startup."
Termination Criteria:
The Main Generator is tied to the grid and carrying load Deficiencies Unit I: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): 8 Unit i Baseline Data: Best Estimate Judgment Unit 2 Haseline Data: Best Estimate Judgment Panel Members: B. Smith, J. Kelley i
I Differing Opinion: None l
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PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 605-0 Date Tested: 02/04/97 TITLE: Operations at hot standby Initial Conditions:
Reactor is Critical at.1% rated power,11% rated core flow,84 psig reactor pressure, BOL.
Transient Initiator:
While in liot Standby, Equalize around the MSIVs per 34GO-OPS-001-2," Normal Reactor Startup."
/
Termination Criteria:
One minute after the MSIVs have been opened and plant conditions have stabilized.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
None l
l Unit 1 Baseline Data:
34GO-OPS-001-2S Data pkg sheets 24-26 R5 I
l Unit 2 Baseline Data:
34GO-OPS-001-2S Data pkg sheets 24-26 R5 l
SPDS Tape B605A Dated 3/22/88 Panel Members: B. Smith, J. Kelley j-Differing Opinion: None I
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PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 6060 Date Tested: 02/05/97 TITLE: Load Changes Initial Conditions:
Nucl. Startup in prog., Rx Pwr at appx. 59%, BOL, Recire flow ctrl in Indiv. Manual ctrl, 2nd Rx Feedwtr. pump /in serv.
Transient initiator:
Transfer Recire Control to Master Manual Control and increase power to rated per 34GO-OPS-001-2, " Normal Reactor Startup" Termination Criteria:
One minute after the reactor is at rated powcr and plant conditions have stabilized.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Haseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None t
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 610-0 Date Tested: 02/06/97 TITLE:
Core performance testing; lleat Balance Initial Conditions:
100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Compute Core Thermal Power (Manually)
Termination Criteria:
Manual heat balance data has been obtained and an OD-3 has been printed.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
SPDS Tape 500000031, SCR l-86-6 Dated 9/4/88 - A610B SPDS Tape 500000023, SCR l-87-1 Dated 1/1/87 - C610B Unit 2 Baseline Data:
SPDS Tape 500000027, SCR 2-87-1 Dated 1/26/87 - D610B SCR 2-88-10 Dated 8/5/88 - B610B Panel Members: B. Smith, J. Kelley Differing Opinion: None l
l WORKSiiEET 17-02 PLANT E. L liATCH SIMULATOR CERTIFICATION PLAN PAGE 6 OF 6 W.S. TITLE:
PERFORMANCE TEST SCHEDULE REVISION 1 l
l PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/15/98 APPROVED BY: R.S. GRANTHAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/Is/98 Performance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the fourth year following certification (Nonnal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
05-12 Loss or degraded electrical power to the station, loss of power to the individual instrumentation buses (AC) that provide power to control room indication or plant control functions affecting the plant's response 05-13 Loss or degraded electrical power to the station, loss of power to the individual instrumentation buses (DC) that provide power to control room indication or plant control functions affecting the plant's response 05-17 Loss of shutdown cooling f
1 05-18 Loss of component cooling system or cooling to individual components 05-19 Loss of normal feedwater or normal feedwater system failure 05-20 Loss of all feedwater (nomial and emergency) 05-35 Process instrumen% tion, alarms, and control system failures j
l 05-36 Passive malfunctions in systems, such as engineered safety features, emergency feedwater 1
systems I
l 05-37 Failure of the automatic reactor trip system j
06-14 Operator conducted surveillance testing on safety-related equipment or systems.
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1 PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN l
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 512-0 Date Tested: 10/22/97 TITLE: Loss or degraded electrical power to the station, loss of power to the individual instrumentation buses (AC) that provide power to control room indication or plant control functions affecting the plant's response.
Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient initiator:
Malfunction # 185 (120/208V AC Instrument Bus 2A Fault)
Termination Criteria:
Reactor water level is restored to above +32 inches Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit i Haseline Data:
Best Estimate Judgment Unit 2 Baseline Data: Event Review Team report 92-009 (no SPDS tape available)
Panel Members: B. Smith, J. Kelley Differing Opinion: None 1
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PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMHER: 513-1 Date Tested: 10/22/97 TITLE: Loss or degraded electrical power to the station, loss of power to the individual instrumentation buses (DC) that provide power to control room indication or plant control functions affecting the plant's response.
Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #204 (loss of 125/250V DC Bus 2B)
Termination Criteria:
After Reactor Recire Pump 2A Flow is less than 45,200 gpm Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (s e attachment A for descriptions):
Unit i Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley DilTering Opinion: None
PLANT E. I. HATCH SlMULATOR CERTIFICATION PLAN ETLE:
MALFUNCDON PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMHER: 513-2 Date Tested: 10/22/97 TITLE: Loss or degraded electrical power to the station, loss of power to the individual instrumentation b uses (DC) that provide power to control room indication or plant control functions affecting the plant's response.
Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #205 (24/48 DC Cabinet 2A Fault - 2R25-S015)
Termination Criteria:
Malfunction inserted for 2 minutes Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see att ament A for descriptions):
Unit 1 Baseline Data:
Best Estin. ate Judgment Unit 2 Haseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 513-3 Date Tested: 10/22/97 TITLE: Loss or degraded electrical power to the station, loss of power to the individual instrumentation buses (DC) that provide power to control room indication or plant control functions affecting the plant's response.
Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #203 less of 125/250V DC Bus 2A)
Termination Criteria:
Reactor water level restored to above +32 inches Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Haseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None l
__________________---_a
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 517-0 Date Tested: 11/17/97 TITLE: Loss of Shutdown Cooling Initial Conditions:
Reactor Shutdown,18% rated core flow, MOL, All control rods full in Rx Press at 92 psig, Rx Mode Switch in SilUTDOWN Transient initiator:
Malfunction #208A (Imss of Shutdown Cooling)
Termination Criteria:
Reactor temperature increase of 20 deg. F after loss of Shutdown Cooling occurs.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Abnormal Event Analysis (NEDE 30156) sec. 9.1 j
j Unit 2 Baseline Data:
Strip Charts 9/21/86 Event file 86-086 Panel Members: B. Smith, J. G. Kelley l
Differing Opinion: None j
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PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 518-1 Date Tested: 10/22/97 TITLE: Loss of component cooling system or cooling to individual components Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #72C (RBCCW Pump Auto Start Failure), and Malfunction #71 A and 71B (RBCCW Pump Trip) i I
Termination Criteria:
Malfunction #71 A and 71 B have been inserted for 5 minutes I
l Deficiencies Unit 1: None Deficiencies Unit 2: None i
Exceptions Numbers (see attachment A for descriptions):
Unit i Baseline Data:
Best Estimate Judgment I
i Unit 2 Baseline Data:
Best Estimate Judgment
)
)
Panel Members: B. Smith, J. Kelley i
Differing Opinion: None l
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PLANT E. i. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 518-2 Date Tested: 10/22/97 TITLE: Loss of component cooling system or cooling to individual components Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #193A and 193B, Rev 33 (Drywell Chiller Compressor Failure)
Termination Criteria:
Drywell Pressure increases to 2.0 psig Deficiencies Unit 1: None Deficiencies Unit 2: None Excepticas Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Easeline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Op!nion: None 1
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PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 I
PERFORMANCE TEST NUMBER: 519-0 Date Tested: 10/22/97 TITLE: Loss of normal feedwater or normal feedwater system failure
)
l Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe l
Transient Initiator:
Malfunction #91B (Loss of Extraction Steam to 4th Stage Feedwater Heater) l Termination Criteria:
Feedwater inlet temperature decreases and Reactor Power stabilizes Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
B:st Estimate Judgment utilizing FS AR date Abnormal Event Analysis data (NEDE 30156) for all other parameters Unit 2 Haseline Data:
Best Estimate Judgment utilizing FSAR data Panel Members: B. Smith, J. Kelley Differing Opinion: None L
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN l
TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 520-0 Date Tested: 10/22/97 l
TITLE: Loss of all feedwater (normal and emergency) l Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malf #113 (RCIC Auto isolates), #108 (IIPCI Auto Isolates),30A (CRD 2A trips), and
- 80A,B, & C (CBPs Trip).
Termination Criteria:
Reactor water level restored to above +32 inches.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
' Unit 1 Ilaseline Data:
Best Estimate Judgment Un.it 2 Haseline Data:
Best Estimate Judgment l
Panel Members: B. Smith, J. Kelley Differing Opinion: None I
4
f PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 535-1 Date Tested: 10/23/97 TITLE: Process instrumentation, alarms, and contrel system failures Initial Conditions: 100% rated power,100% rated core How, EOL, Equilibrium Xe l
Transient initiator:
Malfunction #166 (Automatic Voltage Regulator Failure) l Termination Criteria:
Generator voltage and MVARs have stabilized Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMHER: 535-2 D: te Tested: 10/23/97 TITLE: Process instrumentation, alarms, and control system failures Initial Conditions: 10(F4 rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #213 (Torus Level Sensor Fails liigh)
Termination Criteria:
All valves for llPCI suction transfer have repositioned to either fully open or closed, as required.
Deficiencies Unit 1: None Deficiencies Unit 2: None Excepurns Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Haseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley DiiTering Opinion: None
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 535-3 Date Tested: 10/21/89 TITLE: Process instrumentation, alarms, and control system failures Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Deleted this test because of DCR 90-163 (Rectre Controller Replacement)
Termination Criteria:
Reactor power has been returned to 100% rated thermal power Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit i Haseline Data:
Best Estimate Judgment Unit 2 Haseline Data:
Best Estimate Judgment PancI Members: B. Smith, J. Kelley Differing Opinion: None l
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PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 535-4 Date Tested: 10/23/97 TITLE: Process instrumentation, alarms, and control system failures Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #141 (Main Turbine Lube Oil System Temperature Controller Failure)
Termination Criteria:
Reactor water level is stable and above "0" inches Deficiencies Unit 1: 9805003 Deficiencies Unit 2: 9805003 Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None l
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 535-5 Date Tested: 10/23/97 TITLE: Process instrumentation, alarms, and control system failures Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #90 (Feedwater Master Level Controller Fails minimum)
Termination Criteria:
Reactor water level is restored to above +32 inches Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
SCR l-87-7 Unit 2 Baseline Data:
SCR 2-88-10 I
Panel Members: B. Smith, C. Tyre, J. Kelley Differing Opinion: None i
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PLANT E. l. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 536-3 Date Tested: 10/23/97 TITLE: Passive malfunctions in systems, such as engineered safety features, emergency feedwater systems Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #87A/B (trip of both Reactor Feed pumps). #106 and #109 Termination Criteria:
Reactor water level is restored to above +32 by manually controlling HPCI Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Baseline Data:
Best Estimate Judgment Unit 2 Baseline Data:
Best Estimate Judgment Panel Members: B. Smith, C. Tyre, J. Kelley
'i l
{
Differing Opinion: None l
PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 537-0 Date Tested: 5/13/98 TITLE: Failure of the automatic reactor trip system Initial Conditions: 100% rated power,100% rated core flow, EOL, Equilibrium Xe Transient Initiator:
Malfunction #217 (Rx Protective System Fails to Scram on Reactor Low Level) and SVO #22 ("B" GEMAC failure to 60 inches) l Termination Criteria:
Reactor water level stabilizes above 32" Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions):
Unit 1 Haseline Data:
Best Estimate Judgment Unit 2 Haseline Data:
Best Estimate Judgment Panel Members: B. Smith, J. Kelley Differing Opinion: None 1
PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN TITLE:
MALFUNCTION PERFORMANCE TEST ABSTRACT REV: 2 PERFORMANCE TEST NUMBER: 614-0 Date Tested: 10/01/97 TITLE: Operator conducted surveillance testing on safety-related equipment or systems Initial Conditions:
Transient Initiator:
Termination Criteria:
The data package steps are complete for each of the above listed surveillance.
Deficiencies Unit 1: None Deficiencies Unit 2: None Exceptions Numbers (see attachment A for descriptions): 8 Unit 1 Baseline Data:
Associated plant procedure acceptance criteria Unit 2 Baseline Data:
Associated plant procedure acceptance criteria l
l Panel Members: B. Smith, J. Kelley Differing Opinion: None I
I I
PERFORMANCE TEST SCIIEDULE 04/14/94 I
Plant E. I. Ilatch, Unit 2 Docket # 50-366 Southern Nuclear Operating Company I
l
WORKSilEET 17-02 PLANT E. I. llATCII SIMULATOR CERTIFICATION PLAN PAGE 1 OF 6 W.S. TITLE:
PERFORMANCE TEST SCliEDULE REVISION 1 PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter __ DATE: 05/15/98 APPROVED BY: R.S. GR ANTil AM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 PERFORM ANCE TESTING SCIIEDULE GENERAL STATEMENT The Performance Test Schedule includes all annual operability tests and all performance tests to be performed over a four year period. Performance tests scheduled to be completed each 12 month period includes the 15 annual operability tests and approximately 257c of the performance tests, such that each annual operability test will be performed four times over the four year period and each performance test will be performed once over the same four year period.
Performance tests will be scheduled as described.1lowever, scheduled plant modifications may impact the Performance Test Schedule requiring unplanned delays in performing certain annual operability or performance tests. Unplanned deviations in the Performance Test Schedule will not exceed three months past the original annual due date.
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WORKSHEET 17-02 PLANT E.1. HATCH SIMULATOR CERTIFICATION PLAN PAGE 3 OF 6 W.S. TITLE:
PERFORMANCE TEST SCHEDULE REVISION I l
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PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/15/98 APPROVED BY: R.S.GRANTHAM OPERATOR TRAINING SUPERINTENDENT. DATE: 05/15/98 Annual OperabiHty Test The following operability tests will be conducted annually (Computer Real Time and Simulator Operating Limits Tests and Appendix B - Steady State and Transient Performance Tests):
08-01 Simulator Real Time Test 08-02 Simulator Operating Limits Testing 06-15 Steady State Performance at 25% power 06-16 Steady State Performance at 75% power 06-17 '
Steady State Performance at 100% rated thermal power and verify stability for 60 minutes 07-01 Transient Performance; Manual scram 07-02 Transient Performance; Simultaneous trip of all feedwater pumps 07-03 Transient Performance; Simultaneous closure of all Main Steam Isolation Valves 07-04 Transient Performance; Simultaneous trip of all recirculation pumps 07-05 Transient Performance; Single recirculation pump trip l
07-06 Transient Performance; Main turbine trip (from the maximum power level which will not result in an immediate reactor scram) 1 07-07 Transient Performance; Maximum power ramp (master recire controller in manual) down to approximately 759 and back up to 100%
07-08 Transient Performance Maximum size reactor coolant system rupture combined with a loss of offsite power 07-09 Transient Performance; Maximum size unisolable main steam line rupture 07 10 Transient Performance; Simultaneous closure of all Main Steam isolation Valves combined with single stuck open safety / relief valve (inhibit activation of high pressure Emergency Core Cooling Systems)
WORKSHEET 17-02 PLANT E. I. HATCH SIMULATOR CERTIFICATION PLAN PAGE 3 OF6 W.S. TITLE:
PERFORMANCE TEST SCHEDULE REVISION I PREPARED BY: C. B. Smith -
DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/15/98 APPROVED BY: R.S. GRANTHAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 Performance Tests The following performance tests will be conducte- (in addition to the annual operability tests) in the first year following certification (Normal Operation Tests. Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
05-02 Loss of coolant; Inside primary containment 05-05 Loss of coolant; Small reactor coolant breaks including demonstration of saturation condition 05-07 Loss of instrument air to the extent that the whole system or indvidual headers can lose pressure and affect the plant's static or dynam'c performance G
05-21 Loss of protective system channel 05-25 Turbine trip 05-26 Generator trip 05-32 Main feed line break inside containment 05-34 Nuclear instrumentation failure (s) 05-38 Reactor pressure control system failure including turbine bypass failure (BWR)
)
06-04 Reactor trip followed by recovery to rated power; l
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WORKSilEET 17-02 PLANT E. I. IIATCil SIMULATOR CERTIFICATION PLAN PAGE 4 OF 6 W.S. TITLE:
PERFORMANCE TEST SCilEDULE REVISION 1 PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/15/98 APPROVED BY: R.S. GR ANTilAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 Performance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the second year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
05-03 Loss of coolant; Outside primary containment 05-06 Failure of safety and relief valves 05-08 Loss or degraded electrical power to the station, including loss of offsite power 05-15 Loss of condenser vacuum including loss of condenser level control 05-16 Loss of service water or cooling to individual components 05-22 Control rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, and misaligned rods 05-23 Inability to drive control rods 05-24 Fuel cladding failure resulting in high activity in reactor coolant or off as and the associated F
high radiation alarms 05-27 Failure in automatic control system (s) that affect reactivity and core heat removal 06-08 Plant shutdown from rated power to hot standby 06-09 Cooldown to cold shutdown conditions l
WORKSilEET 17-02 PLANT E.1. IIATCII SIMULATOR CERTIFICATION PLAN PAGE 5 OF6 W.S. TITLE:
PERFORMANCE TEST SCllEDULE REVISION 1 PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: L Richter DATE: 05/15/98 APPROVED BY: R.S. GR ANTilAM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 Performance Tests The following performance tests will be conducted (in addition to the annual operability tests)in the third year following certification (Normal Operation Tests, Malfunction Tests, and Transient Tests not tested as Annual Operability Tests):
05-09 Loss or deFraded electrical power to the station, loss of emergency power 05-10 Loss or degraded electrical power to the station, loss of emerFency Fenerators 05-11 Loss or degraded electrical power to the station, loss of power to the plant's electrical distribution buses 05-31 Main steam line break outside containment 05-33 Main feed line break outside containment 01 Plant startup cold to hot standby. The starting conditions shall be cold shutdown conditions of temperature and pressure. Removal of the reactor vessel head is not a required condition for simulation 06-02 Nucicar startup from hot standby to rated power 06-03 Turbine startup and generator synchronization 06-05 Operations at hot standby 06-06 Load chanFen 06-10 Core performance testhg;lleat Balance r
f WORKSilEET 17-02 PLANT E.1. IIATCil SIMULATOR CERTIFICATION PLAN PAGE 6 OF 6 W.S. TITLE:
PERFORMANCE TEST SCllEDULE REVISION I PREPARED BY: C. B. Smith DATE: 05/15/98 REVIEWED BY: J. Richter DATE: 05/is/91 APPROVED BY: 8.,S. GRANTH AM OPERATOR TRAINING SUPERINTENDENT DATE: 05/15/98 Performance Tests The following performance tests will be conducted (in addition to the annual operability tests) in the fourth year following certification (Normal Operation Tests, Malfunction Te.:s, and Transient Tests not tested as Annual Operability Tests):
05-12 Loss or degraded electrical power to the station, loss of power to the individual instrumentation buses (AC) that provide power to control room indication or plant control functions affecting the plant's response 05-13 Loss or deFraded electrical power to the station, loss of power to the individual instrumentation buses (IX') that provide power to control room indication or plant control functions affecting the plant's response 05-17 Loss of shutdown cooling 05-18 Loss of component cooling system or cooling to individual components 05-19 Loss of normal feedwater or normal feedwater system failure 05-20 Loss of aP feedwater (normal and emergency) 05-35 Process instrumentation, alarms, and control system failures 05-36 Passive malfunctions in systems, such as engineered safety features, emerfency feedwater systems 05-37 Failure of the automatic reactor trip system 06-14 Operator conducted surveillance testing on safety-related equipment or systems.
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WORKSilEET 15-02 PLANT E.1. HATCil SIMULATOR CERTIFICATION PLAN PAGE 4 OF 4 W,S. TITLE:
SIMULATOR INFORMATION ATTACHMEN f REVISION 1 PREPARED BY: C. B. Srnith DATE: _05/15/98 REVIEWED BY:1 RICHTER DATE: 05/15/98 LIST OF CilANGES SINCE LAST REPORT Initial Conditions: None Test Plan changes: None Test Changes:
1995: Power Uprate changed various tests for Unit 2 response.
1996: Power Uprate Changed various tests for Uniti response, 1997:
TEST #:
CIIANGE:
0509:
Test was performed on 1/30/97 prior to implementing DCR 95-054. It was subsequently performed on 6/19/97 to 4160 2E document performance changes.
DCR 92-086: modified power supply to condensate, CDPs, and RFPs minimum flow valves such that on a loss of Instrument Bus 2A, only the isolation valves will fail open. The flow control valves are powered by Vital AC and will remain closed (or cycle at flow setpoint).
DCR 95-054 (053): modified power supply to RFP 2A M/A Station controller,2C32-R601 A, from Vital AC to j
instrument Bus 2A. Upon loss of power to the controller, it will default to TMR Mark V Speedsetter control and maintain its speed one second prior to the power failure. No transient will occur from this malfunction, hence, the intervals had to be modified.
DCR 94-008 (007); totally changed APRMs from six to four, installed ODAs on 21111-P603, and modified power supply for each APRM to be powered from both RPS buses. A loss of one RPS bus will not deenergize any APRM.
0511 Reran 0511 test because DCR 95-054 (053) changed the power supply of RFPT M/A station 2A power supply from Vital AC to Instrument Bus 2A. This totally changed the response to a loss of Vital AC.
Various DCR 94-034 modified stroke time of 2E51-F045 to approximately 41 seconds which affects injection time of RCIC.
0531 Power uprate DCRs94-035 & -036 (94-040 & -041) modified steam flow and feed flow scales and strategic setpoints (PCIS Group 1 isolation on high flow). Thus, a group 1 isolation did not occur on this test.
0533 MDC 94-5044 (5029) removed the low hotwell trip on the Condensate Pumps. On a low level condition with no operator action (ARP requires pumps to be manually tripped under certain conditions), the CDPs will lose NPSil and become ineffective in maintaining RFP suction pressure causing flow rates to decrease, eventually resulting in RFPs tripping on low suction pressure.
0703 DCR 94-036 (94441) modified the SRV mechanical and electrical lift setpoints from 1090,1100 psig, & 1110 to 1120, 1130, & 1140 psig. DCR 95-072 (95-071) modified the SRV mechanical lift setpoints to 1150 psig for all eleven valves. Future tests will reflect SRVs lifting on their cIcctrical lift setpoints vs the mechanical lift setpoint of 1150 psig.
Recire pumps high pressure trip value was changed from 1086 psig to i170 psig per SCR 9503032 (DCR 94-036).
On this test, recirc pumps did not trip on high pressure.
0710 Changed termination criteria to "RWL increased above +32" and pressure increased by CDPs."
l 1998:
TEST #:
CilANGE:
0537 Transient initiator Malfunction #97 Steam flow Totalizer failure would not cause a transient due to DCR 95-054.
This DCR changed the Reac tor Level control system such that this malfunction no longer causes a loss of level.
Replaced with a transmitter og erride malfunction.
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-,n= 0 u, me en in e. nest FACluTY DOCNET NUMBER E.I. HATCH, Unit 1. Nuclear Power Station so-321 LICENSEE DATE Southern Nuclear Operating Company 5-15-98 Tn... c.wy m.t
- 1. The above named facihty tiennees is unme a ennulahan feniley anneonne esissy of a planth sendaior that meets ins reemements of 10 CFR 66 46.
- 2. Documentshon W eveMeMe for NRC feview m encontmos mWn 10 CFR 66 46@k
- 3. The senulaban localdy meets the gunennes coneamed m ANSeANS 3 51985 er AN$ muss 3 5-1810, as endomed by NRC Repdatory Guuss 1140.
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N E <- an-nucaons ANo LOCATION OF SmauLATiON FACiuTY.
E.I. Hatch Simulator US 1 North Approx. 12 miles North of Baxley, Ga Zip 31515 SRAULATION FACluTY PERFORMANCE TEST ASSTRACTS ATTACHED. (For poennense feats conshmend a she poned sneap wm Die deep of the corMoseon) a x
1 DESCRIPTION OF PERFORRAANCE TESTING COMPLETED. (Anncn amesons pages se nosassay ans asenwy pie som essanpean ammg annenses)
The Plant E.I. Hatch Unit Two Training Simulator is utilized to perform Unit One Simulator Training.
The performance tests were run per the Unit Two certification.
Operational characteristics of Unit One were considered and differences which impact training are identified as exceptions in the Attachment 1 to this form.
Sm4ULATION FACILITY PERFORMANCE TESTING SCHEDULE ATTACHED (por she conshof of aspermeadwy 29'ofpeermance asser paryear er the anyyear paned X
eo nrre.i ae ora m a= wn= =racaca s DESCRIPTION OF PERFORMANCE TESTweG TO BE CONDUCTED (Assen assoonW pages as assessary ans assnefy sne som ensanpaon some conomme)
The Plant E.1. Hatch Unit Two Training Simulator is utilized to perform Unit One Simulator Training. The performance tests will be run per the Unit Two Certification.
Operational characteristics of Unit One will be considered and differences which impact. training will be identified.
PERFORMANCE TESTING PLAN CHANOE. (For any mode seon so e poennenos fuseng pian esenuesd on a penous careensson)
DESCRa i,un OF PERFORMANCE TESTING PLAN CHANGE (Amsco seasons pages as nessenery and afsne$ #e dem sneenpoon temp consnueWJ See Unit Two SIMULATOR FACILITY CERTIFICATION Form 474.
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l Plant E. I. Ilatch, Uzit i Docket # 50 321 So:thern Nucle:r Operating Compa1y l 05/15/98 i
Facility design and systems relevant to control room personnel, Technical Specifications, Procedures (primarily abnormal and emerFency operating procedures), Control room design and instrumentation / control location, and Operational characteristics are generally the same between Unit One and the simulator with exceptions as noted in this attachment. Enclosed in this attachment is a summary of the analysis of the differences between Unit One and the simulator facility in compliance with Regulatory Guide 1.149.
Exceptions to ANSI /ANS 3.5 - 1983 for Unit One are the same as those specified for Unit Two. In addition, Exceptions
- 010 and #01 I are Unit One Operational Characteristics exceptions.
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EXCEPTIONS j
05/15 S 8 Plant E.1. Ilatch, Unit I Docket # 50-321 Southern Nuclear Operating Company l
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i PLANT E.1. II ATCli SIMULATOR CERTIFICATION PLAN PAGE 12 TITLE:
CERTIFICATION EXCEPTIONS REVISION I t
PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RICIITER DATE:01-31-89 l
APPROVED BY: R.S.GRANTilAM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 EXCEPTION NUMBER: _Q11 ANSI SPECIFICATION: 3.1.2 m TITLE: Loss of Normal Feedwater or Normal Feedwater System Failure EXCEirTION:
Unit One only Section 3.1 of the Standard requires that the operator shall not observe a difference between the response of the simulator control room instrumentation and the the reference plant. GPC takes exception to these requirements only for the Unit One feedwater heater extraction pressure indication in the control room on an isolation of the extraction steam to a feedwater heater. Unit One 5th stage heater extraction pressure would decrease vice increase due to the kcation of the pressure detector;i.e., Unit One pressure is measured downstream of the heater isolation valve - Unit Two pressure is located upstream of the heater isolation valve.
JUSTIFICATION:
On an isolation of extraction steam to a Unit One feedwater heater, extraction pressure and feedwater temperature would decrease. Reactor power would increase in response to the feedwater temperature decrease. The operator would take initial action on the feedwater temperature indication and not on the heater pressure change. The operator would utilize the heater pressure later to diagnose the cause of the feedwater temperature change. On an isolation of extraction steam to a feedwater heater in the simulator, feedwater temperature decreases but extraction pressure increases (simulating Unit Two's response). This difference in extraction pressure indication is taught to all licensed personnel in the Initial License Training Program at Plant flatch.
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PLANT E.1. II ATCil SIMULATOR CERTIFICATION PLAN PAGE I1 l
TITLE:
CERTIFICATION EXCEPTIONS REVISION 1 l
PERFORMED BY: RUTAN DATE:01-31-89 REVIEWED BY: J. RIC11TER DATE:01-31-89 l
APPROVED BY: R.S. GRANTH AM OPERATOR TRAINING SUPERVISOR DATE:12-20-89 1
EXCEPTION NUMBER: J.l0 ANSISPECIFICATION: 4.1(3)
TITLE: Performance Criteria - Steady State Operation EXCEPTION:
Unit One only Appendix B of the Standard requires feedwater temperature to be a recorded parameter for steady state performance of a minimum of three points over the power range. Section 3.1 of the Standard requires that the operator shall not observe a difference between the response of the simulator control room instrumentation and the the mference plant. Section 4.1 (3) requires the simulator values for critical parameters shall agree within 2% of the reference plant and shall not detract from training. GPC takes exception to these requirements only to the extent of the feedwater temperature parameter tolerance of within 2% of the Unit One reference plant.
JUSTIFICATION:
Unit One utilizes only the fifth stage of extraction steam from the high pressure turbine for feedwater heating.
Unit Two utilizes the fourth and the sixth stages of extraction steam from the high pressure turbine for feedwater heating. The Plant E.I. Ilatch Simulator is modeled after the Unit Two reference plant. This results in the feedwater temperature being lower on Unit One than on Unit Two (and therefore the simulator) by more than the 2% criteria. This difference in feedwater heater and extraction drain system is taught to all licensed personnel in the initial License Training Program at Plant flatch.
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Plut E. L H:tch, Uzit i Dockst # 50-3"Il SoIth:ra Nucle:r Oper: ting CompIny 05/15/98 Hardware and Environmental Differences The E.1. Hatch sinm'ator is modeled after the Unit Two control room. The specific hardware and environmental differences between Unit One and Unit Two Control Rooms were assembled and evaluated to determine the significance of each (major differences which could have a negative impact if a component, component location or environmental condition were not identical). Any noted differences have been evaluated for there potential training impact and are addressed in the Operator Initial License Training Program and in the Licensed Operator Requalification Training Program, as applicable.
I The panels that have been simulated in the E.1. Hatch simulator maintain correct physical relationships to the panels of the Unit One and Unit Two control rooms with minor exceptions related to Unit One Mck panel locations. Control room design and instrumentation / control location are the same between Unit One and Unit Two except as noted below. Environmental conditions (noise level, AC and DC lighting levels, etc.) were evaluated with only minor differences existing.
A summary of the areas identified as differences are as follows:
The simulator includes the contro8 panel for the Hydrogen Recombiners associated with Unit Two. This e
panel is not located in the Unit One control room.
The simulator models the Drywell Chillers and Drywell Cooler arrangement of Unit Two. Unit One uses a e
similar Drywell Cooler arrangement but uses Plant Service Water as the cooling medium vice using Drywell Chillers.
Unit One uses a fifth stage Feedwater Heater with the associated control, indications, and annunciators on front panel P650. Unit Two uses a fourth and sixth stage Feedwater Heater with the associated control and indications on front panel P650 with the annunciators located on back panel P656 (operators are prompted on front panel P650 by a Feedwater Heater Trouble annunciator).
The Unit One control panels contain controls and annunciators for the Main Stack Dilution system, e
Recombiner Building Ventilation system, and the Main Control Room Environmental Control system. Unit Two does not control these plant systems.
The controls and mimic for the LPCI inverters and buses (S018A and S018B) are located on front panel P601 for Unit One and on front panel P652 for Unit Two.
i Nomenclature and MPL label plate wording is not always identical. For example, the label for a Unit One e
relief valve reads "LLS/ Manual Relief Viv 1B21-F013H". The label for the corresponding relief valve for Unit Two " Auto Relief 2B21-F013H".
The Control Building Ventilation system is controlled from Unit One back panels. Unit Two does not control this plant system.
GPC believes the differences noted during the in-depth hardware and environmental review to be acceptable with respect to use of the E.1. Hatch simulator for operator training for both Unit One and Unit Two.
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Pint E. L Hitch, Unit i Dock:t # $0-321 SouthIrn Nucle:r Operztirg Compny 05/15/98
. Operating Procedure Differences The unit specific operating procedures for both units were compared side by side on a one for one basis using tne Unit Two operating procedures as the comparison measure. The Unit Two procedures are used in the simulator and require no modification or changes from those used in the plant. The specific differences between the Unit One and Unit Two procedures were assembled and compared to determine the significance of each (major differences which could have a negative effect if using Unit Two operating procedures for operation of Unit One) and to determine the disposition to address these differences in the E.1. Hatch L
Licensed Operator Training programs.
'Ihe comparison of Unit One and Unit Two procedures focused on the procedures identified for use in simulator training scenarios as part of the Licensed Operator Training Program Master Plans. Procedures not used for simulator training and not specified by the Master Plan were not addressed in this comparisc,n. The types of procedures address-d in this comparison included L
System, Abnormal, and Emergency Operating procedures, Surveillance Procedures, and Administrative Control procedures.
The Unit One and Unit Two operating procedures are essentially identical. Minor differences concerning specific equipment and operating practices were noted during the evaluation. Differences that have been identified between each unit's p
' procedures are addressed in the Operator Initial License Training Program and in the Licensed Operator Requalification Training Program, as applicable.
A summary of the areas identified as differences are as follows:
Unit specific components are covered only by the procedures associated with that unit. (Unit Two has procedures covering the operation of the Post LOCA Hydrogen Recombiner system, the Standby Plant Service Water pump for the B Diesel Generator, and the Drywell Chillers. Unit One does not have these systems.)
l Unit specific surveillr.nce procedures are used to address surveillance items not required by both units (e.g.,
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i "MSIV EXERCISE" testing is not required for Unit 2).
. Emergency Operating Procedures provide specific MPL numbers for those indications required to be l.
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monitored for an action step in the flow charts, abnormal, and EOP 100 series procedures. In some cases, the MPL number for a specific parameter is different between Unit One and Unit Two. (e.g. Different MPL numbers are specified for an.RTD at the same location in both units when used to determine average drywell temperature.)
Differences in setpoints, entry conditions, and various other operational differences have also been addressed.
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GPC believes these differences are acceptable with respect to the use of the E.1. Hatch simulator for operator training for both Unit One and Unit Two.
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Pimit E. I. H:tch, Uxit i Dockit # 50-321 South rn Nucle:r Operating Ccmp2sy 05/15/98 Technical Specification Differences l
The Technical Specifications for Unit One and Unit Two were compared side by side on a one for or,e basis using the Unit l
Two Technical Specifications as the comparison measure. The specific differences betiveen the two units were assembled and compared to determine the significance ofeach (major differences which could have a negative effect when using Unit Two l
Technical Specifications for operation of Unit One) and to detennine the disposition to address these differences in the E.I. Hatch Licensed Operator Training programs.
The Unit One and Unit Two Technical Specifications are very similar with regard to the items covered and the approach to inoperable equipment. Differences that have been identified between each unit's specifications are addressed in the Operator Initial License Training Program and in the Licensed Operator Requalification Training Program, as applicable.
A summary of the areas identified as differences are as follows:
Unit specific components are covered only by the Technical Specifications associated with that unit. (i.e. Unit e
One has specification regarding the Recombiner Building components. Unit Two does not have a Recombiner Building. Unit Two has a Hydrogen Recombiner system covered by Technical Specifications.
Unit One does not have this system.)
Surveillance intervals are very similar except for unit specific components identified above.
e Differences in minor Technical Specification setpoint differences were also addressed.
1 The Technical Requirements Manuals (TRM) are very similar with the exception that Unit 2 has a section T 9.2 (Primary Containment Penetration Conductor Overcurrent Protective Devices - Table T9.2-1)
GPC believes these differences are acceptable with respect to the use of the E.I. Hatch simulator for operator training for both Unit One and Unit Two.
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