ML16256A641
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Enclosure 2 LR-N16-0113 LAR H15-01 NUREG-0800 Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses 3-
Page 1 of 3 HCGS PRNM UPGRADE APPENDIX 18-A ASSESSMENT:
CREDITING MANUAL OPERATOR ACTIONS IN DIVERSITY AND DEFENSE-IN-DEPTH ANALYSES
- 1. Introduction Section 4.1.2, "Instability," of Appendix I (D3 Analysis) to NEDC-33864P (NEDO-33864),
Revision 0 (Enclosures 3 and 2 to LAR H15-01), identified that the diverse means for the safety trip function performed by the DSS-CD (Detect and Suppress Solution-Confirmation Density) algorithms at HCGS for the postulated common-cause failure (CCF) in Power Range Neutron Monitoring (PRNM) is Manual Operator Action. Two scenarios were identified that relied on manual operator actions; Two Recirculation Pump Trip (2RPT) and Loss of Feedwater Heating (LFWH).
This report provides supplemental information in accordance with NUREG-0800, Appendix 18-A, demonstrating that (1) the time available to perform the required manual actions is greater than the time required for the operator(s) to perform the actions, and (2) the operator(s) can perform the actions correctly and reliably in the time available.
The required Phases of Appendix 18-A are addressed below (note that Phase 2 is N/A for HCGS).
- 2. Analysis (Appendix 18-A Phase 1)
Time Available The time available to perform the actions should be based on analysis of the plant response to the AOO/PA using realistic assumptions, and the acceptance criteria of BTP 7-19.
The analysis provided in Appendix I (D3 Analysis) is consistent with Appendix 18-A. The time available for each event was analyzed and documented in Section 4.1.2 of Appendix I of NEDC-33864P (50 seconds for 2RPT and 392 seconds for LFWH). An assessment of the analysis performed against the guidance/criteria of Appendix 18-A is provided in Attachment A of this report.
Time Required The time required for operator action should be based on an HFE analysis of operator response time.
Prior experience with tasks or subtasks similar to the actions proposed to be credited in the defense-in-depth analysis may provide valuable insights for the analysis/estimates of operator response times.
The time required estimate was evaluated as follows:
As discussed in Appendix I (D3 Analysis), both scenarios require immediate operator action per existing procedures.
For the 2RPT scenario the required sole action is to immediately reduce power (lock the Mode switch in shutdown per procedure).
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For the LFWH scenario, the required sole action is to immediately reduce and maintain reactor power to the pre-feedwater heater trip or isolation value per procedure. (As explained in the D3 analysis, the LFWH event is initiated from a point near the minimum pump speed line and the Backup Stability Protection (BSP) Region I boundary. Since both recirculation pumps are at minimum speed, inserting rods is the only means available to reduce reactor power.)
Operators have existing experience (Simulator) with both the 2RPT and LFWH events using the diverse systems credited in the D3 analysis.
The diverse systems that are available are provided by control room annunciators and indicators (ie no remote operator action is required).
The diverse systems remain unchanged by the PRNM upgrade; the diverse operator actions are not performed on the PRNM system.
Based on the above it was determined, with Operations input and review, that the action(s) could be accomplished within the available time. As discussed below, the Integrated System Validation (ISV) validated that the actions can be accomplished within the time available with margin.
Time Margin A time margin should exist between the analyzed time(s) as the difference between time available and time required for operator action is a measure of the safety margin and as it decreases, uncertainty in the estimate of the difference between these times should be appropriately considered.
One acceptable method is for the time margin to equal the maximum recovery time for any single credible operator error.
As discussed under Time Required immediate operator action is required. Since all diverse indications are in the control room and since only one operator action is required, it was concluded that any potential errors would not jeopardize the time margin; sufficient recovery time is available (i.e. these are not complex situations as discussed in NUREG-0800 Appendix 18-A).
The ISV validated the time margin.
3.
Integrated System Validation (Appendix 18-A Phase 3)
The vendor/licensee/applicant should conduct an ISV of manual actions credited in the defense-in-depth analysis using a plant-referenced simulator in real time.
Performance times should be compared to the time available (per defense-in-depth analysis results) and previous estimates of time required.
As noted in Section 2 above, the diverse systems credited remain unchanged by the PRNM upgrade; therefore modification of the simulator with the PRNM upgrade was not required to accurately perform the ISV. As noted in Section G.1 of the PRNM LTR (NEDC-32410P-A):
The information available to the operator is the same as with the current system. No actions are required by the operator to obtain information normally used and equivalent
Page 3 of 3 to that available with the current equipment. However, the replacement system does provide more directly accessible information regarding the condition of the equipment, including automatic self-test, which can aid the operator in diagnosing unusual situations beyond those defined in the licensing basis.
Therefore, replacement of the system will not affect operator response to the events analyzed and will not affect the time required to perform the mitigating actions.
2RPT (Time Available = 50 Seconds)
Attachment B of this report provides the ISV results for the 2RPT scenario with the postulated common-cause failure (CCF) in PRNM. The plant referenced simulator was used and for all Operating crews the time margin was greater than 75%. The mean time required was 9.8 seconds, the maximum required was 12 seconds. All correct actions were taken and verified.
LFWH (Time Available = 392 seconds)
Attachment C of this report provides the ISV results for the LFWH scenario with the postulated common-cause failure (CCF) in PRNM. The plant referenced simulator was used and for all Operating crews the time margin was greater than 20%. The mean time required was 191 seconds, the maximum required was 304 seconds. All correct actions were taken and verified.
4.
Maintaining Long-Term Integrity / Monitoring (Appendix 18-A Phase 4)
The vendor/licensee/applicant should establish a strategy for long-term monitoring of operator ability to reliably perform the manual operator actions credited in a defense-in-depth analysis.
The two scenarios (2RPT and LFWH) identified in Appendix I (D3 Analysis) to NEDC-33864P (NEDO-33864) will be added to the HCGS procedure OP-HC-102-106, Hope Creek Master List of Time Critical and Time Sensitive Operator Actions. The scenarios will be added to the Master List of Time Critical Actions (MLTCA); i.e., actions required to be completed within a certain time period as identified in the plants licensing basis.
5.
Conclusions The manual operator actions credited in the HCGS PRNM D3 Analysis conform to the guidance provided in NUREG-0800, Appendix 18-A. The results demonstrate that the manual actions in response to a BTP 7-19 software CCF are both feasible and reliable, given the time available, and that the ability of operators to perform credited actions reliably will be maintained for as long as the manual actions are necessary to satisfy the defense-in-depth analysis.
Page 1 of 4 18-A ATTACHMENT A Phase 1 Time Available - Review Against Appendix 18-A Guidance App 18A Phase App 18A Requirement Action Completed 1 / Analysis The time available to perform the actions should be based on analysis of the plant response to the AOO/PA using realistic assumptions, and the acceptance criteria of BTP 7-19 (ie the time before the task must be completed to satisfy the diverse action)
The analysis conducted for Appendix I (D3 Analysis) is consistent with Appendix 18-A.
The time available for each event was analyzed and documented in Section 4.1.2 of Appendix I of NEDC-33864P (50 seconds for 2RPT and 392 seconds for LFWH).
Appendix 18A provides the following guidance for determining the time available (excerpts from Appendix 18A).
Section C. Staff Position Page 18-A-3 The time available for manual actions should be based upon the methods and criteria prescribed in BTP 7-19.
BTP 7-19 discussed below.
Section 1.A. Method Page 18-A-3 The time available to perform the actions should be based on analysis of the plant response to the AOO/PA using realistic assumptions, and the acceptance criteria of BTP 7-19.
This statement does not specify methods but does allow the use of realistic assumptions (see BTP 7-19 discussion later).
Section 1.B. Review Criteria Page 18-A-5 The analysis establishes the time available using an analysis method and acceptance criteria consistent with the guidance of BTP 7-19. The basis for the time available is documented.
The statement does not identify a specific method but refers to BTP 7-19 (BTP 7-19 discussed below).
BTP 7-19 provides the following guidance for determining the time available (excerpts from BTP 7-19).
Section 1.4 Four-Point Position, Point 2, Page 7-19-6 In performing the assessment, the vendor or applicant shall analyze each postulated common-mode failure for each event that is evaluated in the accident analysis section of
Page 2 of 4 the safety analysis report (SAR) using best-estimate methods. The vendor or applicant shall demonstrate adequate diversity within the design for each of these events.
o Concerning Point 2 Page 7-19-7 The term best-estimate methods is more accurately referred to as realistic assumptions, which are defined as normal plant conditions corresponding to the event. For example:
- power levels,
- temperatures,
- pressures,
- flows, and
- alignments of equipment.
Thus, in performing the assessment, the vendor or applicant should analyze each postulated CCF for each event that is evaluated in the SAR section analyzing power operation accidents at the plant conditions corresponding to the event. This analysis may use realistic assumptions to analyze the plant response to DBEs, or the conservative assumptions on which the Chapter 15 SAR analysis is based.
Point 2 and the clarification provided in Concerning Point 2 does not define a specific analytical method and allows for the use of realistic or Chapter 15 type assumptions (i.e, use a method capable of simulating the event and may use realistic or Chapter 15 assumptions as input). The TRACG stability analysis performed by GEH is consistent with this interpretation to determine the time available.
Section 1.6 D3 Assessment Page 7-19-10 In this assessment, the applicant may use realistic assumptions to analyze the plant response to DBEs (as identified in the SAR).
Repetitive guidance to Point 2 discussion above.
Section 3.1 Specific Acceptance Criteria Page 7-19-14 (Criteria applicable to the D3 stability assessment and time available discussed below).
(1) For each anticipated operational occurrence in the design basis occurring in conjunction with each single postulated CCF, the plant response calculated using realistic assumptions should not result in radiation release exceeding 10 percent of the applicable siting dose guideline values or violation of the integrity of the primary coolant pressure boundary. The applicant should (1) demonstrate that sufficient diversity exists to achieve these goals, (2) identify the vulnerabilities discovered and the corrective actions taken, or (3) identify the vulnerabilities discovered and provide a documented basis that justifies taking no action.
By conservatively using the SLMCPR as the acceptance criteria for the D3 stability assessment, no fuel fails as a result of the events. In addition, the stability events do not cause a pressurization which would challenge the reactor coolant pressure boundary. (If
Page 3 of 4 stability assumed to be an AOO; see (2) below if stability were assumed to be an accident (DBE). In either case BT 7-19 acceptance criteria is met).
(2) For each postulated accident in the design basis occurring in conjunction with each single postulated CCF, the plant response calculated using realistic assumptions should not result in radiation release exceeding the applicable siting dose guideline values, violation of the integrity of the primary coolant pressure boundary, or violation of the integrity of the containment (i.e., exceeding coolant system or containment design limits). The applicant should (1) demonstrate that sufficient diversity exists to achieve these goals, (2) identify the vulnerabilities discovered and the corrective actions taken, or (3) identify the vulnerabilities discovered and provide a documented basis that justifies taking no action.
By conservatively using the SLMCPR as the acceptance criteria for the D3 stability assessment, no fuel fails as a result of the events. In addition, the stability events do not cause a pressurization which would challenge the reactor coolant pressure boundary or mass / energy releases to the containment which would challenge containment integrity.
Section 3.3 Single Failure and CCF Page 7-19-16 Since CCF is not classified as a single failure (as defined in RG 1.53), a postulated CCF need not be assumed to be a single failure in design basis evaluations. Consequently, realistic assumptions can be employed in performing analyses to evaluate the effect of CCF coincident with DBEs.
Repetitive guidance to Point 2 discussion above.
Section 4.5 Identification of Alternate Trip or Initiation Sequences Page 7-19-21 Thermal-hydraulic analyses using realistic assumptions of the sequence of events that would occur if the primary trip channel failed to trip the reactor or actuate ESF are included in the assessment. (Coordination with the organization responsible for the review of reactor systems is necessary in reviewing these analyses.)
The TRACG analysis tool utilized by GEH to assess the plant response to the proposed D3 stability events is a thermal hydraulic analysis which used realistic assumptions (realistic assumptions as clarified above in item Concerning Point 2 above).
Section 4.6 Identification of Alternative Mitigation Capability Page 7-19-21 For each DBE, alternate mitigation actuation functions that will prevent or mitigate core damage and unacceptable release of radioactivity should be identified. When operator action is cited as the diverse means for response to an event, the applicant should demonstrate that adequate information (indication), appropriate operator training, and sufficient time for operator action are available in accordance with Appendix 18-A of SRP Chapter 18.
By conservatively using the SLMCPR as the acceptance criteria and the proposed manual operator actions for the D3 stability assessment, no fuel fails as a result of the events. In addition, the stability events do not cause a pressurization which would
Page 4 of 4 challenge the reactor coolant pressure boundary or mass / energy releases to the containment which would challenge containment integrity.
General Comment Note: the term time available is not a defined term, i.e., there is no Definition in either Appendix 18A or BTP 7-19. From the context of how the term is used in both documents, PSEG interprets the definition as:
Time Available:
The time from initiation of a Safety Analysis Report event with a common-cause failure (CCF) to the time when the acceptance criteria of BTP 7-19 would be exceeded.
Note: The BTP 7-19 acceptance criteria is 10% fuel failure. For the D3 analysis PSEG conservatively used the SLMCPR as the acceptance criteria, as discussed above.
18-A ATTACHMENT B 2RPT Independent System Validation
Hope Creek Operations Crew A Date 3/2/16 Scenario - 2RPT from 100 % power
- 1. Time available for Operator response - 50 seconds.
- 2. Time required for Operators to respond to initiating event - 8 seconds
- 3. Action expected to be taken -
- 1. Immediate Operator action from memory - Lock Mode switch in Shutdown per HC.OP-AB-RPV-0003(Q)
- 4. Indications available to Operators to diagnose event.
Overhead annunciators C1D4/D5 - A/B Reactor Recirc A/B trouble Recirc pump drive motor breaker flashing OPEN bezel indications - 10C651C
- 5. Actions taken by Operators.
Operators upon verifying trips of both Rx Recirc pumps with the reactor critical, from memory took their immediate operator actions and LOCKED the Rx mode switch in the shutdown position.
- 6. Procedures used that provided guidance.
HC.OP-AB-RPV-0003(Q)
- 7. Did Operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included.
The plots showing Rx power, A/B Recirc pump speed, Rx pressure, and the RPS mode switch position (Run,Shutdown). Time - 8 seconds TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Recirc pump trips - then the RPS Mode switch position change from Run to Shutdown. Time - 8 seconds HC.OP-AB.RPV-0003(Q) - RECIRCULATION SYSTEM/POWER OSCILLATIONS ABNORMAL. (First three pages only.)
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- RPS MODE SWITCH.. RUN (DI)- Monitor
- 00:14:22 False
- Blank Description - Monitor Yes
PSEG Internal Use On!)!
HC. OP-AB.RPV
.. 0003(Q}
RECIRCULATION SYSiSM/POWER OSCILLATIONS Effective Date: 3 Feb 2016 I :
CATEGORY II REACTOR REClRC PUMPS TRIP REACTOR RECIRC PUMP VIB HI COMPUTER POINT IN ALARM LPRM UPSCALE LPRM DOWNSCALE OPRM TRIP ENABLE OPRMAL.ARM OPRM TRIP BYP/INOP/TRSL OPRM IRIP INDICATIONS Unexplained Change in:
ct
.. o3 C1-E4 C1.. F5 C3*D5 C3E5 C3F1 C3
.. F2 C3-F3 C5-B1
> Recirculation Pump Flowr Rx Water Levell Rx Power, Rx Recirc Pump Seal Performance.
Trip of EITHER Re.circ Pump as Indicated b :
> *Recite Pump RPT Breaker OPEN,
0f?f1 Recirc MG Field Breaker OPEN.
The indicated Recirculation loop flow differs by more than
> 10% from the established pump speed"loop flow characteristtcs, 10% from the established total core flow value derived from Recirculationfoopflow. lhe i!idicated diffllser/to-lower plenum differential pressure of any individual jet pump differsfrom the established patterns by more than 20%.
Reclrculatlon Pump Vibration Levels Rising,.
APRM OR LPRM power oscillations.
An OPRM Channel indicates a trip OR alarming condition.
Short Period afarmsl Positive and negative swings on the period meter.
Reclrc Pump seal cavity temperature greater than 160 degrees F (A2998,. A2999, A3008, A3009).
Recirc Pump #2 seal cavity pressure less than 200 paig OR greater than 800 psig.
(A2590, A2592).
TERMINATED Oate/Ti:me: _______ _
Hope creek Page 1: of 40 Rev.30
I.
HC.OP*AB.RPV
.. 0003(Q)
.RECIRCULATION SYSTEM/POWER OSCilLA1IONS RETAINMENt OVERRIDE CONDITION ACTION Affected Recite Pump seal cavity
La REDUCE the affected Reeirc pump temperature greater than 200 degrees F speed to mlnimum, TRIP the affected Reclrc pump and Date/Time:
enter Condition A
- -*
NOTES;
- 1., pg 3 or 4, "POWER TO FLOW MAP (OPRM INOPt:RAE3LE)" is required to be utilized as part of an alternate method to detect and suppress thermal hydraulic instability oscillations to corn ply with T/S 3.3, 11 action a.3 or b.1.
ADDITIONAl INFORMATION:
REFER to Attachment 4 forPOWER TO FLOW MAP Power Oscillations (Thermal Hydraulic Instabilities} are defined as any ofthe following:
10% peak to peak Power Oscillations on APRMs Periodic Upscale OR. Downscale LPRM Alarms (on the Full Core Display)
Strong* positive/negative swings an the Period Meters Hope Creek Page 2 of40 Rev. 30
PScG Internal. Use Ol'lly HC.OP*AB.RPV-0003(Q)
R.ECIRCULATION SYSTEM/POWER OSCILLATIONS Indications of Power Oscillations LOCK the Mode Switch ln SHUTDOWN.
(Thermal Hydraulic Instability)
[CD354F] [IER L2 15;.34, Rec. 1c]
Date/Tlme:
- NOTE 1**
OPRM's INOPERABLE AND ln REGION 1 Date/Time:
6UTOMATIC ACTIONS IF OPRMTRIP Hope Creek LOCK the Mode Switch in SHUTDOWN.
THEN Half or Full Scram Page 3 of 40 Rev.30
-
Hope Creek Operations Crew B, Date 3/22/16 Scenario - Dual recirc pump trip from 100 % power.
- 1. Time available for operator response - 50 seconds.
- 2. Time for operators to respond to initiating event - 8 seconds
- 3. Action expected to be taken -
- 2. Immediate operator action from memory - Lock Mode switch in Shutdown per HC.OP-AB-RPV-0003(Q)
- 4. Indications available to operators to diagnose event.
Overhead annunciators C1D4/D5 - A/B Reactor Recirc A/B trouble Recirc pump drive motor breaker flashing OPEN bezel indications - 10C651C
- 5. Actions taken by operators.
Operators upon verifying trips of both Rx Recirc pumps with the reactor critical, from memory took their immediate operator actions and LOCKED the Rx mode switch in the shutdown position.
- 6. Procedures used that provided guidance.
HC.OP-AB-RPV-0003(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included.
The plots showing Rx power, A/B Recirc pump speed, Rx pressure, and the RPS mode switch position (Run,Shutdown). Time - 8 seconds TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Recirc pump trips - then the RPS Mode switch position change from Run to Shutdown. Time - 8 seconds HC.OP-AB.RPV-0003(Q) - RECIRCULATION SYSTEM/POWER OSCILLATIONS ABNORMAL. (First three pages only.)
"[
Th er Shnulation Tam ort Hope Creek Chris Kittredge, Tue Mar22 12:43:23 2016 Shift.HPRNM Dual Recirc Pump trip
!Description
" *-'"N*-*m-*" ***
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!Manito!'
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- Monitor JfV-l753B CLOSE (DI) *
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!RFPT A TRIP (Dl) Monitor iiJiMiiRED PEN-RECORDER
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- 00
- 08.:13
- 00:08:13
'00:07:55
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- 00
- 07:49
,00:07:48 False False True False 100:07:48' True
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- 00:07:46
- 00;07:24 00:07:18
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.RECORDER SELECT (DI) -*
,Monitor IIRM £:.GREEN PEl
)RECORDER SELECT (Dl)
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!RECORDER SELECT (DI)
- Monitor
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Monitor DRIVING TN/DRIVE IN DETECTOR DRIVE (Dl) -
!Monitor ACKNLDGE SECT (DI) 00:0716 l
'00:07:16 100:07:15 00:07:15 00:07:14 00:07:14 00:07:14 00:07:14 00:07:14 00:07:13 00:07:12 00:07:12 False Yes Tme Yes Ttue False Yes True Yes False Yes False Yes
!Monitor 1ACKNLDGE SE(5T {DI)
Monitor iDRIVINO IN/DRIVE IN
!DETECTOR DRIVE (DI)
!Monitor Bla1k Desctiption - Monit:
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'(Dl) -*Monitor l'fi=rrzM'i::JEirricfoR -SELECT lcDI) Monitorw,.....
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{DI) - Monit,)t
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- (DI} - Monitor
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,(DI) *. Monitet CiiDEiiicroR SELEct*
- (DI) - Mo.nitor
'B=IRM DETECTOR SELECT (DI) - Monitor
- B-IRrvfiJETECTOR SELECT
'(DI) -Monitor A-lRM DETECTOR SELECT (Dl) Monitor A-IRM DETECTORSELRCT (DI) - Moni?t' 00:07:11
- 00:07:11 00:07:11 00:07:11 00;07:10 00:07:10 00:07:09 00:01:09
'00:07:09
'00:07:09 00:07:09 00:07:09 00:07:09 00:07:08 00:07:08 00:07:08 00:07:08 00:07:0&
00:0:7:08
- 00
- 07:08 True True False True False Tnle False False True False True False True False Trne False True False T11.1e Yes Yes Yes Yes Yes Yes Yes
- D-SRM DETECTOR SELECT
'(DI)- MM.itol'
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- (Dl) '"Monitor B-
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- (D I)
- Monitor ASRM DETECTOR sBr:EcT i(Dl) -Monitor
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.(Dl) - MOititor
!POWER ON/OFF-DETEGT;OR DRIVE (D1)
- Monitor POWER ON/OFF-DETECTOR DRIVE (Dl) Monitor ROD SELECT ACCUMULATOR TROUBLE A.CKNOWL8DGE (DI)-
!Mmtitor
'ROD SELECT-
.ACCUMULATOR TROUBLE ACKNOWLEDGE (DI)-
.Monitor ACKNOWLED (DI)- Monitor ACKNOWLED (Dl)- Monitor RFPT C TRIP (DI)- Iv1ortitor POS A (DI) -Monitor RFPT C TRIP (DI)
- Monitor POS A (DI) - Monitor
'****
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- 00:07:07 00:07:07 00:07:07
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- 00:07:01 00:07:00 00:07:00 00:07:00 00:.07:00 00:07:00 00:06:57 00:06:57 00:06:55 False Yes
- --
- 1 True Yes False Yes False Yes True Yes Tme Yes False Yes Trt1e False True Yes False Yes True Yes False Yes True Yes False Yes True Yes False Yes False True True False True False Yes
iBlank Description Monitor 6if06i5s
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- '00:06:54
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- 00;06:52 00:06:52 00:06:52 00:.06:52 00:06:51 00:06:51 "m*******
00:06:49 00;06:49 00:06:49
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00:06:48
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- 00:06:41 Blank Description-Monitor
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- Brank Descdptim:l: - Monitor
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- 00:06:29
,RRM.
- C MAN fNTITIA TI (DI) -
'00:06:29 omtor False True False False Tl'ue
- mank Descdption *Monitor 00:06:29 False
.. RRCS MAN TNTlT PERM (DI)
- 00:06:2<1 False
- Monitor
!RRCS MAN INTIT PERM (Dl)
, M.
00:06:28 True omtor Blank Description
- Monitor mlank Description..
. Monitor
,Blank Desctiption - Monitor RRCS MAN INTITIATI (Dl) -
Monitor Bl.ank Desctiption - Monitor RRCS MAN INTITIATI (DI) -
Monit01' RFPT A TRIP RESET (DI)
- Monitor 00:06:28 00:06:28 00:06:28 00:06:28 00:06:28 00:06:28 00:06:28 RRCS MAN INTIT PERM (DI) 00:06:27
- Monitor Blank Desctiption - Mo11it01' RRCS MAN INTIT PERM (DI)
Monitor Blank Desctiption-Monitor Blank Description - Monitor Blank Description - Monitor Blank Description - Monitor Blank Description* Monitor Blank Description - Monitor Blank Description - Monitor Blank Description-* Mot1itot Blank Description - Monitor 00:06:27 00:06:27 00:06:27
- 00:06:27 00:06:26 00:06:26 00:06:26 00:06:26 00:06:25 00:06:25 00:06:25 False Tme False False True False False True True False True False True False True False Ttue False Yes Yes
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- Monitor iBianr<bcdption - Mo11itor
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.Blank Description - Monitor
.Blank Description - Monitor iRPSTRTP LOGIC l32 MAN
- IN IT.PUSHBUTTON (Dl) -
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- 1Monitor
]Blank Description - Monitor fi31nk Dest{ption - Monitot IRP.srru.P.io.cnc n2 MAN
- fNIT-ARM (DI) - MonitOl' Blank Description-Monitor
- Blank Description-* Monitor RPS TRIPLOGlC Bl IVIAIN INIT
- PUSHBlJTTON (DI)
Monitor RPS TRIP LOGIC B 1 MAIN 00:06:25 00:06;24 00:06:24 00:06:24
>00:06:24
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- 00;06;24 00
- 06:23 00;06:23
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'00:06:22 00:06:22 00:06:22 00:06:21 00:06:21 00:06:21 00:06:21 00:06:21 Trne False nue False True False False True False True True False False True True true False False Twe True Tme Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes
,Blattk Description Monitor
\\00:06:21
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................. *******¥*********....*
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- RPS TRIP LOGIC A iMAlN iiNIT-ARMED (Dl)
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!Monitot' iBiank Description*** Monitor 1Blank Description - Monitot
!Bia;}i i::>escription M;itor
!Blank Description " Monitor
]Blank Descripii6i1 -Monji0t;
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,Blank Description -Monitor
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,R.fp;r; A TRIP (DI) M-nitor r0:;f!r A Tru.Pcor5=M;;;ii0f:
Description Monitor iRPS MODE SWITCH
- REFUEL (DI) - Monitor i:RPS MODESWITCH -
,REFUEL (D I) - Monitor
- MN,,.., *
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'STARTUP & HOT STDY (Dl)
!Monitor
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- 00
- 06:20
- oo:o6:2o 00:06:20
- 00:06:18
'00:06:17 00:06:17
- 00
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- *** wuxyz-{l**-*}-*-~*"*
- 00:06:17
'00:06:17
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& HOT STDY (Dl)
- Monitor
!RPS MODE SWITCH RUN l(Dl) Monitor
- ---*.. m*-.,.......
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- Toggte event 21 00
- 06:15 False
- oo:06:15
.False
Hope Creek Operations Crew C, Date 3/16/16 Scenario - Dual recirc pump trip from 100 % power.
- 1. Time available for operator response - 50 seconds.
- 2. Time for operators to respond to initiating event - 10 seconds
- 3. Action expected to be taken -
- 3. Immediate operator action from memory - Lock Mode switch in Shutdown per HC.OP-AB-RPV-0003(Q)
- 4. Indications available to operators to diagnose event.
Overhead annunciators C1D4/D5 - A/B Reactor Recirc A/B trouble Recirc pump drive motor breaker flashing OPEN bezel indications - 10C651C
- 5. Actions taken by operators.
Operators upon verifying trips of both Rx Recirc pumps with the reactor critical, from memory took their immediate operator actions and LOCKED the Rx mode switch in the shutdown position.
- 6. Procedures used that provided guidance.
HC.OP-AB-RPV-0003(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included.
The plots showing Rx power, A/B Recirc pump speed, Rx pressure, and the RPS mode switch position (Run,Shutdown). Time - 10 seconds TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Recirc pump trips - then the RPS Mode switch position change from Run to Shutdown. Time - 10 seconds HC.OP-AB.RPV-0003(Q) - RECIRCULATION SYSTEM/POWER OSCILLATIONS ABNORMAL. (First three pages only.)
I Recirc Pumps Tripped
- 08:40 08:40 I
08:42 0&:44 Times are from TAMs which does not show tenths of seconds.
**
r
rhunder ?lmulation Tam Regort Hope Creek Shaffer, Wed Mar 16'10:19:54 2016 PRNM test C shift
!Desctiption
- ACKNLDGE SECT (DI)
,Monitor Value 00:11:44 False IACK.NLDOE SECT (DI)..
!Monitor 00: 11 :44 True A (Dl) Monito1*
00:11:33.
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- Monitor lACKNLbGE SECT (Di)~
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- ACKNLDGE SECT (Dl)
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'00:11:18
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- pos A (DI) - Monitor
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- EREAKER(DI) - Monitor
[TRIP-EXCITER FIELD
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!00:10:59 100:10:58 i
j00:10:57 00:10:56 00:10:56 00:10:55
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- Monitor 100:10:55
- TURBINE - TRIP (DI) -6 Monitot
- l00j6l55
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- HV -1753A CLOSE (Dl) -
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- Monitor BV1753B CI,OSE (DI)
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- 00
- 10:38
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'00:10:37
- 00:10:37 00:10:36 iOO:l0:32
- 00:10:32
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'POS A (DI) MonitoY 00:10:14 Ftlse Yes 1 -d*
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- Monitot OO:lO:IO HRM D RED PEN-RECORDER OO:IO:lO SELECT (Dl) - Monitor IR:M'aR"EDrENREC6RriER 00:1 o: 10 SELECT (DI)
- MonitOl'
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- s*E* L. 'ECT (.DI).M.
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- iiM.c:R:EDPEN*RECORDER fSELECT (DI) *Monitor OO: l O: 1 O tiR.Mc:REDPEN-RECORDER oo:lO:lO
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,RECORDER SELECT (Df) X 00:10:09 Monitor h..
'RECORDER SELECT (DI) M 1Monitor
'IRM AGREEN PEN iRECORDER SELECT (DI)
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!RECORDER SELECT (bl) -
.... --------!Monitor---------
'DRIVING IN/DRIVE IN
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'(DI) - Monitor 1H-IRM DETECTOR SELECT
'(Dl).. Monitor 1G-IRM DETECTOR SELECT
- (DI) - Monitor
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'(Dl) - Monitor
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'(Dl)- Monitor m-IRM DETECTORSELICT i(Dl) - Monitor
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.(Dl) - Monitor C-lRM DETECTOR SELECT (Dl) - Monitor 00:10:05 00:10:05 00:10:05 0:05 00:10:04 00:10:04 00:10:04 00:10:04
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- (DI) Monitor BSRM DETECTOR SELECT kDI) - Monitor iA-SRM DETECTOR SELECT
'(DI) Monitor IA
.. SRM.DETECTOR SELECT l(DI) - Monitor POWER ON/OFF-DETECTOR DRIVE (DI) -Monitor POWER ON/OFF-DETECTOR DRIVE(Dl) - Monitor ACKNLDGE SECT (DI)
Monitor ACKNLDGE SECT (DI) -
Monitor POS A (D I) - Monitor
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- 00
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Hope Creek Operations Crew D Date 2/24/16 Scenario - 2RPT from 100 % power
- 1. Time available for Operator response - 50 seconds.
- 2. Time required for Operators to respond to initiating event - 12 seconds
- 3. Action expected to be taken -
- 4. Immediate Operator action from memory - Lock Mode switch in Shutdown per HC.OP-AB-RPV-0003(Q)
- 4. Indications available to Operators to diagnose event.
Overhead annunciators C1D4/D5 - A/B Reactor Recirc A/B trouble Recirc pump drive motor breaker flashing OPEN bezel indications - 10C651C
- 5. Actions taken by Operators.
Operators upon verifying trips of both Rx Recirc pumps with the reactor critical, from memory took their immediate operator actions and LOCKED the Rx mode switch in the shutdown position.
- 6. Procedures used that provided guidance.
HC.OP-AB-RPV-0003(Q)
- 7. Did Operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included.
The plots showing Rx power, A/B Recirc pump speed, Rx pressure, and the RPS mode switch position (Run,Shutdown). Time - 12 seconds NOTE: Crew D was the first to perform the scenario and a TAMS report and Alarm chronolog from the simulator was not captured as they were for the subsequent crews. The transient plots alone clearly document the required time.
HC.OP-AB.RPV-0003(Q) - RECIRCULATION SYSTEM/POWER OSCILLATIONS ABNORMAL. (First three pages only.)
!Mode Switch to Shutdown I 1
I Recirc Pumps Tripped
Hope Creek Operations Crew E, Date 3/8/16 Scenario - Dual recirc pump trip from 100 % power.
- 1. Time available for operator response - 50 seconds.
- 2. Time for operators to respond to initiating event - 11 seconds
- 3. Action expected to be taken -
- 5. Immediate operator action from memory - Lock Mode switch in Shutdown per HC.OP-AB-RPV-0003(Q)
- 4. Indications available to operators to diagnose event.
Overhead annunciators C1D4/D5 - A/B Reactor Recirc A/B trouble Recirc pump drive motor breaker flashing OPEN bezel indications - 10C651C
- 5. Actions taken by operators.
Operators upon verifying trips of both Rx Recirc pumps with the reactor critical, from memory took their immediate operator actions and LOCKED the Rx mode switch in the shutdown position.
- 6. Procedures used that provided guidance.
HC.OP-AB-RPV-0003(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included.
The plots showing Rx power, A/B Recirc pump speed, Rx pressure, and the RPS mode switch position (Run,Shutdown). Time - 11 seconds TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Recirc pump trips - then the RPS Mode switch position change from Run to Shutdown. Time - 11 seconds HC.OP-AB.RPV-0003(Q) - RECIRCULATION SYSTEM/POWER OSCILLATIONS ABNORMAL. (First three pages only.)
Mode Switch to Shutdown Recirc Pumps Tripped
Thundet imulati n Tatn Re rt Hope Creek Chris Kittredge, Wed Mat 0910:28:25 2016
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18-A ATTACHMENT C LFWH Independent System Validation
Hope Creek Operations Crew A Date 5/12/16 Scenario - Loss of A - Feed water heating - entire string. Reactor Recirc pumps at minimum speed.
- 1. Time allowed for operator response - 6 min and 32 seconds.
- 2. Time for operators to respond to initiating event - 1 min and 44 seconds
- 3. Action expected to be taken -
Immediate operator action from memory - Reduce and Maintain Reactor power to the Pre-Feedwater Heater Trip or Isolation Value.
- 4. Indications available to operators to diagnose event:
Overhead annunciators A7-E2 - Feedwater Heater Trip Extraction steam isolation valves going close, FWH Trip lights lit and FWH reset lights extinguished on 10C650 section A Feedwater temperature lowering, followed by reactor power rising on both APRMs and core thermal power (OD-3).
Main Generator (MWE) rising.
- 5. Actions taken by operators.
Operators verified trips/isolations of Feedwater heaters.
From memory took their immediate operator actions: Reduced and Maintained Reactor Power to the Pre-Feedwater Heater Trip or Isolation Value. With Reactor Recirc pumps at minimum speed, the only means to reduce power is to insert control rods.
- 6. Procedures used that provided guidance.
HC.OP-AB-BOP-0001(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included:
The plots showing Rx power, A/B Feed Line Temperature, APRM A power. And Total Core Flow. Heater switch failure (initiating event) at 00:13:18. Feedwater temperature shows a slow lowering in temperature followed by a slow rise in reactor power. Rod Insertion begins at 00:15:02 and continues for the next several minutes to maintain power.
TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Heater switch failure (initiating event) - at time 00:13:18. Rod insertion Commences - at time 00:15:02, and continues.
HC.OP-AB.BOP-0001(Q) - Feedwater Heating (First three pages only.)
I Feed water temp. 1\\
I Rx oower I Heater 2A Hi lvl
- 13:18 11:33 13:12 I Time allowed 392 sec - 19:50 14:51 19:48
Thunder Sbnulation Ta1n ReJlort Hope ()*eek Kepley, Thu May 12 12:52:13 2016 "A" Shift PRNM. Loss of FWH rn;scriptiou
!R:o¬*siiti3cr : INsERT.
(ni)***********
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- Toggle event 2
,"Rdsiect-3039 (DI)- Monitor ou h ******
- oo:13:18 Rod Select 30-39 (DI)- Monitor )00:11 :46 1
Yes No
PSEG Internal Use Only Effective Date ___ 6_M_a_.y"--2_0_15 __ _
CATEGORY II l
FEEDWATER HEATING ALARMS
- 56i.1W¥tlii11f1EAT!JrJBliS; FEEDWATER HEATER PNL 1AIB/G C102 CROSSFLOW ALARM/TRBL INDICATIONS iiWW<ilftt.FixdwØ1,fMi\\!&HÚ.Ü1r
- Rlslng:Mairlf*otatq:.w:.
P.e W@. : D!"#$r H:t%aYE:4.:fglf? @A OQ.&'(.
'.:C *'**,. -;-<s,.,,.-. -
.-c---, o_:_,, _--m_:;_-,-,;*,c. :r <,
TERMINATED Date/Time:*-----
Hope Creek Page 1 of 20 ArS:*M*
A7*F2 B3*F2
. Rev. 18
PSEG Internal Use Only RETAINMSNT OVERRIDE CONDITION I.
Reactor power is >70% RTPAND>0.04 Increase in FLFWTR (CRIO$
II.
00*3) dua to a Loss of FeMwater Heating from a feedwaler heater trip that has OC6t,Jrred, *
[CD*979BJ Pate/Time:
Reactor power Is >70% RTPAND>0.02!ncrease*in FLFWTR(CRIDS Ob*J due to a Lm1s of Feedwatet Heatin from a feedwater heatertrlp thatMs occurred. "'*
[C0"979SJ Date/Time:
H C.OP
.. AB.BQP
.. QOO 1 (Q)
FEEOWATER HEATING ACTION I.A Within 5 tnlnutas, R!EOUCE Reactor PoWer 20%
ll.A.
BELOW the Pre-Feedwater Heater Trio Value.
Within 5 minutes, REDUCE R13actor PoWwS%
.BElLOW. the Pte*Feedwater Heater Trlp Value.
0;04 ln FLFWif{ (CRibS Otl3) Js Indication of a20"!= reductionln !=iiledwater T$mperature due to a feedwater heater trip. This e'Y!SIIW:ation should he made by.compErlng the current steadystate. FLFWTR to thf:l pre-trtp value,.
The resultant change in FLFWTR is independent ofreactor power or initial FWH configur$11on. IF >,l:WF reduction In Feedwater temperature due to a feedwater heater trip Is noted, the R.etarnment Override a.otlons Sh6uld be taken.
'<! 0.02 in FLFWTR (GRIDS QD-3) is indication of a >1 Cl"F reduction In PMdiNatr Temperature due to a reedwater heater trip, Thia evaluation shduld be made by comparing the currentsteady,state FLFWIR to ths pre-trip value, The resultant Ghange rn FLFWTR Is independent of reactor powe:r or lrHilar FWH configuration.. LE>109F reduction in Feedwater nmperature due to a feedwater hi:latertrlp Is noted, fhe Retail"lment Override action<> should be taken, ForSub$equMt FWHTR trip$, 1E subsequent.a¢tlon steps from the ABarE! tken for the lnitl.al FWHTR trip., and the plant has stabilize¢, the new Initial FLFWTRvaJue.shquld be vsed. lF a $econdFWHiR trrp: oc.curs beforeth.e plant Is stabilized from the first FWHTR ttfp, the lniUal PLFWTRValue should be used.
AtiDiifONALINFORMATION:
VALVE.
AF'-LV1532A(B,C)
ACl*HV*1633A(B,C)
AD*HV,.1620A(B,C)
AF-LV-152M(B,C)
.AF*LV*1356A(B,C)
AF*HV-1 351A(B1C)
AFHV*t388A(B,Q).
AF*LV-t514A(8,C)
AF*HV*1358A(B,Cj AF-HV*1377A{B,CJ AF*LV*1506A(B,:C)
AF*LV-1363A(B',C}
AF*LV*13&<iA(B,G}
AF*HV-1362A(B,C)
AF-HV-1<3$7A(B,C)
AF-XV1369A(B,C)
AF*fW*136i5A(B,C)
AF;HVi'366A(B,C)
AF*HV1.361A(B,d)
AF-HV-1$59A(B,C)
AF* LV*1505A(8,C)
AP., LVisl3A(B,C)
AF* LV-:15Z1A(B,Q)
AF* LVA531A(B,C)
AF'- LV"1451A(B,C)
AHV1753A(S,C)
At=*HV,1768A(B,C)
AE*HV1<744A(B,G)
AD*HVi600A(B,C)
AD-HV"HH3A(S,C)
AD*HV*l 7 4SA(8,G)
AD-HV-1625' Hope Creek OESCRIPTION FDW HTR 3 DRN VALVE HTRS 1&2 DRN OLR INLET HTRS *1 &2 DRN CLR OUTLET FDW HTR 4 DRN VALVE FWH # 3 SHELL,. SIDE. SSE: tlRAIN PWH#3 SHELL SIDE E:XTR STM!SLN FWH# 3 SHf.;U, SIDE EXTR LINE ORAIN FDW HIR5DRNVALVS FWH # 4 SHEkLSIDE E:XTRSTM ISLN FWH # 4 SHELL SIDE EXTR LINE DRAIN FDW HTR 6 DRN VALV MSIRE SEP 8 ORN LINE MSTRE St:P A bRN LINE FWH # 5 SHELL SIDE CROSS ARdtJND STM iSLN FWH # 5 SHELL SIDE XARND SIM LJNE DRAIN HTR 6 BLEEDER TRfPVALVE flWH#$SHELLS!OE EXTRSTM ISLN FWH # 6' SHE:LL SIDE EXTR STM DRN VLV FWH # 6 SHELL SIDE EXTR STM DRNVLV FWH # 6 SHELL SIDE EXTR LINE DRAIN fDW HTR e DUMP VALVE FDW HTR 5 DUMP VALVE FDW HTR 4 DUMP VALVE FDWHTR 3 DUMP VALVE FDW HTR2 DUMP VALVE HTRSOUTLET HTR6INLET HTR l;l OUTLEiT BYPASS HTRs 3 & 4 & 5 OUTLET HTRS3&4 &51NLET HTRS 3.& 4 & 5 OUTLET SYP HTRS 1&2 DRN CLR. BYPASS Page 2 of 20 CRIDS Page 27, 02854(5,6)
Page 27, 02842(3,4)
Page.27, D2830(1,2')
Page 27 D21lt8(19,20)
Page 36, D2i'79(80,81)
Page36; D27B2(B3,84}
Page 28, 02815(6,.7)
Page 21, 02627(8,9)
Page 2.7, D2839(4D.41/
Pagl!l 2.7,. 02851(2,3)
Page 25, 02757(819)
Page.28 Page28 f:lage 28, A3112( 3;4)
Pall:ec 21 Page 27 Page 27, A2916(7,B)
Page 25 Rev. 18
PSEG Internal Usa Only Dateffime:
AUTOMATIC ACTIONS IF THEN Hi-Hi level in #1 (29") or #2 (25';)
L V1532A(B,G) CLOSES FWHTR after a 1 0 second time delay li HV1633A(B,C) CLOSES
- HV--1620A(B,C) CLOSES Hi-Hi level (29") in #3 FWHTR
- LV-1523A(B,C) CLOSES
- LV-.1356A(B,C) CLOSES
'i HV-1357A(B,C) CLOSES
- HV1388A(B,C) OPENS Hl-HIIevel {29") ln #4 FWHTR L V1514A(B,C) CLOSES
- HV-1358A(B,C) CLOSES
- HV-1377A(B,C) OPENS HiHi level (29") in #5 FWHTR
- L V1506A(B,G) CLOSES L V:-1363A(B1C) CLOSES
- LV-1364A(s,C) CLOSES
., HV-1362A(B,C) CLOSES
- HV1387A(B,C) OPENS Hi-Hi level (29") in #6 FWHTR
- XV-1369A(B,C) CLOSES
- HV-1365A(B,C} CLOSES
- HV1366A(B,C} OPENS
- HV1367A(B,C) OPENS
- HV-1359A(B) OPENS FWHTR #6A(B or C) HI level of 22.5"
.. LV-150'5A(B or C) OPENS FWHTR #5A(B or C} HI level of 27.5"
- LV1513A(B or C) OPENS FWHTR #4A(B or C) HI level of 28.5"
- LV-1521A(B or C) OPENS FWHTR #3A(B or C) HI level of 25"
- LV-1531A(B or C) OPENS FWHTR #2A(B or C) HI level of 21"
- LV-1451A(B or C) OPENS Hope Creek Page3 of20 Rev.18 i
I l
Hope Creek Operations Crew B Date 4/29/16 Scenario - Loss of A - Feed water heating - entire string. Reactor Recirc pumps at minimum speed.
- 1. Time allowed for operator response - 6 min and 32 seconds.
- 2. Time for operators to respond to initiating event - 2 min and 54 seconds
- 3. Action expected to be taken -
Immediate operator action from memory - Reduce and Maintain Reactor power to the Pre-Feedwater Heater Trip or Isolation Value.
- 4. Indications available to operators to diagnose event:
Overhead annunciators A7-E2 - Feedwater Heater Trip Extraction steam isolation valves going close, FWH Trip lights lit and FWH reset lights extinguished on 10C650 section A Feedwater temperature lowering, followed by reactor power rising on both APRMs and core thermal power.
Main Generator (MWE) rising.
- 5. Actions taken by operators.
Operators verified trips/isolations of Feedwater heaters.
From memory took their immediate operator actions: Reduced and Maintained Reactor Power to the Pre-Feedwater Heater Trip or Isolation Value. With Reactor Recirc pumps at minimum speed, the only means to reduce power is to insert control rods.
- 6. Procedures used that provided guidance.
HC.OP-AB-BOP-0001(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included:
The plots showing Rx power, A/B Feed Line Temperature, APRM A power. And Total Core Flow. Heater switch failure (initiating event) at 00:10:22. Feedwater temperature shows a slow lowering in temperature followed by a slow rise in reactor power. Rod Insertion begins at 00:13:16 and continues for the next 5 minutes to maintain power.
TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Heater switch failure (initiating event) - at time 00:10:22. Rod insertion Commences - at time 00:13:16, and continues.
HC.OP-AB.BOP-0001(Q) - Feedwater Heating (First three pages only.)
I Feed water temp.
I Rx oower 1/
I First Rod inserted-13:16 Time allowed 392 sec - 16:54
Thunsler Shuu\\at\\gn Tam Report Hope Creek Chris Kittredge, Fri Apr291504=32 2016 "B" Shift PRNM - Loss ofFWli
- ** **',. *'*'*'-****"=*******',__...... ".Y'*******"--#"'*'"""""""'W"
!Description jfiV-1753A CLOSE (DI)
!Monitor
!I-N-l753A CLOSE (Dl)
!Monitor
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!Monitor Ramp Yes Yes Yes Yes Yes Yes
'""""""""""""""'"""'"'"""""""'"".........................,--******--- i
!Rod Select 22k15 (DI)-
18:17 frioøfselect 22-15 (DI) - Monitor !oo:18:17 (DI)-
'00:17:29
!RODSELECT :*iNSERT (DI) -
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.Monitor iRodSeiect 38-47 (DI) - Monitor 16:48
!Rod Select 38-47 (DI) Monitor !00:16:48
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- 1Monitor lRod 30-39 (DI)- Monitor iA.c:K'i,fow113i5(rii): Motito:
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..............-*x---Ø*---.........
- ACKNOWLED tDI) Monitor h:-iii{i.RrJ?fiTLEVEL.TRIP 1HTK2/'tRN A(LO)
,OO:J0:27 True No
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- HTR TRIP HI LEVEL TRIP
- HTR 1/TRN A (LO)
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- HTR 6-.TRN A (LO)
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- 00:10:27
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- OO: !0:22
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lMon1tor 00:10:22 HV-l362A CLOSE-FWH #5 SH.ELL. SIDESHELL-CROSS AROUND STM ISLN (DI) -
.. OO: l0:22
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- sfiELL SIDE-SHELL-EXTR 100:10:22
- STM DRN VLVS (DI) - Monitor 1 llV-1358A CLOSE-FWH #4
!SHELL SIDE-SHELL-EXT
- 00
- 10:22
'STM ISLN (Dl) - Monitor LV-1356A CLOSE STMSEAL OO:l0:22 EV AP DRN (DI) - Monitor HVl357A CLOSE-FWH#3 SHELL SIDE-SHELL-EXT 00:10:22 STM ISLN (DT) Monitor il-IS-1365A CLOSE-FWH# 6 SHELL SIDE-SHELL-EXTR 00:10:22
,STM DRN VLVS (DI) lHV-1361A CLOSE-FWH #5
- SHELL SIDE-SHELL-MSTRE
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- SEP A DRN ISLN (DI) iHV:l3.60A CLOSE-FWH#s iSHELL SIDE-SHELL-MSTRE 00:10:22 SEP B DRN ISLN (Dl) 1HV-1362A CLOSE-FWH#5 SHELL SIDESHELL-CROSS 00:10:22 AROUND STM ISLN (DI)
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- j.\\f)i{MFgain (Range
- 0.800
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- 00;08:39 iA_p_RóTEgain (Range: 0.800 Ç-
i00:08:34 h.500)
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!00:08:30
.A.PRM c gin (Range: o.soo -
-oo:os :23
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- 1\\riiMB--gaft--(Rang o:sOO :
oo:os: 19 i 1.500) iA:J?R.iViA.iail(Range: o.soo 4
!1.500)
Ttue 1.157000 1.038000 1.127000 1.045000 No
Hope Creek Operations Crew C Date 4/19/16 Scenario - Loss of A - Feed water heating - entire string. Reactor Recirc pumps at minimum speed.
- 1. Time allowed for operator response - 6 min and 32 seconds.
- 2. Time for operators to respond to initiating event - 5 min and 4 seconds
- 3. Action expected to be taken -
Immediate operator action from memory - Reduce and Maintain Reactor power to the Pre-Feedwater Heater Trip or Isolation Value.
- 4. Indications available to operators to diagnose event:
Overhead annunciators A7-E2 - Feedwater Heater Trip Extraction steam isolation valves going close, FWH Trip lights lit and FWH reset lights extinguished on 10C650 section A Feedwater temperature lowering, followed by reactor power rising on both APRMs and core thermal power.
Main Generator (MWE) rising.
- 5. Actions taken by operators.
Operators verified trips/isolations of Feedwater heaters.
From memory took their immediate operator actions: Reduced and Maintained Reactor Power to the Pre-Feedwater Heater Trip or Isolation Value. With Reactor Recirc pumps at minimum speed, the only means to reduce power is to insert control rods.
- 6. Procedures used that provided guidance.
HC.OP-AB-BOP-0001(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included:
The plots showing Rx power, A/B Feed Line Temperature, APRM A power. And Total Core Flow. Heater switch failure (initiating event) at 00:49:42. Feedwater temperature shows a slow lowering in temperature followed by a slow rise in reactor power. Rod Insertion begins at 00:54:46 and continues for the next several minutes to maintain power.
TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Heater switch failure (initiating event) - at time 00:49:42. Rod insertion Commences - at time 00:54:46, and continues.
HC.OP-AB.BOP-0001(Q) - Feedwater Heating (First three pages only.)
I Feed water temp. 1,\\i I Rx oower 1/
49,30 51:09 52:48
$5 I First Rod inserted
- 54:46 I Time allowed 392 sec - 56:14 54:Z7 56:06 57:45 DataChart -Training Load:1962
- C Shift: Loss of FWH data ID 1
Name NMAPMFX(l) c91al709 fwtina ription APRM CH.A PWR Total Core Flow Feed Line A Inlet Tem...
Feed Line B InletTem...
Value Units PCT MLB/
degF degF 500 450 400.
350 300
- 250 200 Data Chart Min Max 5.5 65 0
5e+004 0
500 0
500
Tlnuder Simulation Tam Report Hon Creek Chris Kitt;edge, Tue Aur 19 15:16:32 2016 PRNM Shift C Loss of FWH jnescripti{)n jJTime HTRTRIPHI LEVEL TRIP-HTR (ol:02:49 2/TRN A (DI) - Monitor HTR TRIP-HI LEVEL TRfP.. HTR 01;02:49 2/TRN A (DI),. Monitor CHANNEL B APRM MONITOR lo1:02:17
-. F (Dl) - Mot1itor ROD SELECT INSERT (DT)- lol:oo:ss Monitor RO SELECT INSERT (DI) - lo I :00:46 Monitor
!Rod Select 46-23 (DI) -Monitor. )jo I :00:41 IJZod Select 46-23 (DT)_ Monior [Jol:00:40 101:00:04 ROD SELECT-INSERT (DI) -
Monitor ROD SELECT E-INSERT (DI) D Monitol' IRod Select 14-39 (Dl)- Monitor
]Rod Select 14-39{DI) - Monitor ROD SELECT-INSERT (DI)-
Monitor ROD SELECT.. INSERT (DI) C Monito.r Rod Select 22-15 (DI) B Monitot IIRod Select 22-15 (DI) - Monitor IROD SELECT-INSERT(DI) F*
Monitor ROD SELECT-INSERT (DI)-
Monitor Rod Select 38Y47 (DI) Monitor Rod Select38-47 (D[)- Monitor ROD SELECT-INSERt (DI) ""
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- ---L..-___...__L_iso_ooo-----'-*-.... ---
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1500)
APR1v1 D gain (Range: 0.800 -
1.500)
APRM C gah1 (Range: 0.800-1.509)
APRM F gain (Range: 0.800-l.5QO)
APRM E gain (Range: 0.800 -
1.500)
APRM D gain (Range: 0.800-1.500)
APRlv{ C gain (Range: 0.800-1.500)
AP.R.MB gain (Range: 0.800 8 1.500)
APRM A gain (Range: 0.800 -
1.500)
APRMF gain (Range: 0.800..
1.500) 00:44:50 00:44:46 00:44:42 00:44:21 00:44:16 00:44:12 00:44:08 00:44:05 II i1VV.""t.57
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APR D gairl-(Rangœ; o:soO ; -- ;43,-19 mn c gain (Range: 0.800- 100,43,15 1,.;00)
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1.500}
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'f ACS clg valvel BE 126, to redrc MIG set.B (Q-100%)
T ACS clg valve, AE--I 26, to recirc M/G set A (0-100%)
ACKNLDGE SECT (Dl) *9 Monitor ACK1\\""LDGE SECT (Dl) -
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!ACKNOWLED (DT) - Monitor JACKNOWLED (Dl) - Monitot*
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Monito1' loo:43:o7 loo:42:ss loo:42:to 00:42:06 00:41:13 Joo:41:12 lloo:4I :09 Jloo:4l:09
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6/7/2016
ACIZNtDGE SECT (.Dl) -
Monitor ACKNLDGE SECT (DI) 6 Monitor ACKNLDGE SECT (DI) -
Monitor JBlank Descdption 5 Monitot*
!Blank Desctiption 4 Monitor ACKNOWLED (DT) Monitor ACKNOWLED (Dl) Monitor JBlank Description - Monitor
!Blank Description - Monitor JPOS A (DI}- Monitor jPOS A (DI) 3 Monitor Blank
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- Monitor Blank Description Monitor Recirc system B inadvertent xunback Recirc system A inadvertent full run back jToggle even.t 1 I
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- IID0:40:55 II lloo:4o:s5 II Joo:40:54 Jl (oo:4o:s4 II 1Joo:40:51 I[
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6/7/2016
Hope Creek Operations Crew D Date 5/3/16 Scenario - Loss of A - Feed water heating - entire string, Reactor Recirc pumps at minimum speed.
- 1. Time allowed for operator response - 6 minutes and 32 seconds.
- 2. Time for operators to respond to initiating event - 2 minutes and 23 seconds
- 3. Action expected to be taken -
Immediate operator action from memory - Reduce and Maintain Reactor power to the Pre-Feedwater Heater Trip or Isolation Value.
- 4. Indications available to operators to diagnose event:
Overhead annunciators A7-E2 - Feedwater Heater Trip Extraction steam isolation valves going close, FWH Trip lights lit and FWH reset lights extinguished on 10C650 section A Feedwater temperature lowering, followed by reactor power rising on both APRMs and core thermal power.
Main Generator (MWE) rising.
- 5. Actions taken by operators.
Operators verified trips/isolations of Feedwater heaters.
From memory took their immediate operator actions: Reduced and Maintained Reactor Power to the Pre-Feedwater Heater Trip or Isolation Value. With Reactor Recirc pumps at minimum speed, the only means to reduce power is to insert control rods.
- 6. Procedures used that provided guidance.
HC.OP-AB-BOP-0001(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included:
The plots showing Rx power, A/B Feed Line Temperature, APRM A power. And Total Core Flow. Heater switch failure (initiating event) at 00:11:34. Feedwater temperature shows a slow lowering in temperature followed by a slow rise in reactor power. Rod Insertion begins at 00:13:57 and continues for the next several minutes to maintain power.
TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Heater switch failure (initiating event) - at time 00:11:34 Rod insertion Commences - at time 00:13:57, and continues.
HC.OP-AB.BOP-0001(Q) - Feedwater Heating (First three pages only.)
I Time allowed 392 sec - 18:06 I
\\
Thunder Sb11 ulation Tam Renort HoveCrpek Chris Kitt:rüdge, Tue 'May 03 lO:ll:58 2016 D Shift Loss of FWH IDNscription jiThne I
Value I
Ramp.
Ia SELECT. INSERT (Dl) - !oo:18!45 I tor ROD SELECT - INSERT (DT)-
00:18:35 True Rod Select 14-23 (D!)- Monitor jOO:l8:32 II False I
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Page 2 of4 ROD SELECT INSERT (DI) w *¥00:16:27 Monitor
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Hope Creek Operations Crew E Date 9/19/16 Scenario - Loss of A - Feed water heating - entire string. Reactor Recirc pumps at minimum speed.
- 1. Time allowed for operator response - 6 min and 32 seconds.
- 2. Time for operators to respond to initiating event - 3 min and 50 seconds
- 3. Action expected to be taken -
Immediate operator action from memory - Reduce and Maintain Reactor power to the Pre-Feedwater Heater Trip or Isolation Value.
- 4. Indications available to operators to diagnose event:
Overhead annunciators A7-E2 - Feedwater Heater Trip Extraction steam isolation valves going close, FWH Trip lights lit and FWH reset lights extinguished on 10C650 section A Feedwater temperature lowering, followed by reactor power rising on both APRMs and core thermal power.
Main Generator (MWE) rising.
- 5. Actions taken by operators.
Operators verified trips/isolations of Feedwater heaters.
From memory took their immediate operator actions: Reduced and Maintained Reactor Power to the Pre-Feedwater Heater Trip or Isolation Value. With Reactor Recirc pumps at minimum speed, the only means to reduce power is to insert control rods.
- 6. Procedures used that provided guidance.
HC.OP-AB-BOP-0001(Q)
- 7. Did operators respond as expected?
Yes, all correct actions were taken and verified.
- 8. What deltas if any between crews?
None observed.
- 9. The following data has been included:
The plots showing Rx power, A/B Feed Line Temperature, APRM A power. And Total Core Flow. Heater switch failure (initiating event) at 00:03:38. Feedwater temperature shows a slow lowering in temperature followed by a slow rise in reactor power. Rod Insertion begins at 00:07:28 and continues for the next several minutes to maintain power.
TAMS report from simulator - Tracks the manipulation of each switch in the simulator - Heater switch failure (initiating event) - at time 00:03:38. Rod insertion Commences - at time 00:07:28, and continues.
HC.OP-AB.BOP-0001(Q) - Feedwater Heating (First three pages only.)
I Feed water temp.
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4 Description APRM CH.A PWR Total Core Flow Feed Line A Inlet Tem....
Feed Line B Inlet Iem...
Value Units Min PCT 55 MlB/
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Thunder Sin1ulation Tam Reuort Hone Creek Chris Kittredge, TIHi May 1910:09:58 2016 "E" Shift PRNM" Loss of FWH Description h.**** ***
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