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{{#Wiki_filter:Appendix D Scenario Outline Form ES-D-1 Facility:
{{#Wiki_filter:Appendix D                                       Scenario Outline                                   Form ES-D-1 Facility:   SALEM 1 & 2                 Scenario No.: NRC 1 (ESG-7) Op-Test No.: 2017 NRG Examiners:                                           Operators:
SALEM 1 & 2 Scenario No.: NRC 1 (ESG-7) Op-Test No.: 2017 NRG Examiners:
Initial Conditions: IC-232, 76% power, EOL.
Operators:
Turnover: Raise power to 89% @ 10% per hour.
Initial Conditions:
Event       Malf. No.                                                     Event Event Type*
IC-232, 76% power, EOL. Turnover:
No.                                                                 Description R
Raise power to 89% @ 10% per hour. Event Malf. No. Event Type* Event No. Description 1 R Raise power to 89% @ 10%/hr using Turbine Controls. (ALL) 2 PR00188 c PZR PORV 2PR2 leaks. Crew enters S2.0P-AB.PZR-0001. (SRO, RO) (TS exercised) 3 RC00148 I 22 RC Loop Tavg fails high causing continuous inward rod (SRO, RO) motion. Crew enters S2.0P-AB.ROD-0003. (TS exercised)
1                                       Raise power to 89% @ 10%/hr using Turbine Controls.
TU0075 M Loss of MTLO resulting in a power reduction and then 4 TU0083A (ALL) manually tripping the reactor due to elevated main turbine TU00838 vibrations.
(ALL) 2       PR00188 c       PZR PORV 2PR2 leaks. Crew enters S2.0P-AB.PZR-0001.
RP0058 RP0059A RP00598 RP0060A All actions from the control room will fail to actuate a reactor 5 RP00608 c trip (ATWT with Loss of Main Feedwater).
(SRO, RO)     (TS exercised)
Crew transitions RP0247 (SRO, RO) to 2-EOP-FRSM-1 . 8440 F DI 8441 F DI C310 F DI C510 F DI Failure of 22 AFW pump pressure override circuit resulting in 6 AF01828 c no AFW flow from 22 AFW pump. AF0353C (SRO, BOP) Failure of 23 AFW pump to auto start requiring manual start. 7 RD0061 I Failure of auto rod control speed controller.
I       22 RC Loop Tavg fails high causing continuous inward rod 3        RC00148 (SRO, RO)     motion. Crew enters S2.0P-AB.ROD-0003. (TS exercised)
Requires RO to (SRO, RO) manually insert rods. Critical Task Start AFW pump to establish 2'.44E 4 lbm/hr flow #1 Critical Task Insert negative reactivity into the core. #2 * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-37 Appendix D Scenario Outline Form ES-D-1 Facility:
TU0075                         Loss of MTLO resulting in a power reduction and then M
SALEM 1 & 2 Scenario No.: NRC 2 (ESG-8) Op-Test No.: 2017 NRC Examiners:
4       TU0083A                         manually tripping the reactor due to elevated main turbine (ALL)
Operators:
TU00838                         vibrations.
Initial Conditions:
RP0058 RP0059A RP00598 RP0060A                         All actions from the control room will fail to actuate a reactor 5
IC-233, 100% power, BOL. PZR level channel Ill removed from service due to failing high, 2PR6 shut due to 2PR1 control circuit problems (no active troubleshooting is in progress).
RP00608               c       trip (ATWT with Loss of Main Feedwater). Crew transitions RP0247         (SRO, RO)     to 2-EOP-FRSM-1 .
Turnover:
8440 F DI 8441 F DI C310 F DI C510 F DI Failure of 22 AFW pump pressure override circuit resulting in 6
Maintain 100% and be prepared to support maintenance troubleshooting on PZR pressure channel and 2PR1. Event Malf. No. Event Type* Event No. Description 1 CV0034 c 23 Charging pump trips. Crew enters S2.0P-AB.CVC-0001. (SRO, RO) 2 VL0245 c Letdown orifice isolation valve (2CV4) fails to close (partially (SRO, RO) open) on loss of all charging pumps. (TS exercised) 3 EL0141 M Loss of 2E Group Bus due to electrical fault in cubicle. Crew FP25D (ALL) enters 2-EOP-TRIP-1.
AF01828               c       no AFW flow from 22 AFW pump.
4 RC0003C c 23 RCP trips following Rx Trip. (Loss of Normal Spray) (SRO, RO) 21 SG tube leak (50 gpm). Crew enters S2.0P-AB.SG-5 SG0078A c 0001. Leak degrades to a 400 gpm rupture. Crew initiates (ALL) SI and re-enters 2-EOP-TRIP-1, then transitions to 2-EOP-SGTR-1. 6 A701 B DI c Train B SI switch fails to actuate. RO initiates Train A SI. (SRO, RO) 7 VL0298 c 2PR2 PZR PORV fails to close during depressurization (SRO, RO) Critical Task Isolate feed flow into and steam flow from 21 SG. #1 Critical Task Establish and maintain RCS temps so transition from SGTR #2 does not occur. * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-37}}
AF0353C         (SRO, BOP)
Failure of 23 AFW pump to auto start requiring manual start.
I       Failure of auto rod control speed controller. Requires RO to 7        RD0061 (SRO, RO)     manually insert rods.
Critical Task                                         4 Start AFW pump to establish 2'.44E lbm/hr flow
                                    #1 Critical Task   Insert negative reactivity into the core.
                                    #2
*   (N)ormal,   (R)eactivity,   (l)nstrument,   (C)omponent,     (M)ajor D-37
 
Appendix D                                     Scenario Outline                                   Form ES-D-1 Facility:   SALEM 1 & 2                 Scenario No.: NRC 2 (ESG-8)         Op-Test No.: 2017 NRC Examiners:                                           Operators:
Initial Conditions: IC- 233, 100% power, BOL. PZR level channel Ill removed from service due to failing high, 2PR6 shut due to 2PR1 control circuit problems (no active troubleshooting is in progress).
Turnover: Maintain 100% and be prepared to support maintenance troubleshooting on PZR pressure channel and 2PR1.
Event       Malf. No.                                                     Event Event Type*
No.                                                                   Description 1       CV0034 c         23 Charging pump trips. Crew enters S2.0P-AB.CVC-0001.
(SRO, RO) 2         VL0245 c         Letdown orifice isolation valve (2CV4) fails to close (partially (SRO, RO)       open) on loss of all charging pumps. (TS exercised)
EL0141               M         Loss of 2E Group Bus due to electrical fault in cubicle. Crew 3
FP25D             (ALL)       enters 2-EOP-TRIP-1.
4       RC0003C c         23 RCP trips following Rx Trip. (Loss of Normal Spray)
(SRO, RO) 21 SG tube leak (50 gpm). Crew enters S2.0P-AB.SG-5       SG0078A c         0001. Leak degrades to a 400 gpm rupture. Crew initiates (ALL)       SI and re-enters 2-EOP-TRIP-1, then transitions to 2-EOP-SGTR-1.
6       A701 B DI c         Train B SI switch fails to actuate. RO initiates Train A SI.
(SRO, RO) 7         VL0298 c         2PR2 PZR PORV fails to close during depressurization (SRO, RO)
Critical Task   Isolate feed flow into and steam flow from 21 SG.
                                    #1 Critical Task   Establish and maintain RCS temps so transition from SGTR
                                    #2       does not occur.
* (N)ormal,     (R)eactivity, (l)nstrument,   (C)omponent,     (M)ajor D- 37}}

Latest revision as of 21:05, 29 October 2019

Draft - Outlines (Folder 2)
ML17249A133
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Site: Salem  PSEG icon.png
Issue date: 04/20/2017
From:
Public Service Enterprise Group
To:
Operations Branch I
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ML17062A888 List:
References
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Download: ML17249A133 (2)
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Text

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC 1 (ESG-7) Op-Test No.: 2017 NRG Examiners: Operators:

Initial Conditions: IC-232, 76% power, EOL.

Turnover: Raise power to 89% @ 10% per hour.

Event Malf. No. Event Event Type*

No. Description R

1 Raise power to 89% @ 10%/hr using Turbine Controls.

(ALL) 2 PR00188 c PZR PORV 2PR2 leaks. Crew enters S2.0P-AB.PZR-0001.

(SRO, RO) (TS exercised)

I 22 RC Loop Tavg fails high causing continuous inward rod 3 RC00148 (SRO, RO) motion. Crew enters S2.0P-AB.ROD-0003. (TS exercised)

TU0075 Loss of MTLO resulting in a power reduction and then M

4 TU0083A manually tripping the reactor due to elevated main turbine (ALL)

TU00838 vibrations.

RP0058 RP0059A RP00598 RP0060A All actions from the control room will fail to actuate a reactor 5

RP00608 c trip (ATWT with Loss of Main Feedwater). Crew transitions RP0247 (SRO, RO) to 2-EOP-FRSM-1 .

8440 F DI 8441 F DI C310 F DI C510 F DI Failure of 22 AFW pump pressure override circuit resulting in 6

AF01828 c no AFW flow from 22 AFW pump.

AF0353C (SRO, BOP)

Failure of 23 AFW pump to auto start requiring manual start.

I Failure of auto rod control speed controller. Requires RO to 7 RD0061 (SRO, RO) manually insert rods.

Critical Task 4 Start AFW pump to establish 2'.44E lbm/hr flow

  1. 1 Critical Task Insert negative reactivity into the core.
  1. 2
  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-37

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC 2 (ESG-8) Op-Test No.: 2017 NRC Examiners: Operators:

Initial Conditions: IC- 233, 100% power, BOL. PZR level channel Ill removed from service due to failing high, 2PR6 shut due to 2PR1 control circuit problems (no active troubleshooting is in progress).

Turnover: Maintain 100% and be prepared to support maintenance troubleshooting on PZR pressure channel and 2PR1.

Event Malf. No. Event Event Type*

No. Description 1 CV0034 c 23 Charging pump trips. Crew enters S2.0P-AB.CVC-0001.

(SRO, RO) 2 VL0245 c Letdown orifice isolation valve (2CV4) fails to close (partially (SRO, RO) open) on loss of all charging pumps. (TS exercised)

EL0141 M Loss of 2E Group Bus due to electrical fault in cubicle. Crew 3

FP25D (ALL) enters 2-EOP-TRIP-1.

4 RC0003C c 23 RCP trips following Rx Trip. (Loss of Normal Spray)

(SRO, RO) 21 SG tube leak (50 gpm). Crew enters S2.0P-AB.SG-5 SG0078A c 0001. Leak degrades to a 400 gpm rupture. Crew initiates (ALL) SI and re-enters 2-EOP-TRIP-1, then transitions to 2-EOP-SGTR-1.

6 A701 B DI c Train B SI switch fails to actuate. RO initiates Train A SI.

(SRO, RO) 7 VL0298 c 2PR2 PZR PORV fails to close during depressurization (SRO, RO)

Critical Task Isolate feed flow into and steam flow from 21 SG.

  1. 1 Critical Task Establish and maintain RCS temps so transition from SGTR
  1. 2 does not occur.
  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D- 37
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