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| number = ML101650166
| number = ML101650166
| issue date = 03/28/2010
| issue date = 03/28/2010
| title = 2007-301 Final Simulator Scenarios (Section 10)
| title = 301 Final Simulator Scenarios (Section 10)
| author name =  
| author name =  
| author affiliation = NRC/RGN-II
| author affiliation = NRC/RGN-II
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:Appendix D Scenario Outline Form ES-D-1 Facility:
{{#Wiki_filter:Appendix D     D                                              Scenario Outline                                       Form ES-D-1 Facility:
Turkey Point Scenario No.: 1 Op Test No.: 2007-301 Examiners:
Facility:              Turkey Point Point                        Scenario No.:
Candidates:
No.:          11    Op Test No.:
US RO BOP Initial Conditions:
Op        No.:    2007-301 2007-301 Examiners:                                                              Candidates:
Mode 1, 75% Power, MOL, Awaiting permission from plant management to increase power back to 100%. 3-GOP-301 in use complete through step 5.96 for return to 100% power following a turbine valve test. Turnover:
Candidates:                                             US RD RO BOP BOP Initial Conditions:       Mode 11, 75% Power, MDL, MOL, Awaiting permission from plant management to increase power back 100%. 3-GOP-301 in use complete through step 5.96 for retum to 100%.                                                                      100% power following aa return to 100%
Equipment OOS: 3B EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 1 & 9 in 4 hrs); B AFW Pump due to bearing failure (OOS 4 hrs; ETR 24 hrs; both trains verified operable);
turbine valve test.
3B CSP due to failed 1ST -low discharge pressure (OOS 12 hr; ETR 36 hr) Perform 3C ICWP isolation valve cycling test per step 7.1.3 of 3-0SP-019.3.
Turnover:                 Equipment DOS:     3B EDG due to failed fuel pump (DOS OOS: 3B                                    (OOS 22 days; next next 0-OSP-023.3 AU Att 11 & 9 in 44 hrs); BB AFW Pump due to bearing               (OOS 44 hrs; ETR 24 bearing failure (DOS              24 hrs; both trains verified operable);
Steps 7.1.1 & 7.1.2 for 3A and 3B ICWP are not scheduled for this shift. Known tube leak in 3A S/G (2 gpd) -unchanged for last week. Chemistry samples are being taken per 3-0NOP-071.2, Attachment  
3B   CSP due 3B CSP    due to failed 1ST 1ST -low
: 1. The current sample, just completed indicates no significant change in leak rate. MOV-3-1403 remains open at management direction due to small size and stability of tube leak rate. Event Event Type* Event Description No. 1 (N) SRO/BOP 3C ICWP discharge isolation valve cycling test per 3-0SP-019.3 step 7.1.3. 2 (I) RO Power range NI channel N-44 upper detector fails high. The crew responds TFN1P4AH = T per 3-0NOP-059.8. (TS,I) SRO 3 See event 4a PT-3-1604 fails low. The crew responds per 3-ARP-097.CR for annunciator TFS1ML3L = T below 0-7/4. 4 (C) BOP Loss of 3C 4kV bus. The crew responds per 3-0NOP-004.4.
                                                        - low discharge pressure   (OOS 12 pressure (DOS  12 hr; ETR 36 hr; ETR    36 hr) 3-0SP-019.3. Steps 7.1.1 & 7.1.2 ICWP isolation valve cycling test per step 7.1.3 of 3-OSP-019.3.
TS are TFE2Z52S = T evaluated for loss of the A SSGFWP. (C, TS) SRO 4a (R) SRO/RO Automatic runback fails due to PT-3-1604 failure and requires manual action (I) BOP* to reduce power < 60 % to avoid reactor trip on slg 10-10 level. The crew responds per 3-0NOP-089.
Perform 3C ICWP for 3A and 3B ICWP are not scheduled for this shift.
5 TVFACN3 = 0.1 (M) ALL Once reactor power stabilized  
Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being taken per 3-ONOP-071 3-0NOP-071.2,  .2, Attachment 1. 1. The current sample, just completed indicates no MOV-3-1403 remains open at management direction due to small significant change in leak rate. MOV-3-1403 size and stability of tube leak rate.
< 60% power, a 3C SG feed break occurs TFW98M=T (C) RO/SRO inside containment.
Event                           Event Type*
A manual reactor trip is required before any SG level TCF1D09M = F drops < 10% since the automatic reactor trip is failed. 3-EOP-E-0 is TFL2XASE = T performed.
Type*                                        Event Description No.
The MOV-3-1409 breaker trips & FCV-3-498 fails to close leaving TFL2XBSE =T an uncontrolled feed path to 3C SG if 3A SGFP started. 6 (M)ALL C AFWP trips on overspeed prematurely at 6300 RPM (from setup). The trip TAFXSRPC = can not be reset. B AFWP is OOS. A AFWP starts, but runs out of steam 6300.0 pressure from the 3C feed line fault. Efforts to realign A AFWP to train 2 TCF5MTC =T steam are prevented by AFSS-3-007 stuck closed. SSGFW can not be used due to loss of 3C 4kV bus and a dead battery on B SSGFWP. The crew transitions to 3-EOP-FR-H.1 when AFW flow < 345 gpm and is eventually required to initiate feed & bleed since all SGs < 32% narrow range with adverse containment conditions.  
11                        (N) SRO/BOP       3C                                                         3-OSP-019.3 step 7.1.3.
.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor * -BOP action to either manually close CV-3-2011 in event 3 or manually reduce load in event 4a due to automatic turbine runback failure satisfies the BOP PT-3-1604 instrument failure manipulation.
30 ICWP discharge isolation valve cycling test per 3-0SP-019.3 2
1 Appendix 0 Scenario Outline Form ES-O-1 Facility:
2                              RD (I) RO             Power range NI channel N-44 upper detector fails high. The crew responds TFN1P4AH =  = T per 3-0NOP-059.8.
Turkey Point Scenario No.: 2 Op Test No.: 2007-301 Examiners:
(TS,I)
Candidates:
TSl SRO 3                         See event 4a       PT-3-1604 fails low. The crew responds per 3-ARP-097.CR for annunciator TFS1ML3L TFSIML3LT  =T     below             0-7/4.
US RO BOP Initial Conditions:
D-7/4.
Mode 1, 50% Power, MOL. Power on hold at 50% following inadvertent trip of 3B SGFP while investigation in progress.
4                          (C) BOP                                                               3-ONOP-004.4. TS are Loss of 3C 4kV bus. The crew responds per 3-0NOP-004.4.
Turnover:
TFE2Z52S = = T evaluated for loss of the A SSGFWP.
Equipment OOS: 3B EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 1 & 9 in 4 hrs); B AFW Pump due to bearing failure (OOS 4 hrs; ETR 24 hrs; both trains verified operable);
(C TS) SRO (C,
3B CSP due to failed 1ST -low discharge pressure (OOS 12 hr; ETR 36 hr) Need to swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 section 7.4 after shift turnover to support possible emergent maintenance on 3A CCW pump (vibration increase last shift). Known tube leak in 3A S/G (2 gpd) -unchanged for last week. Chemistry samples are being taken per 3-0NOP-071.2, Attachment  
4a                         (R) SRO/RO                                           PT-3-1 604 failure and requires manual action Automatic runback fails due to PT-3-1604 BOP*          to reduce power < 60 % to avoid reactor trip on slg   s/g 10-10 b-b level. The crew (I)
: 1. The current sample, just completed indicates no significant change in leak rate. MOV-3-1403 remains open at management direction due to small size and stability of tube leak rate. Event Event Type* Event Description No. 1 (N) SRO/BOP Swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 section 7.4. 2 (I) BOP First stage impulse pressure channel PT-3-446 fails low. The crew responds TFS1MABL = T (TS,I) SRO per 3-0NOP-028 to stop inward rod movement by taking rod control to manual and then 3-0NOP-049.1.
I BOP*
3 (C) ALL 120VAC power panel 3P09 normal inverter fails. The auto swap to the CVT TFE6X06F = T also fails leaving 3P09 deenergized.
3-ONOP-089.
The crew responds per 3-0NOP-003.9.
responds per 3-0NOP-089.
TCE6DI1C =T 3P09 is swapped over to the spare inverter per 3-0NOP-003.9 Attachment
TVFACN3 = = 0.1 (M) ALL           Once reactor power stabilized < 60% power, a 3C       30 SG feed break occurs 5
: 1. 4 TFCMM2A4=T (C) ALL The 3A steam generator tube leak grows to 2 gpm. R-3-19 fails to respond. TYHHSGA= (TS) SRO The crew responds per 3-0NOP-071.2 0.002 4a (R) ALL A fast load reduction from 50% power is initiated and performed per 3-0NOP-071.2 5 TYHHSGA= (M) ALL The 3A steam generator tube leak grows from 2 gpm into a rupture. The 0,4 (C) SRO/BOP reactor is tripped and 3-EOP-E-0 performed.
TFW98M=T                             inside containment. A manual reactor trip is required before any SG level (C)
MOV-3-1433 fails to close TFSW33C=T requiring manual isolation of MSIVs. 6 (C) ALL When transition is made from 3-EOP-E-0 to 3-EOP-E-3, the startup transformer locks out. 3A EDG starts but the output breaker does not TF05A20A=T automatically close, and 3-EOP-ECA-0.0 is entered. 3A EDG output breaker TA05LRSB =T is manually closed and the crew transitions back to 3-EOP-E-3.
C RO/SRO                < 10% since the automatic reactor trip is failed. 3-EOP-E-0 is TCF1D09M =  = F                      drops <
Only 3A & 3D TFP1S38S = T 4kV bus are now available from 3A EDG. 3-EOP-E-3 is performed to cooldown and depressurize the RCS to stop primary-secondary leak flow. .. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor 1 Appendix 0 Scenario Outline Form ES-O-1 Facility:
TFL2XASE = = T MOV-3-1 409 breaker trips & FCV-3-498 fails to close leaving performed. The MOV-3-1409 TFL2XBSE TFL2XBSE=T =T an uncontrolled feed path to 3C 30 SG if 3A SGFP started.
Turkey Point Scenario No.: 3 Op Test No.: 2007-301 Examiners:
6                         (M) ALL (M)ALL             C AFWP trips on overspeed prematurely at 6300 RPM (from setup). The trip TAFXSRPC =
Candidates:
                        =                        can not be reset. B AFWP is OOS. DOS. A AFWP starts, but runs out of steam 6300.0                           pressure from the 3C 30 feed line fault. Efforts to realign A AFWP to train 2 TCF5MTC =T= T steam are prevented by AFSS-3-007 stuck closed. SSGFW can not be used due to loss of 3C 30 4kV bus and a dead battery on B SSGFWP. The crew transitions to 3-EOP-FR-H.1 when AFW flow < 345 gpm and is eventually required to initiate feed & bleed since all SGs < 32% narrow range with adverse containment conditions.
US RO BOP Initial Conditions:
                              ..                                     (M)ajor (l)nstrument, (C)omponent, (M)aJor (R)eactivity, (I)nstrument, (N)ormal, (R)eactlvlty, CV-3-201 1 in event 3 or manually reduce load in event 4a due to
Mode 1, 75% Power, MOL, Awaiting permission from plant management to increase power back to 100%. 3-GOP-301 in use complete through step 5.96 for return to 100% power following a turbine valve test. Turnover:
      * - BOP action to either manually close CV-3-2011 automatic turbine runback failure satisfies the BOP PT-3-1604 PT-3-1 604 instrument failure manipulation.
Equipment OOS: 3B EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 1 & 9 in 4 hrs); B AFW Pump due to bearing failure (OOS 4 hrs; ETR 24 hrs; both trains verified operable);
11
3B CSP due to failed 1ST -low discharge pressure (OOS 12 hr; ETR 36 hr) Perform monthly surveillance on 3A ECC per 3-0SP-055.1 section 7.1 immediately after shift turnover.
 
1ST and remote valve position verification not required.
Appendix 0D                                                  Scenario Outline Scenario   Outline                                 Form ES-O-1 Form    ES-D-1 Facility:
Known tube leak in 3A S/G (2 gpd) -unchanged for last week. Chemistry samples are being taken per 3-0NOP-071.2, Attachment  
Facility:                Turkey Point Turkey    Point                      Scenario No.:
: 1. The current sample, just completed indicates no significant change in leak rate. MOV-3-1403 remains open at management direction due to small size and stability of tube leak rate. Event Event Type* Event Description No. 1 (N) BOP 3A ECC monthly surveillance performed per 3-0SP-055.1 section 7.1. 3A TFKV905A = T ECC inlet valve CV-3-2905 fails to open and 3A ECC is declared OOS. (N,TS) SRO 2 (I) SRO/RO TM-3-408C (Tavg input to rod control) fails high. Crew responds per 3-TFL 1T8CH = T ONOP-028 and takes rods to manual to stop continuous inward rod movement.
Scenario  No.:        22    Op Test Op Test No.:
3 (C) RO/BOP Loss of 3H 480V LC. Also takes 3C charging pump, 3B ECC, 3B ECF & 3D TFE3D37A = T (C,TS) SRO NCC OOS. Requires starting another charging pump or securing the in TFE3D38T = T service 60 gpm orifice. The crew responds per 3-ARP-097.CR for annunciators F-9/6, A-5/4, 1-9/3 or 1-9/4. 4 TAKPXA1=10.0 (C) SRO/BOP 3A 1 Intake screen high Llp. Crew responds per 3-0NOP-011.
No.:      2007-301 2007-301 Examiners:
3A 1 CWP is TAKPXA2 = 4.0 secured. 4a (R) ALL 3A2 Intake screen high Llp. Fast load reduction per 3-0NOP-100 to 60% for TAKPXA2 = 1.0 the purpose of securing 3A2 CWP. Manual rod control must be used due to rod control Tavg failure. 5 TAHUVBSB=22 (M) ALL 3B RCP high vibration.
Examiners:                                                              Candidates:
The crew responds per 3-0NOP-041.1.
Candidates:                                          US US RO RO BOP BOP Initial Conditions:         Mode 1, 50% Power, MOL. Power on hold at 50% following inadvertent trip of 3B SGFP while investigation in investigation  in progress.
Once TAHUVBMB=
progress.
6 vibration reaches the trip setpoint, the crew manually trips the reactor and immediate actions of 3-EOP-E-0 are performed.
Turnover:                   Equipment OOS: 3B EDG    EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 11 & 9 in    in 4 hrs); B AFW Pump due to bearing failure (OOS 4 hrs; ETR    ETR 24 hrs; both trains verified operable);
6 (M) ALL When 3B RCP is tripped, 3B 4kV bus is lost and a large break LOCA occurs. TFE2Z51S = T (cont'd from An automatic SI occurs but train A sequencer fails. Train A ECCS equipment TVHHCLB = 0.1 event 5) must be manually started. The crew completes 3-EOP-E-0 and transitions to TFQ634AF = T (C) ALL applicable FRPs followed by 3-EOP-E-1.
3B CSP due to failed 1ST  1ST -low
6a Once CSFSTs are monitored for implementation, if containment pressure is still above 20 psig, the crew immediately transitions to 3-EOP-FR-Z.1 if no higher red or orange path exists. 6b (C) SRO/RO 3-EOP-E-1 is entered after which 3A RHRP trips. Since neither RHRP is TFM1D3AT =T running, transition is made to 3-EOP-ECA-1.1.
                                                        - low discharge pressure (OOS 12 12 hr; ETR 36 hr)
Measures are taken to minimize the loss of RWST inventory.  
Need to swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005  3-OP-005 section 7.4 after shift turnover to support possible emergent maintenance on 3A CCW     COW pump (vibration increase last shift).
.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor 1}}
Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being 3-ONOP-071 .2, Attachment 1. The current sample, just completed indicates no taken per 3-0NOP-071.2, MOV-3-1 403 remains open at management direction due to small significant change in leak rate. MOV-3-1403 size and stability of tube leak rate.
Event                                 Type*
Event Type*                                     Event Description No.
1 1                         (N) SRO/BOP SROIBOP      Swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 3-OP-005 section 7.4.
2                         (I) BOP           First stage impulse pressure channel PT-3-446 fails low. The crew responds TFS1MABL=T TFS1MABL    =T    (TS I) SRO (TS,I)                 3-ONOP-028 to stop inward rod movement by taking rod control to per 3-0NOP-028 manual and then 3-0NOP-049.1.
3-ONOP-049.1.
3                        (C) ALL             1 2OVAC power panel 3P09 normal inverter fails. The auto swap to the CVT 120VAC TFE6XO6F =
TFE6X06F   = T TcE6DIlc=T also fails leaving 3P09 deenergized. The crew responds per 3-0NOP-003.9.
3-ONOP-003.9.
TCE6DI1C =T 3P09 is swapped over to the spare inverter per 3-0NOP-003.9 3-ONOP-003.9 Attachment 1.
4     TFcMM2A4 TFCMM2A4=T = T    (C) ALL           The 3A steam generator tube leak grows to 22 gpm. R-3-19 R-3-1 9 fails to respond.
TVI-IHSGA TYHHSGA==
(TS) SRO                                     3-ONOP-071 .2 The crew responds per 3-0NOP-071.2 0.002 4a                         (R) ALL           A fast load reduction from 50% power is initiated and performed per 3-ONOP-3-0NOP-071.2 5       TVHHSGA TYHHSGA=
(M) ALL           The 3A steam generator tube leak grows from 22 gpm into aa rupture. The
                &deg; 0,4         (C) SRO/BOP       reactor is tripped and 3-EOP-E-0 performed. MOV-3-1433 fails to close TFSW33CT TFSW33C=T                             requiring manual isolation of MSIVs.
66                        (C) ALL           When transition is made from 3-EOP-E-0 to 3-EOP-E-3, the startup transformer locks out. 3A EDG starts but the output breaker does not TFQ5A2OA=T TF05A20A=T                           automatically close, and 3-EOP-ECA-0.0 is entered. 3A EDG output breaker TA05LRSB =T is manually closed and the crew transitions back to 3-EOP-E-3. Only 3A & 3D TFP1S38S = T 4kV bus are now available from 3A EDG. 3-EOP-E-3 is performed performed to cooldown andand depressurize depressurize the the ROS RCS to stop primary-secondary leak to stop                      leak flow.
(N)ormal, (R)eactivity, (N,iormal,               .. (I)nstrument, (C)omponent, (M)ajor (R)eactlvlty, (l)nstrument,                      (M)aJor 11
 
Appendix D    0                                               Scenario Outline                                   Form ES-D-1 ES-O-1 Facility:             Turkey Point                             Scenario No.:           3     Op Test No.:       2007-301 Examiners:                                                                 Candidates:                                         US RO BOP Initial Conditions:       Mode 1,  1, 75% Power, MOL, Awaiting permission from plant management to increase power back 100%. 3-GOP-301 in use complete through step 5.96 for return to 100% power following a to 100%.
turbine valve test.
Turnover:                 Equipment OOS: 3B EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 AU                  1 &
Att 1 & 9 in 4 hrs); B  B AFW Pump due to bearing failure (OOS 4 hrs; ETR 24 hrs; both trains verified operable);
3B CSP due to failed 1ST -low    - low discharge pressure (OOS 12  12 hr; ETR 36 hr)
Perform monthly surveillance on 3A ECC per 3-OSP-055.1 3-0SP-055.1 section 7.1 immediately after shift turnover. 1ST and remote valve position verification not required.
Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being taken per 3-ONOP-071 3-0NOP-071.2,  .2, Attachment 1. The current sample, just completed indicates no MOV-3-1 403 remains open at management direction due to small significant change in leak rate. MOV-3-1403 size and stability of tube leak rate.
Event                         Event Type*
Type*                                      Event Description No.
1 1                         (N) BOP                                                               3-OSP-055.1 section 7.1. 3A 3A ECC monthly surveillance performed per 3-0SP-055.1 TFKVOO5A=T TFKV905A  =T ECC inlet valve CV-3-2905 fails to open and 3A ECC is declared OOS.
(N,TS) SRO 2                         (I) SRO/RO         TM-3-408C (Tavg input to rod control) fails high. Crew responds per 3-TFL1TSCH TFL 1T8CH == T                         ONOP-028 and takes rods to manual to stop continuous inward rod movement.
3                         (C) RO/BOP           Loss of 3H 480V LC. Also takes 3C charging pump, 3B ECC, 3B ECF &          & 3D TFE3D37A=T TFE3D37A  =T                            NCC OOS. Requires starting another charging pump or securing the in C TS SRO (C,TS)
TFE3D38T == T-r service 60 gpm orifice. The crew responds per 3-ARP-097.CR for annunciators F-9/6, A-5/4, 1-9/3 or 1-9/4.
4       TAKPXA1=10.0       (C) SRO/BOP         3A11 Intake screen high Llp.
3A                                                  3-ONOP-Ol 1. 3A
: p. Crew responds per 3-0NOP-011.       3A11 CWP is TAKPXA2 == 4.0                         secured.
4a                         (R) ALL             3A2 Intake screen high Llp.                             3-ONOP-100 to 60% for
: p. Fast load reduction per 3-0NOP-100 TAKPXA2 == 1.0                         the purpose of securing 3A2 CWP. Manual rod control must be used due to rod control Tavg failure.
5       TAHUVBSB=22 (M) ALL                                                                 3-ONOP-041 .1. Once 3B RCP high vibration. The crew responds per 3-0NOP-041.1.
setpoint the crew manually trips the reactor and vibration reaches the trip setpoint, TAHUVBMB=66 TAHUVBMB=                              .
immediate actions of 3-EOP-E-0 are performed.
6                         (M) ALL             When 3B RCP is tripped, 3B 4kV bus is lost and a large break LOCA occurs.
TFE2Z51S ==TT      (contd from (cont'd             An automatic SI occurs but train A sequencer fails. Train A ECCS equipment event event 5)             must be manually started. The crew completes 3-EOP-E-0 and transitions to TvHHCLB=0.1 TVHHCLB  = 0.1 (C) ALL             applicable FRPs followed by 3-EOP-E-1.
TFQ634AF == T 6a                                               Once CSFSTs are monitored for implementation, if containment pressure is still above 20 psig, the crew immediately transitions to 3-EOP-FR-Z.1 if no higher red or orange path exists.
6b                                 SROIRO (C) SRO/RO           3-EOP-E-1 is entered after which 3A RHRP trips. Since neither RHRP is TFM1D3AT=T TFM1D3AT  =T                          running, transition is made to 3-EOP-ECA-1.1. Measures are taken to minimize the loss of RWST inventory.
(R)eactivity, (I)nstrument, (N)ormal, (R)eactlvlty,                                           (M)ajor (l)nstrument, (C)omponent, (M)aJor 11}}

Latest revision as of 23:10, 11 March 2020

301 Final Simulator Scenarios (Section 10)
ML101650166
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/28/2010
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
50-250/07-301, 50-251/07-301 50-250/07-301, 50-251/07-301, ES-D-1
Download: ML101650166 (3)
v • d • e


Text

Appendix D D Scenario Outline Form ES-D-1 Facility:

Facility: Turkey Point Point Scenario No.:

No.: 11 Op Test No.:

Op No.: 2007-301 2007-301 Examiners: Candidates:

Candidates: US RD RO BOP BOP Initial Conditions: Mode 11, 75% Power, MDL, MOL, Awaiting permission from plant management to increase power back 100%. 3-GOP-301 in use complete through step 5.96 for retum to 100%. 100% power following aa return to 100%

turbine valve test.

Turnover: Equipment DOS: 3B EDG due to failed fuel pump (DOS OOS: 3B (OOS 22 days; next next 0-OSP-023.3 AU Att 11 & 9 in 44 hrs); BB AFW Pump due to bearing (OOS 44 hrs; ETR 24 bearing failure (DOS 24 hrs; both trains verified operable);

3B CSP due 3B CSP due to failed 1ST 1ST -low

- low discharge pressure (OOS 12 pressure (DOS 12 hr; ETR 36 hr; ETR 36 hr) 3-0SP-019.3. Steps 7.1.1 & 7.1.2 ICWP isolation valve cycling test per step 7.1.3 of 3-OSP-019.3.

Perform 3C ICWP for 3A and 3B ICWP are not scheduled for this shift.

Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being taken per 3-ONOP-071 3-0NOP-071.2, .2, Attachment 1. 1. The current sample, just completed indicates no MOV-3-1403 remains open at management direction due to small significant change in leak rate. MOV-3-1403 size and stability of tube leak rate.

Event Event Type*

Type* Event Description No.

11 (N) SRO/BOP 3C 3-OSP-019.3 step 7.1.3.

30 ICWP discharge isolation valve cycling test per 3-0SP-019.3 2

2 RD (I) RO Power range NI channel N-44 upper detector fails high. The crew responds TFN1P4AH = = T per 3-0NOP-059.8.

(TS,I)

TSl SRO 3 See event 4a PT-3-1604 fails low. The crew responds per 3-ARP-097.CR for annunciator TFS1ML3L TFSIML3LT =T below 0-7/4.

D-7/4.

4 (C) BOP 3-ONOP-004.4. TS are Loss of 3C 4kV bus. The crew responds per 3-0NOP-004.4.

TFE2Z52S = = T evaluated for loss of the A SSGFWP.

(C TS) SRO (C,

4a (R) SRO/RO PT-3-1 604 failure and requires manual action Automatic runback fails due to PT-3-1604 BOP* to reduce power < 60 % to avoid reactor trip on slg s/g 10-10 b-b level. The crew (I)

I BOP*

3-ONOP-089.

responds per 3-0NOP-089.

TVFACN3 = = 0.1 (M) ALL Once reactor power stabilized < 60% power, a 3C 30 SG feed break occurs 5

TFW98M=T inside containment. A manual reactor trip is required before any SG level (C)

C RO/SRO < 10% since the automatic reactor trip is failed. 3-EOP-E-0 is TCF1D09M = = F drops <

TFL2XASE = = T MOV-3-1 409 breaker trips & FCV-3-498 fails to close leaving performed. The MOV-3-1409 TFL2XBSE TFL2XBSE=T =T an uncontrolled feed path to 3C 30 SG if 3A SGFP started.

6 (M) ALL (M)ALL C AFWP trips on overspeed prematurely at 6300 RPM (from setup). The trip TAFXSRPC =

= can not be reset. B AFWP is OOS. DOS. A AFWP starts, but runs out of steam 6300.0 pressure from the 3C 30 feed line fault. Efforts to realign A AFWP to train 2 TCF5MTC =T= T steam are prevented by AFSS-3-007 stuck closed. SSGFW can not be used due to loss of 3C 30 4kV bus and a dead battery on B SSGFWP. The crew transitions to 3-EOP-FR-H.1 when AFW flow < 345 gpm and is eventually required to initiate feed & bleed since all SGs < 32% narrow range with adverse containment conditions.

.. (M)ajor (l)nstrument, (C)omponent, (M)aJor (R)eactivity, (I)nstrument, (N)ormal, (R)eactlvlty, CV-3-201 1 in event 3 or manually reduce load in event 4a due to

  • - BOP action to either manually close CV-3-2011 automatic turbine runback failure satisfies the BOP PT-3-1604 PT-3-1 604 instrument failure manipulation.

11

Appendix 0D Scenario Outline Scenario Outline Form ES-O-1 Form ES-D-1 Facility:

Facility: Turkey Point Turkey Point Scenario No.:

Scenario No.: 22 Op Test Op Test No.:

No.: 2007-301 2007-301 Examiners:

Examiners: Candidates:

Candidates: US US RO RO BOP BOP Initial Conditions: Mode 1, 50% Power, MOL. Power on hold at 50% following inadvertent trip of 3B SGFP while investigation in investigation in progress.

progress.

Turnover: Equipment OOS: 3B EDG EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 Att 11 & 9 in in 4 hrs); B AFW Pump due to bearing failure (OOS 4 hrs; ETR ETR 24 hrs; both trains verified operable);

3B CSP due to failed 1ST 1ST -low

- low discharge pressure (OOS 12 12 hr; ETR 36 hr)

Need to swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 3-OP-005 section 7.4 after shift turnover to support possible emergent maintenance on 3A CCW COW pump (vibration increase last shift).

Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being 3-ONOP-071 .2, Attachment 1. The current sample, just completed indicates no taken per 3-0NOP-071.2, MOV-3-1 403 remains open at management direction due to small significant change in leak rate. MOV-3-1403 size and stability of tube leak rate.

Event Type*

Event Type* Event Description No.

1 1 (N) SRO/BOP SROIBOP Swap 3D 4kV bus power supply to 3A 4kV bus per 3-0P-005 3-OP-005 section 7.4.

2 (I) BOP First stage impulse pressure channel PT-3-446 fails low. The crew responds TFS1MABL=T TFS1MABL =T (TS I) SRO (TS,I) 3-ONOP-028 to stop inward rod movement by taking rod control to per 3-0NOP-028 manual and then 3-0NOP-049.1.

3-ONOP-049.1.

3 (C) ALL 1 2OVAC power panel 3P09 normal inverter fails. The auto swap to the CVT 120VAC TFE6XO6F =

TFE6X06F = T TcE6DIlc=T also fails leaving 3P09 deenergized. The crew responds per 3-0NOP-003.9.

3-ONOP-003.9.

TCE6DI1C =T 3P09 is swapped over to the spare inverter per 3-0NOP-003.9 3-ONOP-003.9 Attachment 1.

4 TFcMM2A4 TFCMM2A4=T = T (C) ALL The 3A steam generator tube leak grows to 22 gpm. R-3-19 R-3-1 9 fails to respond.

TVI-IHSGA TYHHSGA==

(TS) SRO 3-ONOP-071 .2 The crew responds per 3-0NOP-071.2 0.002 4a (R) ALL A fast load reduction from 50% power is initiated and performed per 3-ONOP-3-0NOP-071.2 5 TVHHSGA TYHHSGA=

(M) ALL The 3A steam generator tube leak grows from 22 gpm into aa rupture. The

° 0,4 (C) SRO/BOP reactor is tripped and 3-EOP-E-0 performed. MOV-3-1433 fails to close TFSW33CT TFSW33C=T requiring manual isolation of MSIVs.

66 (C) ALL When transition is made from 3-EOP-E-0 to 3-EOP-E-3, the startup transformer locks out. 3A EDG starts but the output breaker does not TFQ5A2OA=T TF05A20A=T automatically close, and 3-EOP-ECA-0.0 is entered. 3A EDG output breaker TA05LRSB =T is manually closed and the crew transitions back to 3-EOP-E-3. Only 3A & 3D TFP1S38S = T 4kV bus are now available from 3A EDG. 3-EOP-E-3 is performed performed to cooldown andand depressurize depressurize the the ROS RCS to stop primary-secondary leak to stop leak flow.

(N)ormal, (R)eactivity, (N,iormal, .. (I)nstrument, (C)omponent, (M)ajor (R)eactlvlty, (l)nstrument, (M)aJor 11

Appendix D 0 Scenario Outline Form ES-D-1 ES-O-1 Facility: Turkey Point Scenario No.: 3 Op Test No.: 2007-301 Examiners: Candidates: US RO BOP Initial Conditions: Mode 1, 1, 75% Power, MOL, Awaiting permission from plant management to increase power back 100%. 3-GOP-301 in use complete through step 5.96 for return to 100% power following a to 100%.

turbine valve test.

Turnover: Equipment OOS: 3B EDG due to failed fuel pump (OOS 2 days; next 0-OSP-023.3 AU 1 &

Att 1 & 9 in 4 hrs); B B AFW Pump due to bearing failure (OOS 4 hrs; ETR 24 hrs; both trains verified operable);

3B CSP due to failed 1ST -low - low discharge pressure (OOS 12 12 hr; ETR 36 hr)

Perform monthly surveillance on 3A ECC per 3-OSP-055.1 3-0SP-055.1 section 7.1 immediately after shift turnover. 1ST and remote valve position verification not required.

Known tube leak in 3A S/G (2 gpd) - unchanged for last week. Chemistry samples are being taken per 3-ONOP-071 3-0NOP-071.2, .2, Attachment 1. The current sample, just completed indicates no MOV-3-1 403 remains open at management direction due to small significant change in leak rate. MOV-3-1403 size and stability of tube leak rate.

Event Event Type*

Type* Event Description No.

1 1 (N) BOP 3-OSP-055.1 section 7.1. 3A 3A ECC monthly surveillance performed per 3-0SP-055.1 TFKVOO5A=T TFKV905A =T ECC inlet valve CV-3-2905 fails to open and 3A ECC is declared OOS.

(N,TS) SRO 2 (I) SRO/RO TM-3-408C (Tavg input to rod control) fails high. Crew responds per 3-TFL1TSCH TFL 1T8CH == T ONOP-028 and takes rods to manual to stop continuous inward rod movement.

3 (C) RO/BOP Loss of 3H 480V LC. Also takes 3C charging pump, 3B ECC, 3B ECF & & 3D TFE3D37A=T TFE3D37A =T NCC OOS. Requires starting another charging pump or securing the in C TS SRO (C,TS)

TFE3D38T == T-r service 60 gpm orifice. The crew responds per 3-ARP-097.CR for annunciators F-9/6, A-5/4, 1-9/3 or 1-9/4.

4 TAKPXA1=10.0 (C) SRO/BOP 3A11 Intake screen high Llp.

3A 3-ONOP-Ol 1. 3A

p. Crew responds per 3-0NOP-011. 3A11 CWP is TAKPXA2 == 4.0 secured.

4a (R) ALL 3A2 Intake screen high Llp. 3-ONOP-100 to 60% for

p. Fast load reduction per 3-0NOP-100 TAKPXA2 == 1.0 the purpose of securing 3A2 CWP. Manual rod control must be used due to rod control Tavg failure.

5 TAHUVBSB=22 (M) ALL 3-ONOP-041 .1. Once 3B RCP high vibration. The crew responds per 3-0NOP-041.1.

setpoint the crew manually trips the reactor and vibration reaches the trip setpoint, TAHUVBMB=66 TAHUVBMB= .

immediate actions of 3-EOP-E-0 are performed.

6 (M) ALL When 3B RCP is tripped, 3B 4kV bus is lost and a large break LOCA occurs.

TFE2Z51S ==TT (contd from (cont'd An automatic SI occurs but train A sequencer fails. Train A ECCS equipment event event 5) must be manually started. The crew completes 3-EOP-E-0 and transitions to TvHHCLB=0.1 TVHHCLB = 0.1 (C) ALL applicable FRPs followed by 3-EOP-E-1.

TFQ634AF == T 6a Once CSFSTs are monitored for implementation, if containment pressure is still above 20 psig, the crew immediately transitions to 3-EOP-FR-Z.1 if no higher red or orange path exists.

6b SROIRO (C) SRO/RO 3-EOP-E-1 is entered after which 3A RHRP trips. Since neither RHRP is TFM1D3AT=T TFM1D3AT =T running, transition is made to 3-EOP-ECA-1.1. Measures are taken to minimize the loss of RWST inventory.

(R)eactivity, (I)nstrument, (N)ormal, (R)eactlvlty, (M)ajor (l)nstrument, (C)omponent, (M)aJor 11

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