ML101650166

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2007-301 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)


Text

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

Turkey Point Scenario No.: 1 Op Test No.: 2007-301 Examiners:

Candidates:

US RO BOP Initial Conditions:

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:

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);

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.

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

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.

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.

5 TVFACN3 = 0.1 (M) ALL Once reactor power stabilized

< 60% power, a 3C SG feed break occurs TFW98M=T (C) RO/SRO inside containment.

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.

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.

.. (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.

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

Turkey Point Scenario No.: 2 Op Test No.: 2007-301 Examiners:

Candidates:

US RO BOP Initial Conditions:

Mode 1, 50% Power, MOL. Power on hold at 50% following inadvertent trip of 3B SGFP while investigation in progress.

Turnover:

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);

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

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.

3 (C) ALL 120VAC power panel 3P09 normal inverter fails. The auto swap to the CVT TFE6X06F = T also fails leaving 3P09 deenergized.

The crew responds per 3-0NOP-003.9.

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

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.

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.

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:

Turkey Point Scenario No.: 3 Op Test No.: 2007-301 Examiners:

Candidates:

US RO BOP Initial Conditions:

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:

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);

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.

Known tube leak in 3A S/G (2 gpd) -unchanged for last week. Chemistry samples are being taken per 3-0NOP-071.2, Attachment

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.

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.

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.

The crew responds per 3-0NOP-041.1.

Once TAHUVBMB=

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

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.

Measures are taken to minimize the loss of RWST inventory.

.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor 1