ML17345B346
| ML17345B346 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/03/1983 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17345B345 | List: |
| References | |
| 0208.1, 208.1, NUDOCS 8311160152 | |
| Download: ML17345B346 (13) | |
Text
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 OFF NORMAL OP RATIa G PROCEDURF 0208 1
AUGUST 3
1483
1.8 Title
SHUTDOWN RESULTING FROM REACTOR TRIP OR TURBINE TRIP 2.0 Approval and List of Effective Paces:
- 2. 1 Aoorova1:
Change Dated 8/3/83 Reviewed by Plant Rutlear Safety Caamittee:
83-75 and Approved by Plant Manager - Nuclear:
8/3/83 2.2 List of Effective Paces:
~Pa e
Date Pace 1
8/3/83 3
2 8/3/83 t
3.0 Purpose and Discussion:
- 3. 1 Puroose:
Date Pa e
'Date Pace Date 8/3/83 5
8/3/83 7
8/3/83 8/3/83 6
8/3/83 8
8/3/83 9
8/3/83 This procedure provides instruc.ions to be followed when a
shutdown occurs due to a reactor or turbine trip.
It also provides guidance or conduc-of initial investigation and post trip review as appropriate for the nature of the trip involved.
3' Discussion:
3.2.1 Turbine thrust bearing pressure trip and al 1
gener ator trips of electrical origin cause an imediate opening of the generator OCB's.
For all other trips, the OCB's remain closed
.or 30 seconds to provide an ener~ drain for the turbine and increase the coastaown time of the reactor coolant pumps.
3.2.2 Any of the following will cause a reactor tr.'p:
1.
Source range high level 2.
Intermediate range high level 3.
Power range high level - low setpoint 4.
Power range high level - h'.gh setpoint t83111601)2 831108 i DR *DOCK 05000~>50 PDR
OFFfQRMAL OPERATING PROCEDURE 0208 ~ 1, PAGE 2
SHUTDOWN RESULTING FROM REACTOR TR IP QR TURB INE TR - P 8/3/83 5.
Pressurizer high pressure 6.
Pressurizer high level 7.
Pressurizer low pressure 8.
Low coolant flow 9.
RCP breakers open 10.
4KV bus low voltage 11.
4KV bus underfrequency 12.
Overpower delta T setpoint 13.
Overtemperature delta T setpofnt 14.
Safety injectfon 15.
Turbine trip 16.
Low-low steam generator level 17.
Steam flow greater than feed flow coincfdent with low steam generator level 18.
Manual trfp 3.2.3 An'.~ of the following will cause a turbfne trip:
1.
Condenser 'low vacuum 2.
Low bearing oil pressure 3.
Thrust bearfng pressure 4.
Turbine overspeed 5.
Reactor trip 6.
Steam generator high-high level 7.
Generator 1 ockout 8.
Generator - Transformer Lockout 9.
Manual trip 10.
Safety Injection
OFFNORMAL OPERATING PROCEDURE 0208.1, PAGE 3
SHUTOOWN R SULTI IG FROM REACTOR TRIP OR TURB IilE TRIP 8/3/83 3.2a4 Inftfal investigation and post trio review guidelines are provided to assure that an adequate investigatfon and restart determination appropriate to the nature of the trip are conducted and documented.
For example, a simple trip with no equipment malfunction consequences that resulted from a
clearly known cause would require proportionately less ef ort to make a safe to restart determination than would a
trip of indeterminate cause or with signfficant equipment damage.
Lack of available recorded data may necessitate more emphasis on interviews, statements, analog or logsheet fnformation, etc.
4.0 gvtnotoflla
4.1 Symptoms are annunciator alarms associated with any of the causes listed in 3.2.2 and 3.2.3.
5.0 Instructions
- 5. 1 Immediate Automatfc Action:
5.1. 1 The turbine wi 11 trip with either a turbine or reactor trip signaI.
- 5. 1.2 The reactor wi 11 trip with any reactor trfp signal or any turbine trip signal with reactor power above P-7.
5.1.3 Steam dumps to condenser or atmosphere may ac fvate.
- 5. 1.4 Mafn Generator Lockout (Mfd and East OCB's open, auxiliary breakers open, startup breakers close, field breaker open).
5.2 Immediate Operator Actions:
5.2. 1 If a reactor'rip fs called for, verffy that reactor trip breakers have opened and that all shutdown and control rods are ful',y fnserted.
- l. If the above automatic ac.ions did not occur, then manually trio the reactor using any of the following methods, which are liste~
fn decending order of preference:
(1)
Reactor trip push button, console or YP-B.
(2)
Locally fn MCC-8
- room, open reac.or breakers and/or M6 set breakers.
(3)
Locally in 480Y load centers, open breakers to MG sets.
(4)
Emergency borate and at. empt to drive in rods manually.
5.2.2 Yerify turbine has tripped and if not, push manual trip and ver'..y turbine stop and control valve closure.
CauT'ON:
Fa! lure of the turoine to trip following a
r eat or =rip can result fn a severe RCS ccoldown accident.
OFF NORMAL OPERATING PROCEDURE 0208. 1, PAGE 4 SHUTDOWN RESULTING FROM REACTOR TRIP OR TURBIiVE TRI?
8/3/83 5.2.3 Verify main generator lockout.
Mid and East OCB's, exciter field breaker and auxiliary transformer breakers should be open.
Startup transformer breakers should be closed.
5.2.4 Verify feedwater isolation.
Close Feedwater Isolation MOV's.
5.2.5 Verify the operation of the steam dumps to condenser.
They should maintain Tavg at 547',
however, if condenser vacuum has be n lost utilize the atmospheric steam dumps to maintain 547'.
CAUTION:
If the steam dumps tu ccndenser were heing used fnr a
unit startup, place the mode selector swi ch to auto and reset the Hagan setpoint controller to prevent an uncontrolled cooldown.
5.2e6 Close reheat steam supply MOV's.
5.2. 7 If all RCP's
- trip, verify and maintain natural circulation per Operating Procedure 1008.7, Natural Circulation.
5.2. 8 Maintafn pressurizer pressure and level at no load valves by energizing backup heaters and cyclfng chargfng pumps as required.
Isolate letdown if necessary to maintain pressurizer level.
5.3 Subseouent Operator Actions:
5.3.1 5.3.2 5.3.3 5.3.4 When unit fs stable, the Plant Supervisor - Nuclear/STA initiate post trip review in accordance with Appendix A.
Verify feed train and with the feedwater by-pass
- valves, manually control steam generator levels.
Care should be taken fn restoring levels to avoid droppfng Tavg below 547'F and to avoid thermal shocking the steam generators.
If low-low steam generator level or loss of feed.rain occurs, verify the auxiliary feedwater MOV's are open.
Regulate auxiliary feed Icw to maintain steam generator levels near no load values.
If unable to maintain adequate steam gener'ator level s, close the b lowdown MOV'.
5.3.5 If unable to maintain adequate steam generator
- levels, steam dumo must be minimized and reactor coolant pumps should be stopped as required to reduce heat input to the steam generators.
NOTE:
Partial loss of RC?s (f.e.,
1 or 2
pumps fafI) can effec:
pressurizer spray capability.
It is desirous to maintain RCPs in operation as Iong as operating conditions. perm.'t to provide a
more orderly reco'very from a trip.
- However, loss of the "B"
4 i(V bus and its associated "B"
and "C"
RC?s results in loss of normal spray capabi li.y
':or the pressurizer.
In this
- event, prudent use of pressuri:e.
heaters and the auxiliary spray valve.must be exercisea to effec ively control the pressurize.
pr ssure.
Loss of the "A"
RCP will not effec.
pressurizer spray control and effective spray should be available wi.h either the "B" or "C" RCP operating.
OFF-ivORMAL OPERATING PROCEDURE 0208.1, PAGE 5
SHUTDOWN RESULTING FROM REACTOR TR IP OR TURB INE TR IP 8/3/83 5.3.6 If all of the reactor coolant pumps are
- stopped, assure that natural cf rcul ation is establ f shed in accordance with Operating Procedure 1008. 7, Natural Circulation.
5.3.7 Verify as turbine slows down, the bearing oil pumps start as follows:
1.
Auxiliary ofl pump at 9 psig, bearing oil pressure, or 2.
Turnfng gear oil pump at 7 psfg, bearing oi I pressure, or 3.
Emergency OC oil pump at 3.5 psig, bearfng oi I pressure.
5.3.8 Verify the bearing oil lift pump starts when turbfne reaches 600 RPM and discharge pressure fs approximately 600 psig.
5.3.9 Verify that at 0
RPM and 600 lbs.
bearing oil liit pressure, the turning gear engages or engage ft manually.
5.3.10 Place Control Switch for turbine drains to open as soon as possible after trip.
5.3.11 Verify gland seal regulator is fn service as long as condenser vacuum is mafntafne4.
5.3.12 Maintain bearing oil temperature between 80' 100'F.
5.3.13 If the reactor fs to be maintained at hot shutdown conditions, commence boration to the xenon free condition as shown in Section III, Figure. 3, of the Plant Curve Book.
5.3.14 If it fs not desfred to maintain the plant fn the hot shutdown condition, bring the unit to cold shutdown per Operating Procedure 0205.2, Reactor Shutdown; Hot Shutdown to Cold Shutdown Condition.
5.3.15 Notify the Lab that RCS sampling is reoui red as per ech Spec
- 3. 1.4.
6.0
References:
- 6. 1 Westinghouse Turbine Operation and Control Instruction
- Book, Volume I, FPL File 56104-3-206, Westfnghouse Instructfon Book No. 1250-C683.
6.2 Westinghouse Turbfne Generator Instruc.fcn Book, FPL File 56i0~9-3-205.
6.3 Operating Procedure 0205.2, Reactor
- Shutdown, Hot Shutdown to Cold Shutdown Conditions.
6.4 Operating Procedure 1008. > - Natural Ci rculatfon.
OFF-NORMAL OPERATING PROCEDURE 0208. 1, PAGE 6
SHUTDOWN RESULTING>G FROM REACTOR TRIP OR TURB,'lE TRlP 8/3/83
~
E 0
Records Required:
- 7. 1 Entry into plant logs of details related to trip.
7.2 Entry into Startup/Shutdown/Trip Log Book 7.3 Appendix 8 of Administrative Procedure 0103.12, Notification of Significant Events to NRC, shall be completed for each reactor or turbine trip.
7.4 Completed copies of Appendix A of this procedure, including all attachments, constitute quality control records
- and, therefore, shall be retained in accordance with Administrative Procedure 0190.14, Oocument Control and gualfty Assurance Records.
OFF-NORMAL OPERATING PROCEDURE 0208.1, PAGE 7
SHUTDOWN RESULT'NG FRCH REACTOR TRIP OR TURBINE TR'P 813/83 APPEINDIX A (Sheet I of 3)
N POST TRIP REVIEW (Cover Sheet or Trip Review ana Appraisal Package) l.
Unit:
Date:
2.
Cause of Reactor Trip:
Time of Trip:
A)
Logic that directly resulted in reactor trip:
B)
Root cause of trip:
3.
Trip Sequence Time Intervals - from DDPS SOE
- NOTE:
If OOPS is Out of Service (OOS) indicate status of components marked l
with asterick.
- Logic Matrix Ac uated:
Time 0 RT Relays Dropout
<<Reactor Trip Breakers A
(OPEN RPI Rod Bottom
) O. 1 second maximum
) from RT relay dropout to breaker open.
Turbine Stop Valves -
(CLOSED)
"Generator Breakers Right Left (OPEN)
B Attach SOE and any per.inent PTR file parameter printouts.
4.
Limi.ing Conditions for Operation:
(List any deviations)
OFF'(ORMAL OPERATING PROCEDURE 0208.1, PAGE 8
SHUTDOWN RESULTING FROM REACTOR TRIP OR TURSI'~E TRIP 8/3/83 APPENDIX A POST TRIP RE'/IEW 5.
Response
of Systems and Equipment:
(Indicate any observed problems or effects) 6.
If appropriate, have system or equipment walkdown inspections or damage assessment conducted and documented.
At.ach results.
7.
Verify unit is stable or controlled to desired conditions, consider:
CHECK (X
Nuclear Instrumentation RCS Fluid Inventory RCS Pressure RCS Temperature RCS Flow Containment Sump PRMS ARMS S/G Level S/G Pressure Turbine Gen. (Vibr., hyd. status, etc)
Secondary Systems REWSKS:
If Safety Injection was actuated verify Emergency Operating Procedure 20000 is implemented.
OFF
')ORMAL OPERATING PROCEDURE 0208. I, PAGE 9
SHUTDOWN RESULTING FROM REACTOR TR IP OR TURB INE T"IP 8/3/83 0
APPENDIX A (Sheet of 3)
POST TRIP RE'IIE'd 8.
Discuss trip cause, any safety considerations, and imediate corrective actions.
A)
If cause of reactor trip is known (see Item 2), acceptably corrected and any safety considerations are
- resolved, and the PS-s'l,
- STA, and Operations Supervisor concur; authorize unit startup fn accordance with OP 0202.2.
8)
If cause of reactor trip is not known (see Item 2) or any safety considerations are not resolved, the Operations Superintendent
- Nuclear or Plant Manager - Nuclear or Site Manage.
shall also be consulted and concur prior to authorizing unit startup.
Additional investigation and/or support may be necessary and shall be provided at this time if required.
This may include prior PNSC review if appropriate and deemed necessary.
REMARKS:
!!eactor startup authorised pending resolution of the following itees (List if appiicabie):
9:
Make appropri ate notifications:
~( Operating Procedure 0103. 12
] Emergency Procedure 20103 Notification of Significant =vents.c NRC Classification of Emergencies Completed Date:
Signed:
P ant Superv>sor - Nuc ear Time:
Signed:
Shif. Techn> ca Aevi sor REMARKS:
Transmit package with attachments to the Operations Supervisor for,urther review and outing.