ML20040G715
| ML20040G715 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/23/1980 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20040G713 | List: |
| References | |
| AP-17, NUDOCS 8202160396 | |
| Download: ML20040G715 (40) | |
Text
8 12-23-30 R2v.-2 AP-17
(
LOGGING OF OPERATIONAL TRANSIENTS 1.0
' PURPOSE To establish the procedures for logging operational transients involving the Nuclear. Steam Supply System of Rancho Seco Unit 1.
2.0 REFERENCES
.1 B & W Specifications. CS(F)-3-92/NSS-11 " Reactor Coolant System Components".
.2 Rancho Seco Unit 1 Technical Specifications.
.3 Rancho Seco Unit 1 FSAR.
3.0 PROCEDURE
.1 In the design of Rancho Seco Unit 1 twenty-four types of NSSS transients have been considered.
To insure that design margins and parameters are observed in operation, each and every tran-sient cycle is to be logged.
This log vill be compiled from the Control Room Log, Computer Logs, Recorder Traces, and other
(
pertinent records of plant operation.
.2 A cycle is defined as a transient deviation from some condition and a return to that initial condition.
Half cycles are re-corded as " cycles" in some cases, e.g. heatup from cold shutdown, or cooldown to cold shutdown.
1
.3 Descriptions of transients for equipment design purposes are given in Reference 2.1.
.4 A record sheet will be kept for each type of transient.
In addition to recording tha : a particular transient did occur, data will be recorded for: upset and faulted condition tran-sients that will assist 1.!t an analysis of the severity of the l1 transient.
.5 At least semi-annually, t1e Assistant Superintendent for Technical Support will review the lpgs to insure that the number of design cycles is not being appro' ached or exceeded, and to determine what,
if any, corrective action lis required.
AP-:;7/1 Rev. 1
(
8202160396 820204 PDR ADOCK 05000312 P
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3.0 PROCEDURE (continued)
.6 Definition and description of each transient cycle.
't Following are the Transients, by number, and a description of each cycle:
.1A Heat-up from ambient temperature to 8% Full Power.
(Normal Condition)
One cycle involves only the heatup and escalation to 8% of Full Pcwer.
Desiga Cycles = 240.
. 13 Cooldown from 8% Full Power to 140 degrees F.
(Normal Condition)
One cycle involves only the cooldown from 8% Full Power.
Design Cycles = 240.
.2 Pcwer change, O to 15% or 15 to 0%.
(Normal Condition)
One cycle includes either a heat-up from 532*F to 582*F or a cooldown from 582*F to 532*F.
l Design Cycles = 1440.
.3
?ower Loading, 8% to 100% Power.
(Normal Condition)
This is one design power loading cycle.
I Design Cycles = 18,000.
.4 Power Unloading, 100% to 8% Power.
(Normal Condition)
This is one design power unloading cycle.
Design Cycles = 18,000.
.5 10% Step Load Increase.
(Normal Condition)
One such step is one cycle.
Design Cycles = 8,000.
.6 10% Step Load Decrease.
(Normal Condition)
One such step is one cycle.
Design Cycles = 8,000.
.7 Step Load Reduction, 100% to 8% Power.
(Upset Condition)
A complete cycle is defined as a turbine trip or electrical load rejection to 8% power with a return to full power.
Design Cycles = 310.
AP-17/2 Rev. 1
3.0 PROCEDURE (Continued)
.6
.8 Reactor Trip (Upset Condition)
There are two types of cycles to be considered for each trip:
.1 Reactor trip from Power, hold at hot shutdown with return to power.
Design cycles = 30 cycles of transient 8A,130 cycles of transient 8B, and 72 cycles of transient 8C.
i
.2 Reactor trip from Power, followed by cooldown.
i Design Cycles = 10 cycles of transient 8A, 30 cycles of tran<2(at 8B, and 16 cycles of transient 8C.
NOTE:
There are no specific design cyc3es listed in Reference 2.1 for transient 8D.
This transient is logged for in-y formation purposes to assist in future evaluations if required.
The trips are listed by their separate causes as:
Transient 8A: Reactor Trip Due to Loss of RCS Flow.,
Transient SB: Reactor Trip Due to High Temp-erature, pressure or power caused by Turbine Trip.
Transient 8C: Reactor Trip Due to High Temp-erature, pressure or power caused by loss of feedwater.
Transient SD: Reactor trip due to Power /
Imbalance / Flow, Low Pressure, 1
Manual or other undesignated causes.
.9 Rapid RCS Depressurization (Upset Condition)
A complete cycle consists of power reduction, rapid de-pressurization from 2155 PSIG to 1050 PSIG in 515 minutes, followed by normal cooldown.
Design Cycles = 40.
AP-17/3 Rev. 1
3.0 PROCEDURE (Continued) s
.6
.10 Change of Reactor Coolant Flow without Reactor Trip (Upset Condition)
The cycle involves a change of flow, due to RCP trip, power reduction to 15%, pump restart and return to full
, power.
Design Cycles = 20.
.11 Rod Withdrawal Accident (Upset Condition)
. A cycle is defined as the withdrawal of a CRA Croup at maximum speed at a power level 515%.
There are two types of cycles to be considered:
a.
Rod withdrawal, reactor trip, and return to 15%
powe r.
Design Cycles = 30.
b.
Rod withdrawal, reactor trip, and cooldown.
Design Cycles = 10.
.12 Hydrotests (Test)
A full hydrotest cycle is used when the pressure a.
exceeds 2750 PSIG (110% of design) in the RCS, or when the Secondary System pressure exceeds 1312.5 PSIG (125% of design).
Pressures exceeding the design of 2500 PSIG for the RCS or 1050 PSIG for the Secondary System shall be logged; however, pressures less than the hydro pressures defined above do not constitute a full hydro design cycle.
o b.
ASME Section XI " hydros" do not require exceeding 2500 PSIG or 1050 PSIC. These* hydros shall be logged, but are not limited.
Transient 12A:
Primary Hydrotests - RCS.
Design Cycles = 35.
Transient 12B:
Secondary Hydrotests -
Steam Side.
Design Cycles - 35.
.13 Steady-State Power Variations (Normal Condition)
An infinite number of these cycles are allowed, as such they need not be recorded.
.m AP-17/4 Rev 1
m-
)
3.0 PROCEDURE (Continued)
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.6
.14 Reactor Power Runback (Upset Condition) f a.
Control Rod Drop with runback.
One cycle involves a CRA drop, runback to 60% power, and return to full power.
Design Cycles - 40.
b.
Feedwater Pump. trip with runback.
One cycle involves a single feed pump tripping, Reactor runback to 60% power, and return to full power.
1 Design Cycles - None listed; logged for information only.
.15 Loss of Station Power (Upset Condition)
Cycle involves loss of station power, restoration of power, and return to power.
Design Cyc1cs = 40.
.16 Main Steam Line Failure (Faulted Condition)
This is an emergency condition and after OTSG isolation involves a cooldown.
Design Cycles = 1.
.17A Loss of Feedwater to One OTSG (Upset Condition)
Dry OTSG because of loss of Feedwater.
Design Cycles = 20.
.17B' Stuck Open Turbine Bypass Valve (Upset Condition)
Dry OTSG because of stuck open turbine bypass or atmos-pheric dump valve.
Design Cycles = 10.
k AP-17/5 Rev. 1 m
.n m -
~1 7
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3.0 PROCEDURE (Continued)
.6
.18 Sudden Loss of Feedwater Heater at 100% Power (Upset Condition)
A cycle involves a sudden (< 30 ' Seconds) decrease in feedwater temperature of at least 50*F.
. Design Cycles = 40.
.19 Feed and Bleed Operations (Normal Condition)
No logging required since no equipment cycle limits are involved.
.20 Pressurizer Spray Flow (Normal Condition)
A cycle consists of opening and closing of the main spray valve during normal plant operation.
Design Cycles = 20,000.
.21 RCS Loss of Coolant (Faulted Condition)
This is based on a double ended rupture of a 36 inch hot leg, one half cycle of blowdown from full pressure con-stitutes the entire transient.
Design cycles = 1.
.22A High Pressure Injection into RCS (Test or Upset Condition)
A cycle occurs anytime H.P. Injection pumps are used to supply water to the RCS through the H.P.I. nozzles (except during cold shutdown). The nozzle at the "A" RCP discharge is the normal makeup nozzle and would not see a cycle un-less makeup flow were stopped entirely prior to start of the H.P.
Injection.
2 l
Design Cycles = 110 cycles per nozzle.
.22B Core Flooding Check Valve Tests (Test)
Each time water from the core flood tanks enters the RV with the RCS at 600 PSIC (415'F) is one cycle.
Design Cycles = 240.
.23A OTSG Secondary Side Filling (Normal Condition) l No logging necessary as this transient is assumed to occur i
concurrent with transient lA.
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AP-17/6 Rev. 2
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3.0 PROCEDURE (continued)
.23B OTSG Primary Side Filling.
(Normal Condition)
No logging necessary as this transient is assumed to occur concurrent with transient IA.
.23C OTSG Chemical Cleaning.
(Normal Condition)
,s One cycle involves repeated fill, soak, and drain operations
" with chemicals added to the water.
Design Cycles = 20.
.24 Hot Functional Testing.
(Test)
This is a test condition expected to occur once and involve two heatup and cooldown transients.
4.0 ACCEPTANCE CRITERIA Transients defined in this procedure have been logged and reviewed at least semi-annually to ensure the number of design cycles for each transient are not exceeded.
5.0 ENCLOSURES
.1 Transients Log She'ets
.2 Data Sources for Transient Logging 1
AP-17/ 7 Rev. 1
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Shrst 1 of 39
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TRANSIENT 1A DESIGN CYCLES 240 Hestup From Ambient Temperature to 8% Full Power (Normal Condition)
Cycle Date Heatup Date 8%
Recorded By/
Remarks Number Started Power Date Reached
~
l a
I AP-17/ 8 Rev. 1
TRANSIE3G IB DESIGN CYCLES 240 Cooldown From 8% Full Power to 140 F (Normal Condition) a.
Cycle Date Cool-Date RCS Recorded By/
Remarks Number down Started 0140 F1 Date
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or Less 1
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AP-17 /9 Rey, 1 l
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TRANSIENT 2 DESIGN CYCLES 1440 I
Power Change, O to 15% or 15% to 0%
(Normal Condition)
Cycle Date Power Change Recorded By/
Remarks Number Transient Increase or Date Complete Decrease a
I AP-17/10 Rev. 1
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(
Sh;;t 4 of 32 DESIGN CYCLES _18,000 Power Loading, 8% to 100% Full Power
~
(Normal Condition)
Cycle Date of Power Loadinn Chance Recorded By/
Remarks Number Transient Initial final Date
% FP
% FP I
AP-17/11 Res. 1
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(-
hReet 5 of 32 TRANSIENT 4 DESIGN CYCLES 18,000 Power Unloading, 100% to 8% Full Power 1
(Normal Condition)
Cycle Date of Power Unloadine Change Recorded By/
Remarks Number Transient Initial Final Date
% FP
% FP a
?-
AP-17/ 12 Rev. 1
TRANSIENT 5 Shast 6 ef 32 DESIGN CYCLES 8,000 10% Step Load Increase (Normal Condition)
Cycle Date of Power Level Maximum Recorded By/
Remarks Number Transient Init.
Final Loading Date s
P,re
% FP
% FP
% FP/nin I
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I AP-3 7/13 Rev. 1
TRANSIENT 6 DESIGN CYCLES 8,000 10% Step Load Decrease (Normal Condition)
Cycle Date of Power Level Maxicum Recorded By/
Remarks Number Transient Init.
Final Unioading Date Rare
% FP
% FP
%~FP/ min 9
am AP-17 /14 Rev. I
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TRANSIEttr 8B DESIGN CYCI.ES A. Trip & IIold at !!at Shutdown 130_
B. Trip & Cooldown 30 Reactor Trip Dite to liigh Temperature, Pressure or Power -
Caused by turbine trip (Upset Condition) i Cycle Date of Reactor Maximum Reactor Trip Stable RCS Type of Cycle Recorded By/
Remarks Number Transient Power Cooldown Cause, Temp.,
Temp. After Trip &
Crip &
Date at Trip,
- Rate, Pressure or
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% FP F/hr.
Power OP llot Shutdwn.
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TRANSIE.Vr 9 DESIGN CYCLES 40 Rapid RCS Depressurization-2155 to 1050psig in 115 minutes (Upset C'ondition)
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Cycle Date of Reactor Maximum Time to Recorded By/
Remarks Number Transient Power Cooldown RCS 1050 Date Prior to
- Rate, psig,
~
Shutdown F/hr.
minutes
% FP A
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AP-17/20 Rev. 1
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Shast 16 of 32 TRANSIENT 12A DESIGN CYCLES 35 Primary Hydrotests - RCS (Pressure E2500psig) i Cycle Date of Peak Minimum Test per Reason Recorded By/
Remarks Number Hydrotest Test Metal Which For Date
- Pressure, Temp.,
Code Test g
psig 0F
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'1 AP-17 /23 Rev. 1
TRANSIENT 12B DESIGN CYCLES 35 Secondary Hydrotests - Steam Side Pre'ssure 21050psig)
Cycle Date of Peak Minimum.
Test per Reason Recorded By/
Remarks Number Hydrotest
. Test Metal Which For Date s
- Pressure, Temp.,
Code Test
' s, psig 0F o
=
AP-17/24 Rev. 1
Shrat 18 or 32 I-TRANSIENT 13!
I DESIGN' CYCLES INFINITE Steady-state Power Variations
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1 (Normal Conditions)
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l AN INFINITE MIDiBER OF. THESE CYCLES ARE ALLOWED, 1
i AS SUCH THEY NEED NOT BE RECORDED.
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AP-17/ 25 Rev.-1
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auvet 13 ot 32 TRANSIENT 14A DESIGN CYCLES 40 Control Rod Drop With Runback o
(Upset Condition)
Cycle Date of Reactor Fower Recorded By/
Remarks Number Transient Prior to After Date
- Drop, Runback
% FP
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AP-17/ 26 Rev. I
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'TRANSIEST 14B
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INFOPJMTION Feedwater Pump Trip With Rupback ONLY (Upset Condition)
Cycic Date of Re.,ctor Pmrer Recorded By/
Remarks Number Transient Prior to After Date Runback P.unback
% FP
% FP
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AP-17/ 27 Rev. 1
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Shent 22 cf 32 TRAN.11ENT 16 DESIGN CYCLES 1 Main Steas.Line Failure (Faulted Condition)
N IF THIS TRANSIETE OCCURS A DETAILED ANALYSIS [
WILL BE REQUIRED PRIOR TO RECOVERY.
ATTACH THAT ANALYSIS FOR LOCGING PURPOSES.
AP-17/29 Rev. 1
TRANSIENT 17A DESIGN CYCLES 20 per.TrSG Dry OTSG Because of Loss of Feedwater j
(Upset Condition)
Cycle Date of OTSG Which Recorded By/
Reciarkss Number _
A B
Transient Uent Dry-Date I
I 1
J AP-17/30 Rev. 1
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Shist 24 of 32 TRANSIENT 17B DESIGN CYCLES 10 per OTSG Dry OTSG Because of Stuck Open Turbine Bypass or Atmospheric Dump Valve
.(Upset Condition)
Cycle Date of OTSG lihich Recorded By/
Remarks
'l'b r
tJent' Dr'v '
Date 7,,
AP-17/ 31 Rev. 1
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Sh::st 26 cf 32 TRANSIENT 19 f
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Feed & Bleed Operations
(!!ormal Conditions)
Tills CYCLE IS NOT LOGGED SINCE NO EQUIPMENT CYCLE LI:ITS ARE INVOLVED.
9 AP-17/ 33 Rev. 1
(
(
Sh:ct 27 cf 32 TRANSIENT 20 DESIGN CYCLES 20,000 Pressuriser Spray Flow i
(Normal Condition)
Recording Cycles This Total Cycles Recorded By/
Remarks
- Period, Period Date N
Give Dates l
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TRANSIENT 21.
DESIGN CYCLES 1
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RCS Loss of Coolant (Faulted Condition)
N-ha j
IF THIS TRANSIENT OCCURS A DETA'ILED ANALYSIS "';.'-
.7 WILL BE REQUIRED PRIOR TO RECOVERY.
ATTACH THAT ANALYSIS FOR LOGGING PURPOSES.
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~ TRANSIENT 22B DESIGN CYCLES 240 Core Flooding Check Valve Tests (Test Condition)
Cycle Date of RCS CFT-A CFT-B Recorded By/
Remarks Number Test T
vol.,
vol.,
Da te
,"F"***
gallons gallons (if available) (if available)
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TRANSIENT 24 DESIGN CYCLES 1
'(.
Hot Functional. Testing INCLUDE WITH THIS RECORD A CHART SHOWING THE CONTIN 0U RCS
~
AND SECONDARY
- PRESSURE /TDLDERATURE HISTORY VERSUS TIME FROM THE. ','.
START OF HFT UNTIL RV HEAD REMOVAL FOR INITIAL FUEL LOADING.
4 I
/NP-17L 39 Rev. A
\\
1 EXCLOSURE 2
~
DATA SOURCES FOR TRANSIENT LOGGING-Control Roon Log Shift Supervisors',' Log Trip Reports.
Recorder Charts:
TR 21025, Unit T,y,
's XR 00403, Reactor Auctioneered Power PR 21037, RCS Narrow Range Pressure
~'
PR 21038, RCS Narrow Range Pressure PR 21092, RCS Wide Range Pressure FR 21027, RC Flow LR 21503, Pressurizer Level TR 21031, Unit Thot LR 20503, A OTSC Operate Level LR 20504, B OTSG Operate Level PR 20543, Steam Pressure PR 30119, Steam Pressure FR 20535, A OTSG FW Flow FR 20536, B OTSG FW Flow LR 23502, Makeup Tank Level Computer Points:
C009, Reactor Auctioneered Powar C139, 140, Unit Tave T010, 011, 108, 109, Unit Thot T012, 013, 014, 015, 016, 017, Unit Teold P034, 015, 016, 017, 034, 035, 036, RCS Pressure F016, 017, 018, 019, 020, 021. 022, 023, RCS Flow LOO 8, 009, Pressurizer Level TOIS, Pressurizer Surge Line Temperature l
T009, Pressurizer Temperature LO35, 036, OTSG A, B Full Range Level LO37, 038, OTSG A, B Operate Range Level LO39, 040, OTSG A, B Startup Range Level T800, 801, 802, Painsteam Temperature F800, 801, OTSG A, B Mainstean Pressure i
T067, 208, Feedwater Temperature F013, 014, 801, 802, 807, 808, Feedwater Flow F015, Letdown Flow T217, Makeup Temperature l
AP-17/40 Rev. 1
"