ML20205D617
| ML20205D617 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/18/1988 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20205D578 | List: |
| References | |
| NUDOCS 8810270157 | |
| Download: ML20205D617 (7) | |
Text
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LIST OF TICURES Tta.re
!!:le Pace 1.1 '.
APRM Flow Sias Scram Relationship 70 16 i
Normal Operating Conditions 4.1.1 Ins:rument Tes: Interval Determinati:n 55 Curves 4.2.2 Probacility of Sys:em Unavailability 98 vs. Test Interval 3.3.1 SRM Count Rate vs. Signal-to-Noise Ratio 103a l
3.4.1 Deleted 122 3.4.2 Deleted 123 i
3.5.K.1-1 MCPR Operating Limit vs. 1!, BP/P8X8R Fuel, 142 Standard Operating C nditions 3.5.K.1-2 MCPR Operating Limit vs. 1, GE8X8E3 Puel, 142a-1 Standard Cperating Conditions 3.5.K.1-3 MCPR Operating Limi: vs.
't, LTA310 Fuel, 142a-2 i
Standard Operating Conditions 3.5.K.2-1 MCPR Operating Limi vs. 17, BP/PSX8R ruel, 142a-3 Increased Core Flcw 3.5.K.2-2 ACPR Operating Limit vs. 17, CISX8EB Tuel, 142a-4 Increased Core ricw
'l 3.5.K.2-3 MCPR Cperating Limi: vs. 17, LTA310 Fuel, 142a-5 I
ncreased Core Tlcw i
3.5.K.3 Deleted 142b l
3.5.1.E Kf Tac:ct vs. Core F1 w 142d
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3.5.'.T Oeleted 142e 3
3.5.1 G Deleted 142f 3.5.;.H MAPLHGR vs. Planar Average Exposure, 142g Unit 2, P SX8R ruel, Type PSCR3235, 100 mil enannels t
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i 6810270157 sego;g 1
[,DR ADOCK 0500o 77 FDC I
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4 PBAPS UNIT 3 LIST OF FIGURES i
i Figure Title pace I
i 1.1-1 APRM Plow Bias Scram Relationship To Normal 16 l
Operating Conditions l
4.1.1 Instrument Test Interval Determination Curves 55 4.2.2 Probability of System Unavailability vs. Test 98 i
Interval l
3.3.1 SRM Count Rate vs. Signal-to-Noise Ratio 103a l
l 3.4.1 Required Voluue and Concentration of 122 i
Standby Liquid Control System Solution 3.4.2 Required Temperature vs. Concer.tration for 123 Standby Liquid Control System Solution 3.5:K.1 MCPR Operating Limit vs. Tau, LTA 142 3.5.K.2 MCPR Operating Limit vs. Tau, BP/PSX8R Fuel 142a 1
3.5.1.A DELETED 3.5.1.B DELETED
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3.5.1.C DELETED 3.5.1.0 DELETED J
3.5.1.E Kf Factor vs. Core Flow 142d
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3.5.1.F DELETED j
l 3.5.1.G DELETED
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3.5.1.H HAPLHGR vs. Planar Average Exposure, Unit 3 1429
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P8X8R Puel (P8DRh184H) r 3.5.1.!
HAPLHGR vs. Planar Average Exposure, Unit 3 142h l
P8X8R and BP8X8R ruel (P80RB299 and BP80RB299) l 3.5.1.J HAPLHGR vs. Planar Average Exposure, Unit 3 1421
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BP8X8R Tuel (BP8DRB299H) j 3.5.1.K MAPLHGP vs. Planar Average Exposure, Unit 3 142j j
P8X8Q LTA (P8DQB326)
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i 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2 Minimum Temperaturc for Mechanical Heatup or 164a Cooldown following Nuclear Shutdown l
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3.6.3 Minimum Temperature for Core Operation 164b l
l (Criticality)
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j 3.6.4 Transition Temperature Shift vs. Fluence 164c l
l 3.6.5 Thermal Power Limits of Specifications 164d i
3.6.r.3, 3.6 F.4, 3.6,0.5, 3.6 r.6 and 3.6.T.7 3.3.1 Site Boundary and Effluent Release Points 216e J
6.2-1 Management Organization Chart 244 l
6.2-2 Organization for Conduct of Plant operation 245 l
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Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SCRVEILLANCE REQUIREMENTS i
1.3.8 Control Rods (Cont'd.)
4.3.B Control Rods (Cont'd.)
j 4.
Control rods shall not be with-4.
Petar te control rod with-drawn for startup or refueling drawal for startup or dur-unless at least two source ing refueling vwrify that range enannels have an observed at least two sources range count rate equal to or greater channels have an observed I
than three c:unts per second
- count rate of at least j
three counts per second.*
I 5.
During operation with limiting 5.
When a limiting control rod
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control rod patterns as deter-pattern exists, an instru-mined by the designated quali-ment functional test of the fied personnel, either:
RBM shall be performed prior to wititdrawal of the desig-nated rod (s),
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May be reduced for startup b.
Control rod withdrawal shall be blocked, or only, provided at least l
- c. The operating power-level r.nree source range channels i
shall be limited so enat nave an observed count rate the MCPR will remain above and a Jignal-to-noise ratio l
ene fuel cladding integrity on or above the curve safety limit assuminn a shown on Figure 3.3.1.
single error that results
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i in complete withdrawal of i
a single cperable control i
rod.
f C.
Scram Insertion Times C.
Scram Insertion Times 1.
Tne average scram insertion time.
1.
After each refueling outage, l
based on tne deenergization of and prior to synchronizing I
tne scram pilot valve solenoids the main turbine generator i
as time :ero, of all operable initially following restart control reca in the reactor of the plant, all operable poaer operation condition fully withdrawn insequence shall be no greater thans rods shall be scram time tested during operational l
s Inserted from Avg. Scram Inser-nydrostatic testing or i
Tully Witndrawn tion Times (seel during startup from ene fully withdrawn posi-
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5 0.375 tion with the nuclear 20 0.90 system pressure above
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50 2.0 800 psig.
I 90 3.5 l
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Unit 3 i
PBAPS l
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i
3.3.P Cintrcl Rods (Cont'd.)
4.3.B Contra: Reds (Cont'd.)
4.
Control rods shall not be with-4.
Prior to control tod with-d awn for startup or refueling drawal for startap or dur-unless at least two source ing refueling verify that range channels have an observed at least two sources range count rate equal to or greater channels have an observed l
enan three counts per second
- count rate of at least l
thrae counts per second.*
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i 5.
During operation witn limiting 5.
When a limiting control rod l
cor. trol rod patterns as deter-pattern exists, an instru-mined by tne designated quali-ment functional test of the fied personnel, either:
RBM shall be performed prior i
to withdrawal of the desig-nated red (s).
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- a. Both RBM channels shall be t
operable, ur
- b. Control rod withdrawal shall
- May be reduced for startup be block.ed, or only, provided at least l
- c. The cpe'.'ating power level three sourca range channels shall be limited so that have an observed count rate
.the HCPR will remain above and a signal-to-noise ratio the fuel cladding integrity on or above the curve i
safety limit assuming a shown on Figure 3.3.1.
single error that results in complete withdrawal of a single operable control l
rod.
l C.
Scram Irisertion Times C.
Scram Insertion Times l
i' 1.
The average scram insertion time, 1.
After each refueling outage, based on the deenergi:ation of and prior to synchronizing the scram pilot valve solenoids the main turbine generator
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as time :ero, of all operable initially fc11owing restart control rods in the reactor of the plant, all operable i
power operation condition fully withdrawn insequence l
snall be no greater thant rods shall be sciam time i
tested during operational
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s Inserted frca Avg. Scram Inser-hydrostatic tes'.ing or t
rally Withdrawr.
tion Times (sec) during startup frem the fully withdrawn posi-l 5
0.375 tion with the nuclear 20 0.90 system pressure above 50 2.0 800 psig.
90 3.5 i
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4 Tiguro 3.3.1 t
SRM Count Rate Versus
$12..' ' -t o-Nois e Rat to 3.0 t
2.9-2$_
t 2.7
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2.3 2. :.
t b
2.3 1
F 2.2 -
7 2.1 ~'
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3 2.0
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1.9 -
w 0
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- 1. 8 --
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1,7 _
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- 1. 6 --
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1.5 l
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- 1. 3...
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l 1.1 l
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1.0 N
0,9 t
.m
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f 0.8 l
0.7 l
6 10 le 18 22 76 30 t
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Signal-to-Soise Ratio j
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PBAPS 3.,.B anf 4.3.B BASES (Cont'd)
'! n e requirement of at least 3 coun:s per second (may be reduced f or startup p".6 4'sd the count rate and signal-to-noise ratio is snown on Figure 3.3.1) assures that any on or above
- 4 transignc.1 cccur begins at or above the initial value of 10~
of..
er used in analyses of transient cold conditicas.
"able SRM channel would be adequate to meritor th.
to criticality using homogeneous patterns of sca t te r ed <-
.od withdrawal.
A minimum of two operable SRM's are pre
..o as an added conservatism.
- 5. Tne Rod Block Monitor (RBM) is designed to automatically prevent fuel damage in the event of erronecus rod withdrawal 2 rom locations of high power density during high power level Operation.
Two channels are provided, and one of these may be by: assed from the consol? for maintenance and/or testing.
Tripping of one of the channels will block erroneous rod v.tndrawa'. soon enough to prevent fuel damage.
This system backs up the operator who withdraws control rods according to written sequences.
The specified restrictions witn one channel out of service conservatively assure that fuel damage will not occur due to rod withdrawal errors when this condition exists.
A limiting control red patteta is a pattern wnich results in the core being on a thermal hydraulic limit (i.e., operating on a limiting value for APLHGR, LHGR, or MCPR as defined in TechnicaA 3pecifications 3.5.I.,
3.5.J. and 3.5.K.).
During use of such patterns, it is judged that testing of the RBM system prior to withdrawal of such rods to assure its operability will assure that improper withdrawal does not occur.
It is the responsioility of the Re.ctor Engineer to identify these limiting patterns and tne designated rods either when the patterns are initially established or as they develop due to the occurrence of inoperable control rods in other than limiting patterns.
Other personnel ge_lified to perform this function may be designated by the station superintendent.
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CELTIFICATE OF SERVICE I hereby certify that copies of the foregoing Application were served on the following by deposit in the United States Mail, first class postage prepaid, on the 21st day of October,1988.
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i William T. Russell, Regional Administrator t
U.S. Nuclear Regulatory Commission 475 Allendale Road l
King of Prussia, PA 19406 3
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T. P. Johnson, Resident Inspector U.S. Nuclear Regulatory Commission i
Peach Bottom Atomic Power Station P. O. Box 399 i
Delta, PA 17314 Mr. Thomas Gerusky, Director i
Bureau of Radiological Protection Department of Environmental Resources P. O. Box 2063 Harrisburg, PA 17120
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EupneD.Bradley
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Attorney for i
Philadelphia Electric Company i
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