ML20154C068
| ML20154C068 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/07/1988 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20154C040 | List: |
| References | |
| NUDOCS 8809140229 | |
| Download: ML20154C068 (4) | |
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PBAPS 3
3.3.B and 4.3.8 6ASES (Cont'd)
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..he requirement of at least 3 counts per second (may be reduced j
to 0.7 cps for startup on three source range channels provided 1
the signal-to-noise ratio is greater than 2) assures that any 4
transi of10-gnt, should it occur begina at or above the initial value
% of rated power in analys:s of transient cold j
conditions.
One operable SRM channel would be adequate to monitor the approach to criticaAlty using homogeneous patterns of t
scattered control rod withdrawal.
A minimum of two operable l
SRM's are provided as an added conservatism.
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5.
The Rod Block Monitor (RBM) is designed to automatically l
prevent fuel damage in the event of erroneous rod withdrawal from locations of high power dersity during high power level i
operation.
Two channels are provided, and one of these may be bypassed from the console for maintenance and/or testing.
Tripping of one of the channels will block errcneous rod
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withdrawal soon enough to prevent fuel damage.
This system backs up the operator who withdraws control rods according to written sequences.
The specified restrictions with one l
channel out of service conservatively assure that fuel i
i damage will not occur due to rod withdrawal errors wher. this condition exists.
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A limiting control rod pattern is a pattern which results in the c
core being on a thermal hydraulic limit (i.e., operating on a limiting value for APLHGR, LEGR, or MCPR as defined in Technical Specifications 3.5.I., 0.5.J. and 3.5.K.).
During use of such patterns, it is judged that testing of the RBM system prior to l
withdrawal of such rods to assure its operability will assure f
that improper withdrav '. dces not occur.
It is the l
responsibility of the.eactor Engineer to identify these limiting 1
patterns and the designated rods either when the patterns are
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initially established or as they develop due to the occurrence of inoperaule control rods in other than limiting patterns.
Other personnel qualified to perform this function may be designated by a
j the station superintendent.
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-110-j 0809140229 eso9oy DR ADOCK 05000277 PUC
Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.B Control Rods (Cont'd.)
4.3.B Control Rods (Cont'd.)
4.
Control rods shall not be with-4.
Prior to control rod with-drawn far startup or refueling drawal for startup or dur-unless et least two source ing refueling verify that range channelc nave an obrerved at least two sources range count rate equal to or greater channels have an observed than three counts per second.*
count rate of at lease three counts per second.*
5.
During operation with limiting 5.
When a limiting control rod control rod patterns as deter-pattern exists, an instru-mined by the designated quali-ment functional test of the fled personnel, either:
RBM shall be performed prior to withdrawal of the desig-nated rod (s).
- b. Control rod withdrawal shall
- May be reduced for startup be blocked, or only, provided at least
- c. The operating power level three tource range channels sha): be limited so that have an observed count rate the MCPR will remain above greater than or equal to 0.7 cps the fuel cladding integrity and a signal-to-noise ratic safety limit assuming a greater than or equal to 2.
single error that results in complete withdrawal of a single operable control rod.
C.
Scram Insertion Times C.
Scram Insertion Times 1.
The average scram insertion time, 1.
After each refueling outage, based on the deenergization of and prior to svnchronizing the scram pilot valve solenoids the main turbii.a generator as time zero, of all operable initially following restart control rc'-
in the reactor cf tre plant, all operable power operacion condition fully withdrawn insequence shal' be no greater than:
rods shall be scram time tested during operational
% Inserted from Avg. Scram Inser-hydrostatic testing or Fully Withdrawn tion Times (sec) during startup from the fully withdrawn posi-0.375 tion with the nuclear 20 0.90 system pressure above 50 2.0 800 psig.
90 3.5
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Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.B Control Rods (Cont'd.)
4.3.B Control Rods (Cont'd.)
4.
Control rods shall not be with-4.
Prior to control rod with-drawn for startup or refueling drawal for startup or dur-unless at least two source ing refueling verify that range channelt have an observed at least two sources range count rate equal to or greater channels have an observed than ;hree counts per second.*
count rate of at least three counts per second.*
i 5.
During operation with limiting 5.
When a limiting control rod control rod patterns as deter-pattern exists, an instru-mined by the designated quali-ment functional test of the fled personnel, either:
RBM shall be performed prior to withdrawal of the desig-nated rod (s),
- b. Control rod withdrawal shall
- May be reduced for startup be blocked, or only, provided at least
- c. The operating power level three source range channels shall be limited so that have an observed count rate the MCPR will remain above greater than or equal to 0.7 cps the fuel cladding integrity and a signal-to-noise ratio safety limit assuming a greater than or equal to 2.
single error that results in complete withdrawal of a single operable control rod.
C.
Geram Insertion Times C.
Scram Insertion Times 1.
The average scram insertion timu, After each refueling outage, based on the deenergization of and prior to synchronizing the scram pilot valve solenoids the main turbine generator as time zero, of all operable initially following restart control rods in the reactor of the plant, all operable power operation condition fully withdrawn insequence shall be no greater thans rods shall be scram time tested during operational
% Inserted from Avg. Scram Inser-hydrostatic testing or Fully Withdrawn tion Times (sec) during etartup from the fully withdrawn posi-5 0.375 tion witt the nuclear 20 0.90 system pressure above 50 2.0 800 psig.
90 3.5
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CERTIFICATE OF SERVICE i
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 7th day of September, 1988 i
William T. Russell, Regional Administrator U.S. Nuclear Regulatory Conmission 175 Allendale Road King of Prussia, PA 19406 T. P. Johnsen, Resident Inspector U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station l
P. O. Box 399 Delta, PA 17314 Mr. Thomas Gerusky, Directcr Bureau of Radiological Protection Department of Environmental Resources P. O. Box 2063 liarrisburg, PA 17120 L
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[v3 Euge
- 4. Bradley I
Attorney for i
Philadelphia Electric Company j
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