ML20246N125
| ML20246N125 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/28/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246N132 | List: |
| References | |
| 0PR-56-A-149, PR-56-A-149, NUDOCS 8909080043 | |
| Download: ML20246N125 (14) | |
Text
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~ UNITED STATES L
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~i NUCLEAR REGULATORY COMMISSION o
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WASHWGTON D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY 00CKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et
-al. (the licensee) dated December 28, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR rart 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
8909080043 890828 PDR ADOCK 05000277 P
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2-(2)
Technical Specifications' L
The Technical Specifit ations contained in Appendices A and B, as revised through Amendment No. 147, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 44tt28A Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications
- Date of Issuance: August 28, 1989 m._______--_...-m.-- - - - - - _ - _ - - - - - - - - - - - - - - - - -
.4 s
ATTACHMENT TO LICENSE AMENDMENT NO. 147 FACILITY OPERATING LICENSE NO.'DPR-44 DOCKET NO. 50-277.
Replace the following pages of the Appendix'A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 103 103 110 110 228 228 231 231'
--____m_
m y
Unit 2 PBAPS-I LIMITING' CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS 3.3.B. Control Rods (Cont'd.)'
4.3.8 Control Rods (Cont'd.)
4.
Control rods shall not be with-4.
Prior to control rod drawn for startup'or, refueling withdrawal for startup unless.at least two' source or during refueling, range channels have an observed verify that at least count rate equal to or greater two source range than three counts per second.*
channels have an observed.
count rate of at.least three counts per second.*
5.
During operation with limiting 5.
When a' limiting control control. rod. patterns, as deter-
-rod pattern exists, an mined by.the designated quali-instrument functional test fied personnel, either:
of the RBM shall be performed prior to with-drawal'of the designated rod (s).
a.
Both RBM channels shall be operable, or b.
Control rod withdrawal.shall
- May be reduced provided be blocked, or at least three source c.
The operating power level range channels for shall be limited so that startup or at least two the MCPR will remain above source range channels the fuel cladding integrity for refueling have an safety limit assuming a observed count rate and single error that results a signal-to-noise ratio in. complete withdrawal of on or above the curve a single operable control shown on Figure 3.3.1.
rod.
C.'
Scram Insertion Times C.
Scram Insertion Times 1.
The average scram insertion time, 1.
Af ter 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 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-5 0.375 nion with the nuclear 20 0.90 system pressure above 50 2.0 800 psig.
90 3.5 Amendment No.
D, 48, 86, lag.
-103-147
{
4..
PBAPS Unit 2 l
3.3.B_and 4.3.B BASES (Cont'd.)
The requirement of at least 3 counts per second (may be reduced provided the l
count' rate and signal-to-noise ratio is on or above the curve shown on Figure-
- 3.3.1)' assures that any transient, should it occur begins at or above the initial value of 10 8 of rated power used in analyses of transient cold con-ditions.
One operable SRM channel would be adequate to monitor the approach to criticality using homogeneous patterns of scattered control rod withdrawal.
Increasing the required number of operable SRM's is provided as an added conservatism.
5.
.The Rod Block Monitor (RBM) is designed to automatically prevent fuel damage in the event of erroneous rod withdrawal from locations of high power density during high power level operation.
Two channels are pro-vided, and one of these may be bypassed from the console for maintenance and/or testing.
Tripping of one of the' channels will block erroneous rod 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 channel out of service conservatively assure that fuel damage will not occur due to rod withdrawal errors when this condition exists.
A limiting control rod pattern is a pattern which 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 Technical Specifications 3.5.I., 3.5.J and 3.5.K).
During use of such patterns, it is judged tnat 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 responsibility of the Reactor Engineer to identify these limiting patterns and the 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 qualified to perform this function may be designated by the Plant Manager.
l Amendment No. 23, 36, 149,
-110-147
g b~
PBAPS Unit 2 l;.:
" LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l-3.10.B.(Cont'd)'
4.10.B (Cont'd)
L
'a.
The SRM shall be inserted to 2.
Prior to unloading or the normal operating level, reloading of fuel as l
(Use of special movable, dunking provided for in sections
. type detectors during fuel loading 3.10.B.2 & 3.10.B.3, the and major core alterations in place SRM's shall be functionally of normal detectors is permissible tested.
Prior to unload-as long as the detector is connected ing of fuel, the SRM's to the normal SRM circuit.)
should also be checked for neutron response.
b.
The SRM shall have a minimum of l
3 cps
- with all rods fully inserted
- May be reduced provided.
in the core.
the SRM has an observed count rate and signal-to-2.
Prior to unloading of fuel, the SRM's noise ratio on or above shall be proven operable as stated above; the curve shown on Figure however, during unloading of fuel, the 3.3.1.
SRM count rate may drop below 3 cps, provided all control rods are full inserted and rendered electrically inoperable with the except:an of the following provision.
Individual control rods outside the periphery of the then existing fuel matrix may be electrically armed and moved after all fuel in the cell containing that control rod have been removed from the reactor core.
3.
Prior to reloading of fuel, two, three or four fuel assemblies may be returned to their previous core positions adjacent to each of the 4 SRM's to obtain the required 3 cps *.
Until these assemblies are loaded, the SRM minimum count rate is not required.
l4.
The SRM minimum count rate is not required with all fuel removed from the core.
5.
During the unloading and reloading of fuel, intermediate arrays of fuel shall always contain at least one SRM.
Amendment No. 65, 147
-228-
m PBAPS-Unit 2 3.10 BASES (Cont'o)
The requirements for SRM Operability.during these core alterations assure
. sufficient core. monitoring.
B.'
Core Monitoring The'SRM's.are provided to monitor the core during periods.of s'tation L
shutdown and to guide the operator during refueling operations and station'startup.
Requiring two operable SRM's in or adjacent to any core quadrant where fuel-or control rods are being moved assures adequate monitoring of that quadrant during such alterations.
The requirement _of-3 counts per second* provides assurance that neutron flux'is being l
monitored and insures that startup i_s conducted only if the source range flux. level is above the minimum assumed in the control rod drop accident.
During unloading of' fuel, it is permissible to allow the SRM_ count rate to decrease below 3 cps.
Since al_1 fuel moves during core unloading will reduce reactivity, the lower number of counts will not present a hazard.
Requiring the SRM's to be functionally tested prior to fuel removal assures that the SRM's will be operable at the start of f'uel removal.
The daily response check of.the SRM's ensures their continued operability until the count rate diminishes due to fuel removal.
Control rods in cells from which all fuel has been removed and which are outside the periphery of the then existing fuel matrix may be armed electrically and moved for maintenance purposes during fuel removal, provided all_ rods that control fuel are fully inserted and electrically disarmed.
During core. loading, the loading of adjacent assemblies around the four SRM's before attaining the minimum count rate of 3 cps
- is permissible l
because these assemblies were-in a subcritical configuration when they were removed and therefore will remain subcritical when the same assemblies are placed back into their previous positions.
Since specification 3.'10.A.2 requires that all control rods be fully inserted prior to' loading fuel, inadvertent' criticality is precluded during core loading.
C.
Spent Fuel Pool Water Level The intent of the Technical Specification is to provide, adequate water coverage for cooling and shielding at all times.
With the water at elevation 233' (its normal operating level at the top of the pool weir),
approximately 23 ft. of water is maintained above fuel stored in the spent fuel storage racks.
They physical arrangement of the spent fuel pool overflow to the skimmer surge tanks may be adjusted such that the minimum operating water level provides 22 ft. of water coverage over irradiated fuel in the storage racks.
For this reason, the specification for minimum water coverage has been established at 22 ft.
This level provides adequate
- May be reduced provided the count rate and signal-to-noise ratio are on or above the curve shown on Figure 3.3.1.
Amendment No. 65, 129, 147
-231-
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- UNITED STATES 1
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- I NUCLEAR REGULATORY COMMISSION -
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PHILADELPHIA' ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT-COMPANY ATLANTIC CITY ELECTRIC-COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 149 License No. DPR-44 q
1.
The Nuclear Regulatory Commission (the Comission) has found that:
'A..
The application for amendment by Philadelphia Electric Company, et al. (the 'ticensee) dated December 28, 1988, complies with the standards-and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the.
provisions of the Act, and the rules and regulations of.the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be. conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
- i K
(2)
Technical Specifications The Technical Specifications corhined in Appendices A and B, as revised through Amendment No. 149, are hereby incorporated in the~
license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-
[f ie v
/g Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: August 28, 1989 l
1
F
.l *..
4
' ATTACHMENT TO LICENSE AMENDMENT NO. 149 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specificat' ions with the enclosed.pages. The revised areas are indicated by marginal lines.
Remove Insert 103 103 110 110 228 228 231 231 i
e l
l.
L___-----------_.-------
Unit 3-PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.B. Control Rods (Cont'd.)
4.3.B ' Control Rods (Cont'd.)
n L
4.'
Control rods shall not be with-4.
Prior to control rod drawn for'startup or refueling withdrawal for startup unless at least two source or during refueling, range channels have an observed
-verify that at least count rate equal to or greater two source range than three counts per second.*
channels have an observ'ed count rate of at least three counts per second.*
5.
During operation with limiting 5.
When a limiting' control control rod patterns, as deter-rod pattern exists, an mined by the designated quali-instrument functional test fied personnel, either:
of the RBM shall be performed prior to with-drawal of the designated rod (s).
a.
Both RBM channels shall be operable, or b.
Control rod withdrawal.shall
- May be reduced provided be blocked, or at least three source c.
The operating power level range channels for shall be limited so that startup or at least two
. the MCPR will remain e'oove source range channels the fuel cladding-int.grity for refueling have an safety limit assuming a observed count rate and single error that results a' signal-to-noise ratio in complete withdrawal of on or above the curve a single operable control shown on Figure 3.3.1.
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 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 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-5 0.375 tion with the nuclear 20 0.90 system pressure above 1
50 2.0 800 psig.
90 3.5 Amendment No. 14, 41, 79, 142,
-103-149 1
7 1
I PBAPS Unit 3 3.3.B and 4.3.8 BASES (Cont'd.)
The requirement of at least 3 counts per second (may be reduced provided the l
count rate and signal-to-noise ratio is on or above the curve shown on Figure 3.3.1) assures that any transient, should it occur begins at or above the initial value of 10 8 of rated power used in analyses of transient cold con-ditions.
One operable SRM channel would be adequate to monitor the approach to criticality.using homogeneous patterns of scattered control rod withdrawal.
Increasing tne required. number of operable SRM's is provided as an added conservatism.
5.
The Rod Block Monitor (RBM) is designed to automatically prevent fuel damage in~ the event of erroneous rod withdrawal from locations of high
~
power density during high power level operation.
Two channels are pro-vided, and one of these may be bypassed from the console for maintenance and/or testing.
Tripping of one of the channels will block erroneous rod 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 channel out of service conservatively assure that fuel damage will not occur due to rod withdrawal errors when this condition exists.
A limiting control rod pattern is a pattern which 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 Technical Specifications 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 responsibility of the Reactor Engineer to identify these limiting patterns and the 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
- qualific : to perform this function may be designated by the Plant Manager.
l Amendment No. 33, 142, 149
-110-
PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS -3.10.B (Cont'd) 4.10.B (Cont'd) a.
The SRM shall be inserted to~
2.
Prior to unloading or the normal operating level.
reloading of fuel as (Use of special movable, dunking provided for in sections ty'pe detectors during fuel loading 3.10.B.2 & 3.10.B.3 the and major core alterations in place SRM's shall be functionally of normal detectors is permissible tested.
Prior to unload-as long as the detector is connected ing of fuel, the SRM's to the normal SRM circuit.)
should also be checked for neutron response.
b.-
'The SRM shall have a minimum of l
3 cps
- with all rods fully inserted
- May be reduced provided in the core.
the SRM has an observed count rate and signal-to-2.
Prior to unloading of fuel, the SRM's noise ratio on or above shall be proven operable as stated above; the curve shown on Figure however, during unloading of fuel, the 3.3.1.
SRM count rate may drop below 3 cps, provided all control rods are full inserted and rendered electrically inoperable with the exception of the following provision.
Individual control rods outside the periphery of the then existing fuel matrix may be electrically armed and moved after all fuel in the cell containing that control rod have been removed from the reactor core.
3.
Prior to reloading of fuel, two, three or four fuel assemblies may be returned to their previous core positions adjacent to each of the 4 SRM's to obtain the required 3 cps *.
Until these assemblies are loaded, the SRM minimum count rate is not required.
l4.
The'SRM minimum count rate is not required with all fuel removed from the core.
5.
During the unloading and reloading of fuel, intermediate arrays of fuel shall always contain at least one SRM.
Amendment No. 64, 149
-226-
i-h PBAPS Unit 3
~
3;10 BASES (Cont'd)
The requirements for SRM Operability during these core alterations assure sufficient core monitoring.
B.
Core Monitorina The SRM's are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and L
station'startup.
Requiring two operable SRM's in or adjacent to any core quadrant where fuel or control rods are being moved assures adequate monitoring of that quadrant during such alterations. The requirement of
. 3 coun;s per second* provides assurance that neutron flux is being
\\
monitored and. insures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
During unloading of fuel, it is permissible to allow the SRM count rate to decrease below 3 cps.
Since all fuel moves during core unloading will reduce reactivity, the lower number of counts will not present a hazard.
Requiring the SRM's to be functionally tested prior to fuel removal assures that the SRM's will be operable at the start of fuel removal.
The daily. response check of the SRM's ensures their continued operability until the count rate diminishes due to fuel removal.
Control rods in cells from which all fuel has been removed and which are outside the periphery of the then existing fuel matrix may be armed electrically and moved for maintenance purposes during fuel removal, provided all rods that control fuel are fully inserted and electrically disarmed.
During core loading, the loading of adjacent assemblies around the four SRM's before attaining the minimum count rate of 3 cps
- is permissible l
because these assemblies were in a subtritical configuration when they were removed and therefore will remain subcritical when the same assemblies are placed back into their previous positions.
Since specification 3.10.A.2 requires that all control rods be fully inserted prior to loading fuel, inadvertent criticality is precluded during core loading.
C.
Spent Fuel Pool Water Level The intent of the Technical Specification is to provide, adequate water coverage for cooling and shielding at all times.
With the water at elevation 233' (its normal operating level at the top of the pool weir),
approximately 23 ft. of water is maintained above fuel stored in the spent fuel storage racks.
They physical arrangement of the spent fuel pool overflow to the skimmer surge tanks may be adjusted such that the minimum operating water level provides 22 ft. of water coverage over irradiated fuel in the storage racks.
For this reason, the specification for minimum water coverage has been established at 22 ft.
This level provides adequate
- May be reduced provided the count rate and signal-to-noise ratio are on or above the curve shown on Figure 3.3.1.
Amendment No. 64, 124, 149
-231-
_ - _ _ _ _ - _ - - _