ML20206L958
| ML20206L958 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/11/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20206L962 | List: |
| References | |
| DPR-44-A-120, DPR-56-A-124 NUDOCS 8608200418 | |
| Download: ML20206L958 (12) | |
Text
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A 0'IG yL UqA UNITED STATES v
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i NUCLEAR REGULATORY COMMISSION j
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WASHINGTON. D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AhD LIGHT COMPANY ATLAhTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. DFR-44 1.
The huclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 14, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Coanission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cormission'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 1.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
8608200418 e60811 PDR ADOCK 0500 7
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Technical Specifications The, Technical Specifications contained in Appendices A and B, as revised through Amendment No.120, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days.
/FRTHENUCLEARREGULATORYCOMM i
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Daniel R. Muller, Director BWR Project Directorate.#2 Division of BWR Licensing
Attachment:
l Changes to the Technical Specifications Date of Issuance: August 11, 1986 e
3 4
.I
ATTACHMENT TO LICENSE AMENDMENT N0.120 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 228a 228a l
231 231 232 232 4
4 l
O i
I l
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.C Spent Fuel S torage 4.10.C Spent Fuel Storage Pool Water Level Pool Water Level 1.
At least 22 feet of water Whenever irradiated fuel is shall be. maintained over the stored in the spent fuel pool, top of the irradiated fuel the water level shall be seated in the spent fuel recorded daily.
storage pool racks.
2.
If specification 3.10.C.1 cannot be satisfied, suspend all movement of fuel assemblies I
and crane operations with loads i
in the spent fuel storage pool area after placing the fuel assemblies and crane load in a safe condition.
D.
Heavy Loads Over Spent Fuel Loads in excess of 1000 lbs. (excluding the rigging and transport vehicle) 4 shall be prohibited from travel over fuel assemblies in the spent
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fuel storage pool.
L i
-228a-1 Amendment N'o. 85, 120
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3.10 BASES (Con t' d)
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 l
station 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 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 i
during core unloading will reduce reactivity, the lower number of counts will not present a hazard.
Requiring the i
SRM's to be functionally tested prior to fuel removal assures i
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 dominishes due to fuel removal.
Control rods in cells from which all fuel has been removed and which are outside the periphery of the then l
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 3 cps is permissible because these assemblies were in a suberitical configuration when they were removed and therefore will
)
4 i
remain suberitical when the same assemblies are placed back
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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.
lh i
j C.
Spent Fuel Pool Water Level l
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 l
fuel storage racks.
The physical arrangement of the spent l
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 kiendment No. $5, 120
-231-l
f.
water coverage for both shielding and cooling at all times, including during fuel movement.
The minimum water coverage measurement is the distance between the top of the fuel rod plenum and the spent fuel pool water level at its lowest adjusted level.
With the water maintained at the minimum level, there is sufficient water depth to ensure that any iodine released from a hypothesized fuel handling accident would be reduced to acceptable levels before it reached the refueling floor.
There are no piping connections to the spent fuel pool at any lower elevation.
4.10 BASES i
A.
Refueling Interlocks l
Complete functional testing of all refueling interlocks before any refueling outage will provide positive indication i
that the interlocks operate in the situations for which they were designed.
By' loading each hoist with a weight equal to the fuel assembly, positioning the refueling platform and withdrawing control rods, the interlocks can be subjected to valid operational tests.
Where redundancy is provided in the logic circuitry, tests can be performed to assure that each redundant logic element can independently perform its function.
1' B.
Core Monitorinq Requiring the SRM's to be functionally tested prior to any core, alteration assures that the SRM's will be operable at the start of that alteration.
The daily response check of the SRM's ensures their continued operability.
4 i
i I
-232-Amendment No. H, 120
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UNITED STATES l
E NUCLEAR REGULATORY COMMISSION p,
5 Aj WASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GA5 COMPANY i
DELMARVA POWER AND LIGHT COMPANY ATLAhTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BCTTOM /TOMIC POWER STATION, UNIT N0. 3 AMEh0 MENT TO FACILITY OPERATING LICENSE Amendment No. 124 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 14, 1986, 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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted withc.ut 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 common defense and security or to the health and 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:
4 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days.
I FOR THE NUCLEAR REGULATORY COM I ION
't jf f
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 11, 1986
.i l
ATTACHMENT TO LICENSE AMENDMENT N0. 124 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET N0. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of ci.ange.
Remove Insert 228a 228a 231 231 232 232 O
l 9
P2APS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.10.C Spent Fuel S torage 4.10.C Spent Fuel Storage Pool Water Level Pool Water Level 1.
At least 22 feet of water Whenever irradiated fuel is shall be maintained over the stofed in the spent fuel pool, top of the irradiated fuel thefwater level shall be seated in the spent fuel reclbrded daily.
storage pool racks.
2.
If specification 3.10.C.1 cannot be satisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel storage pool area after placing the fuel i
assemblies and crane load in a safe condition.
D.
Heavy Loads Over Spent Fu 1 Loads in excess of 1000 lbs. (excluding the rigging and transport vehicle) shall be prohibited from travel over fuel assemblies in the spent i
fuel storage pool.
i
-228a-klendment No. SA,124
PBAPS '
L f
3.10 BASES (Cont' d)
U t
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 station shutdown and to guide the operator during refueling operations and station startup.
Requiring two operable SRM's 4
in or adjacent to any core quadrant where fuel or control i
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 1
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 deminishes 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 3 cps is permissible because these assemblies were in a suberitical configuration when they were removed and therefore will remain suberitical when the scme assemblies are placed back into their previous positions.
Since specification 3.10.A.2 requires that all control rods be fully inserted prior to i
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.
The 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 f t.
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 Amendment Nm E3, h4
-231?
- -- 1
water coverage for both shielding and cooling at all times, including during fuel movement.
The minimum water coverage measurement is the distance between the top of the fuel rod plenum and the spent fuel pool water level at its lowest adjusted level.
With the water maintained at the minimum level, there is sufficient water depth to ensure that any iodine released from a hypothesized fuel handling accident would be reduced to acceptable levels before it reached the refueling floor.
There are no piping connections to the spent fuel pool at any lower elevation.
4.10 BASES A.
Refueling Interlocks Complete functional testing of all refueling interlocks before any refueling outage will provide positive indication that the interlocks operate in the situations for which they were designed.
By loading each hoist with a weight equal to the fuel assembly, positioning the refueling platform and i
withdrawing control rods, the interlocks can be subjected to valid operational tests.
Where redundancy is provided in the logic circuitry, tests can be performed to assure that each redundant logic element can independently perform its function.
B.
Core Monitoring Requiring the SRM's to be functionally tested prior to any core, alteration assures that the SRM's will be operable at the start of that alteration.
The daily response check of the SRM's ensures their continued operability.
-232-Miendment No. $J, 124
-