ML20205L194
| ML20205L194 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/26/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20205L197 | List: |
| References | |
| DPR-19-A-101, DPR-25-A-097 NUDOCS 8811010508 | |
| Download: ML20205L194 (18) | |
Text
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'o UNITED STATES l
g NUCLEAR REGULATORY COMMISSION o
8 fr WASHINGTON, D. C. 20656
- %.....}
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 ORESDEN NUCLEAR POWER STATION. UNIT N0. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.101 License No. DPR-19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (thelicensee)datedAugust 31, 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 confonnity with the application, the provisions of the Act and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amenoment can be conducted without endangering the health and safety of the public, and (11) 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 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.
M ccrdingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Provisional Operating License No. OPR-19 is hereby amended to read as follows:
8811010500 081026 PDR ADOCK 05000237 P
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8.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within C0 days.
FOR THE NUCLEAR REGULATORY COMMISSION
?
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: October 26, 1988 r
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ATTACHMENT TO LICENSE AMENDMENT NO. 101 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 50-237 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.5-1 3/4.5-1 3/4.5-4 3/4.5-4 3/4.5-5 3/4.5-5 3/4.5-12 3/4.5-12 3/4.5-12a 3/4.5-13 3/4.5-13 I
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DRESDEN II DPR-19 Amendment No. 82, 101 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT CORE AND CONTAINMENT COOLING CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Applicability:
Applicability:
Applies to the operational Applies to periodic testing status of the emergency of the emergency cooling cooling subsystems.
subsystems.
Objective:
Objective:
To assure adequate cooling To verify the operability of capability for heat removal the emergency cooling in the event of a loss of subsystems.
coolant accident or isolation from the normal reactor heat sink.
Specification:
Specification:
A.
Core Spray and LPCI Subsystems A.
Surveillance of the Core Spray and LPCI Subsystems shall be performed as follows:
1.
Except as specified 1.
Core Spray in 3.5.A.2, 3.5.A.3, and Subsystem l
3.5.F.3 through 3.5.F.6 Testing:
below, both core spray subsystems shall be operable whenever Item Frequency irradiated fuel is in the reactor vessel.
- a. Simulated Each Automatic Refueling Actuation Outage Test
- b. Flow Rate After pump Test Core maintenance spray pumps and every 3 shall months deliver at least 4500 gpm against a system head cor-responding 3687a 3123A
DRESDEN II DPR-19 Amendment No. 14, 82, 98, 101 3.5 LIMITING CONDITION FOR OPExATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
for any reason, reactor the containment cooling operation is permissible subsystem, shall only during the suc-be demonstrated to ceeding seven days un-be operable immediately less it is sooner made and daily thereafter.
operable, provided that during such seven days all active com ponents of both core spray subsystems, the containment cooling subsystem (including 2 LPCI pumps) and the diesel generators required for operation of such components if no external source of power were available shall be operable.
6.
Containment cooling 6.
During each five year spray loops are required period an air test to be operable when shall be performed on the reactor water the drywell spray temperature is greater headers and nozzles, than 212'F except that a maximum of one dry-well spray loop may be inoperable for thirty days when the reactor water temperature is greater than 212'F.
7.
If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initi-ated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Sub-sequently, the reactor may be placed in Refuel in accordance with 3.5.F.3 through 3.5.F.6.
~
3/4.5 4 3687a 3123A
DRESDEN II DPR-19 Amendment No. 34, 82, 101 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
-(Cont'd.)
B.
Containment Cooling Subsystem B.. Surveillance of the Containment Cooling Subsystem shall be performed as follows:
1.
Except as specified in 1.
Containment Cooling 3.5.B.2, 3.5 B.3, and Service Water Subsystem l
3.5.F.3 through 3.5.F.6 1e.*:f ng:
below, both containment cooling subsysteo ? oops Item Frequency shall be operable whenever irradisted fuel is in
- a. Pump &
Once/3 l
the reactor vessel and Valve months l
reactor coolant Operability temperature is greater than 212'F.
l
- b. Flow Rate After pump Test. Each maintenance containment and every cooling 3 months water pump shall deliver at least 3500 gpm against a pressure
(
of 180 psig.
1 l
2.
From and after the 2.
When it is determined date that one of the that one containment containment cooling cooling service water service water subsystem pump is inoperable, the pumps is made or found remaining components of to be inoperable for that subsystem and the any reason, reactor other containment operation is permissible cooling subsystem shall only during the be demonstrated to be succeeding thirty days operable immediately unless such pump is and daily thereafter, sooner made operable, provided that during such thirty dr/s all other active components, of the containment cooling subsystem are operable.
3/4.5-5 3687a 3123A
ki DRESDEN II DPR-19 Amendment No. 20, 58, 82, 101 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
3.
When irradiated fuel is in the reactor vessel and the reactor is in cold shutdown or refuel condi-tions, at least two of the following pumps, with each having an operable flow path capable of taking suc-tion from the suppression pool or the condensate stor-age tank and transferring the water to the reactor vessel, shall be operable except as specified in 3.$.F.4, 3.5 F.5 and 3.5.F.6 below:
a.
Two Core Spray pumps or, b.
Two Low Pressure Coolant Injection pumps or, c.
One Core Spray pump and one Low Pressure Coolant Injection pump.
4.
With one of the pumps and/or associated flow paths required by 3.5.F.3 inoperable, restore at least two pumps and asso-ciated flow paths to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations with a potential for draining the reactor vessel.
5.
With both of the pumps and/or associated flow paths required by 3.5.F.3 inoperable, suspend core alterations and all opera-tions with a potential for draining the reactor vessel.
Restore at least one pump and associated flow path to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or estab-lish secondary containment integ-rity within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3/4.5-12 3687a 3123A
DRESDEN II DPR-19 Amendment No. 101 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd )
(Cont'd.)
6.
When irradiated fuel is in the reactor vessel and the reactor is in the cold shut-down or refuel condition, all low pressure core and containment cooling subsystems may be inoperable provided the reactor vessel head is removed, the cavity is flooded, the spent fuel pool gates are removed, the fuel pool water level is maintained above the low alarm point, and the reac-tor cavity water temperature e
is below 140*F.
l 7.
When irradiated fuel is in the reactor vessel and th-reactor is in the refuel condition, the torus may be drained completely and con-trol rod drive maintenance performed provided that the spent fuel pool gates are open, the fuel pool water level is maintained above the low level alarm point, and the minimum total con-densate storage reserve is maintained at 230,000 gallons, and provided that not more than one control rod drive housing is open at one time, the control rod drive hous-ing is blanked following removal of the control rod drive, no work is being performed in the reactor vessel while the housing is open and a special flange 3/4.5-12a 3687a 3123A
1 DRESDEN II DPR-19 Amendment No. 20, 58, 92, 101 3.5 LIMITING CONDITIO:I FOR OPERATION 4.5 SURVEILLANCE REOUIREMENT (Cont'd.)
(Cont'd.)
is available which can be used to blank an open housing in the event of a leak.
l 8.
When irradiated fuel is in the reactor and the vessel head is removed, work that has the potential for drain-ing the ve=sel may be performedgithlessthan 112,000 ft of water in the suppression pool, provided that:
(1) the total volume 1
of water in the suppression pool, dryer separator above the shield blocks, refueling cavity, and the fuel storage pool above the bottom of the fuel pool gate (s greater than 112,000 ft"; (2) the fuel storage peol gate is removed; (3) the low pressure coolant injection and core spray systems are operable as specified in 3.5.F.3, 3.5.F.4 an.d 3.5.F.5; and (4) the automatic mode of the dryvell sump pumps is d'.sabled.
J '
H.
Maintenance of Filled H.
Maintenance of Filled i
Discharge Pipe Discharge Pipe Whenever core spray, The following LPCI, or HPCI ECCS are surveillance requirements required to be operabla, shall be adhered to, to the discharge piping assure that the discharge from the pump discharge piping of the core spray, i
a 3/4.5-13 3687a 3123A
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
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WASHINGTON. D. C. 20666
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COMMONWEALTH EDIS0N COMPANY t
DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 97 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonweslth Edison Company (the licensee) dated August 31, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 6nd the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act and the rules and regulations of the Comission;
' 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 complionce with the Comission's regulations; D.
The issuance of this amendrrent will not be inimical to the comon cefense 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 l
of the Comission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby I
amended to read as follows:
. B.
Technical Specificatioig The Technical Specifications cuntained in Appendix A, as revised through Amendment No. 97, are hereby incorporated in the license. The licensca shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: October 26, 1988
ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.5-1 3/4.5-1 3/4.5-4 3/4.5-4 3/4.5-5 3/4.5-5 3/4.5-12 3/4.5-12 3/4.5-12a 3/4.5-13 3/4.5-13
ORESDEN III DPR-25 Amendment No. 75, 97
(
3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT CORE AND CONTAINMENT COOLING CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Applicability:
Applicability:
Applies to the operational Applies to periodic testing status of the emergency of the emergency cooling cooling subsystems, subsystems.
Objective:
Objective:
To assure adequate cooling To verify the operability of capability for heat removal the emergency cooling in the event of a loss of subsystems.
coolant accident or isolation from the normal reactor heat sink.
Specification:
Specification:
A.
Core Spray and LPCI Subsystems A.
Surveillance of the Core Spray and LPCI Subsystems shall be performed as follows:
1.
Except as specified 1.
Core Spray in 3.5.A.2, 3.5.A.3, and Subsystem I
3.5.F.3 through 3.5.F.6 Testing:
below, both core spray subsystems shall be oper-able whenever irradiated Item Frequency fuel is in the reactor vessel.
i a.
Simulated Each Automatic Refueling Actuation Outage Test b.
Flow Rate After pump Test Core maint.riance spray pumps and every 3 shall months deliver at
' east 4500 gpo against a system head cor-responding l
3/4. 5-1
DRESDEN III DPR-25 Amendment No. 4, 75, 90, 97 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont' d. )
for any reason, reactor the containment cooling operation is subsystem, shall permissible only be demonstrated to during the succeeding be operable immediately seven days unless it and daily thereafter.
is sooner made operable, provided that during such seven days all active components of both core spray subsystems, the containment cooling subsystem (including 2 LPCI pumps) and the diesel generators required for operation of such components if no external source of power were available shall be operable.
6.
Containment cooling 6.
During each five year spray loops are period an air test required to be shall be performed on operable when the the drywell spray reactor water headers and nozzles.
temperature is greater than 212 F except that a maximum of one drywell spray loop may be inoperable for thirty days when the reactor water temperature is greater than 212'F.
7.
If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Sub-sequently, the reactor may be placed in Refuel in ac:ordance with 3.5.F.3 through 3.5.F.6.
3/4.5-4
f ORESDEN III DPR-25 Amendment No. 23, 75, 97 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
B.
Containment Cooling Subsystem B.
Surveillance of the Containment Cooling Subsystem shall be performed as follows:
1.
Except as specified in 1.
Containment Cooling 3.5.B.2, 3.5.B.3, and Service Water Subsystem l
3.5.F.3 through 3.5.F.6 Testing:
below, both containment cooling subsystem loops Item Frequency shall be operable when-ever irradiated fuel is a.
Pump &
Once/3 in the reactor vessel Valve months and reactor coolant Operability temperature is greater than 212 F.
b.
Flow Rate After pump Test.
Each maintenance containment and every cooling 3 months water pump shall deliver at least 3500 gpm against a pressure of 180 psig.
2.
From and after the 2.
When it is determined date that one of the that one containment containment cooling cooling service water service water subsystem pump is inoperable, the pumps is made or found remaining components of to be inoperable for that subsystem and the any reason reactor other containment operationIspermissible cooling subsystem shall only during the be demonstrated to be succeeding thirty days operable immediately unless such pump is and daily thereafter, sooner made operable, provided that during such thirty days all other active components of the containment cooling subsystem are operable.
3/4.5-5
r ORESDEN III DPR-25 Amendment No. 18, 28, 75, 97 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
3.
When irradicted fuel is in the reactor vessel and the reactor is in cold shutdown or refuel condi-tions, at least two of the following pumps, with each having an operable flow path capable of taking suction from the suppres-sion p,ool or the condensate storage tank and trans-ferring the water to the reactor vessel, shall be operable except as speci-fied in 3.5.F.4, 3.5.F.5 and 3.5.F.6 below:
a.
Two Core Spray pumps or, b.
Two Law Pressure Coolant Injection pumps or, c.
One Core Spray pump and one Low Pressure Coolant Injectionpump.
4.
With one of the pumps and/or associated flow paths required by 3.5.F.3 inoperable, restore at least two pumps and associ-ated flow paths to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations with a potential for draining the reactor vessel.
5.
With both of the pumps and/or associated flow paths required by 3.5.F.3 inoperable, suspend core alterations and all operations with potential for draining the reactor vessel.
Restore at least one pump and associated flow path to oper-able status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish secondary contain-ment integrity within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3/4.5-12
DRESDEN III DPR-25 Amendment No. 97 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
6.
When irradiated fuel is in the reactor vessel and the reactor is in the cold shut-down or refuel condition, all low pressure core and containment cooling sub-systems may be inoperable provided the reactor vessel head is removed, the cavity is flooded, the spent fuel pool gates are removed,
+
the fuel pool water level is maintained above the low level alarm point, and the reactor cavity water temperature is below 140 F.
l 7.
When irradiated fuel is in the reactor vessel and the reactor is in the refuel condition, the torus may be drained completely and control rod drive maintenance performed provided that the spent fuel pool gates are open, the fuel pool water level is maintained above the low level alarm point, and the minimum total condensate storage reserve is maintained at 230,000 gallons, and provided that not more than one control rod drive housing is open at one time, the control rod drive housing is blanked following removal of the control rod drive, no work is being performed in the reactor vessel while the housing is open and a special flange is 3/4.5-12a
-r
DRESDEN III DPR-25
^>
Amendment No. 18, 75, 97 3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
available'which can be used to blank an open housing in the event of a leak.
l 8.
When irradiated fuel is in the reactor and the vessel head is removed, work that has the potential for draining the vessel may be performedwith}ess than 112,000 ft of water in the suppression pool, provided that:
- 1) the total volume of water in the suppression pool, dryer separator above the shield blocks, refueling cavity, and the fuel storage pool above the bottom of the fuel pool gateisgrgaterthan 112,000 ft ; 2) the fuel storage pool gate is removed; 3) the low pressure coolant injection and core spray systems are operable as spect-fled in 3.5.F.3, 3.5.F.4 and 3.5.F.5; and 4) the automatic mode of the drywell sump pumps is dis-abled.
H.
Maintenance of Filled H.
Maintenance of Filled Discharge Pipe Discharge Pipe Whenever core spray, The following LPCI, or HPCI ECCS are surveillance requirements required to be operable, shall be adhered to, to the discharge piping assure that the discharge from the pump discharge piping of the core spray, 3/4.5-13