ML17158B756
| ML17158B756 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/13/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17158B757 | List: |
| References | |
| NPF-14-A-159, NPF-22-A-130 NUDOCS 9608230180 | |
| Download: ML17158B756 (18) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. i>9 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
B.
C.
D.
E.
The application for the amendment filed by the Pennsylvania Power Light Company, dated February 29, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; 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 Commission's regulations set forth in 10 CFR Chapter I; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9608230i80 9608i3 PDR ADQCK 05000387 P
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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technic 1
S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
159 and the Environmental Protection, Plan contained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1996 J
F. Stolz, Direct r ject Directorate
>vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
TTACHHENT TO ICENSE AMENDMENT NO. 1 FACI ITY OPERATING LICENSE NO.
NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOV 1X xv 3/4 9-8 3/4 9-9 B 3/4 9-2 INSERT 1X XV 3/4 9-8 3/4 9-9 B 3/4 9-2
~
~
LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8.1 A.C. SOURCES A.C. Sources-Operating.
A.C. Sources-Shutdown.
3/4 8-1 3/4 8-9 3/4.8.2 D.C. SOURCES D.C. Sources-Operating.........,.....
~ ~ ~.. ~ ~~...........'.....
3/4 8-10 D.C. Sources-Shutdown.
.......3/4 8-15 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Distribution - Operating....,....,..........~..........
3/4 8-17 Distribution - Shutdown...............,...~...................,...3/4 8-19 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary Containment Penetration Conductor Overcurrent Protective Devices.
~..3/4 8-22
'otor-Sperated Valves Thermal Overload Protection................3/4 8-28 Reactor Protection System Electric Power Monltorlngo
~ ~ ~ ~ ~ ~ ~ ~
~
~
~
~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~I3/4 8 33 3/4.9.1 REACTOR MODE SWITCH.......
.3/4 9-1 3/4.9.2 INSTRUMENTATION.
~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ a3/4 9 3 3/4.9.3 CONTROL ROD POSITION..~.....
~ ~ ~.....
~ ~ ~ ~ ~. ~ ~ ~ ~ ~
3/4.9.4 DECAY TIME.. ~.~....
.3/4 9-5
.3/4 9-6 3/4.9.5 COMMUNICATIONS.~. ~..,
~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e3/4 9 7 3/4.9.6 DELETED 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL..
~. ~. ~ ~ ~ ~ ~ ~......
~ ~.3/4 9-10 SUSQUEHANNA - UNIT 1 Amendment No. i59
BASES SKGIIQH 3/4.7.1 SERVICE WATER SYSTEMS
...B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY.
~
... ~..~... B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM............. B 3/4 7-1 3/4.7.4 SNUBBERS 3/4.7.5 SEALED SOURCE CONTAMINATION.
... ~.. ~.. B 3/4 7-2
.......... B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS
~.B 3/4 7-3 3/4.7.7 FIRE RATED ASSEMBLIES.. ~ ~ ~ ~ ~.. ~. ~ ~..~..."
.B 3/4 7-4 3/4.7.8 MAINTURBINE BYPASS SYSTEM.
.... B 3/4 7-4 3/4.8.1, 3/4.8,2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS................
B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES............ B 3/4 8-3 3/4.9.1 REACTOR MODE SWITCH.'..
3/4.9.2 INSTRUMENTATION.
... B 3/4 9-1 B 3/4 9-1 3/4.9.3 CONTROL ROD POSITION.
3/4.9.4 DECAY TIME 3/4.9.5 COMMUNICATIONS 3/4.9.6 DELETED
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
B 3/4 9 1
.....B 3/4 9-1 B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL...~............ B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE POOL...
~ ~.......~... B 3/4 9-2 3/4.9.10 CONTROL ROD REMOVAL B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVALAND COOLANT CIRCULATION.
. B 3/4 9-2 SUSQUEHANNA - UNIT 1 Amendment No.
DELETED SUSQUEHANNA - UNIT 1 3/4 9-8 36
, Amendment NoÃ9
, SURVEILLANCEREQUIREMENTS (Continued)
DELETED SUSQUEHANNA - UNIT 1 3/4 9-9 Amendment No.>59
BASES DELETED The restriction on movement of loads in excess of the nominal weight of a fuel assembly over other fuel assemblies in the storage pool ensures that in the event this load is dropped
- 1) the activity release will be limited to that contained in a single fuel assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity.release assumed in the safety analyses.
The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10%
iodine gap activity released from the rupture of an irradiated fuel assembly. This minimum water depth is consistent with the assumptions of the safety analysis.
These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous removal of more than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn.
The requirement that at least one residual heat removal loop be OPERABLE or that an alternate method capable of decay heat removal be demonstrated and that an alternate method of coolant mixing be in operation ensures that
- 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140~F as required during REFUELING, and 2) sufficient coolant circulation would be available through the reactor core to assure accurate temperature indication and to distribute and prevent stratification of the poison in the event it becomes necessary to actuate the standby liquid control system.
The requirement to have two shutdown cooling mode loops OPERABLE when there is less than 22 feet of water above the reactor vessel flange ensures that a single failure of the operating loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 22 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus, in the event a failure of the operating RHR loop, adequate time is provided to initiate alternate methods capable of decay heat removal or emergency procedures to cool the core.
SUSQUEHANNA - UNIT 1 B 3/4 9-2 Amendment No. 29, 159
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20M&4001 PENNSYL ANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.>3O License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 5 Light Company, dated February 29,
- 1996, complies with the standards and requirements of the Atomic Energy Act of 1954,. as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the
.provisi.ons of the Act, and the regulations of the Commission; C.
D.
E.
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 Commission's regulations set forth in 10 CFR Chapter I; 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 The issuance of this amendment is in accordance with 10 CFR Part 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 the Facility Oper'ating License No. NPF-22 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 130 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPKL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance
'and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1996 F. Stolz, Dir tor oject Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO.
1 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A'Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 1X xv 3/4 9-8 3/4 9-9 8 3/4 9-2 INSERT 1X xv 3/4 9-8 3/4 9-9' 3/4 9-2
e'IMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREIVIENTS BEG:GQH 3/4.8.1 A.C. SOURCES A.C. Sources - Operating.
A.C. Sources
- Shutdown.
3/4.8.2 D.C. SOURCES
... ~.3/4 8-1
~3/4 8-10 D.C. Sources
- Operating.
D.C. Sources - Shutdown.
.,3/4 8-1 1
.....3/4 8-16 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS Distribution - Operating.
Distribution - Shutdown.
~ 3/4 8-18
.3/4 8-21 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary Containment Penetration Conductor Overcurrent Protective Devices....
~ ~. ~.
~~..........3/4 8-24 Motor-Operated Valves Thermal Overload Protection.~...............3/4 8-30 Reactor Protection System Electric Power Monitoring..... ~. ~.~......3/4 8-35 3/4.9.1 REACTOR MODE SWITCH.
~ 3/4 9-1 3/4.9.2 INSTRUMENTATION
........3/4 9-3 3/4.9.3 CONTROL ROD POSITION.
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ e 3/4 9 5 3/4.9.4 DECAY TIME
...3/4 9-6 3/4.9.5 COMMUNICATIONS
.3/4 9-7 3/4.9.6 DELETED 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL......................3/4 9-10 SUSQUEHANNA - UNIT 2 IX Amendmengg.
i
BASES SEQIIQH 3/4.7.1 SERVICE WATER SYSTEMS B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.......
~ B 3/4 7-1 3/4.7.4 SNUBBERS.
~ ~..
3/4.7.5 SEALED SOURCE CONTAMINATION
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 7 2 B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS..
~.
~. B 3/4 7-4 3/4.7.7 FIRE RATED ASSEMBLIES 3/4.7.8 MAINTURBINE BYPASS SYSTEM.
3/4 7-,4
............., B 3/4 7-4 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION SYSTEMS..~.....
~.. B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES....... B 3/4 8-3 3/4.9.1 REACTOR MODE SWITCH..
. B 3/4 9-1 3/4.9.2 INSTRUMENTATION..~........
~
3/4.9.3 CONTROL ROD POSITION.
3/4.9.4 DECAY TIME
.. B 3/4 9-1
. B 3/4 9-1
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 9 1
3/4.9.5 COMMUNICATIONS 3/4.9.6 DELETED
.. B 3/4 9-1 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL.;.....~... B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE POOL..... B 3/4 9-2 3/4.9.10 CONTROL ROD REMOVAL SUSQUEHANNA - UNIT 2 xv 3/4.9.11 RESIDUAL HEAT REMOVALAND COOLANT CIRCULATION.
. B 3/4 9-2
~ B 3/4 9-2 Amendment No. 1~0
DELETED SUSQUEHANNA - UNIT 2 3/4 9-8 Amendment No. >30
, DELETED SUSQUEHANNA - UNIT 2 3/4 9-9 Amendment No.130
BASES DELETED The restriction on movement of loads in excess of the nominal weight of a fuel assembly over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel
- assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap.activity released from the rupture of an irradiated fuel assembly.
This minimum water depth is consistent with the assumptions of the safety analysis.
These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous removal of more than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn.
The requirement that at least one residual heat removal loop be OPERABLE or that an alternate method capable of decay heat removal be demonstrated and that an alternate method of coolant mixing be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F
as required during REFUELING, and (2) sufficient coolant circulation would be available through the reactor core to assure accurate temperature indication and to distribute and prevent stratification of the poison in the event it becomes necessary to actuate the standby liquid control system.
The requirement to have two shutdown cooling mode loops OPERABLE when there is less than 22 feet of water above the reactor vessel flange ensures that a single failure of the operating loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 22 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus, in the event a failure of the operating RHR loop, adequate time is provided to initiate alternate methods capable of decay heat removal or emergency procedures to cool the core.
SUSQUEHANNA - UNIT 2 B 3/4 9-2 Amendment No. 130