ML20216H689
| ML20216H689 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/24/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216H681 | List: |
| References | |
| NUDOCS 9910010445 | |
| Download: ML20216H689 (12) | |
Text
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UNITED STATES p"
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
.....,o PECO ENERGY 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. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 229 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated March 29,1999, as supplemented July 21,1999, 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; i
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 Commission'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 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:
9910010445 990924 PDR ADOCK 05000277 P
PDR t
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. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 229, are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION af//
J mes W. Cliff
, Chief, Section 2 i
Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation
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. Attachmant: Changes to the Technical Specifications
' Date of issuance:. September 24,1999 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 229 FACILITY OPERATING LICENSE NO. DPR-44
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DOCKET NO. 50-277 i
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.9-2 3.9-2 B 3.9-1 B 3.9-1 B 3.9-3 8 3.9-3
Refueling Equipment Interlocks 3.9.1
-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1-Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment interlock-inputs:
La.
All-rods-in, b.
Refuel p'latform position, c.
Refuel platform fuel grapple, fuel
- loaded, l
d.
Refuel platform frame mounted auxiliary hoist, fuel loaded, l
e.
Refuel platform monorail mounted hoist, fuel loaded.
c PBAPS UNIT 2 3.9-2 Amendment No. 210, 229 j
Refueling Equipment Interlocks B 3.9.1 B 3.9 REFUELING OPERATIONS B 3.9.1 Refueling Equipment Interlocks BASES l
BACKGROUND Refueling equipment interlocks restrict the operation of the refueling equipment or the withdrawal of control rods to reinforce unit procedures that prevent the reactor from achieving criticality during refueling.
The refueling interlock circuitry senses the conditions of the refueling equipment and the control rods. Depending on the sensed conditions, interlocks are actuated to prevent the operation of the refueling equipment or the withdrawal of control rods.
Design criteria require that one of the two required independent reactivity control systems be capable of holding the reactor core subcritical under cold conditions (Ref. 1).
The control rods, when fully inserted, serve as the system capable of maintaining the reactor subcritical in cold j
conditions during all fuel movement activities and 1
accidents.
One channel of instrumentation is provided to sense the position of the refueling platform, the loading of the refueling platform fuel grapple and the full insertion of all control rods. Additionally, inputs are provided for the loading of the refueling platform frame mounted auxiliary hoist and the loading of the refueling platform monorail mounted hoist.
With the reactor mode switch in the shutdown or refueling position, the indicated conditions are combined in logic circuits to determine if all restrictions on refueling equipment operations and control rod insertion are satisfied.
A control rod not at its full-in position interrupts power to the refueling equipment and prevents operating the equipment over the reactor core when loaded with a fuel assembly.
Conversely, the refueling equipment located over l
the core and loaded with fuel inserts a control rod withdrawal block in the Reactor Manual Control System to prevent withdrawing a control rod.
(continued) i PBAPS UNIT 2 B 3.9-1 Amendment No. 229 J
Refueling Equipment Interlocks B 3.9.1 BASES (continued)
LCO To prevent criticality during refueling, the refueling interlocks ensure that fuel assemblies are not loaded with any control rod withdrawn.
To prevent these conditions from developing, the all-rods-in, the refueling platform position, the refueling platform fuel grapple fuel loaded, the refueling platform frame mounted auxiliary hoist fuel loaded, and the refueling platform monorail mounted hoist fuel loaded inputs are required to be OPERABLE.
These inputs are combined in logic circuits, which provide refueling equipment or control rod blocks to prevent operations that could result in criticality during refueling operations.
APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.
The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5.
The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.
In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and in-vessel fuel movements are not possible.
Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.
ACTIONS A.1 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LCO does not apply.
In-vessel fuel movement with the affected refueling equipment must be immeaiately suspended.
This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn).
Suspension of in-vessel fuel movement shall not preclude completion of movement of a convenent to a safe position.
(continued)
PBAPS UNIT 2 B 3.9-3 Amendment No. 229
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i UNITED STATES NUCLEAR REGULATORY COMMISSION E
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PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 l
PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 232 License No. DPR-56 1.
The Nuclear Regulatory Commis.sion (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated March 29,1999, as supplemented July 21,1999, 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 1.
G.
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 Commission's regulations; I
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 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 56 is hereby amended to rend as follows:
i (2) Technical Specificat ons The Technical Specifications contained in' Appendices A and B, as revised through Amendment No. 232, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION M24
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J mes W. Cliffor, Chief, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 24,1999 i
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4
E ATTACHMENT TO LICENSE AMENDMENT NO. 232 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.9-2 3.9-2 B 3.9-1 B 3.9-1 B 3.9-3 8 3.9-3
\\
j i
r-Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment
, interlock inputs:
a.
All-rods-in, b.
Refuel platform position, c.
Refuel platform fuel grapple, fuel
- loaded, l
d.
Refuel platform frame mounted auxiliary hoist, fuel loaded, l
e.
Refuel platform monorail mounted hoist, fuel loaded.
I PBAPS UNIT 3 3.9-2 Amendment No. 2f4, 232
p..
Refueling Equipment Interlocks B 3.9.1 B 3.9 REFUELING OPERATIONS B 3.9.1 Refueling Equipment Interlocks BASES BACKGROUND Refueling equipment interlocks restrict the operation of the refueling equipment or the withdrawal of control rods to reinforce unit procedures that prevent the reactor from achieving criticality during refueling.
The refueling interlock circuitry senses the conditions of the refueling equipment and the control rods.
Depending on the sensed conditions, interlocks are actuated to prevent the operation of the refueling equipment or the withdrawal of control rods.
Design criteria require that one of the two required independent reactivity control systems be capable of holding the reactor core subcritical under cold conditions (Ref.1).
The control rods, when fully inserted, serve as the system capable of maintaining the reactor subcritical in cold conditions during all fuel movement activities and accidents.
One channel of instrumentation is provided to sense the position of the refueling platform, the loading of the refueling platform fuel grapple and the full insertion of all control rods. Additionally, inputs are provided for the loading of the refueling platform frame mounted auxiliary hoist and the loading of the refueling platform monorail mounted hoist. With the reactor mode switch in the shutdown or refueling position, the indicated conditions are combined in logic circuits to determine if all restrictions on refueling equipment operations and control rod insertion are satisfied.
A control rod not at its full-in position interrupts power to the refueling equipment and prevents operating the equipment over the reactor core when loaded with a fuel assembly.
Conversely, the refueling equipment located over the core and loaded with fuel inserts a control rod withdrawal block in the Reactor Manual Control System to prevent withdrawing a control rod.
(continued) l l
PBAPS UNIT 3 8 3.9 1 Amendment No. 232
Refueling Equipment Interlocks B 3.9.1 BASES (continued)
LC0 To prevent criticality during refueling, the refueling interlocks ensure that fuel assemblies are not loaded with any control rod withdrawn.
To prevent these conditions from developing, the all-rods-in, the refueling platform position, the refueling platform fuel grapple fuel loaded, the refueling platform frame mounted auxiliary hoist fuel loaded, and the refueling platform monorail mounted hoist fuel loaded inputs are required to be OPERABLE. These inputs are combined in logic circuits, which provide refueling equipment or control rod blocks to prevent operations that could result in criticality during refueling operations.
APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.
The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5.
The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.
In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and in-vessel fuel movements are not possible.
Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.
ACTIONS A.1 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LC0 does not apply.
In-vessel fuel movement with the affected refueling equip =,t must be j
immediately suspended.
This action ensures that operations are not performed with equipment that would potentially not i
be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn).
Suspension of in-vessel fuel movement shall not preclude completion of movement of a component to a safe position.
(continued)
PBAPS UNIT 3 B 3.9-3 Amendment No. 232
,