ML20137B768
| ML20137B768 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/07/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137B772 | List: |
| References | |
| NUDOCS 8601160072 | |
| Download: ML20137B768 (10) | |
Text
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o, UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendmen't No. 32 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Commission or the NRC) having found that:
A.
The application for amendment filed by the Comonwealth Edison Compan',,
dated October 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 regulations of the Comission; 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 set forth in 10 CFR Chapter 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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of i
the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendnent and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 32 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This amendaent is effective as of date of issuance, f
FOR THE NUCLEAR REGULATORY COMMISSION
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Elinor G. Adensam Director Project Directorate No. 3 Division of BWR Licensing
Enclosure:
I Changes to the Technical Specifications 1
Date of Issuance: J44 0 7 Eg6
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ENCLOSURE TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 9-3 3/4 9-3 B3/4 9-1 B3/4 9-1 3
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REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor * (SRM) channels shall be OPERA 8LE# and inserted to the normal operating level with:
a.
Continuous visual indication in the control room, b.
One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and The"shortinglinks"removedfromtheRPSciguitrypriorto'and c.
during the time any control rod is withdrawn and shutdown margin demonstrations.
APPLICA8ILITY: OPERATIONAL CONDITION 5, unless the following conditions are met:
a.
No more than four (4) fuel assemblies are present in each core quadrant associated with an-SRM; b.
While in core, these four. fuel assemblies are in locations adjacent to the SRM; and c.
In the case of movable detectors, detector location shall be selected such that each group of fuel assemblies.is separated by at least two (2) fuel cell locations from any other fuel assemblies.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS ** and insert all insertable-control rods.
SURVEILLANCE REQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERA 8LE' l
by:
a.
At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
1.
Performance of a CHANNEL CHECK, f
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Verifying the detectors are inserted to the normal operating l
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3.
During CORE ALTERATIONS, verifying that'the detector of an L
OPERABLE SRM channel is located in the core quadrant where CORE l
l ALTERATIONS are being performed and another is located in.an I
adjacentquadrant.
"The use of special movable detectors during CORE ALTERATIONS in place of f
the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.
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- The normal or emergency power source may be inoperable.
"Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
1 LA SALLE - UNIT 1 3/4 9-3
' Amendment No. 32 t
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c 3/4.9 REFUELING OPE' RATIONS BASES t
l 3/4.9.1 REACTOR MODE SWITCH i
Locking the OPERABLE reactor mode switch in the Shutdown or Refuel position, 4
as specified, ensures that the restrictions on control rod withdrawal and j-refueling platform movement during the refueling operations are properly activated. ' These conditions reinforce the refueling procedures and reduce the probability of inadvertent crhicality; damage to reactor internals or fuel assemblies,' and exposure of personnel'to excessive radioactivity.
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3/4.9.2 INSTRUMENTATION The OPERABILITY of at least twa source range monitors ensures-that redundant mon.itoring capability is available to detect changes in the reactivity condition of the core, whenever reactor criticality is possible, 1
g-1 3/4.9.3 CONTROL ROD POSITION v
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The requirement that 31.1 contb1 rods be inserted during other CORE ALTERATIONS ensures that fuel will-not be loaded into a cell without a control rod.
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3/4.9.4 DECAY TIME i
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The minimum requirement for reactor subcriticality prior to fuel movement l,
ensures that sufficient time has elapsed to allow the radioactive decay of_the i
short lived fission products. This decay time is ;ct,nsistent with the assumptions used in the accident analyses.
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3/4.9.5 COPMUNICATIONS y
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The require:wnt for, communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
Q 3/4.9.6 CRANE AND HOIST X
l The OPERA 8ILITY requirements ensure that the cranes and hoists used for
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i handling control rods and fuel assembifes within the reactor pressure vessel:
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(1) have sufficient load capacity,for-handling fuel assemblies 'and control rods, and (2) the core internels and pressure vessel are protected from excessive lifting force in the evertCthey are _ inadvertently engaged during lifting operations.
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LA SALLE - UNIT 1(
8 3/4 9-1 Amendment No. 32
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION 7.
p WASHINGTON, D. C. 20555 f
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 18 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for amendment filed by the Commonwealth Edison Company, dated October 11, 1985, 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 confonnity with the application, the provisions of the Act, and the regulations of the Comission; 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 set forth in 10 CFR Chapter 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.18 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporateo in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
This amendment is effective as of date of issui,nce.
e FOR THE NUCLEAR REGULATORY COMISSION
.s Elinor G. Adensam, Director Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical j
Specifications i
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ENCLOSURE TO LICENSE AMENDMENT NO.18 FACILITY OPERATING LICENSE N0. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 9-3 3/4 9-3 83/4 9-1 B3/4 9-1
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l REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor * (SRM) channels shall be OPERA 8LE# and inserted to the normal operating level with:
Continuous visual indication in the control room, a.
b.
One of the required SRM detectors located.in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and The " shorting links" removed from the RPS ciguitry prior. to and c.
during the time any control rod is withdrawn and shutdown margin demonstrations.
APPLICABILITY: OPERATIONAL CONDITION 5, unless the following conditions are met:
i a.
No more than four (4) fuel assemblies are present in each core quadrant associated with an SRM; b.
While in core, these four fuel assembifes are in locations adjacent to the SRM; and 1
i c.
In the case of movable detectors, detector-location shall be selected l
such that each group of fuel assemblies is separated by at least two j
(2) fuel cell locations from any other fuel assemblies.
ACTION:
With the requirements of the soove specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS ** and insert all insertable control rods.
l SURVEILLANCE REQUIREMENTS l
4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE:
by:
a.
At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
1.
Perfo,rmance of a CHANNEL CHECK,-
2.
Verifying the detectors are inserted to the normal operating level, and j
3.
During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and another is located in an adjacent quadrant.
"The use of special movable detectors during CORE ALTERATIONS in place of i
the normal SRM nuclear detectors is permissible as long as these special J
i detectors are connected to the normal SRM circuits.
The normal or emergency power source may be inoperable.
- ot required for control rods ~. removed per' Specification 3.9.10.1 or 3.9.10.2.
N LA SALLE - UNIT 2
- 3/4 9-3 Amendment No.18
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3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 REACTOR MODE SWITCH Locking the OPERABLE reactor mode switch in the Shutdown or Refuel position, as specified, ensurcs that the restrictions on control rod withdrawal and refueling platform movement during the refueling operations are properly activated.
These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, dtiage to reactor internals or fuel assemblies, and exposure of personnel to excessive radioactivity.
3/4.9.2 INSTRUMENTATION The OPERABILITY of at least two source range monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core, whenever reactor criticality is possible.
l 3/4.9.3 CONTROL ROD POSITION The requirement that all control rods be inserted during other CORE ALTERATIONS ensures that fuel will not be loaded into a cell without a control rod.
3/4.9.4 DECAY TIME The minimum requirement for reactor subcriticality prior to fuel movement ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
3/4.9.6 CRANE AND HOIST The OPERABILITY requirements ensure that the cranes and hoists used for handling control rods and fuel assemblies within the reactor pressure vessel:
(1) have sufficient load capacity for handling fuel assemblies and control-rods, and (2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lif ting operations.
LA SALLE - UNIT 2 B 3/4 9-1 Amendment No.18
.