ML20063M273
| ML20063M273 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/09/1994 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063M275 | List: |
| References | |
| NUDOCS 9403110371 | |
| Download: ML20063M273 (10) | |
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.h(lg.fg UNITED STATES NUCLEAR REGULATORY COMMISSION y Qg.y!
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WASHINGTON. o.C 20665 0001 s*
COMMONWEALTH EDIS0N COMPANY DOCKET N0. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. NPF-ll 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application ~ for amendment filed by the Commonwealth Edison Company (the licensee), dated October 28, 1993, as supplemented by letter dated January 21, 1994, 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 provisions of the Act, and the 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 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 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 enclosure to this license amendment and paragraph 2.C.(2) of the facility Operating License No. NPF-ll is hereby amended to read as follows:
9403110371 940309 U
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Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 96
, and the Environmental Protection Plan contained 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.
3.
This amendment is effective immediately to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 2f, Gar' James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 9, 1994
... =.. -.
.0 ATTACHMENT TO LICENSE AMENDMENT NO. 96 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 3-31 3/4 3 B 3/4 2-6 B 3/4 2-6 5
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a,n, e.,
v v
TABLE 3.3.3-3 EMERGENCY CORE COOLING SYS_lEM RESPONSE TIMES ECCS RESPONSE TIME (Seconds) 1.
LOW PRESSURE CORE SPRAY SYSTEM s 60*
2.
LOW PRESSURE COOLANT INJECTION MODE Of l
RHR SYSTEM (Pumps A, B, and C) s 60*
3.
AUTOMATIC DEPRESSURIZATION SYSTEM NA 4.
HIGH PRESSURE CORE SPRAY SYSTEM s 41 S.
LOSS OF POWER NA l
i l
l l
- Injection valves shall be fully OPEN within 40 seconds after receipt of the l
reactor vessel pressure and ECCS Injection Line Pressure Interlock signal concurrently with power source availability and receipt of an accident initiation signal.
LA SALLE - UNIT 1 3/4 3-31 Amendment No. 96
POWER QlSTRIBUTION SYSTEMS
^
BASES 3/4.2.4 LINEAR HEAT GENERATION RATE The specification assures that the LINEAR HEAT GENERATION RATE (LHGR) in any rod is less than the design linear heat generation even if fuel pellet densification is postulated. The power spike penalty specified is based on the analysis presented in Section 3.2.1 of the GE topical report NEDM-10735 Supplement 6, and assumes a linearly increasing variation in axial gaps between core bottom and top and assuras with a 95% confidence that no more than one fuel rod exceeds the design LINEAR HEAT GENERATION RATE due to power spiking.
References:
1.
General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR 50, Appendix K, NEDO-20566A, September 1986.
2.
" Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," General Electric Company Licensing Topical Report NEDO 24154 Vols. I and II and NEDE-24154 Vol. III as sup-plemented by letter dated September 5, 1980, from R. H. Buchholz (GE) to P. S. Check (NRC).
3.
"LaSalle County Station Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," General Electric Company Report NEDC-32258P, October 1993.
4.
" General Electric Standard Application for Reactor Fuel,"
NEDE-240ll-P-A, (latest approved revision).
5.
" Extended Operating Domain and Equipment Out-of-Service for LaSalle County Nuclear Station Units 1 and 2," NEDC-31455, November 1987.
LA $ALLE UNIT 1 B 3/4 2-6 Anendment No. 96
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UNITED STATES i
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j NUCLEAR REGULATORY COMMISSION vim 2}@k j
WASHINGTON o.C. 20 % 5 0001
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 28, 1993, as supplemented by letter dated January 21, 1994, 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 provisions of the Act, and the 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 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 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is i
hereby amended to read as follows:
?
(2) lechnical Sp nifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as ;evised through Amendment No. 80
, and the Environmental Protection Plan contained 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.
3.
This amendment is effective immediately to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,, Wf GV ames E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications -
i Date of Issuance: March 9, 1994
.l l
i
J ATTACliMENT TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. 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 3-31 3/4 3-31 B 3/4 2-6 B 3/4 2-6
'l l
.~..,. _ __
-. ~. -
TABLE 3.3.3-3
[MERRENCY_ CORE COOLING SYSTEM RESPONSE TIMES
[fLS RESPONSE 11ME (Seconds) 1.
LOW PRESSURE CORE SPRAY SYSTEM s 60*
1 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Pumps A, B, and C) s 60*
l
)
3.
AUTOMATIC DEPRESSURIZATION SYSTEM NA 4.
MIGH PRESSURE CORE SPRAY SYSTEM s 41
~l l
5.
LOSS OF POWER NA
- Injection valves shall be fully 0 PEN within 40 seconds after receipt of the l
reactor vessel pressure and ECCS Injection Line Pressure Interlock signal concurrently with power source availability and receipt of an accident initiation signal.
LA SALLE - UNIT 2 3/4 3-31 Amendment No. 80
POWER DISTRIBUTION SYSTEMS
^
BASES 3/4.2.4 LINEAR HEAT GENERATION RATE The specification assures that the LINEAR HEAT GENERATION RATE (LHGR) ia any rod is less than the design linear heat generation even if fuel pellet densification is postulated. The power spike penalty specified is based on the analysis presented in Section 3.2.1 of the GE topical report NEDM-10735 Supplement 6, and assumes a linearly increasing variation in axial gaps between core bottom and top and assures with a 95% confidence that no more than one fuel rod exceeds the design LINEAR HEAT GENERATION RATE due to power spiking.
References:
1.
General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR 50, Appendix K, NED0-20566A, September 1986.
2.
" Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," General Electric Company Licensing Topical Report NED0 24154 Vols. I and II and NEDE-24154 Vol. III as sup-plemented by letter dated September 5, 1980, from R. H. Buchholz (GE) to P. S. Check (NRC).
3.
"LaSalle County Station Units 1 and 2 SAFER /GESTR-10CA Loss-of-Coolant Accident Analysis," General Electric Company Report NEDC-32258P, October 1993.
4.
" General Electric Standard Application for Reactor fuel,"
NEDE-240ll-P-A, (latest approved revision).
5.
" Extended Operating Domain and Equipment Out-of-Service for LaSalle County Nuclear Station Units 1 and 2," NEDC-31455, November 1987.
i LA SALLE - UNIT 2 B 3/4 2-6 Amendment No. 80 l
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