ML20098D175
| ML20098D175 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/19/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20098D176 | List: |
| References | |
| NUDOCS 9205280071 | |
| Download: ML20098D175 (10) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
p Mou 2[ D
$g o
UNITED STATES E
i NUCLEAR REGULATORY COMMISSION
%,.... + /[
WAsHINoTON D C. 20%6
[Df1@lMAllti EDISON COMPANY P0CKET tl0, 50-373 LASALLI_C@NTY STATION. UNIT 1 AfiENDMENT TO FACILITY OPERATING Li[11[SI Amendment No. 83 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 January 21, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Com*nission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the ::ppilcation, 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 l Specifications as indicated in the enclosure to this license amendment and )aragraph 2.C.(2) of the facility Operating License No. NPF-ll is heresy amended to read as follows:
9205280071 920519 PDR ADOCK 05000373 P
7
.g.
(2) lechnical Specifications and Environmentti Protection Plan 1he Technical Specifications contained in Appendix A, as revised through Amendment No. 83, 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 upon date of issuance.
FOR THE NUCLEAR REi ATORY COMMISSION l
$Al Riciar J. Barrett, Director Project Directorate 111-2 Divi. ion of Reactor Projects - !!!/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance.
May 19, 1992 l
l
ATTACHMENT _JO LICENSE AMENDMLt1T NO. 83 FAClllTY OPERATING LICENSE NO. NPF-11 DOCKET RO. 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 i
contain vertical lines indicating the area of change.
Pages identified by an asterisk are provided for convenience.
REMOVE INSERT 3/4 9-7 3/4 9-7 3/4 9-8 3/4 9-8 o
..v...
-m,
.,..~,.-_m....,_,...,__,.m,.m_.,-,_
.._.___,.._.,,,-,_.,_.__,__.,.._...,_...m._-,_,m,_...-.,,.,-.._m._,,_,
_,. _.. ~,..
,..._,.,,.,,,--,.,___m--,,,_..,m.,--
r
REFUEL 8NG OPERATIONS i
3/4.9.5 COMMUNICATIONS LIMITING CONDITION FOR OPERATION 3.9.5 Direct communication shall be maintained between the control room and refueling platform personnel.
APPLICABILITY:
OPERATIONAL CON,DITION 5, during CORE ALTEP.ATIONS.*
ACTION:
When direct communication between the control room and refueling platform personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*
SURVEILLANCE REQUIREMENTS 4.9.5 Direct communication between the control room and refueling platform personnel shal! be demonstrated within one hour prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> dur*:ag CORE ALTERATIONS.*
"Except movement of incore instrumentation and control rods with their normal drive system.
LA SALLE - UNIT 1 3/4 9-7
l l
l REFUELING OPERATIONS 3/4.9.6 CRANE AND HOIST LIMITING CONDITION FOR OPERATION 3.9.6 All craras and hoists used for handling fuel assemblies or control rods within the reactor pressure vessel shall be OPERABLE.
APPLICABILITY:
During handling of fuel assemblies or control rods within the reactor pressure vessel.
ACTION:
With the requirements for crane and hoist OPERABILITY not satisfied, suspend use of any inoperable crane or hoist from operations involving the handling of control rods and fuel assemblies within the reactor pressure vessel after placing the load in a safe condition.
SURVEILLANCE REQUIREMENTS 4.9.6 Each crane or hoist used for handling of control rods or fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 7 days prior to the start of such operations with that crane or hoist by:
a.
Demonstrating operation of the overload cutoff when the load exceeds:
1.
For the fuel hoist:
a) 1600 +100/-0 pounds witt the NF500 mast, b) 1200 150 pounds with the 762E974 mast.
2.
1000 1 50 pounds for the auxiliary hoist.
b.
Demonstrating operation of the loaded interlock when the loat' exceeds:
1.
For the fuel hoist:
a) 700 +50/-0 pounds with the NF500 mast.
h) 485 150 pounds and 550 150 pounds with the 762E974 mast.
2.
400 1 50 pounds for the auxiliary hoist.
c.
Demonstrating operation of the fuel hoist downtravel stop when downtravel exceeds 54 feet below the platform rails.
d.
Demonstrating operation of the fuel hoist and auxiliary hoist up-travel stops when the grapple is lower than or equal to 8 feet below the platform rails.
e.
Demonstrating operation of the fuel hoist slack cable cutoff when the hoist is unloaded.
LA SALLE - UNIT 1 3/4 9-8 Amendment No. 83 1
. _ ~
t
! 3 g
n UNITED STATES 5
<i NUCLEAR REGULATORY COMMISSION
[
WASHINoToN. D.C. 70%5 o
%,e..* /
COMMONWEALTH EDISON COMPANY DQCKET N0. 50-374 LASALLE COURTY STATION. UNIT 2 AMENDMENT TO FAClllTY OPERATING Ll(INS _E Amendment No. 67 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 January 21, 1992, 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 conducter without endangering the health and safety of the public, and (iij 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 Facil.cy Operating 1.icense No NPF-18 is hereby amended to read as follows:
I t
. (2) lechnical sp1cifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 67, and the Envirnnmental 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 upon date of issuance.
FOR THE NUCLEAR REGU t ORY COMMISSION
~
'S' /
LA4l i
Richar arrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 19, 1992
ATTACHMENT TO LICENSE AMENDMENT h0. 67 FACILITY.DPERATING LICENSE NO. NPE_10 DOCKET NO, 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed paget.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Pages identified by an i
asterisk are provided for convenience.
REMOVE jfigBI
- 3/4 9-7
- 3/4 9-7 3/4 9-8 3/4 9-8 t
i 7
I i
lo
... ~.
REFUELING OPERATIONS 3/4.^.5 COMMUNICATIONS LIMITING CONDITION FOR OPERATION 3.9.5 Direct communication shall be maintained between the control room and refueling platform personnel.
APPLICABILITY:
OPERATIONAL CONDITION 5, during CORE ALTERATIONS.*
ACTION:
When direct communication between the control room and refueling platform personnel cannot be maintained, immediately suspend CORE ALTERATIONS.*
k
,S'JRVEILLANCE REQUIREMENTS 4.9.5 Direct communication between the control room and refueling platform personnel shal's be demonstrated within one hour prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.*
- Except movement of incore instrumentation and control tcds with their normal drive system.
LA SALLE - UNIT 2 3/4 9-7
REFUELING OPERATIONS 3449.6 CRA'l! AND HOIST t
LIMITING CONDITION FOR OPERATION 3.9.6 All cranes and hoists used for handling fuel assemblies or control rods within the reactor pressure vessel shall be OEERABLE.
APPLICABI_ LIT _Y: During handling of fuel assemblies or control rods within the l
~
ACTION:
With the requirements for crane and hoist OPERADILITY not satisfied, suspend use of any inoperable crane or hoit.t from operations involving the handling of control rods and fuel assemblies within the reactor pressure vessel af ter placing the load in a safe condition.
SURVEILLANCE REQUIREMENTS 4.9.6 Each crane or hoist used 'or handling of control rods or fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 7 days prior to the start of such operations with that crane Or hoist by:
a.
Demonstrating operation of the overload cutoff when the load exceeds:
1.
For the fuel hoist:
a) 1600 +100/-0 pounds with the NF500 mast.
b) 1200 150 pounds with the 762E974 mast.
2.
1000 1 50 pounds for the auxiliary hoist.
b.
Demonstrating operation of the loaded interlock when the load exceeds:
1.
For the fuel hoist:
a) 700 +50/-0 pounds with the NF500 mast.
l b) 485 150 pounds and 550 +50 pounds with the 762E974 mast.
2.
400 t 50 pounds for the auxiliary hoist.
c.
Demonstrating operation of the fuel hoist downtravel stop when downtravel eneeds 54 feet below the platform rails, d.
Demonstrating operation of the fuel hoist a id auxiliary hoist up-travel stops when the grapple is lower than or equal to 8 feet below the platform rails.
e.
Demonstrating operation of the fuel hoist slack cable cutoff when the hoist is unloaded.
LA SALLE - UNIT 2 3/4 9-8 Amendment No. 67
...