ML20141P005
| ML20141P005 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/12/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141P006 | List: |
| References | |
| NUDOCS 8603180415 | |
| Download: ML20141P005 (19) | |
Text
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION O
j WASHINGTON D. C. 20656 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated December 3, 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 provision of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (1) that the activities auth'orized by this amend.nent 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.
TheissuanceofthisamndmentisinaccordancewithIbCFRPart51of 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 enclosure to this license amendment and paragraph 2.C.(2) of the 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. 35, 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.
8603180415 060:.sta PDR ADOCK 05000373 P
2-3.
This amendment is effective as of date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h4
/-
Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: My 12 m
+
ENCLOSURE TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
REMOVE INSERT 6-15 6-15 1.
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ADMINISTRATIVE CONTROLS 6.1.1 HIGH RADIATION AREAS 6.1.1.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR 20, in lieu of the l
" control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr* but less than 1000 mrem /hr* shall be barricaded and I
conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures, i.e., a Rad / Chem technician, or personnel continuously escorted by such individuals, may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas in which the intensity of radiation is greater than 100 mrem /
hr* but less than 1000 mrem /hr*, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them, A health physics qualified individual, i.e., qualified in radiation c.
protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physicist in the Radiation Work Permit (RWP).
6.1.1. 2 In addition to the requirements of 6.1.1.1, above, for areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrem *, the computer shall be l
programmed to permit entry through locked doors for any individual requiring access to any such High-High Radiation Areas for the time that access is required.
6.1.1. 3 Keys to manually open computer controlled High Radiation Area doors and High-High Radiation Area doors shall be maintained under the Administra-tion control of the Shift Supervisor on duty and/or the Health Physicist.
6.1.1. 4 High-High Radiation areas, as defined in 6.1.1.2 above, not equipped l
with the computerized card readers shall be maintained in accordance with 10 CFR 20.203 c.2 (iii), locked except during periods when access to the area is required with positive control over each individual entry, or 10 CFR 20.203.c.4.
In the case of a High Radiation Area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted.
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radiation levels such that a major portion of the bodycouldreceiveinonehouradoseinexcessof1000 mrem *thatarelocatedwithinl
" Measurement made at 18" from source of radioactivity.
LA SALLE UNIT 1 6-15 Amendment No. 35
UNITED STATES g
p, NUCLEAR REGULATORY COMMISSION n
j waswiworow.o. c. zosos COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.19 License No. NPF-18 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated December 3, 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; 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: (1) 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 comon 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 enclosure to this license amendment and paragraph 2.C.(2) of the 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.19, 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, cm
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. 3.
This amendment is effective as of date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
v Elinor G. Adensam Director l
BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: #4 : 3 9;,
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ENCLOSURE TO LICENSE AMENDMENT NO.19 FACILITY OPERATING LICENSE NO. NPF-18 l
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 i
6-15 6-15 6-16 6-16 i
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ADMINISTRATION CONTROLS l
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6.1.1 HIGH RADIATION AREAS I
j 6.1.1.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR 20, in lieu of the " con-l
{
trol device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, j
t each high radiation area in which the intensity of radiation is greater than r
i 100 mres/hr* but less than 1000 mres/hr* shall be barricaded and conspicuously
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posted as a High Radiation Area and entrance thereto shall be controlled by l
i requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures, i.e., a Rad / Chem technician, or personnel con-j tinuously escorted by such individuals, may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas in which the intensity of radiation is greater than 100 mrem /hr* but less than 1000 mrom/hr*, provided they are otherwise following plant radiation pro-tection procedures for entry into such high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the
(
a.
radiation dose in the area.
E; b.
A radiation monitoring device which continuously integrates the i
radiation dose rate in the area and alarms when a preset integrated i
dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established l
)
and personnel have been made knowledgeable of them.
A health physics qualified individual, i.e., qualified in radiation c.
protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities j
within the area and shall perform periodic radiation surveillance at l
the frequency specified by the Health Physicist in the Radiation
{
l Work Permit (RWP).
J 6.1.1. 2 In addition to the requirements of 6.1.1.1, above, for areas accessible f
j topersonnelwithradiationlevelssuchthatamajorportionofthebodycould
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receive in one hour a dose greater than 1000 arem, the computer shall be l
t 1
programmed to permit entry through locked doors for any individual requiring
^
access to any such High-High Radiation Areas for the time that access is required.
l 6.1.1.3 Keys, to manually open computer controlled High Radiation Area doors i
j and High-High Radiation Area doors shall be maintained under the Administra-tion control of the Shift Supervisor on duty and/or the Health Physicist.
fl 6.1.1.4 High-High Radiation areas, as defined in 6.1.1.2 above, not equipped l
with the computerized card readers shall be maintained in accordance with 1
10 CFR 20.203 c.2 (iii), locked except during periods when access to the area 4
is required with positive control over each individual entry, or 10 CFR 20.203.c.4.
[
j In the case of a High Radiation Area established for a period of 30 days or less, 1
i direct surveillance to prevent unauthorized entry may be substituted.
Doors shall remain locked except during periods of access by personnel under an t
approved RWP which shall specify the dose rate levels in.the immediate work i
area and the maximum allowable stay time for individuals in that area.
For i
]
individual areas accessible to personnel with radiation levels such that a i
i
- Measurement made at 18" from source of radioactivity.
j LA SALLE - UNIT 2 6-15 Amendment No.19 3
e
ADMINISTRATION CONTROLS HIGH RADIATION AREAS (Continued) major portion of the body could receive in one hour a dose in excess of 1000 mrem
- that are located within large areas, such as the containment, where l
no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, con-spicuously posted and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the RWP, direct or remote, such as use of closed circuit TV cameras, continuous surveillance may be made by per-sonnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
6.2 PLANT OPERATING PROCEDURES AND PROGRAMS A.
Detailed written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:
1.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
2.
Refueling operations.
3.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.
4.
Emergency conditions involving potential or actual release of radioactivity
" Generating Stations Emergency Plan" and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an effect on the safety of the facility.
6.
Preventive and corrective maintenance operations which could have an effect on the safety of the facility.
7.
Surveillance and testing requirements.
8.
Tests and experiments.
9.
Procedure to ensure safe shutdown of the plant.
10.
Station Security Plan and implementation procedures.
11.
Fire Protection Program implementation.
12.
Process Control Program implementation.
13.
OFFSITE DOSE CALCULATION MANUAL implementation.
14.
Company Quality Assurance Program and Procedures for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, December 1977.
- Measurement made at 18" from source of radioactivity.
LA SALLE - UNIT 2 6-16 Amendment No.19
-