ML20056C049
| ML20056C049 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/09/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056C048 | List: |
| References | |
| NUDOCS 9206160186 | |
| Download: ML20056C049 (6) | |
Text
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIl l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 138 License No. DPR-39 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 26, 1991, as supplemented March 27, April 3, and April 10, 1992, complies Mith the standards and l
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; 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 Comission'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-39 is hereby amended to read as follows:
2 0 & l b O l Wh u-
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- (2)
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised throu the license. gh Amendment No. 138, are hereby incorporated in The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATO COMMISSION Richar J. Barrett, 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: June 9, 1992 N
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 127 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 26, 1991, as supplemented March 27, April 3, and April 10, 1992, 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; 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 i
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-48 is hereby amended to read as follows:
t
.- (2)
Technical Soecifications The Technical Specifications contained in Appendices.A and 8, as revised through Amendment No. 127, are hereby incorporated in the license. The licensee shall cperate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULAT RY COMMISSION Richar
. Barrett, 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: June 9, 1992 i
a ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.138 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO,127 TO FACILITY OPERATING LICENSE HO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the page identified.
below and inserting the attached page. The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
Remove Paces Insert Paoes 2
2 I
4
).0 DEFINITIONS CKaNNEL_[UNC[IQNAL_IESI CONT 61NMENT_INTEGR((y shall exist when:
(Continued)
A CHANNEL FUNCTIONAL TEST shall be:
1.
Capable of being closed by an OPERABLE automatic containment isolation valve system, a.
Instruments - The injection of a simulated or signal (s) into the channel as close to the 2.
Closed by manual valves. blind flanges. or primary sensor (s) as practicable to verify deactivated automatic valves secured in their OPERABILITY, including all channel outputs, as closed positions, except for valves that are appropriate.
open under administrative control as permitted by Specification 3.9.3.
b.
Logics - The application of input signals, or the operation of relays or switch contacts, in b.
Equipment hatch is closed.
all the combinations required to produce the required decision outputs including the c.
At least one door in each air lock is closed and operation of all ACTUATION DEVICES.
Hhere sealed.
practicable, the test shall include the operation of the ACTUATED EQUIPMENT as well d.
Containment leakage satisfies Specification 3.10.
(i.e. pumps will be started, valves operated, etc.).
e.
Penetration pressurization systems are in service as required by Specification 3.9.2.
c.
Digital channels - The injection of a simulated signal (s) into the channel as close to the
'l.12 CONilHUQUS_RELE6SE sensor input to the process racks as practicable to verify OPERABILITY Including A CONTINUOUS RELEASE is the discharge of liquid or alarm and/or trip functions.
gaseous wastes of a nondiscrete volume; e.g., from a volume or system that has an input flow during the
)CQtf0SIIE_SAMP_LE release.
A COMPOSITE SAMPLE is one in which the quantity of 1.13 CONIBQLLEQ_ LEAKAGE liquid sample is proportional to the quantity of Ilquid waste discharged and in which the method of CONTROLLED LEAKAGE shall be the seal water flow from sampilng employed results in a specimen which is the reactor coolant.nump seals.
i representative of the liquids released.
1.14 CORE _8LIERA110N CQHIAIHMEHLIMIEGRLII shall exist when:
CORE ALTERATION shall be the movement or manipulation a.
All penetrations required to be closed during of any component within the reactor pressure vessel accident conditions are either:
with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe l
conservative position.
1 2
Amendment Nos.138 and 127
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