ML19273B266
| ML19273B266 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/07/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19273B263 | List: |
| References | |
| NUDOCS 7904060052 | |
| Download: ML19273B266 (8) | |
Text
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UNITED STATES NUCLE AR REGULATORY COMMISSION 3-
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WASHINGTON, D. C. 20666 I
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 21, 1978 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-ments have been satisfied.
7904060052
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this lict lse amendment and paragraph 2.C.(2) of Facility License No. OPR-39 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are hereby incorporated in the license. 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 REGULATORY COMMISSION (ftf W O W A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Oate of Issuance.
March 2,1979
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-304 ZION STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-48 1.
The "' clear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 21, 1978 complies with the standards and requirements of the Ttomic Energy Act of 1954, as amended (the Act), and the Comm.ssion's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is ruasunable 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 Commission's regulations and all applicable require-ments 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 License No. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, are hereby incorporated in the license. 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 REGULATORY COMMISSION t'O&d S L A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 2, 1979
ATTACHMENT TO LICENSE AMENDMENTS 43 TO FACILITY OPERATING LICENSE FJ. DPR-39 AMENDMENT NO.
AMENDMENT NO.40 TO FACILITY OPERATING LICENSE NO. OPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:
Insert Revised Pages Remove Pages 244 244 245 245 248 248
SURVEILLANCE REQUIRE.v.EW
- M:T:::G CC'QITIO : FGR CPEPATIO!;
(,
3.13.1.B fuel is in the reactor, neutron 4.13.1 I
flux shall be monitored continuously l
by at least one source range neutron monitor with both visual and audible indication.
I C.
Not applicable C.
The movement of an irradiated fuel l
assembly in the reactor core shall i
not begin until the reactor has l
been suberitical for a period of D.
The operation of at least one i
at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
RER pump and heat exchanger shall be verified once a shift.
D.
At least one RHR pump and heat exchanger shall be in operation Com:r.anication between the control E.
during a refueling operation.
room and the containment shall be verified before any alteration E.
Direct cournunication between the of the reactor core begins.
control room and containment shall be operable.
F.
Not applicable.
F.
A licensed fuel handling foreman or licensed senior reactor operator shall be present at the reactor cavity during any movement of fuel within the containment.
2.
Fuel drop protection 2.
Fuel drop protection The implementation of the charcoal The auxiliary building ventilation system filter ventilation mode shall be shall be operating in the charcoal filter mode verified and logged once a shift whenever irradiated fuel is being handled.
during fuel handlino operations.
Amendment No. 43 (Unit 1)
Amendment No. 40 (Unit 2) 2 44
SURVEILI.ANCE REQUIREME
- .:.v1TI!;G CO OITIO!; FCR OPERATIO!;
lN 3.13.3 Containment state 4.13.3.
Containment status Containment door status shall be A.
During refueling operations.
A.
I containment integrity (See section verified once a shift.
1.0.C) shall be mair.tsined as specified in section 3.9.5 except as specified in 3.13.3.B.
B.
The equipewnt hatch or both doors B.
Reactor coolant boron concen-tration and Tavg shall be on the personnel hatch may be verified once a shift when the opened during the refueling oper-equipment hatch is open or both ation provided the shutdown margin doors on the personnel hatch are is maintained equal to or greatef than 10% AK/K and Tagg is maintained open.
at or less than 140 F.
Amendment No. 43 (Unit 1)
Amendment No. 40 (Unit 2) 245
Bases:
3.13 The restriction on shutdown margin The presence of a licensed fuel handling insures adequate core protection foreman or senior reactor operator at the that no inadvertent retuen to criti-refueling cavity provides qualified super-cality could occur through control rod vision of the refueling operation during removal.
(1) changes in core geccetry.
Two source range neutron monitors The charcoal filters in the ventilation continuously measuring neutron flux train from the fuel building insure that during fuel movements provides the site boundary doses will be below 10CFR100 operacors with immediate redundant limits assuming all rods on a dro;. ped fuel indication of an unsafe condition.
When-assembly break during a postulated fuel drop ever changes are not being made in the accident.
(3)
The containment, fuel building, core geocetry one flux monitor is and radiation monitoring requirements insure sufficient.
This permits maintenance the capablity to isolate these areas from the environment in the event of an activity of the instrumentation.
release from the fuel.
The fuel handling accident assumes that the first fuel assembly is moved The verification of fuel handling system 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after initial reactor chut-interlocks prior to refueling operation provides assurance that an unsafe operating down.
(2) condition will not be approved. (1)
The operation of one residual heat fuel inspection program is intended to removal pump system assures that a The uniform boron exists in the primary provide information on anomalous conditions of the fuel resulting from power operation.
The system and that decay heat will be results of the visual examinations and the tests removed.
for failed fuel will be reviewed as a basis Direct coenunication between the for determining the requirements for further control room and the containment allows off-site destructive fuel examinations.
FSAR the control room operator to inform the Section 3.2.3.5.4 provides further discussion manipulator operator of any impending on the fuel inspection program.
unsafe condition detected from the main control board indicator during fuel movement.
(3)
FSAR, Section 14.2.1.5 (1)
FSAR, Section 9.7.2 (2)
PSAR, Section 14. 2.1. 2 Amendment No. 43 Unit 11 248 Amendment No. 40 Unit 2)