ML19340A941
| ML19340A941 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/12/1975 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340A939 | List: |
| References | |
| NUDOCS 8009100764 | |
| Download: ML19340A941 (6) | |
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UNITED STATES f
NUCLEAR REGULATORY COMMISSION g-(,/
W ASHINGT ON. D. C. 2055 5 l
l CO3NONWEALTH EDISON COMPAhY DOCKET NO. 50-10 DRESDEN NUCLEAR PONER STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 11 License No. DPR-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 3,1974, 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; 1
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; and D.
The issuance of this mnerdment will not be inimical tc the common defense and security or to the health and safety of the public.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Facility License No. DPR-2 is hereby amended to read as follows:
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-(2) 'Icchnical Specifications lhe Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the liccuse.
1he licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto tnrough Cht:nge !!o. 30.
3.
'Diis license amendment is effective as of the date of its issuance.
FOR Tile NUCLEAR REGULATORY COTMISSION Original Signed by:
Dennis L. Ziemann Dennis L. Zicmann, Chief operating Reactors Branch c2 Division of Reactor Licensing
Attachment:
Change No. 30 to the Technical Specifications Date of issuance:
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J ATTACIMEhT TO LICENSE AMENDMENT NO.11 CHANGE NO. 30 TO THE TECHh'ICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-2 Delete pages 63 and 64 from the Technical Specifications and insert the attached replacement pages numbered 63, 63a, and 64.
The changcs on the revised pages are shown by marginal lines.
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3.5 LIMITING CONDITION FOR OPERATION 4.5 SURVEIIJ.ANCE REQUIREMENT 12.
If the requirements of 3.5.A
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i ann t be.m t, an orderly shutdown 30 of the reactor shall be initiated and the reactor shall be.in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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i Bases:
3.5 Dresden Unit 1 is provided with a spray type, such as redundant valves, post incident cmergency core cooling system for use in the pumps, etc.
cvent of a serious loss-of-coolant accident.
Supplement E to Chango !!o. 17 provides an The periodic testing intervals are specified ana lysis which shows that the core spray to provide a monthly test of al] pumps and system in conjunction with the isolation valves in the post incident (core and containment) condenser and fecdwater system limits peak cooling system.
These tests are to verify clad temperatures to 1 css than 2300*F.
Metal operability only and not to determine capability water reactions are limited to 1 css.than 1%
of the component to perform its intended by the above sys:cus.
function.
Capability tests, such as flow tests of the core spray pumps, are performed The core spray system piping enters through each refueling outage.
This interval is i
the reactor vessel head and therefore the adequate since no changes to the system are
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sytems is only operable'when the reactor head foreseen following ins,tallation.
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in in place.
The corc~ spray system gets its I
water from the station fire main system. This The operability of the primary reactor feedwater system obtains-its water from the Unit 1 system provides added assurance that feedwater 30 screen wash pumps, Unit 2/3 service water will be available to supplement the core spray pumps or the Unit 1 or Unit 2 diesel driven system for small to intermediate size loss-of-fire pucps.
The latter pumps are for escrgency coolant accidents, use if off-site power is lost.
The allowabic repair times were arrived at by a consideration of the redundancy of components and reliability of performing the intended function if required.
The core spray system has 3 pumps, any 2 of which are capabic of supplying the required flow.
Thus, if one pump is out of service, no additional failure could be tolerated.
Thus, an out of service time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is specified.
This is true for other components l '
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64
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