ML17222A613
| ML17222A613 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/19/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17222A614 | List: |
| References | |
| NUDOCS 8812200204 | |
| Download: ML17222A613 (5) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 FLORIDA POWER
& LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
38 License No.
NPF-16 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power
& Light Company, et al. (the licensee),
dated October 20,
- 1988, as supplemented November 21, 1988, 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; 8.
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 requirements have been satisfied.
38i2200204 88i2i'9 PDR
'ADOCK 05000389 P ",...
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2.
Accordingly, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:
{2)
Technical S ecifications The Technical Specifications contained in Appendices A
and B, as revised through Amendment No. 38
, 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
Attachment:
Changes to the Technical Specifications erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 19,'1988
ATTACHMENT TO LICENSE AMENDMENT NO.
38 TO FACILITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-335 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Pa e
3/4 1-24 Insert Pa e
3/4 1-24
REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS -
SHUTDOWN LIMITINQ CONDITION FOR OPERATION
- 3. 1.3.3 At least one CEA position indicator channel shall be OPERABLE for each shutdown or regulating CEA not fully inserted.
APPLICABILITY:
MODES 3", 4," and 5".
ACTION:
With less than the above required position indicator channel(s)
- OPERABLE, immediately open the reactor trip breakers.
SURVEILLANCE RE UIREMENTS 4.1.3.3 Each of the above required CEA position indicator channel(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.
With the reactor trip breakers in the closed position.
ST.
LUCIE - UNIT 2 3/4 1-23
REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length (shutdown and regulating)
CEA drop time, from a fully withdrawn position,'shall Ue less than or equal to 3.1 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90K insertion position with:
a.
T greater than or equal to 515'F, and b.
All reactor coolant pumps operating.
APPLICABILITY:
MODES 1
and 2.
ACTION:
a ~
b.
With the drop time of any full-length CEA determined to exceed the above limit:
l.
If in MODE 1 or 2, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or 2.
If in MODE 3, 4, or 5, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2.
With the CEA drop times within limits but determined at less than full reactor coolan. flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.
SURVEILLANCE RE UIREMENTS
- 4. 1.3.4 The CEA drop time of full-length CEAs shall be demonstrated through measurement prior. to reactor criticality:
'a ~
b.
C.
For all CEAs following each removal and installation of the reactor vessel
- head, For specifically affected individuals CEAs following any main-tenance on or modification to the CEA drive system which could affe'ct the drop time of those specific
- CEAs, and At least once per 18 months:
ST.
LUCIE - UNIT 2 3/4 1-24 Amendment No. )S