ML17216A518
| ML17216A518 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/29/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | City of Orlando, FL, Florida Municipal Power Agency, Florida Power & Light Co, Orlando Utilities Commission |
| Shared Package | |
| ML17216A520 | List: |
| References | |
| NPF-16-A-014 NUDOCS 8605060067 | |
| Download: ML17216A518 (5) | |
Text
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 8( 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.
14 License No.
NPF-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 8 Light Company, et al. (the licensee),
dated December 30, 1985 as supplemented March 17, 1986, 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 requirements have been satisfied.
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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.
14
, 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 Date of Issuance:
April 29, 1986 As k C. Thadani, Director PW Project Directorate ¹8 Division of PWR Licensing-B
ATTACHMENT TO LICENSE AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-389 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Pa es 3/4 1-5 Insert Pa es 3/4 1-5
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 b.
C.
The moderator temperature coefficient (MTC) shall be:
Less positive than +0.5 x 10 delta k/k/'F at
< 70K RATED THERMAL
- POWER, Less positive than +0.3 x 10 " delta k/k/'F at
> 70K RATED THERMAL
- POWER, and Less negative than -2.7 x 10 delta k/k/4F at RATED THERMAL POWER.
APPLICABILITY:
MODES 1 and 2"¹ ACTION:
With the moderator temperature coefficient outside any one of the above limits, 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 />.
SURVEILLANCF. RE UIREMENTS
- 4. l. 1.4. 1 The MTC shall be determined to be within its l.imits by confirmatory measurements.
MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
- 4. l. 1.4.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
a.
Prior to initial operation above 5X of RATED THERMAL POWER, after each fuel loading.
b.
At any THERMAL POWER, within 7 EFPD after reaching a
RATED THERMAL POWER equilibrium boron concentration of 800 ppm.
c.
At any THERMAL POWER, within 7 EFPD after reaching a
RATED THERMAL POWER equilibrium boron concentration of 300 ppm.
With K greater than or equal to 1.0.
eff
¹See Special Test Exceptions
- 3. 10. 2 and 3. 10. 5.
ST.
LUCIE - UNIT 2 3/4 1-5 Amendment No. 14
REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION
- 3. l. 1.5 The Reactor Coolant System lowest operating loop temperature (T
)
shall be greater than or equal to 515'F.
APPLICABILITY:
MODES 1 and 2¹.
ACTION:
With a Reactor Coolant System operating loop temperature (T
) less than 5154F, restore T'o within its limit within 15 minutes o'PHe in HOT STANDBY within tQ next 15 minutes.
SURVEILLANCE RE UIREMENTS
- 4. l. 1.5 The Reactor Coolant System temperature (T
) shall be determined to be greater than or equal to 5154F:
a.
Within 15 minutes prior to achieving reactor criticality, and b.
At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T
is less than 525'F.
avg
¹With K << greater than or equal to 1.0.
ST.
LUCIE " UNIT 2 3/4 1-6