ML17352A408
| ML17352A408 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/11/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17352A409 | List: |
| References | |
| NUDOCS 9402010398 | |
| Download: ML17352A408 (9) | |
Text
go~ R<<oc Wp0 Cy I
0O
/~i7 0p*~4 UNITED STATES NUCLEAR REGULATORY COIVIIVIISSION WASHINGTON, D.C. 20555.0001 FLORIDA POWER AND LIGHT COMPANY DOCK NO. 50-250 TURK Y POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No.
DPR-31 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated October 4,
- 1993, 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.
94020i0398
'WOiii'DR ADOCK 05000250I
PDR P
c~
J P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.
DPR-31 is hereby amended to read as follows:
(B)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.158
, are hereby incorporated in the license.
The Environmental Protection Plan contained in Appendix B is hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 11, 1994
4<~uC Wp0
@1~
+**y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.
4 AM NOMEN TO FACI ITY OPERATING LICENSE Amendment No. 152 License No.
DPR-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated October 4,
- 1993, 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.
DPR-41 is hereby amended to read as follows:
(B)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 152, are hereby incorporated in the license.
The Environmental Protection Plan contained in Appendix B is hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and
'hall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
january 11, 1994
TTACHMENT TO LICENSE AMENDMENT M NDM NT NO, 158 ACILITY OPERATING LICENSE NO.
DPR-31 M NDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-41 DOCKET NOS.
50-250 AND 50-251 Revise Appendix A as follows:
Remove a es 3/4 6-2 B 3/4 6-1 Insert a es 3/4 6-2 B 3/4 6-1
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6. 1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to La, 0.25K by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 49.9 psig.
b.
A combined leakage rate of less than 0.60 La for all penetrations and valves subject to Type B and C tests, when pressurized to Pa.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With either the measured overall integrated containment leakage rate exceeding 0.75 La or the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall inte-grated leakage rate to less than 0.75 La and the combined leakage rate for a11 penetrations subject to Type B and C tests to less than 0.60 La prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE RE UIREMENTS 4.6. 1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
a.
Type A test shall be performed at a pressure not less than Pa, 49.9 psig, in accordance with 10 CFR 50 Appendix J, as modified by approved exemptions.
TURKEY POINT - UNITS 3 EL 4 3/4 6-2 AMENDMENT NOS 158AND 152
3 4.6 CONTAINMENT SYSTEMS BASES 3 4.6. 1 PRIMARY CONTAINMENT 3 4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.
This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.
3 4.6. 1.2 CONTAINMENT LEAKAG The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident
- pressure, P
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L
during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50, as modified by approved exemptions.
3 4.6. 1. 3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door interlock may provide the required locking.
In addition, the outer air lock door is secured under administrative controls.
3 4.6. 1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that:
(1) the containment structure is prevented from exceeding its design negative pressure differential of 2.5 psig with respect to the outside atmosphere, and (2) the containment peak pressure does not exceed the design pressure of 59 psig during LOCA conditions.
The maximum peak pressure expected to be obtained from a LOCA event is 49.9 psig assuming an initial containment pressure of 0.3 psig.
An initial positive pressure of as much as 5 psi would result in a maximum containment pressure that is less than design pressure and is consistent with the safety analyses.
TURKEY POINT UNITS 3 5 4 B 3/4 6-1 AMENDMENT NOS 158AND 152