ML20212B674
| ML20212B674 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/13/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212B679 | List: |
| References | |
| NUDOCS 9909200197 | |
| Download: ML20212B674 (5) | |
Text
V
'e' pn naf
[
8%
UNITED STAT IS j-
{j NUCLEAR REGULATORY COMMISSION
'C WASHINGTON, D.C. 2055W1
\\...../
FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION.
CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE. INC.
CITY OF TALLAHASSEE l
DOCKET NO. 50-302 l
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE
~~
j Amendment No.187 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al. (the licensees), dated May 17,1999, complies with the standards and reauirements 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 9909200197 990913 PDR ADOCK 05000302 P
PDR a
1
. 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 2.C(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.187, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION D
Sheri R. Peterson, Chief, Section 2 Project Directorate !!
Division of Project Licensing Management Office of Nuclear Reactor Regulation Attachnent: Changes to Technical Specifications Date of issuance: September 13, 1999 l
I l
I ATTACHMENTTO' LICENSE AMENDMENT NO.187 TO FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302
- Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pace Insert Pace 3.3-21 3.3-21 B 3.3-71 B 3.3-71 4
l l
E EDG LOPS 3.3.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE f
FREQUENCY SR 3.3.8.1
NOTE--------------------
When EDG LOPS instrumentation is placed in an inoperable status solely for performance of this Surveillance, entry into associated Conditions and Required Actions is not required provided the applicable Condition (s) and Required Actions for the EDG made inoperable by EDG LOPS are entered.
J Perform CHANNEL FUNCTIONAL TEST.
NOTE--------------------
Voltage sensors may be excluded from j
CHANNEL CALIBRATION.
)
1 Perform CHANNEL CALIBRATION with setpoint 18 months Allowable Value as follows:
a.
Degraded voltage 2 3933 and s 3970 V with a time delay of 5.0 seconds i 0.5 seconds; and 1
b.
Sudden loss of voltage from full voltage to 0.0 V with a time delay of 7.8 seconds z 0.55 seconds at 0.0 V.
1-Crystal River Unit 3 3.3-21 Amendment No. 187
W:
E EDC LOPS 5.3.8
. BASES ACTIONS W
li-
.(continued)
Condition' C is the default Condition should Required Action A.1;orf B.1 not be met within the associated Completion Time.
Required Action 1C.1 ensures that Required Actions for affected diesel generator inoperabilities are initiated.
Depending on MODE, the Actions specified in LCO 3.8.1, "AC Sources-Operating," or LCO 3.8.2, are required to be entered'immediately.
SURVEILLANCE SR 3.3.8.1 REQUIREMENTS q
l A CHANNEL FUNCTIONAL TEST is performed on each required EDG
{
LOPS channel to ensure the entire channel will perform the intended function. This test ensures functionality of each channel to output relays.
'The Frequency of 31 days is considered reasonable based on the reliability of the components and on operating 1
. experience, j
A Note has been added to allow performance of the SR without f
taking the ACTIONS for inoperable instrumentation channels l
j although during this time period the relay instrumentation cannot initiate a diesel start. This allowance is based on the assumption that the EDG is maintained inoperable during this functional test and the appropriate actions for the inoperable EDG are entered.
- a.-
i i
(continued)
{
l Crystal River Unit 3:
B 3.3-71 Revision No.187 t