ML20069E422
| ML20069E422 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/27/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069E424 | List: |
| References | |
| NUDOCS 9406070182 | |
| Download: ML20069E422 (7) | |
Text
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pa nog i-S UNITED STATES
(
NUCLEAR REGULATORY COMMISSION
/
WASHINGTON. D.C. 20555 0001 g.....f FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE-CITY OF KISSIPMEE -
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 SEMIN0LE ELECTRIC COOPERATIVE. INC.
CITY OF TALLAHASSEE
- DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING-LICENSE bP 2-l c
e o 1.
The Nuclear Regulatory Comission,(the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated May 19, 1994,. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and.the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate'in conformity with the-application, the e
provisions of the Act, and the -rules 'and regulations of the-Comission; 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 Comission's regulations;-
D.
The issuance of this amendment will not be inimical to the comon-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 Comission's _ regulations and all applicable requirements have J
been satisfied..
F 1
9406070182 940527 PDR ADOCK 05000302 P
PDR n
. 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 Soecifications The Technical Specifications contained in Appendices'A and B, as revised through Amendment No.150, 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 A
V.
l l1 '
fitG 2 Herbert 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: May 27, 1994
i i
ATTACHMENT TO LICENSE AMENDMENT NO. 150 FACILITY OPERATING LICENSE NO.~DPR-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 Insert 3.3-23
- 3.3-23
~3.3-25 3.3-25
.B 3.3-77 8 3.3-77 i
B 3.3-81 B 3.3,
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Source Range Neutron Flux 3.3.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
(continued)
B.4 Verify SDM is I hour 2 1% Ak/k.
MQ Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter i
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.9.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.9.2
NOTE--------------------
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
18 months SR 3.3.9.3 Verify at least one decade overlap with Once each intermediate range neutron flux channels.
reactor startup prior to source range counts exgeeding l
10 cps if not performed within the previous 7 days Crystal River Unit 3 3.3-23 Amendment No.150
3 Intermediate Range Neutron Flux 3.3.10 4
s SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.10.2
NOTE--------------------
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
18 months e
4 SR 3.3.10.3 Verify at least one decade overlap with once each power range neutron flux channels.
reactor startup prior to intermediate range indication exceeding IE-5_ amp if not l
performed within the previous 7 days i
Crystal River Unit 3 3.3-25 Amendment No. 150 i
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, Source Range Neutron Flux B 3.3.9 BASES SURVEILLANCE SR 3.3.9.2 (continued)
REQUIREMENT!
any failures in the detectors will be_ apparent as change in channel output. The Frequency of 18 months is based on op9 rating experience and industry-accepted practice.
SR 3.3.9.3:
SR 3.3.9.3 is the verification of one decade of overlap between source and intermediate range neutron flux instrumentation. The SR is required to be performed prior 8
to source range count rate exceeding 10 cps if it has not been performed within 7 days prior to reactor startup.
Failure to verify one decade of overlap on one or more source range channels requires the plant to be maintained in subcritical condition until the verification can be made.
This ensures a continuous source of neutron power indication during the approach to criticality. The verification may be i
omitted if performed within the previous 7 days. The 7 day portion of the Frequency is based on operating experience, which shows that source range and intermediate range instrument overlap does not change appreciably over this time interval.
i REFERENCES None.
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Crystal River Unit 3 B 3.3-77 Amendment No. 150
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Intermediate Range Neutron Flux B 3.3.10 j
BASES SURVEILLANCE SR 3.3.10.2 (continued) i REQUIREMENTS The SR is modified by a Note excluding neutron detectors from CHANNEL CALIBRATION.
It is not necessary to test the detectors because generating a meaningful. test signal is difficult.
In addition,. the detectors are of simple construction, and any failures in the detectors will be apparent as a change in channel output. The 18 month Frequency is based on operating experience and industry-i accepted practice.
SR 3.3.10.3 SR 3.3.10.3 is the verification of one decade of overlap between intermediate and power range neutron flux instrumentation. The SR is required to be performed prior to intermediate range indication exceeding IE-5 amp if it has not been performed within 7 days prior to reactor startup. Failure to verify one decade of overlap on one or more channels requires the plant to remain in a condition where the intermediate range channels provide adequate indication until the verification can be made. This ensures the power range nuclear instrumentation is functioning properly prior to the transition to this range of indication.
The test may be omitted if performed within the previous 7 days. The 7 day portion of the Frequency is based on operating experience, which shows that intermediate range i
instrument overlap does not. change appreciably over this time interval.
REFERENCES None.
Crystal River Unit 3 B 3.3-81 Amendment No. 150 g