ML20039G299
| ML20039G299 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/23/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Florida Power Corp, City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, Utilities Commission, City of New Smyrna Beach, FL, City of Ocala, FL, City of Orlando, FL, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative, City of Tallahassee, FL |
| Shared Package | |
| ML20039G300 | List: |
| References | |
| TAC 47464, DPR-72-A-048 NUDOCS 8201180018 | |
| Download: ML20039G299 (7) | |
Text
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,i UNITED STATES
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',p, NUCLEAR REGULATORY COMMISSION 5
E WASHINGTON, D. C. 20555
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I 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 ORLAND0 UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT A_MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 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 December 22, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), ar.d the Commission's rules and regu;ations 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 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 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.
8201180018 811223 DR ADOCK 05000302 PDR i
. 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48, 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 the date of its issuance.
j FOR THE NUCLEAR REGULATORY COMMISSION L&
oh
. Stolz, Chief 2, pe ating Reactors Branch #4 ifision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 23, 1981 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A' Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contcin vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
3/4 3-2 3/43-3 8
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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECT!ON SYSTEM INSTRUMENTATION LIMITING ~ CONDITION F00. OPEDATION
- 3. 3.1.1 As a minimum, the Reactor protection System it.strumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table'3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE RE JIPEMENTS
- 4. 3.1.1.1 Each Peactor Protection System instrumentation channel shall be de enstrated CPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALISRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.1.2 The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALISRATION testing of each channel affected by bypass operation.
4.3.1.1.3 TheREACTORPPOTECTfCNSYSTEMRESPONSETIMEofeachreactor trip function shall be der.onstrated to be within its limit at least once per 18 months.
Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function. as shown in the " Total No. of Channels" column of Table 3.3-1.
i CRYSTAL RIVER - UNIT 3 3/4 3-1
TABLE 3.3-1 REACTOR PROTECTION SYSTfM INSTRUMENTATION 5
vi MINIMUM 12 TOTAL NO.
CIMNNELS CilANNELS APPLICABf.E FUNCTIONAL UNIT 0F CilANNELS TO TRIP OPERABLE MODES ACTION 1.
1 1
, 1, 2 and
- 8 2.
Nucicar Overpower 4
2 3
1, 2 2#
{
3.
RCS Outlet Temperature--liigh 4
2 3
1, 2 37 4.
Nuclear Overpower Based on RCS flow and AXIAL-POWER IMBALANCE 4
2(a) 3 1, 2 2#
5.
RCS Pressure--Low 4
2(a) 3 1, 2 3#
6.
RCS Pressure--liigh 4
2 3
1, 2 3#
7.
Variable Low RCS Pressure 4
2(a) 3 1, 2 3f 8.
Reactor Containment Pressure--liigh 4
2 3
1, 2 3#
9.
Intermediate Range, Neutron Flux w
and Rate 2
0 2
1, 2 and
- 4 10.
Source Range, Neutron Flux and Rate A.
Startup 2
0 2
2ff and'*
- 5 B.
Shutdown 2
0 1
3, 4 and 5 6
11.
Control Rod Drive Trip Breakers 2 per trip 1 per trip 2 per 1, 2 dnd
- 7f
{
system system trip system
, (
- 12. Reactor Trip Module 2 per trip 1 per trip 2 per 1, 2 and
- 7f g
system system trip system 13.
Shutdown Bypass RCS Pressure-liigh 4
2 3
2**,
6f
- 14. Reactor Coolant Pump Power Monitors 4
2(a,b) 3 1, 2 37 l
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TABLE 3.3-1 (C:ntinu:o)
TABLE NOTATION
- With the control rod drive trip breakers in the closed position and the control rod drive system capable of rod withdrawal.
- When Shutdown Bypass is actuated.
- The provisions of Specification 3.0.4 are not applicable.
- High voltage to detector may be de-energized above 10-10 amps on both Intermediate Range channels.
(a) Trip may be manually bypassed when RCS pressure 1 1720 psig by actuating Shutdown Bypass provided that:
(1) The Nuclear Overpower Trip Setpoint is 1 5% of RATED THERMAL
- POWER, (2) The Shutdown Bypass RCS Pressure--High Trip Setpoint of 1 1720 psig is imposed, and (3) The Shutdown Bypass is removed when RCS pressure > 1800 psig.
(b) Trip may be manually bypassed when reactor power is less than 40%
to perform the following operations:
1)
Switchover between Startup and Unit Auxiliary Transformers, 2)
Energizing an idle Reactor Coolant Pump, or 3)
De-energizing an active Reactor Coolant Pump, ACTION STATEMENTS i
ACTION 1 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the control rod drive trip breakers.
ACTION 2 -
With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided all of the following conditions are satisfied:
The inoperable channel is placed in the tripped a.
condition within one hour.
b.
The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, Amendment No.48 CRYSTAL RIVER - UNIT 3 3/4 3-3
1 TABLE 3.3-1 (Continued) i ACTION STATEMENTS (Continued) i and the ir.9perable channel above may be by-passed for up to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary to test the trip breaker associated with the logic of the channel being tested per Specification 4.3.1.1, and c.
Either, THERMAL POWER is restricted to 1 75%
of RATED RATED THERMAL and the Nuclear Over-power Trip Setpoint is reduced to 1 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the QUADRANT POWER TILT is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped conditior within one hour.
b.
The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypa. sed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, and the inoperable channel above may be bypassed for up, to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary to test the trip breaker associated with the logic of the channel being tested per Specification 4.3.1.1.
With the number of channels OPERABLE one less than Action 4 required by the Minimum Channels OPERABLE requirement and with the THERMAL Power level:
CRYSTAL RIVER - UNIT 3 3/4 3-4
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