ML20041D223
| ML20041D223 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/12/1982 |
| From: | Miner S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20041D224 | List: |
| References | |
| TAC-47884, NUDOCS 8203040587 | |
| Download: ML20041D223 (7) | |
Text
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a aseg'o UNITED STATES
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',i NUCLEAR REGULATORY CC)MMISSION s,
e WASHING TON, D. C. 20S65 e
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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 SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 i
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 51 License No. OPR-72 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated February 8,1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amenced (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 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 df this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8203040587 820212 PDR ADOCK 05000302 P
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. 2.
Accordingly, the license is ar. ended 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. 51, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
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/ John
. Stolz, Chief
( Operating Reactors Branc #4 W' vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 12, 1982 e
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ATTACHMENT TO LICENSE AMENDMENT'NO. 51 FACILITY OPERATING LICENSE NO. DPR-72
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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 contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain doctanent completeness.
3/4 3-2 3/4 3-3 1
3/a.3 INSTRU"INTATION 3/a.3.1 REACTCR OROTECT!ON SYSTEM INSTRUMENTATION LIMITI!:3'C0!:OITICN FOR CPEUTION 3.3.1.1 As a minimum, the Rea: or Protection System ir.strumentation channels and by; asses of Table 3.3-1 shall be OPERABLE with RESPCNSE TIMES as shewn in Table *3.3-2.
APPLIC A!!L!TY : As shewn in Table 3.3-1.
ACTION:
As shc6.n in Table 3.3-1.
SURYE!LLANCE RE!.' R E'<E NTS
- tacter Frctecticn System instrumentation channel shall 4.3.1.1.1 Ea:9 be de :nstrata: CPERA3LE by the cerformance of the CHANNEL CHECK, CbANNEL CALI5EATICN at: CHANNEL FUNCTIC':AL TEST cperations during the MCDES and at the frequercies sh:wn in Table 4.3-1.
4.3.1.1.2 The t tal by;8ss functi0n shall be de Onstrated CEERA3LE at least en e per 18 mentas during CHANNEL CALIBRATION testing of each char.nel affected by by; ass cperatien.
4.3.1.1.3 The REACTCR PROTECTiCN SYSTEM RESPCNSE TIME of ea:5 reacter tri; fun::icn shall be dem:nstrated to be within 'ts limit at least once
- er 18 m:ntns. Each tes: shall include at least ene channel per function su:n that all channels are tested at least once every N' times la mentns where 3 is the ::tal num:er of redundant channels in a s;ecific reacter tri: fun::icn. as shewn in :ne " Total No. of Channels" column of Table 3.3-1.
CRYSTAL RIVER - UNIT 3 3/ 3-1
TABLE 3.3-1 Ug REACTOR PROTECTION SYSTEM INSTRllMENTATION h
MINIMUM m
TOTAL NO.
CilANNELS CilANNELS APPLICABLE l
f
- FilNCTIONAL llNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION l
1.
I I
I, 2 and
- 8 2.
Nuclear Overpower 4
2 3
1, 2 2#
y 3.
RCS Outlet Temperature--liigh 4
2 3
1,2 3#
4.
Nuclear Overpower liased on RCS Flow and AXIAL POWER IMBALANCE 4
2(a) 3 1, 2 2#
3.
RCS Pressure--Low 4
2(a) 3 1, 2 3#
I 6.
ItCS Pressure-liigh 4
2 3
1, 2 3#
w s
7.
Variable Low RCS Pressure 4
2(a) 3 1, 2 3#
Y N
8.
Reactor Containment Pressure--liigh 4
2 3
1, 2 3#
9.
Intermediate Range, Neutron Flux and Rate 2
0 2
1, 2 and a 4
10.
Source Range. Neutron Flux and Rate A. Startup 2
0 2
2## and
- 5 1). Shutdown 2
0 1
3, 4 and 5 6
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Control llod Drive Trip lireakers 2 per trip I per trip 2 per trip I, 2 and
- 7#
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system system system 12.
Reactor Trip Module 2 per trip i per trip 2 per trip 1, 2 and a 7#
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system system system i
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13.
Shutdown Ilypass 11CS Pressure--liigh 4
2 3
2*8,3**
6#
4ee,3..
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14.
Reactor Coolant Pump Power Monitors 4
2(a,b) 3 le**,2***
3#
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TABLE 3.3-1 (Continued)
TABLE NOTATION With the control rod drive trip breakers in the closed position and the control rod drive system capable of rod withdrawal.
Then Shutdown Bypass is actuated.
For one time only, the reactor coolant pump power monitor trip function may
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be manually bypassed in Modes 1 and 2 (at less than 40% Full Power) for the duration of special testing. These tests are to be conducted following startup from the unit outage which began on January 28,1982.
The provisions of Specification 3.0.4 are not applicable.
High voltage to detector may be deenergized above 10-10 amps on both Intermediate Range channels.
(a)
Trip may be manually bypassed when RCS pressure 1 1720 psi:; by actuating Shutdown Bypass provided that:
4 (1)
The Nuclear Overpower Trip Setpoint is 15% of RATED THERMAL
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- POWER, 1
(2)
The Shutdown Bypass RCS Pressure-High Trip Setpoint of 11720 psig is imposed, and
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(3)
The Shutdown Bypass is removed when RCS pressure > 1300 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 I
(3)
Deenergizing an active Reactor Coolant Pump.
1 ACTION STATEMENTS ACTION 1 -
With the number of channels OPERABLE one less than recuired by the i
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.
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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 condition within one a.
hour.
5.
The Minimum Channels OPERABLE recuirement 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 a.3.1.1.
CRYSTAL RIVZR - (MIT 3 3/4 3-3 Amendment No. 4,51
TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued) and the inoperable 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 Either, THERMAL POWER is restricted to < 75:
c.
of RATED RATED THERMAL and the Nuclear 6ver-power Trip Setpoint is reduced to < 85% of 7
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 />.
With the number of OPERABLE channels one less than the ACTION 3 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 condition within one hour.
l b.
The Minimum Channels GPERABLE requirement is I
l met; however, one additional c' nnel 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 l
testing per Specification 4.3.1.1, and the l
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 l
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 CPERABLE one less than Action 4 required by the Minimum Channels OPERABLE requirement and with the THERMAL Power level:
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l CRYSTAL RIVER - UNIT 3 3/4 3-4 O
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