ML20247M121
| ML20247M121 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/30/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247M124 | List: |
| References | |
| NUDOCS 8906020366 | |
| Download: ML20247M121 (9) | |
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UNITED STATES l'
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[,g NUCLEAR REGULATORY COMMISSION
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FLORIDA POWER CORPORAT10f' CITY OF' ALACHUA CITY 0F OUSHNELL CITY OF GAlhE5VILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSIOh AND CITY OF CRLANDO SEBRING UTILITIES COMill5SION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHA5SEE DOCKET fl0. 50-302 CRYSTAL RIVER UNIl 3 UUCLEAR GEtERATING PLANT AMENDMENT TO FACILITY OFERATING LICEKSE Amendment Ho.115 License No. CPR-72 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Florida Pcwer Corporation, et al.
(the licensees) deted JLae 22, 1983, as superseded April 25, 1988, and ciarified f4 arch 31,1989 con. plies with the standaros and requirements of the Atcmic Energy Act of 1954, as acnded (the Act), ana the Cemission's rules and regulations set forth in 10 CFR Chapter 1; 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
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E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Commission's regulations and cil applicable requirements have beer, satisfied.
4 8906020366 890530 PDR ADOCK 05000302 p
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. ll5, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordar,ce with the Technical Specification.s.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Y Herbert N. Berkow, Directcr Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation Attachnent:
Ct,anges to the Technical Specifications Date of Issuance:
P. y 30, 1989
ATTACHMENT TO LICENSE AMENDMENT NO.11_5_
1 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET N0. 50-302 i
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.
The corresponding overleaf. pages are also'provided to maintain docunent completeness.
i Remove Insert IV IV 3/4 3-55 3/4 3-56 B3/4 3-6 B3/4 3-6 i
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M imTne enemms e om:riou no stv.mm:2 mwnens-SECTICU PAE
.3/4.2 PCEER DIFIRIETICH LDGTS 3/4.2.1-AXIAL TOWIR IMBAIANCE 3/4 2-1 3/4.2.2 : NUC22AR HEAT H17X H7T CHANNEL FACIIR - Tg
'3/4 2-4 3/4.2.3 NUC2 EAR DCHAIH!Y RISE }CT CHANNEL FACER-@
3/4 2-6 3/4.2.4 QCA3WTT PCEER TILT 3/4 2-8 3/4.2.5 DiB PAPATERS 3/4 2-12 3/4.3 D4FFJMDTD2 ION 3/4.3.1 ~ REACIDR Wum.;uCH SYSTEM INSIRNDUATICH 3/4 3-1 3/4.3.2 DGINEECD SAFETY FEAIURE ACIDATICH SYFTDi E N Cri 3/4 3-9~
3/4.3.3
}ChTIORDC INSIRUMDTDCICU Radiaticri Manitorizg Ins +mtation 3/4 3-22 hre Detectors 3/4 3-26 Seimic Ins +mtation 3/4 3-28 Metacrological Ins *mtation
'3/4 3-31 Rente Shut &un Instzunentation 3/4 3-34 Post-accident Instzunen*ation 3/4 3-37 Fire Detection Instrumentation 3/4 3-40 Radioactive Liquid Effluent Mer11toring Instrumentation 3/4 3-42 Radioactive Fa-Efflued Marlitarirg Instrumentation 3/4 3-47 Wasta Gas Decay Tank - Explosive Gas
?bnitorirg Instzu'entation 3/4 3-53 Toxic Gas.Sys+Jms Chlorine Detection 3/4 3-55 Sulfur Dicxide Detmetion 3/4 3-56 CRYFTAL RIVER-UNTT 3 IV Amen $nant No. 7 3,3R, f P.115
INDEX
~ LIMITING CONDITIONS FCR OPERATION AND SURVEILLANCE nEOL2EMENTS SECTION -
- Pac,
- /4.4' REACTOR COOLANT SYtT**8
-3/4.4.1 REACTOR COOLANT LOOPS 3/4 L1 3/4.4.2 RELIEF VALVES - SHUTDOWN 3/4 L3 3/4.4.3 RELIEF VALVES - OPERATING 3/4 L4
~ Code Safety Valves 3/4 E4 Power-operated Relief Valve 3/4 4-4a CRYSTAL RIVER. UNIT 3 IVa
/cendment No. 69
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1 DLNQi 70XIC GAS SYSTTDG - CHLDPlNE urwanOf I
LMU CnfDITIOf FOR OPEDATIOf 3.3.3.11.1 Two irdef=de.nt chlorine detection systes, with their alarrVtrip setpoints adjusted to actuate at a cidorine concentration of less than or equal to 5 ppm, shall be OPERAB2.
APPLICABILITY: All PODES ACTIQi:
a.
With one chlorine detection sys*m inoperable, restore the inoperable detection systa= to OPERABE status within 7 days or within the ne>:t 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and reintain operation of the Contzel Rocn ventilation systen in the recirculation mode of op m tion using the norral duty fans.
b.
With both ciderine detection systers inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain cperation of the Control Rocn ventilation sys's in the recirculation mode of operation usirg the normal duty fans.
c.
'Ibe prtuisions of Specification 3.0.4 are not applicable.
SmTIIIANT Pm*Irm?IS 4.3.3.11.1 Each chlorine detection system shall be demonstrated OPERABE by performance of a OWOEL OECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a OWOEL FUNCTIQU1 TET at least once per 31 days and a OWOEL CALIBPATIai at least once per 18 ron+As.
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CRYSTAL RIVER-UNIT 3 3/4 3-55 Anents'Tt No. II E
DEIH2(ENDTIQ4 TDXIC GAS SYstrDE - SUT1rR DioXIDF 1m:nm twrrING cnmTTTON mR opEPATION 3.3.3.11.2
'No independent sulfur dicacide detection systats, with their~
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alam/ trip setpoints adjusted to actuata at a sulfur dicacide wad. ration of less than or equal to 2.4 ppn, shall be OPERABT.E.
APPLICABIUTY: All MXES
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ACTIQ 1:
With one sulfur dioxide detection system inoperable, restore the a.
irxperable detection systan to 01TRAB!.E status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operatico of the Cbntrol Ibcn ventilation system in the recirculation made of operation using the norral duty fans.
b.
With both sulfur dioxide detection sys*ams inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate ard maintain operation of the Control Rocn ventilation system in the recirculation node of operation usirq the normal' duty fans.
'Ihe provisicms of Specification 3.0.4 are not applicable.
c.
St*F",'EIll#77 PlrCILND7IS 4.3.3.11.2 Each sulfur dioxide detection system shall be de.w. h ted OPERABII by performance of a QWOEL OECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a OWciEL FUCTIONAL TEST at least anoe per 31 days and a OWCEL CALIBR;u~10N at least once per 18 conthsi.
GYSTAL RnTR-UhTI 3 3/4 3-56 Ame. h No. 115
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s's Bases Figure 3 2 incore instrumentation Specifiartson Acceptaby Minimum OUADRANT POWER TILT Arrangement CRYSTAL RIVER - UNIT 3 8 3/4 3 5
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3/4.3 DEIR1MENDJICH ELcIs 3/4.3.3.8 RADIOACTIVE LICUID DTI1TTT DFIWJMENDJIO7
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The radioactive liquid affluent instnanentation is prwided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents darirg actual or potential r31a===c of liquid affluents. The alart/ trip setpoints for these instruments -shall be calculated in accordance with the proostares in the OmITE DOSE CAICJIATIG4 MANUAL (ObcM) to ensure that the alare/ trip will occur prior to w big the lir.its of 10 C2R Part 20. The OPERABILITY and use of this instrumentation is consistent with the zucpirwments of General Design Critaria 60, 63 arri 64 of Appendix A to 10 C22 Part 50.
3 /4. ?. 3. 9 PADICAtTI\\T GASIUJS DTILT7T DSTRUMD7DJIai The radioactive g=came effluent instrumentation is prwided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents darirg actual or potential relaacas of <Ja=ama effluents.. The alarc/ trip setpoints for these instruments are calculatal in ao:ordance with the proostJres in the OMITT DOSE CAIDJIATION MANUAL (OCCM) to ensure that the alarn/ trip will occur prior to eWhig the irr.its of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Apperriix A to 10 CFR Part 50.
3/4'3.3.10 WESTE GAS DE1 ( TMIK - EXPIMIVE GAS PONITORDC DsIRv.D7DJIai The OPERASILTTY of the Waste Gas Decay Tank explosive gas monitoring instrumentation or the samlirg and analysis program reqaired by this specification prwides for the monitorirg (and ocritrulling) of potentially erlosive gas mixtures in the Wasta Gas Decay Tanks.
3/4.3.3.11 TCXIC GAS SYSTEMS The OPERABILITY of the tox.ic gas systams ensures that sufficient capability is available to pzwytly detect and initiate protective action in the ar/ent of an accidental toxic gas release. This capability is reqaired to protect control rocn personnel and is consistent with guidance prwided in Tegalatory Guide 1.78, "Assur:pticris for Evaluating the Habitability of a Nuclear Power Plant During a Postulated Chemical Release", June 1974 and Esgalatory Guide 1.95, "Protecticri of Nuclear Power Plant Control Bocc Optors Against an Accidental Chlorine Release", Revision 1, January 1977.
The chlorine detection syrtam is designed so that a ctilorine aanmntration of 15 p.czn by volume is not a-4ad in the oorfJol rocn within 2 mirutas after detection.
The sulfur dioxide detecticri sys*am is designed so that a sulfur dioxide con:entration of 40 ppr by volume is not *M in the control rocn within 2 mirutes after detection.
GYFDL RIVER-UNIT 3 B 3/4 3-6 Amendnent No. H.115
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