ML20247H365
| ML20247H365 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/22/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247H369 | List: |
| References | |
| NUDOCS 8905310220 | |
| Download: ML20247H365 (17) | |
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,'o UNITED STATES 4
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{ p') c NUCLEAR REGULATORY COMMISSION e(
5-j WASHINGT ON, D. C. 20555 0; +
a g*v f FLORIDA POWER CORPORATION j
CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESEURG CITY OF NEW SMYRNA BEACH AND UTILITIES C0tiltISSION, CITY OF NEW SMYRiiA BEACH CITY OF OCALA ORLANDO UTILITIES CCMMISSIOh AND CITY OF ORLAND0 SEBRING UTILITIES C0lti;ISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE i
DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 LUCLEAR GEhERATING PLANT AtENDMENT TO FACILITY OPEPATING LICENSE Amendment No.114 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for arrendment by Florida Power Corporation, et al.
(the licensees) dated March 31, 1983, as supplemented June 22, 1983, and application dated December 31, 1984, as superseded April 25, 1988, dnd revised November 28, 1988, complies with the standards and requirements of the Atomic Energy /sct of 1954, as arrended (the Act),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 ano 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 co' mon 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 been satisfied.
P
1 2.
Accordingly, the license is amended by changes to the Technicel Specifications as indicated in the attachment to this license acendment, i
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. 114, are hereby incorporated in the l
license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately and shall be implemented within 30 days of date of issuance.
FOR THE NUCLE REGULATORY COMMISSION 1
h Herbert fl. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 22, 1989
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ATTACHMENT TO LICENSE AMENDMENT N0.114 i
FACILITY OPERATING LICENSE N0. 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.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 1-2 1-2 3/4 6-1 3/4 6-1 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 3/4 6-19 3/4 6-19 3/4 6-20 3/4 6-20 3/4 6-21 3/4 6-21 3/4 6-21a 3/4 6-21a B3/4 6-4 B3/4 6-4 i
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1.0 DEFINIT 80NS-DJrINEDTERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughcut these. Technical Specifications.
THERMAL POWER.
l.h ~ THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.-
RATED THERMAL POWER 1.3 ' RATED. THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2544 MW:.
0,PERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combina-tion of core reactivity condition, power level and average reactor coolant' temperature specified in Table 1.1.
t ACTION.
1.5 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.
l OPERABLE - OPERABILITY
'l 1.6 A system, subsystem, train, component or. device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, nomal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component i
or device to perform its function (s), are also capable of performing their related sup' ort function (s).
p CRYSTAL RIVER - UNIT 3 1-1 Amendment No. 41 i
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M FINITIW S REPORD4E EVINT:
1.7 A REFORDRIE EVENT shall be any of those conditions specified in Secticri 50.73 to 10 CFR Part 50.
CNIAINMD7T INTEGRITY:
1.8 CNIAINMENT INTEGRITY shall exist when:
All pw=Lations required to be closed during accident a.
conditions are either:
1.
Capable of being closed by an OPERABIE containment autenatic isolation system, or 2.
Closed by manual valves, blind flanges, or deactivated autenatic valves secured in their closed positions, except those approved to be ep=i-2 under administrative ebuls, b.
All Mi==nt hat &ns are closed and sealed, Each airlock is OPERABIE pursuant to Specification 3.6.1.3, c.
d.
'Ihe containment leakage rates are within the limits of Specification 3.6.1.2, and
'Ihe sealing mectenism associated with each p=r-Latieri (e.g.,
e.
welds, bellows or 0-rirgs) is OPERABIE.
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WANNEL CAIZERATION 1.9 A GANNEL CAI2BRATICN shall be the adjustaant, as pammamary, of the channel output such that it r pcius with namammary range and accuracy to known values of the parameter whid the channel monitors. 'the WANNEL CAIIBRATIN shall ermTama the entire dannel including the sensor and alarm and/or trip functions, and shall include the CHANNEL ITNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total dannal steps sucts that the entire dannel is calibrated.
GANNEL CHECK 1.10 A CHANNEL WECK shall be the qualitative assessment.of channel behavior during operation by observaticri.
'Diis de arnination shall include, r
where possible, ocuparison of the dannel indication and/or status with other indications and/or status derived frun irdep 4-ut instrument channels - @ the same parameter.
CRYS'IAL RIVER - UNIT 3 1-2 Amendment No. 99. II4 m
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A 3/4,6. CQfIADETT SYSTINS 3/4.6.1 PRD9RY CDtTIADETF CDFIADEE DffEGRITY LIvIiTC Cr*1DITIOti FOR OPEDATION 3.6.1.1 Prirary CQ7IADEC DEIGRITY shall be maintained.
APPLTCABIIlTY: KES 1, 2, 3 ard 4.
ACTICN:
Without primary CQ7IADETI DEEERITY, restore CUTIADEE DuuT.x1FY within one hour or be in at least }Efr SIANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CLI.D SHLTIDOWN within the folicwing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SLWTTT ANCE FIrtNTIS 4.6.1.1 Primary CDfIAINMENT DEEERITY shall be hakuted:
a.
At least enae per 31 days by verifying that:
1.
All p-Lations* not capable of being closed by OPERABIZ containment autcznatic isolation valves and required to be closed during acx:ident ocnditions are closed by valves, blind flanges, or cienctivated autcznatic valves secured in their positicos, mi those valves that may be opened under administrative controls per Specification 3.6.3.1, and 2.
All v4M hatches are closed and sealed, b.
By verifying that and ccrstainnent air lock is OPERABIE per
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Specification 3.6.1.3.
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- Except valves, blind flanges, and deactivated automatic valves whid are located inside the ocntainment and are locknd, sealed, or otherwise secured in the closed position. 'Ihese i--Lstions shall be verified closed during each CDID SHLTI1XMN Wi. that verificaticm of these @-Lations being closed need not be performed more often than once per 92 days.
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l CRES'IAL RIVER - DET 3 3/4 6-1 Amendment No. II4 i
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.0.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of < L, 0.25 percent by weight of the containment air per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> $ at P,, 49.6 psig.
valves subject to Type B and C test $,for all penetrations and A combined leakage rate of < 0.60 L b.
when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a)'the measured overall integrated containment leakage rate exceeding 0.75 L or (b) with the measured combined leakage rate for all a
penetrations and valves subject to Type B and C tests exceeding 0.60 L,,
restore the leakage rate (s) to within the limit (s)' prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE REQUIREMENTS
- 4. 6.1. 2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at.40 + 10 month intervals during shutdown at P 49.6 psig, durin_g each 10-year service period.
Thethirdtest,ofeachsetshallbeconductedduringthe shutdown for the 10-year plant inservice inspection.
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CRYSTAL RIVER - UNIT 3 3/,4 6-2
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CNDlNMENT SYSTDS 3/4.6.3 GNDdNMDff ISOIATION VALVES uvmuc ammm xm ommm 3.6.3.1 All containment isolation valves shall be OPERABIE with isolation times less than or equal to required isolation times.
APPLICABIIIIY: PDDES 1, 2, 3 and 4.
ACTIOli:
With one or more of the isolation valve (s) inoperable, either:
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Restore the inoperable valve (r) to OPERADLE Ltatus within 4 houni, or i
- b.
Isolate each affected pr.r-hation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least l l one deactivated automatic valve secured in the isolation position or,
- c.
Isolata each affected por= Lation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least l.
one closed manual valve or blind flange; or d.
Be in at least IKTI 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 in CDLD' SHCJIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, stmvm1Anm wouveArms 4.6.3.1.1
'Ihe isolation valves shall be demonstrated OPERABIE prior to l
returning the valve to service after ad ntanance, repair or replacement work that could affect the valve's performarsi is performed on the valve or its l-associated actuator, - Lul or power circuit by performance of a cycling test and verification of isolation time.
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- The provisions of Specification 3.0.4 are not applicable. Valves may be opened on an intermittent basis under administrative control.
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C3&SThL RIVER - IMIT 3 3/4 6-15 Amendment No. 39.59.63. 114
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e CQfRINMENT SYSTEMS SURWTTIANCE REnfIRDOTTS (Contirnwl)
I 4.6.3.1.2 Each isolaticri valve shall be (
-Lated OPERABIE durirg the l
CDID SHUIDOWN or RE2UELING )CDE at least once per 18 acriths by:
Verifying that on a corth isolation test signal, eacti autmatic a.-
isolation valve an:tuates to its isolation position.
b.
Verifying that on a ocritairunent radiatial-high test signal, each purge and exhaust autmatic valve actuates to its isolation position.
4.6.3.1.3 Die isolation time of each power operated or tutmatic valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.1.4 The containment purge supply and exhaust isolation valves (AHV 1-A, B, C and D) shall be determined sealed closed before proceeding from Mode 5 to Mode 4 and at least once every 31 days when in Modes 1, 2, 3 and 4.
QUSML RlVER - T.1 NIT 3 3/4 6-16 Amendment No. II4
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f CRYSTAL RIVER - UNIT 3 3/4 6-17 Amendment No. 27,70J3.
- 97. 114 a
i DELETED CRYSTAL RIVER - UNIT 3 3/4.6-18 Amendment No. @B,63,114
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i CRYSTAk. RIVER-UNIT 3 3/4 6-19 Amendment No. 77,U,3E.63, 114
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CRYSTAL RIVER - UNIT 3 3/4 6-20 Amendment No. 38,63,114
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CRYSTAL RIVER - UNIT 3 3/4 6-21 Amendment No.27,2E.38,76, 97, 114
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CRYSTAL RIVER - UNIT 3 3/4 6-21a Amendment No.38,63,77,Il4
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CONTAINMENT SYSTEMS BASES i
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM
.The OPERABILITY of the containment spray system ensures that.contain.
ment depressurization and cooling capability will be available in the i:
event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses. The leak rate surveillance requirements assure that the leakcge rates assumed for the system during the recirculation phase will not be exceeded."
3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The
' limits on contained sodium hydroxide solution volume and concentration ensure a pH value of between 7.2'and 11.0 of the solution sprayed within containment after-a design basis' accident. The pH band minimizes the evolu' tion of iodine and* minimizes the effect of chloride and caustic stress corrosion cracking on mechanical systems and components..- The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical character-1stics.
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3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment' cooling; system ensures that 1) the containment air temperature will be maintained within limits during nomal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA _condi tions.
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CRYSTAL RIVER - UNIT 3 B 3/4 6-3 Amendment No.17 l
JAN 4 1979
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CONTAINMENT SYSTEMS BASES 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the required l
time limits ensures that the release of radioactive material to the environment Will be consistent with tne assumptions. used in the analyses for a LOCA.
Containment Isolation Valves and their required isolation times are addressed in the FSAR. The opening of a closed inoperable containment isolation valve on an intermittent basis during plant operation is permitted under administrative control. Operating procedures identify those valves which may be opened under
. administrative control as well as the safety precautions which must be taken when opening valves under such controls.
3/4.6.4 COMBUSTIBLE GAS CONTROLS The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its' flammable limit during post-LOCA conditions. The purge system is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions,
- 2) radiolytic decomposition of water and 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations ^in Containment Following a LOCA," March 1971.
In addition to the two inplace hydrogen monitors, there are two portable hydrogen analyzing units.
In the event that one hydrogen monitor is inoperable, one of the portable units may be used to monitor the hydrogen concentration in the Reactor Building.
l CRYSTAL RIVER - UNIT 3 B 3/4 6-4 Amendment No. 77), 114 j
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