ML20058F493
| ML20058F493 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/16/1982 |
| 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 | |
| ML20058F494 | List: |
| References | |
| TAC 48471, DPR-72-A-056 NUDOCS 8207300532 | |
| Download: ML20058F493 (14) | |
Text
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[s uq[0, UNITED STATES E
NUCLEAR REGULATORY COMMISSION L
E WASH WGTON, D. C. 20655 C
e
% *... /
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 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 56 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 May.28,1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10,CFR Chapter I; l
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 defe,nse 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.
l l
8207300532 820716 PDR ADOCK 05000302 P
PDR A
.. 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.56, 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 Johh F. Stolz, Chief Operating Reactors Branch #4
' vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 16,1982 l
[
l
ATTACHMENT TO LICENSE AMENDMENT NO. 56 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 contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
2-3 2-5 2-7 B2-4 B2-5 82-6 3/4 3-3 e
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FIGURE 2.I-2 REACTOR CORE SAFETY LIMIT
- 0peration with three reactor coolant pumps with RCCPMs bypassed is not permitted.
CRYSTAL RIVER - UNIT 3 2-3 Amendment No. J$, 77, H, 97,
$$, 56
..e
' 5ATE Y LIMI ! AND LIM-hMG Sarm $YS T* Sei t NGS
- d 2.2 LI*ITING SAF D 5'5 I" SE-~i M3 RUC" R 8tC~i:T!:N SYS~iv 51 70!Y.*3 2.2.1 The React:r Protec. ion Syste ins PJnentati0nset:Cint3sball be se c:nsistant wita ce Tri; Set;: int values shown in Table 2.2-1.
A;oLICA!!L m : As shown for each channel in Table 3.3-1.
AC !:N:
With a React:r Pre ection System instra:e:i atica set: cia: less c=nserv-ative than the value shewn in the Allowable Yalues c=1u:::n c# Table 2.2-1, declare the channel ine:eratie and a:;1y the a:;1(caele A ~ICN s.atamaa.:
recui tment =f S;ecifica:icn 3.3.1.1 until the channel is rest: red ::
OPERA!LI status witn its tri; set;cin: adusted c:nsisten: with the Trip Set; int value.
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Om TABLE 2.2-1 j
REACTOR PROTECTION SYSTEM INSTRilMENTATION TRIP SETPOINTS
.-i f
30 FUNCTION UNIT TRIP SETPOINT ALLOWABLE VALUES
- o I
C3 1.
Manual Reactor Trip Not Applicable Not Applicable
-i 2.
Nuclear Overpower 5 102.0% of RATED s 102.0z of RATED THERMAL POWER TilERMAL POWER with four with four pumps operating pumps operating 179.924 of RATED i 79.92% of RATED THERMAL POWER TilERM AL POWER with three with three pumps operating (3) pumps operating (3)
Y u
3.
RCS Outlet Temperature -
High 5 6180F i 6180F 4.
Nuclear Overpower Trip Setpoint not to exceed Allowable Values not to exceed tiw Based on RCS Flow and the limit line of Figure limit line of Figure 2.2-1 2.2-1 AXIAL POWEB)
IMBALANCEtl 5.
RCS IVessure - Low (1) 2 1800 psig 2 1800 psig 6.
RCS Pressure - High 1 2300 psig i 2300 psig y
E.
7.
RCS Pressure - Variable 2 (11.59 Tout OF - 5037.8) 2(!!.39 Tout OF - 5037.8) psig a
3 Low (1) psig a
N I
=
wd
ON TABl.E 2.2-1 (Continued) j REACTOR PROTECTION SYSTEM INSTRtlMENTATION TRIP SETPOINTS
-1 h
a FilNCTION tlNIT TRIP SETPOINT ALLOWABLE VAltlES Q
~f 8.
Pump Status Based More than one pumpdrawing More than one ptunp drawing C
H on Reactor Coolpqt Pump
< 3900 kw or > 9000 kw
< 3900 kw or > 9000 kw Power Monitors tii(2) 9.
Reactor Containment Vessel 4 psig 4 psig Pressure liigh Y
s
(
l l
Trip may be manually bypassed when RCS pressure < 1720 psig by actuating Shutdown Bypass provided that (1) 5% of RATED THERMAL POWER The Nuclear Overpower Trip Setpoint is 1 The Shutdown Bypass RCS Pressure - High Trip Setpoint of 1 720 psig is imposed, and a.
1 b.
y The Shutdown Bypass is removed when RCS Pressure > 1800 psig.
c.
g 3
Trip may be manually bypassed when reactor power is less than or equal to 2300 MWt.
(2) g Operation with three reactor coolant pumps with RCPPMs bypassed is not permitted.
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FIGURE 2.2-1 TRIP Sr.iPOINT FOR NUCLEAR OVERPOWER BASED ON RCS FLOW AND AX1AL POWER IMBALANCE
- 0peration with three reactor coolant pumps with RCPPMs bypassed is not permitted, cnysTAL servet - useT 3 2-7 Anendment No. 77, R, #, M,
M, 56
SAFETY LIMITS BASES For each curve of BASES Figure 2.1, a pressure-temperature point atove and to the lef t of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22% for that particular reactor coolant pump situation. The 1.30 DNBR curve for tr.ree pump ooeration is more restrictive than any other reactor coolant pump situation because any pressure / temperature point above and to the lef t of the three pump curve will be above and to the lef t of the other curves.
2.1.3 REACTCR CCOLANT SYSTEM PRESSURE The restriction of this Safety Limit protects the integrity of the Reactor Coolant System from overpressurization and thereby prevents the release of radionuclides contained in the reactor coolant from reaching the containment atmosphere.
The reactor pressure vessel' and pressurizer are designed to Section III of the ASME Boiler and Pressure Yessel Coce which permits a maximum transient pressure of 110%, 2750 psig, of design pressure. The Reactor Coolant System piping, valves and fittings, are designed to USAS B 31.7, February,1968 Draf t Edition, which permits a maximum transient pressure of 110t, 2750 psig, of component design pressure. The Safety Limit of 2750 psig is therefore consistent with the design criteria and associated r
I code requirements.
The entire Reactor Coolant System is hydrotested at 3125 psig,125%
of design pressure, to demonstrate integrity prior to initial operation.
l 1
CRYSTAL RIVER - UNIT 3 B 2-3 Amendment No. J4F, 41 A
2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The Reactor Protectio.' System Instrumentation Trip Setpoint specified in Table 2.2-1 are the values at which the Reactor trips are set for each parameter. The Trip Setpoints have been selected to ensure that the reactor core and reactor coolant system are prevented from exceeding their safety limits. Operation with a trip setpoint less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
l The Shutdown Bypass provides for bypassing certain functions of the Reactor Protection System in order to permit control rod drive tests, zero power PHYSICS TESTS and l
certain startup and shutdown procedures. The purpose of the Shutdown Bypass RCS Pressure-High trip is to prevent normal operation with Shutdown Bypass activated. This high pressure trip setpoint is lower than the normal low pressure trip setpoint so that the reactor must be tripped before the bypass is initiated. The Nuclear Overpower Trip Setpoint of f. 5.0% prevents any significant reactor power from being produced.
Sufficient natural circulation would be available to remove 5.0% of RATED THERMAL POWER if none of the reactor coolant pumps were operating.
Manual Reactor Trip The Manual Reactor Trip is a redundant channel to the automatic Reactor Protection System instrumentation channels and provides manual reactor trip capability.
Nuclear Overpower A Nuclear Overpower trip at high power level (neutron flux) provides reactor core protection against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry.
During normal station operation, reactor trip is initiated when the reactor power level, rea'ches 102.03% of rated power. Due to calibration and instrument errors, the maMmum actual power at which a trip would be actuated could be 109.15% which was used in the safety analysis.
I CRYSTAL RIVER - UNIT 3 B 2-4 Amendment No.pGW,53, 56
LIMITING SAFETY SYSTEM SETTINGS BASES RCS Outlet Temperatwe - High The RCS Outlet Temperature High trip.1 6180F prevents the reactor outlet temperature from exceeding the design limits and acts as a backup trip for all power cxcursion transients.
Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE The power level trip setpoint produced by the reactor coolant system flow is based on a flux-to-flow ratio which has been established to accommodate flow decrea ing transients from high power.
The power level trip setpoint produced by the power-to-flow ratio provides both high power level and low flow protection in the event the reactor power level increases or thm reactor coolant flow rate decreases. The power level setpoint produced by the ratio provides overpower DNB protection for all modes of pump power-to-flowFor every flow rate there is a maximum permissible power level, and for cperation.
Typical power level svery power level there is a minimum permissible low flow rate.
and low flow rate combinations for the pump situations of Table 2.2-1 are as follows:
Trip would occur when four reactor coolant pumps are operating if power is 1.
y_101.3% and reactor flow rate is 100%, or flow rate is s 96.03% and power level is 97.28%.
Trip would occur when three reactor coolant pumps are operating if power is 2.
> 79.921l and reactor flow rate is 74.7%, or flow rate is < 70.09'a and
~
power is /5%. Operation with, three reactor coolant puraps with RCPPM's bypassed is not permitted.
For safety calculations the maximum calibration and instrumentation errors for the power level were used.
Amenda ent No.,Mf,,,1#;2,/#,35, 56 CRYSTAL RIVER - UNIT 3 B 2-5
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l O
=<
LIMITING SAFETY SYSTEM SETTINGS 1
BASES The AXIAL POWER IMBALANCE boundaries are established in order to prevent reactor thermal limits from being exceeded. These thermal limits are either power peaking kw/ft limits or DNBR limits. The AXIAL POWER IM-SALANCE reduces the power level trip produced by the flux-to-flow ratio The flux-to-flow such that the boundarias of rigure 2.2-1 are produced.
ratio reduces the power level trip and associated reactor power-reactor l
pcwer-imcalance boundaries by 1.013% for a 1% flow reduction.
RCS Pressure - Low, High, and Variable Low The High and Low trips are provided to limit the pressure range in which reacter cperation is permitted.
During a slow reactivity insertion startup accident from low power or a slow reactivity insertion fr m high power, the RCS Pressure-High set-The trip point is reached before the Nuclear Overpower Trip Se: point.
setpoint for RCS Pressure-Hist, 2300 psig, has been established to main-tain the system pressure below the safety limit, 2750 psig, for any de-The RCS Pressure-High trip is backed up by the pressur-sign transient.
1:e* c:ce safety valves for RCS over pressure pr:tection and is,,phere-lower than the se* pressure for these valves, 2500 psig.
T'*
f:re, se:
RCS Pressure-High trip also backs up the Nuclear Overpower trip.
ISOC psig, and RCS Pressure-Variatie L:w, The ECS Pressure-Lew,
- F - 5037.5) psig, Trip Set;cints have been establishec to (12.59 T:u:
maintain, ne DNS ra-i greater than or equal to 1.30 for those cesign accicer.:s that result in a pressure reduction.
It also prevents reactor operati:n at pressures celow the valid range of DNS correlation limits, pr:tectir.; agai-s UNE.
and i strumentation err:rs, ne sa'ety analysis Oue :: :ne :alibra ier.
used a ;CS P-essure-Varia:1e Low Trip Set;ci-: Of (11.59 Teg-l I
- F 5C77.3) psig.
+
8 2-6 knenement No. X, W. Y,.F. W, 56
,CUSTAL R:yER - UNIT 3
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.
o*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 < 1720 psig by actuating Shutdown Bypass provided that:
The Nuclear Overpower Trip Setpoint is 15% of RATED THERMAL (1)
- POWER, 1720 The Shutdown Bypass RCS Pressure - High Trip Setpoint of 1 (2) psig is imposed, and The Shutdown Bypass is removed when RCS pressure >1800 psig.
(3)
Trip may be manually bypassed when reactor power is less than or equal to (b) 2475 MWt and 4 reactor coolant pumps are operating.
ACTION STATEMENTS 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 hou rod drive trip breakers.
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may ACTION 2 -
proceed provided all of the following conditions are satisfied:
The inoperable channel is placed in the tripped condition within a.
one hour, The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 b.
hours for surveillance testing per Specification 4.3.1.1.
l Amendment No..W,X,55,56 CRYSTAL RIVER - UNIT 3 3/43-3
TA8LE 3.3 1 (Continued)
ACTION STATEMENTS (Continued) and the inoperable channel above may be by-i 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 4 75%
c.
of RATED RATED THERMAL and the Nuclear Iver-power Trip Setpoint is reduced to < 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 />.
With the number of OPERABLE channels one less than the ACTICN 3 Total Numeer of Channels STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfied:
The inoperable channel is placed in the tripped a.
condition within one hour.
The Minimum Channels OPERABLE requirement is b.
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, 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 witn the logic of the channel being tested per Specification 4.3.1.1.
With the number of c6annels OPERABLE one less than Action 4 recuired by the Minimum Channels OPERA 8LE requirement and with the THERMAL Power lev'el:
< 5% of RATED THERMAL POWER restore the inoperable channel to a.
UPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.
I
>5% of RATED THERMAL POWER, POWER OPERATION may continue.
b.
CRYSTAL R:VER - UNIT 3 3/43-4 Amendment No. 55
-. - - - - -, - - - -. - - -