ML20058F532
| ML20058F532 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  (DPR-072) |
| Issue date: | 07/15/1982 |
| 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 | |
| ML20058F533 | List: |
| References | |
| TAC 48126, DPR-72-A-055 NUDOCS 8207300555 | |
| Download: ML20058F532 (24) | |
Text
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'o UNITED STATES E
",7.
NUCLEAR REGULATORY COMMISSION h
E WASHINGTON, D. C. 20555 k,
8 j
=
FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNEl.L CITY OF GAINESVILLE i
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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55.
License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Florida Power Corporation, et al (the licensees) dated March 4,1982, and April 1,1982, as supplemented _,
by letters dated March 9,1982, April 6,1982, and April 30, 1932, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules :and regula-tions set forth-in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Cornission; 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.
~
8207300555 820715 PDR ADOCK 05000302 P
i e
Accordingly, the license.is amended by changes to the-Technical -
2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operati~ng License fio. 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. 55, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
Portions of this license amendment became effective March 3,1982, March 9,1982, April 1,1982, and April 6,1982, and portions of this amendment are effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISS10ft John F. Stolz, Chief Op rating Reactors Br' ch #4 1 vision of Licensing
Attachment:
Changes to the Technical Specifications f
Date of Issuance: July 15,1982 l
ATTACHMENT TO LICENSE AMENDMENT NO. g ',
~
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.
2-5 2-6 2-7 B2-4 B2-5 B2-7 3/43-2 3/43-3 3/43-4 3/43-5 3/43-6 3/44-4' l
3/4 4-4a (new page) l O
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ik i c
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e Nj TABLE 2.2-1 e
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REACTOR PROTECTION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3
t y
FUNC%N UNIT TRIP SETPOINT ALLOWABLE VALUES C
3 1.
Manual Reactor Trip Not Applicable Not Applicable j
-4
[
2.
Nuclear Overpower 194.8% of RATED 194.8% of 11ATED T11ERMAL POWER THEllMAL POWEll with four with four pumps operating pumps operating 179,92F., of RATED 179.92% of RATED THERMAL POWER TliEllMAL POWER with three with three pumps operating (3) pumps operating (3)
'P u
3.
RCS Outlet Temperature -
liigh 1 6180F 1 6180F 4.
Nuclear Overpower Trip Setpoint not to exceed Allowable Values not to exceed the Based on RCS Flow and the limit line of Figure limit line of Figure 2.2-1 AXIAL POWE[1 2.2-1 IMBALANCE (1) 5.
RCS Pressure - Low (1) 2 1800 psig 21800 psig y
6.
RCS Pressure - High 1 2300 psig i 2300 psig a
E.
7.
RCS Pressure - Variable 2 (11.59 Tout OF - 5037.8) 2 (11.59 Tout OF - 5037.8) psig Q
Low (1) psig 3
P p
O,'., s 7
0 j
TABLE 2.2-1 (Continued)
-i REACTOR PROTECTION SYSTEM INSTRUMENTATION TRIP SETPOINTS
- c l
~2 ALLOWABLE VALUES ;
Q FUNCTION UNIT TRIP SETPOINT C2 8.
pump Stat'us Based More than one pump drawing More than one pump drawing H
on Reactor Coolpnt Pump
<,3900 kw or > 9000 kw
< 3900 kw or > 9000 kw Power Monitors (1)(2) i 9.
Reactor Containment Vessel I
Pressure liigh 4 psig 5 4 psig I
4 i
'?
l l
i i
(1)
Trip may be manually bypassed when RCS pressure < 1720 psig by actuating Shutdown Bypass provided that:
l a.
The Nuclear Overpower Trip Setpoint is 15% of RATED TilERMAL POWER l
b.
The Shutdown Bypass RCS Pressure - liigh Trip Setpoint of 1 1720 psig is imposed, and j
jg c.
The Shutdown Bypass is removed when RCS Pressure > 1800 psig.
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g (2)
Trip may be manually bypassed when reactor power is less than or equal to 2300 MWt.
(3) Opciation with three reactor coolant pumps with RCPPMs bypassed is not permitted, Zo m
5 o
S g
9 4
<. y..
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120
-110
-100
(-7,96.51 I (+2.96.5) g=+0.6800 90 M =-0.7391 2
ACCEPTABLE 4 80
(-32,79.5)
PUMP OPERATION
(+25,79.5)
(-7,72. 08)-
(+2,72.08)
-1 d<-60 3
(-32,55.08) 2
(+25,55.08) 4 ACCEPTABLE h.50 3 & 4 PUMP OPERATION
- M E.40
~
@s I..30 n
E 20 2
8g-10 d
a:
1 1
1 I
I I
I l
I I
I I
-60
-50
-40
-30
-20
-10 0
10 20 30 40 50 60 l
REACTOR POWER IMBALANCE, %
FIGURE 2.2-1 TRIP SETPOINT FOR NUCLEAR OVERPOWER BASED ON RCS FLOW AND AXIAL POWER IMBALANCE r
I
- 0peration with three reactor coolant pumps with RCPPMs bypassed is not permitted.
CRYSTAL' RIVER-UNIT 3 2-7 Amendment No. p,R,M,X,55 9
l SAFETY LIMITS BASES
- q. <.
3 o
For each curve of BASES Figure 2.1, a pressure-temperature point above 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 three pump coeration is more restrictive than any other reactor coolant pump situation because any pressure / temperature point above and to the left of the three pump curve will be above and to the left of the other curves.
2.1.3 REACTOR COOLANT 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 Vessel Code 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 S 31.7, February,1968 Oraf t Edition, which permits a maximum transient pressure of 110%, 2750 psig, of component design pressure.
The Safety Limit of 2750 psig is therefore consistent with the design criteria and associated code requirements.
The entire Reactor Coolant System is hydrotested at 3125 psig,125%
of design pressure, to demonstrate integrity prior to initial operation.
CRYSTAL RIVER - UNIT 3 B 2-3 Amendment No. 34P, 41
2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS The Reactor Protection 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.
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 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 normai low pressure trip setpoint so that the reactor must be tripped before the bypass is initiated. The Nuclear ove power Trip Setpoint of.1 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 reaches 94.3% of rated power. Due to calibration and instrument errors, the maximum actual power at which a trip would be actuated could be 101.9% which was used in the safety analysis.
CRYSTAL RIVER - UNIT 3 B 2-4 Amendment No.,W,ff,55
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LIMITING SAFETY SYSTEM SETTINGS BASES i ?2.
RCS Outlet Temperature - High The RCS Outlet Temperature High trip
_ 6180F prevents the reactor outlet temperature from exceeding the design limits and acts as a backup trip for all power excursion 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 decreasing 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 the reactor, coolant flow rate decreases. The power level setpoint produced by the power-to-flow ratio provides overpower DNB protection for all modes of pump operation. For every flow rate there is a maximum permissible power level, and for every power level there is a minimum permissible low flow rate. Typical power level and low flow rate combinations for the pump situations of Table 2.2-1 are as follows:
1.
Trip would occur when four reactor coolant pumps are operating if power is 196.5% and reactor flow rate is 100%, or flow rate is $_93.69% and power level is 90.41%.
2.
Trip would occur when three reactor coolant pumps are operating if power is -
> 79.92?4 and reactor flow rate is 74.7%, or flow rate is < 70.09% 'and power is 75%. Operation with three reactor coolant pumps with RCPPM's bypassed is not permitted.
i For safety calculations the maximum calibration and instrumentation errors for the power level were used.
l l
1 l
1 l
CRYSTAL RIVER - UNIT 3 B 2-5 Amendment No.XfXX,W, 55
5,
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LIMITING SAFEYf SYSTEM SETTINGS BASE 5
.y -.
The AXIAL POWER IMSALANCE bcundaries are established in order to prevent reactor thermal limits frem being exceeded.
These thermal limits are either power peaking kw/f t limits or DNBR limits.
The AXIAL POWER IM-l SALANCE reduces the ;cwer level trip produced by the flux-to-ficw ratio I
such that the bcundaries of Figure 2.2-1 are produced. The flux-to-flew ratio reduces the pcwer level trip and associated reactor pcwer-reactor pcwer-imoalance boundaries by 1.07% for a 1% flew reduction.
RCS pressure - Lcw, High, and Variable Lcw The High and Low trips are provided to limit the pressure range in which reactor Operation is permitted.
During a slow reactivity insertion startup accident frcm 1cw power or a slow reactivity insertion frca high power, the RCS Pressure-High set-point is reached before the Nuclear Overpower Trip Se point. The trip setpoint for RCS Pressure-High, 2300 psig, has been established to main-tain the system pressure belcw the safety limit, 2750 psig, for any 'de-sign transient. The RCS Pressure-High trip is backed up by the pressur-izer code safety valves for RCS over pressure protecticn and is 4here-fore, set lower than the set pr. essure for these valves, 2500 psig. The RCS Pressure-High trip also backs up the Nuclear Overpewer trip.
The RCS Pressure-Low, 1500 psig, and RCS Pressure-Variable Lew,
.(11.59 Teut *F - 5037 8) psig Trip Set;cints have been established to
...aintain.the DNS ratio Sreater than or equal to 1.30 for those design accidents that result in a pressure reduction.
It also prevents reactor operation at pressures celcw the valid range of CN3 correlatien limits, protecting agains DNB.
Due to the calibraticn and ins rumentaticn errers, ne safety analysis used a RCS Pressure-Variable Lew Trip Setpcint Of (11.59 Teut
- F - 5077.8) psig.
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CRYSTAL RIVER - UNIT 3 5 2-6 Amendment No. X, W I,.sY, 46
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LIMITING SAFETY SYSTEM SETTINGS BASES Reactor Containment Vessel Pressure - High The Reactor Containment Vessel Pressure-High Trip Setpoint 6 4 psig, provides positive assurance that a reactor trip will occur in the unlikely event of a steam line failure in the containment vessel or a loss-of-coolant accident, even in the absence of a RCS Pressure - Low trip.
Reactor Coolant Pumo Power Monitors In conjunction with the power / imbalance / flow trips, the Reactor Coolant Pump Power Monitors trip prevents the minimum core DNBR from decreasing below 1.30 by tripping the reactor due to more than one reactor coolant pump not operating.
A reactor coolant pump is considered to be not operating when the power required by the pump is 7.120% or is s 70% of the nominal operating power. The nominal operating power decreases from when a pump is first started during heatup and is pumping dense fluid (typically 7500 KW) to when a pump is operating at full reactor power and is pumping less dense fluid (typically 5500KW).
In order to avoid spurious trips during normal operation, the 120% trip setpoint (9000KW) is based on the nominal operating power for a pump during heatup and the 70% trip setpoint (3900KW) is based on the nominal operating power for a pump operating at full reactor power. Florida Power has agreed to take credit for the pump overpower trip in order to assure that certain potential faults such as a seismically induced fault high signal will not prevent this instrumentation from providing the i
protective action (i.e., a trip signal).
CRYSTAL RIVER-UNIT 3 B 2-7 Amendment No. X,hr,AF, 55 l
9
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-'g.
e 2400 CURVE 2 3 PUMP s
2200 cm i
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1 y
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3 m
M CURVEI 4 PUMP L
9 l
l 1
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2000 o
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=
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u l
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)-
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l e-,,.,0 i
i t
l SSO 600 620 640 REACTOR OUT LET TEM *ER ATURE. F REACTOR COOL A NT FLOW FUMPS OPERATING CU:VE F LOW (% O E SIGN)
D O W ER (R"'P)
(TYPE OF LIMIT) l.
I 139.7 x IC S ( 10 6.5 "/.)
113.05 %
'4 PUMPS (DNER) 2 104.4 x 10 8 ( 79.5 %),
90.84 %
3 PUMPS (DNSR)
PRESSURE / TEMPER ATURE LIMITS AT MAXIMUM ALLOWABLE POWER FOR MINIMUM CNER l
BA SES FIGURE 2.1 l
l CRYSTAL RIVER UNIT 3 9 2-8 Amendment No..?r6",.Jf; 41 e
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Y-3/4.3 INSTRU"ENTATICN 3/1.3.1 REACTCR DROTECT:CN SYSTE24 INSTRUMEN~ATION i
LIMITI':7 CON 0! TION FOR CPEUTION
- 3. 3.1.1 As a minimu=, the Reac ce Prote: icn System instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPCNSE TI!4E5 as sn:wn in Tatle '3.3-2.
A?7t!CA!!LITY: As shewn in Table 3.3-1.
ACTICN:
As shes.5 in Table 3.3-1.
SUE'.*E* LLANCE EE".'! P.E"EWS a. 3.1.1.1 Ea:n Eaactor Frctecticn System instramentation channel shall
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be de :nstra:e: ".? ERA 3LE by the ;er#cr.ance of the CHANNEL CHECX, C:-ANNEL CALI5UTION a.: CHANNEL FUNCTIONAL TEST Operatiens during ne F.CCES and at :ne fre:;uencies sh:wn in Table 4.3-1.
4.3.1.1.2 The : a1 bypass functicn shall be dem:nstrated 07ERABLE at.
leas: ence ;er 15 m:ntns curing CHANNEL CALI5RATICN testing cf ea:h channel affe::ec by by; ass cperatien.
4.3.1.1.3 The REACTCR PROTICTiCN SY3 EM RESPCNSE TIME of ea:h ree ::r -
ri: fur.::icn shall be de =nstrated :s be within its limit.a least once
- er 13 m
- n:hs. Ea:n tes: shall include at least ene char.nel per functicn suen :na: all channels are tested at leas 1_ n=e. every N times 18 menths 3enere N is :ne :::a1 num:er of redundant channels in a 's ecific reacter tri: fun :i:n as shewn in :ne "Tc a1 No. of Channels" c:1ur:n of Table 3.3-1.
CEYSTA'. RIVER - UNIT 3 3/4 3-1 i
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- 1 TABLE 3.3-1
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REACTOR PROTECTION SYSTEM INSTRUMENTATION
!I o
[
W MINIMUM g
- 1 m
TOTAL NO.
CilANNELS CilANNELS APPLICABLE
,j FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION
.j F
- 1 N
<g 1.
1 1
1, 2 and
- 8 2.
Nuclear overpower 4
2 3
1, 2 2#
C 3
3.
RCS Outlet Temperature - High 4
2 3
1, 2 3#
H 4.
Nuclear Overpower Based on RCS u
Flow and AXIAL POWER IMBALANCE 4
2(a) 3 1, 2 2#
,'I 5.
RCS Pressure - Low 4
2(a) 3 1, 2 3#
6.
RCS Pressure - High 4
2 3
1, 2 3#
7.
Variable Low RCS Pressure 4
2(a) 3 1, 2 3#
u
- 3 3
8.
Reactor Containment Pressure - High 4
2 3
1, 2 3#
! I y
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
2//# and a 5
B.
Shutdown 2
0 1
3, 4 and 5
'6 i
11.
Control Rod Drive Trip Breakers 2 per trip i per trip 2 per 1, 2 and
- 7#
j system system trip system 12.
Reactor Trip Module 2 per trip 1 per trip 2 per
'1, 2.and
- 7#
g system system trip system S.
13.
Shutdown Bypass RCS Pressure -liigh 4
2 3
2**,3**,
6#
2 4*,3 -
m m7 14.
Reactor Coolant Pump Power Monitors 2 per pump 1[from 2 2 per pump 1,.2 2S
~
m o or more i
pumps (a,b) ii
.k x
a
.j
'i o
TABLE 3.3-1 (Continued)
TABLE NOTATION
..l -
- With the control rod drive trip breakers in the closed position and the control ~ rod 2
drive systeni capable of rod withdrawal.
++When Shutdown Bypass is actuated.
l
- 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:
(1)
The Nuclear overpower Trip Setpoint is 15% of RATED THERMAL
- POWER, (2)
The Shutdown Bypass RCS Pressure - High Trip Setpoint of 11720 psig is imposed, and (3)
The Shutdown Bypass is removed when RCS pressure > l800 psig.
(b)
Trip may be manually bypassed when reactor power is less than or equal to 2300 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 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 i
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:
a.
The inoperable channel is placed in the tripped condition within one hour.
b.
The Minimum Channels OPERAELE 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.
CRYSTAL RIVER - UNIT 3 3/43-3 Amendment No..W,X,55
~
TABLE 3.3-1 (Con 2inued)
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 />
' ci -
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 < 75" of RATED RATED THERMAL and the Nuclear Ever-power Trip Setpoint is reduced to < 85" of
~
RATED THERMAL PUWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the CUADRANT 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 fo11cwing conditions are satisfied:
a.
The inoperable channel is placed in the tripped 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, and the inoperable channel above may be byps: sed 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 it and with the THERMAL Power lev'el:
< 5% of RATED THERMAL POWER restore the inoperable channel to a.
OPERABLE status prior to increasing THERMAL POWER above 5% of
~
RATED THERMAL POWER.
b.
>5% of RATED THERMAL POWER, POWER OPERATION may continue.
r CRYSTAL RIVER - UNIT 3 3/4 3-4 e
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With tha number of channals OPERABLE 'ona inss 'than required ACTION 5 by the Minimum Channels OPERABLEirequirement and with the THERMAL POWER level:
- a. " (10-Yamps on the Intermediate Range (IR) in-
~
Ttrumentation, restore the inoperable channel to
.~
..a,
OPERABLE _gatuspriortoincr,easingTHERMALPOWER
~
above 10 amps on the IR instrumentation.
b.,
> 10-10 amps on the IR instrumentation, operation may continue.
With the number of channels OPERABLE one less than re-ACTION 6 quired by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 within one hour and at least.
once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
~
With the number of OPERABLE channels one less than t W ACTION 7 Total Number of Channels STARTUP and/or POWER OPERATION ray prcceed provided all of the following conditions are '
satisfied:
a.
Within 1 hour:
1.
Place the inoperable channel in the tripped
~
cendition, or 2.
Remove power supplied to the control rod trip device associated with the inoperative channel.
b.
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 sur'veillance testing per Specification 4.3.1.1, and the inoperable channel above may be bypassed for uq 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 g
when necessary to test the trip-breaker associated with the logic of the channel being tested per Speci fi ca tion -4. 3.1.1.
The inoper'able channel above may not be bypassed to test the logic of a channel of the trip system associated with the inoperable channel.
ACTION 8
. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 25 With the numb ~er of channels OPERABLE one less than the required 111nimum Channels OPERABLE requirement, plant operation may continue until the next required Channel Functional Test pro-vided the inoperable channel is placed in the tripped condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
CRYSTAL RIVER-UNIT 3 3/4 3-5 Amendment No. 55
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_l TABLE 3.3-2 ni i
y REACTOR PROTECTION SYSTEM INSTRUMENTATION RESPONSE TIMES
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G o.
Functional Unit Response Times
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=i jj l.
Manual Reactor Trip.
Not Applicable
- ]J 2.
Nuclear Overpower *
<, 0.266 seconds 3.
RCS Outlet Temperature - High Not Applicable 4.
Nuclear Overpower Based on RCS Flow and 4
w
~ l.79 seconds AXIAL POWER IMBALANCE
- 7 j
5.
RCS Pressure - Low 5 0.44 seconds w
i in
- j 6.
RCS Pressure - High 1 0.44 seconds i
l 7.
Variable Low RCS Pressure Not Applicable E
i 3.
Pump Status Based on RCPPMs 5 0.56 seconds l
0 l
9.
Reactor Containment Pressure - High Not Applicable y
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N
=
u 8' Neutron detectors are exempt from response time testing. Response time of the neutron flux signal j
portion of the channel shall be measured from detector output or input of first electronic component in channel.
l REACTOR COOLANT SYSTEM RELIEF VALVES - SHUTDOWN CODE SAFETY VALVES l
y.
LIMITING CONDITION FOR OPERATION A minimum of one pressurizer code safety valve shall be OPERABLE 3.4.2 with a lif t setting of 2500 psig +_1%.
APPLICABILITY : MODES 4 and 5.
ACTION:
With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE 1
DHR 1oop into operation.
l SURVEILLANCE REQUIREMENTS l
No additional Surveillance Requirements other than those required 4.4.2 by Specification 4.0.5.
Amendment No. 38 CRYSTAL 1TVER - UNIT 3 3/4 4-3 APR 17 ;gg; 9
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RELIEF YALVES - OPERATING
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CODE SAFETY VALVES LIMITING CONDITI N FOR OPERATION
- 3. 4. 3.1 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 psig + 15 APPLICABILITY: MODES 1, 2, and 3.
I ACTION:
With one pressurizer code safety valve inoperable, either restore the -
i noperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
\\
SURVEILLANCE REQUIREMENTS 4.4.3.1 No additional S'urveillance Requirements' other than those.
I required by Specification 4.0.5.
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CRYSTAL RIVER - UNIT 3 3/4 4-4 Amendment t:o. E, 55
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P(ACTOR COOLANT SYSTEM
.p POWER OPERATED RELIEF VALVES
.e.
LIMil1NG CONDI. TION FOR OPERATION.
3.4.3.2. The power operated; reiief valve (PORV) and its associated block valve shall be OPERABLE.
f APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With the PORV inopera'ble,i within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or,close the. associated block valve and remove power from the block valve; otherwise, 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the block' valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve to OPERABLE status or close the block valve and remove power.from the block valve or close the PORV and remove power from the associated solenoid valve;.ctherwise, be in at least HOT STANDBY within thc next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d, The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specifications 4.0.5, the PORV shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL 4
CALIBRATION.
4.4.3.2.2 The block valve shall be demonstrated OPERABLE at least ance per 92 days by operating the valve through one complete cycle of full travel.
4.4.3.2.3 The emergency power supply for the PORV and block valve shall be demonstrated OPERABLE at least once per 18 months by transferring motive and control power from the normal to the emergency power supply and operating the valve through a complete cycle of full travel.
CRYSTAL RIVER-UNIT 3 3/4 4-4a Amendment No.55
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