ML19351D323
| ML19351D323 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/24/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19351D324 | List: |
| References | |
| TAC-42345, NUDOCS 8010090534 | |
| Download: ML19351D323 (10) | |
Text
.. _ _ _ _ _
b %g' k
UNITED STATES of NUCLEAR REGULATORY COMMISSION WASHINGTCN. D. C. 20658
.g
'\\C...../
FLORIDA POWER CORPORATION 3
_ CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESB'JRG CITY OF NEW SMYRNA BEACH Af4D UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 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 July 23. 1980, complies with the standards and requirements of the Atomi Energy Act of 1954, as amended (the Act), and the Comisrion's rules and regulations set forth 1
in 10 CFR Chapter I; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
I 8010oso$y/
i
\\
j
. 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 34, 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
-e
)
)l
..t, ':
f' ft Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 24, 1980 P
- MP-WM'M***
d6 m
p.
eeagpeep g wpggg pg
,,g 4
L I
ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE NO. DPR-72
!4 DOCKET N0. 50-302 l
Replace the following pages of Appendix "A" Te hnical Specifica"..ans with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
l' The corresponding _ overleaf pages are also-provided to maintain document completeness.
l III 3/4 1-27 3/4 1-28 3/4 l'-36 B3/4 1-4 1
I L
l i
I l
~
INDEX LIMITING CONDITIONS FOR.0PERATION ANr 'URVEILLANCE REQUIREMENTS SECTION
_PAGE 3/4.0 APPLICABILITY............................................
3/4 0-1 3/4.1 REACTIVITY' CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL S hu tdown Ma rgi n - O pe ra ti n g..........................
3/4 1-1 Shutdown Margin.e. Shutdown...........................
3/4 1-2a B o ro n D i l u t i o n.......................................
3/4 1-3 Moderator Temperature Coefficient....................
3/4 1-4 Minimum Temperature for Cri ticali ty..................
3/4 1-5 3/4.1.2 BORATION SYSTEMS Flow Paths - Shutdown................................
3/4 1-6 Fl ow Pa th s - Ope rati n g...............................
3/4 1-7 Makeup Pump - Shutdown..................
3/4 1-9 Makeup Pumps - Operating.............................
3/4-1-10 Decay Heat Removal Pump - Shutdown...................
3/4 1-11 Bori c Aci d Pump - Shutdown..........................
3/4 1-12 Bori c Aci d P umps - Ope ratin g.........................
3/4 1-13 Borated Water Sources - Shutdown.....................
3/4 1-la Borated Water Sources - Operating....................
3/4 1-16 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height - Safety and Regulating Rod Groups......
3/4 1-18 Group Height - Axial Power Shaping Rod Group.........
3/4 1-20 Position Indicator Channel s..........................
3/4 1-21 Rod Drop Time..
3/4 1-23 Sa fety Rod Insertion Limi t...........................
3/4 1-24 Regulating Rod Insertion Limits......................
3/4 1-25 Rod Program..........................................
3/4 1-33 Axial Power Shaping Rod Insertion Limits..............
3/4 1-37 CRYSTAL RIVER - UNIT 3 III Amendment No. ~ 16, 32, 34 e
n_
INDEX
' LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RFOUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL POWER IMBALANCE................................
3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - F................................ 3/4 2-4 9
3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F3g......~...................
3/4 2-6 L 3/4.2.4 Q UADRAN T POWE R TI LT..................................
3/4 2-8 i
3/4.2.5 DN B P ARAMET E R S.......................................3/4 2-12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION....................................
3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Moni toring Ins trumentation.................
3/4 3-22 Incore Detectors.....................................
3/4 3-26 Seismic Instrumentation...........:..................
3/4 3-28 Meteorological Instrumentation.......................
3/4 3-31 Remote Sh,utdown Instrumentation......................
3/4 3-34 Post-accident Instrumentation........................
3/4 3-37 Fi re Detection Ins trumentation......................
3/4 3-40 l
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT L00PS................................
3/4 4-1 3/4.4.2 S AFETY VALVES - SHUTD0WN.............................
3/4 4-3 3/4.4.3 S AFETY VALVES - 0PERATING............................
3/4 4-4 CRYSTAL RIVER - UNIT 3 IV Amendment No.13
-v
i 110 j.
_;.t,.;. g. 9., _.. w=== r.:_. 33_5.
- li-wiiiii77.1021F7x(230,1&5
.... t.. :, :.
_-myu- :-.;4 :-.; ;
_. : -t
..... 4...... p;.. :
4.
'r {..... ::-t:::.-
- .1:. -.
go
- il-iiff,'gbi)._...1230,s01-r l
.. _... i'.h ~.~ :.T :'
if- -
4 :.: :-
5 UNACCEPTABLEp-Aurh;.!:
(161,80) :'4-(2$0.80) 3 a0- OPERATION o
-t:-
y ::=s...._ ::.\\
A I
~ f/
- - E i-\\ ;
y 2
'/ :
\\
c
/ I A
E r
60
. f
,,\\..
a W
j(100 50) y 50 (300,501 8
I u.
O m -
(
- -~ --- AN6l(PWA h].E---~
~
g 30 OPERATION O
A 20 t
10 g
(0.05 j t
i j
0 50 100 150 200 250 300 0 25 50 75 100 0
25 50 75 100 1 1 i f f
I I I I I
GROUP 5 GROUP 7 0
25 50 75 100 I
i i
i I
GROUP 6 i
FIGURE 3.1-1 REGULATING ROD GE UP INSERTION LIMITS FOF.. PUMP OPERATION FROM 0 EFPD TO 250 10 EFPD Co.YSTAL RIVER - UNIT 3 3/4 1-27 Amendment No. 7, 2, 76, X, p,34
110 (261'102)
(300,102) 100
]
90 -
i(261,90lr_
1 3
80 (250,80) f
~
k
-UN'ACCEPTA'SLE' 3
OPERATION y
70
- w W
e l
5
~-
j 50
." (175.50) u.
O
/
~
40 ~'h i
.~
w
& A_.
f7 ACCEPTABLE 20
=.
... - <... "..OPERATION -
,f
.____._[__~._..____..
10.
y-N0.01i 0
0 50 100 150 200 250 300 ROD INDEX, % WITHDRAWN 0 25 50 75 100 0
25 50 75 100 1 I i
1 1
I f
f f
I GROUP 5 GROUP 7 0
25 50 75 100
?
1 1.
I I
1 GROUP 6 FIGURE 3.1-2 REGUI ATING ROD GROUP INSERTION LIMITS FOR 4 PUMP OPERATION AFTER 250 10 EFPD
)..
Amendment flo.16, 79,/ k CRYSTAL. RIVER - UNIT 3 3/4 1-28 34 l
y
--.y
___y
_y.
.,,,,w---.,y
---w--
DELETED CRYSTAL RIVER - UNIT 3 3/4 1-35 Amendment No. 19 i
DELETED CRYSTAL RIVER - UNIT 3 3/4 1-36 Amendment No. g, 34 l
c7
REACTIVITY CONTROL SYSTEMS BASES 4
3/4.1.2 BORATION SYSTEMS (Continued) i The boron capability in Modes 4 at 3 5 is based on a potential moderator dilution accident and is sufficient to provide a SHUTDOWN MARGIN of 3.0% ak/k after xenon decay and a cc oldown from 200*F to 140*F. This condition requires either 300 gallons c f 11,600 ppm boron from the boric acid storage system or 1608 gallons of 2270 ppm boron from the borated water storage tank.
To envelop future cycle BHST contained borated water l
volume requirements, a minimum volume o-13,500 gallons is specified.
The contained water volume limits include allowance for water-not available because of discharge line location and other physical charac-i teristics. The limits on contained water volume, and boron concenti ition ensure a pH value of between 7.2 and 11.0 of the solution sprayed within 2
containment after a design basis accident.
The pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion cracking on mechanical systems ind components.
The OPERABILITY of one boron inject on syste.n during REFUELING ensures
,~
ts.t this system is available for reacti -ity control while in MODE 6.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section (1) ensure that acceptable power distribution limits are maintained. (2) ensure that the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of a rod ejection accident. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
l The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.
For example, misalignment of a safety or regulating rod requires a restriction in THERMAL POWER.
The reactivity i
worth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding -the assumptions used in the safety analysis.
The position of a rod declared inoperable due to misalignnent should not be included in computing the average group position for determining the OPERAEILITY of rods with lesser misalignments.
i CRYSTAL RIVER - UNIT 3 5 3/4 1-3 Amendment ?!o. jsp', 3 2
~
t
?.
,..--,,,-,-..n
-n
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued)
The maximum rod drop time pennitted is consistent with the assumed rod drop time used in the safety analyses. Measurement with T
> 525'F and with reactor coolant pumps operating ensures that (M iiieasured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
The limitation on Axial Power Shaninn Rnd intartion is necessary to ensure that power peaking limits arp not exceeded.
l CRYSTAL RIVER
. UNIT 3 B 3/4 1-4 Amendment No. )(, 34
_. _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _. _ _