ML20132E183
| ML20132E183 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/16/1985 |
| 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 | |
| ML20132E186 | List: |
| References | |
| DPR-72-A-078 NUDOCS 8508010733 | |
| Download: ML20132E183 (20) | |
Text
'yf UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 3
j WASHINGTON. D. C. 20555 g
FLORIDA POWER CORPORATION 4
CITY OF ALACHUA CITY OF BUSHNELL i
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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.78 License No. DPR-72 4
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated January 23, 1985, as supplemented June 6, and June 28, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (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 and regulations of the Comission; C.
There is reasonable assurance (1) 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
p PDR
i 4
2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby 3
amended to read as'follows:
Technical Specifications I
I j
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78, are hereby incorporated in the license.
Florida i
i Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
^\\
r j
U i
John IF. Stolz, Chief.
Operating Reactors Branch #4 Division of Licensing
Attachment:
i j
Changes to the Technical Specifications l
Date of Issuance: July 16,1935 i
i i
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...._,_....-,__,m_m_,,_..m_..m_.,_.,-._______,.~,_-
l ATTACHMENT TO LICENSE AMENDMENT NO. 78 f
FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50'-302 r
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.
.i D
3/4 3-12 i
3/4 3-14 3/4 3-16 3/4 3-17 i
l 3/4 3-17a 1
3/4 3-19
~
3/4 3-21 i
3/4 3-38 1
I 3/4 3-39 3/4 7-5 j
I i.
I i
l 1
-.._ -... ~__ _ _
- $s T_A_B_LE 3.3-3 (Cont'd)
~
,q 1
3 EllGINEERED SAFETY FEATURE ACTUATION _ SYSTEM IftSTRUMENTATION P
E'.
si MINIMUM i
TOTAL NO.
CilAllNELS CilANNELS APPLICABLE Ei TUNCTIONAL UNIT OF CilANNEl.S TO TRIP OPERABLE MODES ACTION G
- 3.. REACTOR BLDG. SPRAY o,
1 a.
Reactor Bldg. Pressure liigh-liigh coincident with IIPI Signal 3
2 2
1,2,3 12 b.
Automatic Actuation Logic 2
1 2
1,2,3 10 (J
i j
1:
4.
OillER SAFETY SYSTEMS u,
Reactor Bldg. Purge Exhaust Duct '
2, a.
Isolation on liigh Radioactivity Gascous 1
1 1
1,2,3,4 11#
!I i
e i
- 3..
)
1
)
4
~
TAllLE 3.3-3 (Cont'd)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM n:s TOTAL NO.
CilANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION
-4>
F E
b.
Main Feedwater and Main Steam rl Isolation
- o h
I.
Manual Initiation a.
SGA MFW isolation 4
2####
3 1,2,3 14#
b.
SGB MFW Isolation 4
2####
3 1,2,3 14#
c.
SGA MSL Isolation 4
2####
3 1.2,3 14 #
d.
SGn MSL ! solation 4
2####
3 1,2,3 I t. g 2.
OTSG A or n Pressure Low 4/ Steam 2/ Steam 3/ Steam 1,2,3 ' *
- 14#
Generator Generator Generator l
w if 3.
Automatic Actuation Logic
[
a.
SGA MFW Isolation 2
1 2
1,2,3 10 b.
SGn MFW ! solation 2
1 2
1,2,3 10 c.
SGA MSL isolation 2
1 2
1,2,3 10 f
d.
1 2
I,2,3 10 c.
Emergency Feedwater l
I 1.
Manual Initiation 4
2####
3 1,2,3 14#
2.
MFW Pump Turbines A and n Control Oil Low 4
2 3
l##
14#
>g 3.
OTSG A or n 4/ Steam 2/ Steam 3/ Steam 1,2,3 14#
R Level Low-Low Generator Generator Genera tor 3
9 4
OTSG A or n 4/ Steam 2/ Steam 3/ Steam I,2,3 * *
- 14#
Pressure Low Generator Generator Generator
=
5.
All Reactnr Coolant Pumps Tripped 4
2 3
1,2###
14#
6.
Automatic Actuation Logic 2
1 2
1,2,3 10 5
,z v
. =
TABLE 3.3-3 (Cont'd) b ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION N
MINIMUM
- o2 TOTAL NO.
CHANNELS CilANNELS APPLICABLE 9
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5.
REACTOR BLDG. ISOLATION a.
Manual Initiation 2
1 2
1,2,3,4 13 b.
Reactor Bldg. Pressure High 3
2 2
1, 2, 3 9#
c.
Automatic Actuation Logic 2
1 2
1, 2, 3, 4 10 5
d.
Manual Initiation 2
1 2
1, 2, 3, 4 13 (HPI Isolation) w e.
RCS Pressure Low 3
2 2
1, 2, 3*
13 (HPI Isolation) f.
Automatic Actuation Logic 2
1 2
1,2,3,4 10 (HPI isolation) i e
3a E
t TABLE 3.3-3 (Continued)
TABLE NOTATION 4
- Trip function may be bypassed in this MODE with RCS pressure below 1700 psig. Bypass shall be automatically removed when RCS pressure exceeds 1700 psig.
- + Trip function may be bypassed in this MODE with steam generator pressure below 750 psig.
Bypass shall be automatically removed when steam generator pressure exceeds 750 psig.
- The provisions of Specification 3.0.4 are not applicable.
- Trip automatically bypassed below 20 pe'rcent of RATED THERMAL POWER.
]
- Trip function may be bypassed below 10 percent of RATED THERMAL POWER.
- Manual trip function occurs if two channels in the same train are actuated.
)
ACTION STATEMENTS ACTION 9 _With the number of OPERABLE Channels one_less t.han the Total Numb Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placec in the tripped condition within I hour.
4 ACTION 10 -
With the number of OPERABLE channels one less than the Total Number of Channels, 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 /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to I hour for Surveillance testing per Specification 4.3.2.1.1.
1 I
ACTION 11 -
With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.
ACTION 12 -
With the number of OPERABLE Channels one less than the Total Number of Channels, operation *rna) pc sc.ed provided the inoperable thswei is place ir.
the bypassed condition and the minimum channels OPERABLE required is demonstrated within I hour; one additional channel may be bypassed for up l
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 4.3.2.1.1.
i ACTION 13 -
With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channe! to OPERABLE status within 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-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 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 />.
i ACTION 14 -
With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the tripped evndativa witlun i hour, one additional cl annel may t,e bypassee 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 4.3.2.1.1.
i CRYSTAL RIVER - UNIT 3 3/4 3-14 Amendment flo. M,78
g.
m L
___A
~
--_ -. 2
--_4---
_._m I
TABLE 3.3-4 h
ENGINEERED SAFETY FEATURE ACTUATION SYSTEMS If!STR,UMENTATION TRIP SETPOINTS O
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
=
29 1.
SAFETY INJECTION liigh Pressure Injection ES i
a.
Actuat ion "A" and "B" g
1.
Manual Initiation Not Applicable Not App 1tcable 2.
Reactor Bldg. Pressure liigh f 4 psig I 4 psig 3.
RCS Pressure Low
> 1500 psig
> 1500 psig 4.
RCS Pressure Low-Low T 500 psig T 500 psig 5.
Automatic Actuation Logic Not Applicable Not Appilcable w
b.
Low Pressure Injection ES 1
Actuation "A" and "B" 1.
Manual Initiation Not Applicable Not Applicable 2.
Reactor Bldg. Pressure liigh f 4 psig f 4 psig 3.
RCS Pressure Low-Low
> 500 psig
> 500 psig 4.
Automatic Actuatton Logic Wot Applicable Wot Applicable 2.
REACT (R BLDG. COOLING a.
ES Actuation "A" and "B" E
1.
Manual Initiation Not Applicable Not Applicable i
2.
Reactor B1dg. Pressure liigh
< 4 psig
'< 4 psig
'S 3.
Automatic Actuation Logic Rot Applicable Wot Applicable r
5 b.
ES Actuatfon Indication "A8" S
1.
Automatic Actuation Logic Not Applicable Not Applicable j
TAl%LE 3.3-4 (Continued)
ENGINEEltED SAFETY FEATUllE ACTUATION SYSTEMS INSTittlMENTATION TRIP SETPOINTS FUNCTIONAL UNIT Titil' SETPOINT ALLOWAI)LE VALUES O
3.
REACTOlt I)UILDING SPitAY to a.
Ileactor Building Pressure liigh-liigh f 30 psig 6 30 psig F
coincident with See I.a.2, 3, 4 See I.a.2, 3, 4 2
IIPI Signal ty b.
Automatic Actuation (Logic) Not Applicable Not Applicable 4.
OTilEll SAFETY SYSTEMS E
a.
Reactor iluilding Purge
[
Exhaust Duct isolation on liigh Radioactivity Gaseous Not Applicable b.
Main Feedwater and Main Steam Isolation 1.
Manual Not Applicable Not Applicable s*
2.
OTSG A or B
{
Pressure Low 2600 psig 3600 psig 3.
Automatic Actuation Logic Not Applicable Not Applicable c.
Emergency Feedwater I.
Manual Initiation Not Applicable Not Applicable 2.
MFW Pump Turbines A and l} Control Oil t 55 psig
? 55 psig 3.
OTSG A or B Level Low-Low a 0 inches 2 0 inches 3
4.
OTSG A or B Pressure Low 2600 psig e: 600 psig o
i'.
5.
All Reactor Coolant Pumps Tripped Loss of 4 pumps Loss of 4 pumps
=
(per Table 2.2-1, //3)
Z 6.
Automatic Actuation Lo;;ic Not Applicable Not Applicable E
" Determined by the requirements of Appendix "B" Technical Specifications Section 7.4.
y Crystal River 3 Operating License No. OPR-72.
a
TABLE 3.3-4 (Cont'd)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUtiENTATION TRIP SETPOINTS W
hk FUNCTIONAL UNIT
~
TRIP SETPOINT ALLOWABLE VALUES m
[*
5.
REACTOR BLDG. ISOLATION a.
ES Actuation "A" aml "B" u,
1.
Manual Initiation Not Applicable Not Applicable 2.
Reactor Bldg. Pressure liigh
< 4 psig
' < 4 psig 3.
Automatic Actuation Logic Rot Applicable Iiot Applicable 4.
Manual Initiation (IIPI Isolation)
Not Applicable Not Applicable u,
5.
RCS l'ressure Low ls (IIPI isolation)
< 1500 psig
< 1500 psig u,
6.
Automatic Actuation logic g.
(llPI isolation)
Not Applicable Not Applicable t
i a
5 li an M
l TABLE 3.3 5 ENGINEERED SAFETY FEATURES P.ESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 1.
Manual a.
High Pressure Injection Not Applicable b.
Low Pressure Injection Not Applicable Reactor Bu!! ding Cooling Not Applicable c.
d.
Reactor Building Isolation Not Appilcable Reactor Building Spray Not Applicable e.
f.
Reactor Building Purge Isolation Not Applicable g.
MPW and MSL 1 solation l
1.
Emergency Peedwater Actuation Not Applicable 2.
Feedwater Isolation Not Applicable 3.
Steam Line Isolation Not Applicable h.
Emergency Feedwater Actuation Not App!! cable l
2.
Reactor Bu!! dine Pressure-Hir_h a.
High Pressure Injection 25*
b.
Low Pressure injection 25*
Reactor Bu!! ding Cooling 23' c.
d.
Reactor Building Isolattor.
60*
3.
Reactor Buildine Pressure Hieh-High (with HPI sienal) a.
Reactor Bullding Spray 36*
4.
RCS Pressure Low a.
High Pressure Injection 23+
b.
HPIisolation 60*
5.
RCS Pressure Low-Low a.
High Pressure Injection 25' b.
Low Pressure Injection 23' 6.
Low Steam Generator Pressure a.
Feedwater Isolation 34 b.
Steam Line Isolation 3
c.
Emergency Feedwater Actuation Not Applicable l
~
CRYSTAL RIVER - UNIT 3 3/4 3-17
i I
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES i
i J
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS +
7.
Containment Radioactivitv-High
)
a.
Reactor Building Purge Isolation 15+
S.
Main Feedwater Pumo Turbines A and B Control Oil Low t
a.
Emergency Feedwater Actuation Not Applicable 9.
OTSG A or B Level Low-Low l
l a.
Emergency Feedwater Actuation 50+
b
\\
10.
All Reactor Coolant Pumos Tricoed i
a.
Emergency Feedwater Actuation Not Applicable i
1 i
4 f
1 e
i I
t 1
I 1
l I
l 1
1 l
t i
- Diesel Generator starting and sequence loading delays included.
j Response time limit includes movement of valves and attainment of pump or blower discharge pressure.
i i
1 CRYSTAL RIVER - UNIT 3 3/4 3-17a Amendment flo. 3$, 78 4
i n.
e-,c.~
.,,-----m--
man.-.
..-e.
.,---.-..-n.-
O.
T. A.n.t li.4.. 3-2 I!NGINiil!Iti!D SAI:1!IY I 11A l'tlitti AC i tIATIOf1 SYS II!M INS rittIMl!NTATIOf4 St fit Vlill.I.ANCI! III!QtliitI!Ml!NTS t~
g CII ANNiii.
MODliS IN WillCil m
Cll ANiilil.
CIIANiilil.
I;tir1CIIONAI, SIlit Vlill.l. ANCl!
N 1:llNCTION AI. tINI f ClltiCK CAI.lillt A I ION TliST
_1111911111110 e
C hg 1.
SAFliTY INJiiCTION a.
liigli l'ressure injectlon I.
Manual Initiation N/A N/A It 3 or 6 2.
Iteactor fluiliting l'ressure liigh S
lt M(2) 1, 2, 3 3.
IRCS l'ressure 1.ow 5
Il M
1, 2, 3 4.
ItCS l'ressin e 1.ow-Low S
Il M
1, 2, 3 5.
Automatic Actuation Logic N/A N/A M(1)(3)(5)
I, 2, 3, 4 b.
Low I'ressure injection 1.
Manual Initia tion N/A N/A 11 5 or 6 2.
Itcactor llullding l'ressure liigh
.S 11 M(2)
I, 2, 3 3.
ItCS l'ressur e I.ow-Low S
It M
1, 2, 3
{
4.
Autoinatic Actuation 1.o;;ic f4/A N/A M(1) (3)
I, 2, 3, 4
{
2.
IlliACTOlt llulLDING COOL.ING a.
Manual Initiation II/A ft/A 11 Sor 6 y
b.
Itcactor llullding I'ressure Iligh S
Il M(2)
I, 2, 3
{
c.
Automatic Actuation I.ogic N/A T4/A M(1)(3)(5)
I, 2, 3, 4 e
na e
TABLE 4.1-7 (Continued)
ENGINEEltED SAFliTY FEATUltE ACTUATION SYSTEMS INSTitUMENTATION SultVEILLANCII IREQUlitliMENTS CIIANNEL MODES IN WillCII CIIANNEL Cil ANNEL FtJNCTIONAL StJItVEILLANCE FUNCTIONAL UNIT CllECK CALIllitATION TEST IREQtJIIRED r-3.
IREACTOlt BtJILDING SPitAY h
a.
Iteactor Building Pressure rn liigh-liigh coincident with f
IIPI Signal S
11 M(4)
I,2,3
}
b.
Autornatic Actuation Logic N/A N/A M(1)(3)(5) 1,2,3 4
4.
OTilEll SAFETY SYSTEMS a.
Iteactor Building Purge Exhaust Duct Isolation on liigh Itadioactivity 1.
Gaseous S
Q M
All Modes b.
Main Feedwater and Main Stearn Isola tion M
l.
Manisal Initia tion
I,2,1
[
- b. SGB MFW Isolation N/A N/A M
I,2, 3 e
- c. SG A MSI Isolation N/A N/A M
1,2,1
- d. SGB MSL isolation N/A N/A M
I,2, 3 2.
OTSG A or B Pressure Low 5
It M
1,2,1 3.
Autornatic Actuation Logic
- b. SGB MFW isolation N/A N/A M(6) 1,2,3
- d. SGB MSL Isolation N/A N/A M(6)
I,2,3 3c' g
c.
Erner gency Feedwater 1.
Manual Initia tion N/A N/A M
I,2,3 D
2.
MFW 1%np Turbine A and 11 Control Oil Low S
it M
i 5
3.
OTSG A or B Level
~~
Low-Low 5
11 M
1,2, 3 w
4.
OTSG A or il l'ressure Low S
11 M
1,2,3 y
5.
All Itcactor Coolant Puenps Tripped
'i 11 M
1,2 yy 6.
Autoinatic Actuation Logic N/A N/A M
1,2,3
O
.vil l.
w,,y
=
es
=-
4 g < -.
e e
~
e m
e m
~.
.d 8
= :,
m i
u
- .' J I N N
~-
l
~
N
~
e n
- =
-a l
-: A
~
n..
- n.,
.w
.c.
.m.
c 1
2: = ;a.:,
- m N
~
< g ;..,
4 4 4
, = =,. -
.v:
&g up t
_1, e(
4 "I
2.8 Z <-
g g
u
=-
Q. -<
e=.
=
g
/.:
N. I.
gh m.
~-... e.g
'd As
" =l
~ x v:
--*8 g
<.o s
-i 1
.; 7!
C.
w
.== e w
e# ;
-. =.
U -=
- y
. rs
.s
~ =
.. =. -
~.
- = '
.e.2
,, =.
e u.
a a
. a
==
. =-..=.
.f...c.
. =. = =.
h"
-. = =
( o. e g g I.I
=
g-
- p. =
W
. =
- i rs -.
m w
4 c :
4-C=
==
O "I.'
Eg < EC=~ <. "
=
U
=
=.
=
4
=
.=4
- J U
m=
N!
I t
n l
1 I
CRYSTA1. RIVF.A - UNIT 3 3/4 3-20 Ataenc=ent i o. 32. 37,66 4
.e.
ea
~
TABLE 4.3-2 (Continued)
TABLE NOTATION 1
(1) The CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic need only demonstrate one combina. tion of the three two-out-of-three logic
)
combinations that are operable provided that a different combination is tested at each. test interval, such that all three combinations will be confirmed to be operable by the time the third successive test is completed.
(2)
The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying pressure to the appropriate side of the transmitter.
(3)
Each locic channel shall be tested at least once every other 31-day period (applies only to Test Groups HPI-3, LPI-l and LPI-2 for the dura. tion of Fuel Cycle 5 - see (5) below).
(4)
Reactor building pressure High-High signal only.
l (5) Monthly CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic circuitry has been waived for all Test Groups with the exception of Test Groups HPI-3, LPI-l and LPI-2 for the duration of Fuel Cycle 5 for Crystal River Unit 3.
i (6)
Tne Chr:nel functional tes need not include actuation of the end j
d exice.
i 1
1 i
CRYSTAL RIVER UNIT 3 3/4 3-21 Amendment No $$, 78
,-s v.
-n e
v.
vv.
INSTRUMENTATION 3/4.3.3 MONITCRING NSTRUMENTATICN i
RADI ATION '10NITOR!'iG :NSTRUME'lTAT!3N
)
i LIMITING CONDITION FOR OPERATICN 1
4 3.3.3.1 The racia:icn meni::r'ng ins:rumentation :nannels snewn 'n acie 3.3-6 snali ce OPERABLE ai:n neir alarme tric se::oints at:r.in :ne 1
scecifiec limits.
APPLICABILITY:
As snown in Tacle 3.3-6.
su..ON:
,r-.
a.
di n a racia:icn meni : ring channel alarm / r se :oint excescirg d
- ne value snown in acie 3.3-6, acjus
- ne se :cin: :: wi:nin i
- ne lim 1: 41 nin 2 neurs Or ceclare :ns :nannel inc:eracie.
t
'41:n one or more raciation monitoring :nanneis ine:eracie, taxe
- ne
,,C_. 0N snown in. ac t e a. 3-c_.
1 i
rovisions of S:ecifications 3.0.3 anc 3.3.1 are no:
aa acciicaole.
i SURVEILLANCE REOUIREMENTS 4
h 4.3.3.1 Each radiation monit: ring instrumentation cnannel snail ce cemen-t stratec OPERABLE by the cerformance of the CHANNEL CHECK, CHANNEL CALISRA-TION and CHANNEL FUNCTIONAL TEST operations durinc :ne modes and at the
~
i frecuencies shown in Table 4.3-3.
l f
CRYSTAL RIVER - UNIT-3 3/4 3-22
Tant.E 3o3-10 POST-ACCIDENT MONITOltlNG INSTittlMENTATION g
W H
MINIMUM MEAStJItEMENT CilANNELS gq INSTilllMENT ItANGE OPEltAllLE til f
1.
Poser Itange Nuclear Flux 0-125%
2 2.
Ileactor Building Pressure 0-70 psia 2
]9 3.
Source llange Nuclear Flux 10-1 to 106 cps 2
w 1
's.
Itcactor Coolant Outlet Temperaturc
$200 F - 6200 F 2 per loop 5.
Itcactor Coolant Total Flow 0-160 x 106 lb./hr.
I 6.
IRC Loop Pressure 0-2500 psig 2
0- 600 psig i
I700-2500 psig 2
w2 7.
Pressurizer Level 0-320 inches 2
y 3.
Stearn Generator Outlet Pressure 0-1200 psig 2/stcarn generator U
9.
Steam Generator Operating Ilange Level 0-100 %
2/stcain generator l
10.
Borated Water Stnrage Tank Level 0-50 feet 2
11.
Startup Feedwater Flow 0- 1.5 x 106 lb./hr.
2 y
12.
Itcactor Coolant System Subcooling Margin Monitor
-658'F to + 668 F 1
k 13.
PoltV Position Indicator (Primary Detector)
N/A I
ag I 's.
PoltV Position Indicator (Backup Detector)
N/A N/A h
15.
POltV 131ock Valve Position Indicator N/A N/A 16.
Safety Valve Position Indicator (Primary Detector)
N/A 1/ Valve te 17.
Safety Valve Position Indicator (Backup Detector)
N/A N/A
.N 13.
Emergency Feedwater Flow 0-350 gpm 2/ steam generator E
h
TABLE 4c3-7 POST-ACCIDENT MONITORING INSTRilMENTATION SURVEILLANCE REQUIREMENTS O
- U j
CII ANNEL CIIANNEL
--i INSTRUMENT CllECK CAllBRATION t-
- o2 1.
Power Range Nuclear Flux M
Qs rn
~0 2.
Reactor Building Pressure M
R b
3.
Source Range Nuclear Flux M
Ra zq 4.
Reactor Coolant Outlet Temperature M
R 5.
Reactor Coolant Total Flow Rate M
R 6.
RC Loop Pressure M
R 7.
Pressurizer Level M
R 3.
Steam Generator Outlet Pressure M
R e
9.
Steam Generator Level M
R l
10.
Borated Water Storage Tank Level M
R 11.
Startup Feedwater Flow Rate M
R 12.
Reactor Coolant System Subcooling Margin Monitor M
R 13.
PORY Position Indicator (Primary Detector)
M R
14 PORV Position Indicator (Backup Detector)
M R
g I 5.
PORV Block Valve Position Indicator M
R k
l (i.
Safety Valve Position Indicator (Primary Detector)
M R
(
17.
Safety Valve Position Indicator (Backup Detector)
M R
[
13.
Emergency Feedwater Flow M
R
?
- Neutron detectors may be excluded from CIIANNEL CAllBRATION D
X u
I PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.
Verifying that each valve (manual, power operated, or automatic) in the l
flow path is in its correct position.
b.
At least once per IS months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on an emergency feedwater actuation test signal.
2.
Verifying that the steam turbine driven pump and the motor driven pump are capable of starting automatically:
l a.
Upon receipt of an emergency feedwater actuation OT5G A or B level low-low test signal, and b.
Upon receipt of an emergency feedwater actuation main feedwater pump turbines A and B control oil low test signal, and j
c.
Upon receipt of an emergency feedwater actuation OTSG A or B low pressure test signal, and i
d.
Upon receipt of an emergency,feedwater actuation all reactor coolant pumps tripped test signal.
1
+ c.
Prior to startup after any refueling outage or other cold shutdown of longer j
than 30 days, verify the operability of an emergency feedwater flow path by utilizing an Emergency Feedwater Pump to pump water from the emergency feedwater supply tank to the steam generators.
- This surveillance requirement becomes effective af ter completion of the new emergency l
feedwater supply tank.
I
~
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