ML20100N107
| ML20100N107 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/29/1996 |
| From: | Pickett D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100N111 | List: |
| References | |
| NPF-62-A-102 NUDOCS 9603060163 | |
| Download: ML20100N107 (15) | |
Text
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION l
2 WASHINGTON, D.C. SomeH001 g,*****,f ILLINOIS POWER COMPANY. ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-62 1.
The IInclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated October 27, 1995, 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; 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 (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 Commission's regulations; D.
The issuance of this amendment will not to 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
- lllinois Power Company is authorized to act as agent for Soyland Power Cooperative Inc. and has exclusive responsibility and control over the plysical construction, operation and maintenance of the facility.
9603060163 960229 PDR ADOCK 05000461 i
P PDR
' ^
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 102, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY Com ISSION T --h V Douglas V. Pickett, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 29, 1996
ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 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.
Remove Paati Insert Paoes 3.1-9 3.1-9 3.1-10 3.1-10 3.3-22 3.3-22 3.3-27 3.3-27 3.3-55 3.3-55 3.3-56 3.3-56 3.3-57 3.3-57 3.3-58 3.3-58 3.3-59 3.3-59 3.3-60 3.3-60 3.3-81 3.3-81 3.6-56 3.6-56
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C:ntrol Rod OPERABILITY 3.1.3
)
s ACTIONS (co$tinued) t i
f. '
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e f
, CONDITION-
' REQUIRED ACTION COMPLETION TIME l
i l
E.. Required Action and E.1
.Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion i
Time of Condition A, C, or D not met.
i QB Nine or more control rods' inoperable.
i i
SURVEILLANCE REQUIRENENTS
)
SURVEILLANCE FREQUENCY j
l SR 3.1.3.1 Determine the position of each control rod.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i
NOTE--------------------
Not required to be performed until 8 days i
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> after the control rod is fully withdrawn and THERMAL POWER is greater than the LPSP of the RPCS.
Insert each fully withdrawn control rod at 7 days least one notch..
(continued) 4 8.
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I i
CLINTON 3.1-9 Amendment No. 45;- 102 r
t
Centrol Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued) -
' SURVEILLANCE FREQUENCY 4
SR 3.1.3.31
N3TE--------------------
~'
Not required to be performed until 38 days 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RPCS.-
Insert each partially withdrawn control rod 31 days at least one notch.
SR 3.1.3.4 Verify each control rod scram time from In accordance fully withdrawn to notch position 13 is with 5 7 seconds.
SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.5 Verify each control rod does not go to the Each time the withdrawn overtravel position.
control rod is withdrawn to
" full out" position bG Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling v
+
CLINTON 3.1-10 Amendment No. 4Hk 102
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e e
~ _. _ _
f PAM Instrumentation 3.3.3.1 l
Table 3.3.3.1-1 (pose 1 of 1)
, Post Accident Monitoring Instrumentation p
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COISITIONS REFERENCED FRON REGUIRED REGUIRED FlalCTION.
, r CNANNELS ACTION D.1 l
1 l
1.
Reacter steen Dame Preneure,,'., '
2 E
y l
2.
Reacter'Veseet Water Level 2
E
't=
ic 3.
hepreselon Poet Water Level 4.
f' s.
Nigh Renee' 2
E
'b.*
Low Renee 2
E i*
4.
Drywell Preeaure-ut 2
E 5.
Prlanry' Containment Area Radletion 2
F
(
~
6.
Drywett Aree Radiation 2
F e
l 7.
Penetratlon Flow Path, Automatic PCIV Positten 2 per t[ g flow E
S.
Drywell and Containment it, & C Analyzer 2
E 9.
Primary Contairment Pressure e.
Nish Range" 2
E b.
Low Range 4
2 E
- 10. segproselon Poet eundrant Water Temperature 2("I E
(a) Not respired for feetation vetwee he eseociated penetration flow path le f ootsted.
(b) Only one poeltlen Indication channet le required for penetration flow pathe with only one Installed control roen Indicotten channel.
(c) Nonttoring each spedrent.
l l
l l
CLINTON 3.3-22 Amendment No. -95r 102 I.
T 4
EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.4.1.2 Perform CHANNEL CALIBRATION. The 18 months Allowable Values shall be:
j a. ' TSV Cl$sure:
7% closed; and m
,.2,
.s i e bT..TCV Fast, Closure, Trip 011 6
'[
Pressure-Low: 1 465-psig.
.,, W)
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q.' *,
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SR 3.3.4.1:3~
Perform LOGIC-SYSTEM FUNCTIONAL TEST, 18 months
- "5
- including breake'r actuation.
/
- 'c.*
3.., '
SR 3.3.4.1.4 1 Verify TSV Clo~sure'and'TCV Fast Closure, 18 months
, Trip 011 Pressure-Low Functions are not
/ bypassed when THERMAL POWER is 2 40% RTP.
t
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.------------------NOTES------------------
1.
Breaker interruption time may be assumed from the most recent performance of SR 3.3.4.1.6.
l 2.
The STAGGERED TEST BASIS Frequency shall be determined on a per Function basis.
Verify the EOC-RPT SYSTEM RESPONSE TIME 18 months on a is within limits.
STAGGERED TEST BASIS SR 3.3.4.1.6 Determine RPT breaker interruption time.
60 months CLINTON 3.3-27 Amendment No. 102 l
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Primary Centainment and Drywell Isolation Instrumentaticn 3.3.6.1 Table 3.3.6.1 1 (page 1 of 6)
Primary Centelreinnt and Drywell Isolation Instrumentation APPLICAsLE CONDITIONS te0 des OR REGUIRED REFERENCED OTHER CHANetELS Fret.
SPECIFIED PER REGUIRED SURVEILLANCE ALLOW 4sLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REGUIREMENTS VALUE 1.
Mein steen Line Isolation e.
Reector vessel Water 1,2,3 4-G st 3.3.6;1.1 t.-147.7 inches Level -Low Low Low, SR 3.3.6.1.2 Level 1 SR 3.3.6.1.3 st,3.3.6.1.5
. at1 3.3.6.1.6
.at<3.3.6.1.7 b.
Mein Steen Line 1
4i li SR 3.3.6.1.1-t 837 pois Pressure - Low 7s SR 3.3.6.1.2-st 3.3.6.1.3.
st 3.3.6.1.5 sif 3.3.6.1.6 st 3.3.6.1.7 c.
Noin steen Line 1,2,3 t
4' Gs SR 3.3.6.1.1 5 178 paid Ftou - Nf sh SR 3.3.6.1.2' -
SR 3.3.6.1.3 sa 3.3.6.1.5 sa 3.3.6.1.6 st 3.3.6.1.7 d.
Condenser Vacuus-Low 1,2(83, 4
G sa 3.3.6.1.1 2 7.6 inches sa 3.3.6.1.2 Ng vacuun 3(e)
. st 3.3.6.1.3 st 3.3.6.1.5 sa 3.3.6.1.6 e.
Mein steen Turviet 1,2,3 4
G st 3.3.6.1.1 5 171*F Temperature - Nigh sa 3.3.6.1.2 st 3.3.6.1.5 sa 3.3.6.1.6 f.
Mein steen Line Turbine 1,2,3 4
G st 3.3.6.1.1 Modules 1 4 suilding st 3.3.6.1.2 s 142'F, Temperature - Nigh st 3.3.6.1.5 Modate 5 SR 3.3.6.1.6 s 150'F g.
Manuet Initiation 1,2,3 4
J sa 3.3.6.1.6 NA (continued)
(a) With any turbine stop valve not closed.
CLINTON 3.3-55 Amendment No.-9h 102
4
)
Primary Centainment and Drywell Isslation Instrumentatien 3.3.6.1 febte 3.3.6.1 1 (pese 2 of 4)
Primary Contalrusent and Drywell Isolation Instrumentation APPLICA8LE CONDITIONS NODES OR REQUIRED REFERENCED OTNER CNANNELS FROM SPECIFIED PER REQUIRED SURWEILLANCE' ALLOW 4BLE FLRICTION CONDITIONS FUNCTION ACTION F.1 REGUIRE8ENTS VALUE 2.
Prienry Contaltunent and Drywett Isoletten e.
Reector vesset Water 1,2,3 4(b)
K SR 3.3.6.1.1 t - 47.7 inches Level-Law Law, Level 2 SR 3.3.6.1.2 SR 3.3.4.1.3 at 3.3.6.1.5 SR 3.3.6.1.6 (c) 4 0
SR 3.3.6.1.1 t - 47.7 inches at 3.3.6.1.2 sa 3.3.6.1.3 SR 3.3.6.1.5 e
b.
Drywott Pressure-Nish 4
1,*,3 4(b)
K st 3.3.6.1.1 5 1.88 pais at 3.3.6.1.2 at 3.3.6.1.3 sa 3.3.6.1.5 sa 3.3.6.1.6 c.
Reactor vessel Water
'1,2,3 4
I st 3.3.6.1.1 2 -47.7 inches Lovet -Law Low, SR 3.3.6.1.2 Level 2 (ECCs SR 3.3.6.1.3 Divisions 1 and 2) st 3.3.6.1.5
{
d.
DrywelL Pressure - Nish.,,
1,2,3 4(b)~
I st 3.3.6.1.1 5 1.88 pois (ECCs Divisions 1 st 3.3.6.1.2 and 2)
SR 3.3.6.1.3 at '3.3.6.1.5 i
'~
st 3.3.6.1.6 4 ;-
' I st 3.3.6.1.1 2 47.7 inches e.
Reactor Vessel Water
' 1,2,3 -
4 Level-Law Lov, Lovet SR 3.3.6.1.2 2 (NPCs usPs Div 3 and-
/
- D 4) sa 3.3.6.1.5 e
SR 3.3.6.1.6 f.
Drywell Pressure-Nish 1,2,3
,4 I
st 3.3.6.1.1 5 1.88 pois (NPCs usPS Div 3 and 4) d SR 3.3.6.1.2 j
SR 3.3.6.1.3 SR 3.3.6.1.5 st 3.3.6.1.6 (continued) i (b) Aloe roeptred to initiate the associatN drywell isolation function.
(c) During operettens with a potentist for draining the reactor vessel.
CLINTON 3.3-56 Amendment Nor45v 102
- ct-
,z v
a 1 Pridiary Containment'and Drywell Isolatien Instrumentatien
,S 3.3.6.1 e
Tebte 3.3.6.1 1 (page 3 of 6)
Primary Centalsment and Drywell leolation Instrumentation t
APPLICABLE CONDIT10NS I
NWEs OR REeulRED REFERENCED OTNER CNANNELS FRial SPECIFIES PER REeUIRED SURVEILLAIICE ALLOW 4SLE FIAICTION 00SITIONS FUNCTION ACTION F.1 REGUIREMENTS VALUE l
2.
Primary Centelnment and
. DrymoLL Isoletten
'(continued).
f
-s.
Centelament tullding (c),(d) 4 N
st.3.3.6.1.1 s 500 sa/hr Fuel Transfer Peel at 3.3.6.1.2 Wentitetten Plenum at 3.3.6.1.5 Radletten - Nish SR 3.3.6.1.6 h.
Centelement Building 1,2,3 4(b)
I sa 3.3.6.1.1 s 400 mR/hr E doust SR 3.3.6.1.2 Redf atten - Nish SR 3.3.6.1.5 SR 3.3.6.1.6 (c),(d) 4 N
st 3.3.6.1.1 5 400 eR/hr at 3.3.6.1.2 sa 3.3.6.1.5 i
sa 3.3.6.1.6 s
I.
Centelement Building 1,2,3 4(b)
I sa 3.3.6.1.1 s 400 as/hr l
Continuous Cantelement at 3.3.6.1.2 Purse (CCP) Enhaust at 3.3.6.1.5 Radlet ten - Nish at 3.3.6.1.6
{
(c),(d) 4 N
st 3.3.6.1.1 s 400 met /hr
[
st 3.3.6.1.2 t
SR 3.3.6.1.5 st 3.3.6.1.6
- j. Reacter Vessel Water 1,2,3 4(b) g
. SR 3.3.6.1.1 2 -147.7 inches i
Level-Les Lau Lem, at 3.3.6.1.2 Level 1 sa 3.3.6.1.3 BR 3.3.6.1.5 sa 3.3.6.1.6
'(c) 4 0
sa 3.3.6.1.1 1 147.7 inches z
sa 3.3.6.1.2 i
sa 3.3.6.1.3 sa 3.3.6.1.5 t
sa 3.3.6.1.6
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k.
Centelament Preneure-(e) 2 I
SR 3.3.6.1.1 s 3.0 paid Nish sa 3.3.6.1.2 st 3.3.6.1.5 r
sa 3.3.6.1.6 y
L.
Manuel Initletten
,1,2,3
'2(b)
J sa 3.3.6.1.6 NA (c),(d)
'2 N
SR 3.3.6.1.6 NA
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(continued) 1 -[n 1-
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(b) Atee required te initlete the essecleted drywell,isoletten fmetion.
-s (c) Durire aperations with a potentlet for dretning, tie' reactor vessel.
- ^
(d) During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the primary or secondary containment.
(e) IIDDES 1, 2, and 3 with the eseectated PCIVs not closed.
CLINTON 3.3-57 Amendment No.-M,102
^
Primary Containment and Drywell Isolaticn Inttrumentation 3.3.6.1 Table 3.3.6.1 1 (page 4 of 6)
Primary Centainment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS i
NODES OR REQUIRED REFERENCED OTNER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLom BLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIRENENTS VALUE 3.
Reacter Core Isoletten Coellne (RCIC) systere Isoletten e.
RCIC Steam Line 1,2,3 2
I at 3.3.6.1.1 s 118.5 inches Ftow - Nish at 3.3.6.1.2 water sa 3.3.6.1.3 at 3.3.6.1.5 st 3.3.6.1.6 b.
RCIC steen Line 1,2,3 2
I st 3.3.6.1.2 s 13 seconde
?
F t ow - Nigh, SR 3.3.6.1.5 Time Deiey SR 3.3.6.1.6 c.
RCIC Steen s e ly Line 1,2,3 2
I st 3.3.6.1.1 2 52 pois Preeewe - Low SR 3.3.6.1.2 st 3.3.6.1.3 sa 3.3.6.1.5 st 3.3.6.1.6 d.
RCIC Turbine Emhouet 1,2,3 4
I st 3.3.6.1.1 s 20 pels Diaphrego st 3.3.6.1.2 Presswe - Nish 1 SR 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 e.
RCIC E pipment Room 1,2,3 2-I SR 3.3.6.1.1 s 207'F.
Ambient.
st 3.3.6.1.2 Temperature - Nish SR 3.3,6.1.5 i
's st 3.3.6.1.6 f.
Noin steem Line Te nel 1,2,3 2
I st 3.3.6.1.1 s 171'F at 3.3.6.1.2 Aablant a
Temperetwo - Nish,
e
~
- s. Noin steen Line Tunnet., 1,2,37 2
I st 3.3.6.1.2 s 28 minutes Temperature Timer s
1 2..
,t-at '3.3.6.1.6 4+
^2 h.
RNR Neet Exchanger 1,2,3 2 per I.
st 3.3.6.1.2 SR 3.3.6.1.1 5 160'F Ambient, 2 e, room '
i stwe - Nish. >
t SR 3.3.6.1.5 t
.a I.
RCIC/RNRs'toneilne*'
1,2,3 :
'421 I
st 3.3.6.1.1 s 188 inches Flow
- Nigh, st 3.3.6.1.2 water
~
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st 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 (continued) t t
CLINTON 3.3-58 Amendment No. 45,102
~-
i.
4 Primary Containment and Drywell Isolation InstrumentatiCn 3.3.6.1 febte 3.3.6.1 1 (page 5 of 6)
Primary Containment and Drywell isolation Instrismantation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED l
OTNER CHANNELS FROM sPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE -
FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE 3.
RCIC system laetetten (continued)
J. Drywell Pressure -
1,2,3 2
I sa 3.3.6.1.1 s 1.88 psis Nigh sa 3.3.6.1.2-sa 3.3.6.1.3 sa 3.3.6.1.5 sa 3.3.6.1.6 k.
Menwel Initiation 1,2,3 2
J sa 3.3.6.1.6 NA
- 4. Reacter Water Cleanup (RWCU) system Isolation e.
Differentist Flow -
1,2,3 2-I SR 3.3.6.1.1 s 66.1 spa Nigh SR 3.3.6.1.2 sa 3.3.6.1.5 sa 3.3.6.1.6 b.
Differentist 1,2,3 2
I st 3.3.6.1.2 s 47 seconds Ftow Tleer SR 3.3.6.1.4 SR 3.3.6.1.6 c.
RWIM Neet Enchanger 1,2,3 2 per room I
sa 3.3.6.1.1 5 205'F Espalpment Room st 3.3.6.1.2 Temperature-Nishl~
SR 3.3.6.1.6 SR 3.3.6.1.5 d.
RWCW Pump Reems 1,2,3 2 per room I
st 3.3.6.1.1 5 202*F Temperature Nish SR 3.3.6.1.2 SR 3.3.6.1.5 sa 3.3.6.1.6 i
e.
Main team Line Tunnel 1,2,3 2
I st 3.3.6.1.1 5 171* F Ashlent Temperature-sa 3.3.6.1.2 Nigh s.
SR 3.3.6.1.6 SR 3.3.6.1.5 t
f.
Reacter vessel Water 1,2,3
'4 I
sa 3.3.6.1.1 P. -47.7 inches Level - Low Low, SR 3.3.6.1.2 Level 2 3
+
's" r
st 3.3.6.1.5 4
,p sa 3.3.6.1.6 7
T.
(c) 4 O
sa 3.3.6.1.1 2 -47.7 inches st 3.3.6.1.2
'A
=
st 3.3.6.1.3
+
u st 3.3.6.1.5 g-sa 3.3.6.1.6 4
- s. Stan6 y Liquid control 1,2 3
'2 L
st 3.3.6.1.6 W
system Inittetten h.
menuel Inittetten
'1,2,3 2
J st 3.3.6.1.6 NA l
(c),(')
2 N
st 3.3.6.1.6 NA d
t (continued)
(c) During operations with a potentist for draining the reactor vesset.
(d) During CORE ALTERATIONS and daring movement of irradiated fuel essemblies in the primary or secondary containment.
CLINTON 3.3-59 Amendment No. -95,102
.77.--
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Primary. Containment"and Drywell Isolation Instrumentation nc*;' '
.c j 3.3.6.1 c
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i
- Table 3.3.6.1 1 (page 6 of 6)
Primary Centainment and Drywell Isoletten Instrumentotten APPLICABLE COWITIONS NODES OR REFERENCED OTNER REQUIRED FRtm SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION COS ITIONS FUNCTION ACTION F.1 REGUIREMENTS VALUE 5.
RNA system leetetten e.
RNE Rest Enchanger 1,2,3 2 per room I
et 3.3.6.1.1 s 160'F Ashlent SR 3.3.6.1.2 Teignoreture - ulsh at 3.3.6.1.5 SR 3.3.6.1.6 f
l
- b.
Reacter Vessel Water 1,2,3(f) 4 I
sa 3.3.6.1.1 2 8.3 Inches I
Level - Low, Level 3 et 3.3.6.1.2 at 3.3.6.1.3 i
SR 3.3.6.1.6 c.
Reacter vessel Water 3(8) 4,5 4(h)
N sa 3.3.6.1.1 2 8.3 Inches l
Level - Low, Level 3 st 3.3.6.1.2 st 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 d.
Reacter vessel Water 1,2,3 4
I st 3.3.6.1.1 2 147.7 Level Low Low Low, sa 3.3.6.1.2 inches i
Levet 1 sa 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 e.
Reacter vessel 1,2,3 4
1 SR.3.3.6.1.1 s 150 pois Preneure - Nish SR 3.3.6.1.2 sa 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 l
f.
Drywell Pressure-Nish 1,2,3 8
I SR 3.3.6.1.1 s 1.88 psis SR 3.3.6.1.2 i,
sa 3.3.6.1.3
+
4 sa 3.3.6.1.5 st 3.3.6.1.6
- s. Nenuet Inttletten 1,2,3 2
J SR 3.3.6.1.6 NA
[3
+
(f) With reactor steem done pressure grooter then or egal to the RNR cut in permissive pressure.
(s) Withreactersteendome'pressurelessthentheRNRcutinpermissivepressure.
(h) only one trip system required in *BEs 4 and 5 with RNR shutdown Coellns system Integrity asintained.
+
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i 1
CLINTON 3.3-60 Amendment No. 49; 102 i
RPS Electric Power Monitoring s
6 3.3.8.2
,1 y
3.3 INSTRUMENTATION
. j u.
l 3.3.8.2 Reactor Protection System-(RPS)eE1'ectric Power Monitoring l
s i
., j
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- J sn.
<o-l LC0 3.3.8;2: ;.
One'RPS electric power. monitoring assembly shall be OPERABLE
'; for~eachlinservice RPS special solenoid power supply or
~ alternate: power, supply.
i
~ ' s.,
l APPLICABILITY:
MODES 1, 2, and 3,.
MODES 4 and 5 with any control rod withdrawn from a core a
cell containing one or more fuel assemblies.
l
' ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i
l l
A.
One or both inservice A.1 Remove associated I hour power supplies with inservice power the electric power supply (s) from monitoring assembly service.
l l.
B.
Required Action and 8.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion' l
Time of Condition A Algl l
not met in MODE 1,-2, or 3.
B.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.
Required Action and C.1 Initiate action to Immediately associated Completion fully insert all Time of Condition A insertable control not met in MODE 4 or 5 rods in core cells with any control rod containing one or withdrawn from a core more fuel assemblies.
l cell containing one or more fuel assemblies.
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CLINTON 3.3-81 Amendment No.-9fs 102 f
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Drywell Air Lock 3.6.5.2 3.6 CONTAINMENT SYSTEMS 3.6.5.2 Drywell Air Lock LCO 3.6.5.2 The' drywell air lock shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS-4 s
______________--NOTES------------------------------------
1.
Entry and exit is permissible to perform repairs of the affected air lock components.
.s 2.
Enter applicable Conditions add: Required. Actions of LCO 3.6.5.1, "Drywell," when air 1.ock' leakage results in exceeding overall drywell bypass. leakage rate acceptance criteria.
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CLINTON 3.6-56 Amendment No. -96,102 i