ML20094D203
| ML20094D203 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/27/1995 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20094D198 | List: |
| References | |
| NUDOCS 9511030209 | |
| Download: ML20094D203 (15) | |
Text
__
LS-95-004 Page 2 of 13 Control Rod OPERABILITY 3.1.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME 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 Time of Condition A, C, or D not met.
E Nine or more control rods inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 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 /> B
NOTE--------------
Not required to be performed until days e 16 hNr5 after the control rod isAwithdrawn and
^
THERMAL POWER is greater than the LPSP of Oll the RPCS.
Insert each fully withdrawn control rod at 7 days least one notch.
(continued)
CLINTON 3.1-9 Amendment No. 9'T 9511030209 9' 27 PDR ADOCK O 1461 P
PDR to U-602498 LS-95-004 Page 3 of 13 Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.3.3
NOTE------------
Not required to be perfomed until N days 4-QOhong l
after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RPCS.
Insert each partially withdrawn control rod 31 days at least one notch.
SR 3.1.3.4 Verify each control rod scram time from In accordance fully withdrawn to notch position 13 is with
- s 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SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.5 Verify each control rod does not go to the Each time the withdrawn overtravel position.
control rod is withdrawn to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 MQ Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling CLINTON 3.1-10 AmendmentNo.JMI
LS-95-004 Page 4 of 13 PAM Instrumentation 3.3.3.1
[]
Table 3.3.3.1 1 (page 1 of 1) i Post AccIdont Monitoring InatrumentatIon CON 0lil0NS REFERENCED FROM REQUIRED REQUIRED FUNCTION CNANNELS ACTION 0.1 1.
Reactor Steam Dome Pressure 2
E 2.
Reettor vesset Water Level 2
E 3.
S w ession Poot Water Levet a.
High Range 2
E b.
Low Range 2
E 4 Drywell Pressure 2
E 5.
Primary Containment Area Radiation 2
F 6.
Drywell Area Radiation 2
F 7.
Penetration Flow Path, PC W Position 2 per t g t g flow E
8 Drywell and Contalnnent N & 0, Analyzer 2
E 9.
Primary Contalrunent Pressure a.
Nigh Range 2
E b.
Low Range 2
E
- 10. S w ession Poot Guadrant Water Tenperature 2(8)
E (a) Not required for Isotation valves whose associated penetration flow path is Isotated.
(b) only one position Indication chamel is required for penetration flow paths with only one instatted control room indication channel.
(c) Monitoring each gmdrant.
CLINTON 3.3-22 AmendmentNo.JHf c.
-.m.
LS-95-004 Page 5 of 13 EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)
StJRVEILLANCE FREQUENCY SR 3.3.4.1.2 Perform CHANNEL CALIBRATION. The 18 months Allowable Values shall be:
a.
TSV Closure: :s 7% closed; and b.
TCV Fast Closure, Trip 011 Pressure-Low: a 465 psig.
SR 3.3.4.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST, 18 months including breaker actuation.
SR 3.3.4.1.4 Verify TSV Closure and TCV Fast Closure, 18 months Trip 011 Pressure-Low Functions are not bypassed when THERMAL POWER is a 40% RTP.
NOTES------------------
1.
Breaker interruption time may be assumed from the most rec &
l performance of SR 3.3.4.
2.
The STAGGERED TEST BASIS Frequency shall be determined on a per Function basis.
Verify the E0C-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 AmendmentNo.J&
/R Ei@c N A W5WU T
LS-95-004 Page 6 of 13 Pri::ary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (past 1 Prianery contaltwent and Drywett Isotati notrumentation APPLICASLE CON 0lfl0Ns C ES OR REQUIRE 0 REFERENCE 0 OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWASLE FUNCTION CONotfl0Ns FUNCTION ACTION F.1 REQUIREMENTS VALUE i
1.
Main steam Line Isolation s.
Reactor vessel Water 1,2,3 i
G sR 3.3.6.1.1 t 147.7 inches Levet - Low Low Low, SR 3.3.6.1.2 Levet 1
$R 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 b.
Main Steam'Line 1
4 H
SR 3.3.6.1.1 1 837 pois Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 c.
Main steam Line 1,2,3 4
G SR 3.3.6.1.1 5 178 psid Flow - Nigh SR 3.3.6.1.2 i
$R 3.3.6.1.3 SR 3.3.6.1.5
$R 3.3.6.1.6 st 3.3.6.1.7 d.
Condenser Vacuum-Low 1,2(*),
4 G
SR 3.3.6.1.1 t 7.6 inches SR 3.3.6.1.2 Hg vacwe 3(*)
sa 3.3.6.1.6 e.
Main steam Tunnel 1,2,3 4
G SR 3.3.6.1.1 5 171*F Teaperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 f.
Maln steam Line Turbine 1,2,3 4
G SR 3.3.6.1.1 Modules 1 4 Building SR 3.3.6.1.2 s 142*F, Teaperature - High SR 3.3.6.1.5 Modute 5 SR 3.3.6.1.6 5 150'F g.
Manual Initiation 1,2,3 4
J SR 3.3.6.1.6 NA (continued)
(e) With any turbine stop valve not closed.
Cl.INTON 3.3-55 Amendment No.,5Hf
Attachmsnt 3 to U-602498 LS-95-004 Page 7 of 13 Prinary contain:ent and Drywell Isolation Instrumentation 3.3.6.1 febte 3.3.6.1 1 (pese 2 f Primary containment and Drywell Isolet notrumentation APPLICAstt CONelfl0Ns MODES 04 REQuitte RtfERENCEO OtNER CHANNELS FROM SPECIFIED PER R40Ultt0 suRytlLLANCE ALLOWASLE PUNCit0N CONolTious FUNCited ACTION F.1 ateUIREMENis VALut 2.
Primary Contelnment and Drywelt Isetetton e.
Reactor vessel Water 1,2,3 4(b)
K st 3.3.6.1.1 t
47.7 inches Level-Low Low, Level 2 sa 3.3.6.1.2 sa 3.3.6.1.3 sa 3.3.6.1.5 sa 3.3.6.1.6 (c) 4 0
sa 3.3.6.1.1 1
47.7 inches sa 3.3.6.1.2 sa 3.3.6.1.3 SR 3.3.6.1.5 SA 3.3.6.1.6 b.
Drywett Pressure-High 1.2,3 4(b)
K SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 sa 3.3.6.1.3 SR 3.3.6.1.5 SA 3.3.6.1.6 c.
Reactor Vessel Water 1,2,3 4
i SR 3.3.6.1.1 t 47.7 Inches Level - Low Low, SR 3.3.6.1.2 Level 2 (ECCS sa 3.3.6.1.3 Olvletone 1 ervi 2) sa 3.3.6.1.5 sa 3.3.6.1.6 d.
Drywetl Pressure-High 1,2,3 4(b) 1 SR 3.3.6.1.1 s 1.88 pels I
(ECCS Olvletone 1 SA 3.3.6.1.2 and 2)
SR 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 e.
Reactor vessel Water 1,2,3 4
i
$4 3.3.6.1.1 t 47.7 inches 1
Lovet -Low Low, Level SA 3.3.6.1.2 2 (NPCs NSPs Olv 3 and SR 3.3.6.1.3 4) st 3.3.6.1.5 SA 3.3.6.1.6
- f. Drywell Pressure - Migh 1,2,3 4
i SA 3.3.6.1.1 s 1.88 psig (NPCs NSPs Olv 3 and 4)
SA 3.3.6.1.2 SA 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 (continued) l (b) Also re @ lred to initiate the associated dryweLL isolation fwwtlon.
(c) During operations with a potentlet for deelning the reactor vesset.
CLINTON 3.3-56 AmendmentNo.)MI
(M@acRman2 3 Ro F789fS$)
LS-95-004 Pags 8 of 13 Prl:ary Containment and Drywell Isolation Instrumentation 3.3.6.1
?
l Table 3.3.6.1 1 (page 3
/f j
Primary Contalraent and Drywell Isolett natrumentation i
APPLICA8LE COMolfl0Ns MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM l
$PECIFIED PER REQUIRED SURVE!LLANCE ALLOWABLE FUNCil0N CON 0lfl0Ns FUNCil0N ACTION F.1 REQUIREMENis VALUE 2.
Primary Contaltwent and l
i Drywelt !aotation 1
(continued) 3 Containment Building (c),(d) 4 W
SR 3.3.6.1.1 5 500 d /hr Fuel Transfer Pool
$R 3.3.6.1.2 Ventilation Plenun SR 3.3.6.1.5 Radiation - High SR 3.3.6.1.6 h.
Contairwnt tullding 1,2,3 4(b)
I SR 3.3.6.1.1 s 400 set /hr
'i Exhaust SR 3.3.6.1.2 Radiation - Hlgh SR 3.3.6.1.5 SR 3.3.6.1.6 (c),(d) 4 N
SR 3.3.6.1.1 s 400 set /hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 1.
Contairment Building 1,2,3 4(b)
SR 3.3.6.1.1 s 400 set /hr Continuous contairment SR 3.3.6.1.2 Purge (CCP) Exhaust SR 3.3.6.1.5 Radletion - High SR 3.3.6.1.6 (c),(d) 4 N
$R 3.3.6.1.1 s 400 eft /hr st 3.3.6.1.2 sR 3.3.6.1.5
$A 3.3.6.1.6
- j. Reactor vessel Water 1,2,3 4(b)
I
$R 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
$R 3.3.6.1.5 SR 3.3.6.1.6 (c) 4 0
SR 3.3.6.1.1 t a147.7 Inches SR 3.3.6.1.2 SR 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 k.
Contairment Pressure *
(e) 2 i
SR 3.3.6.1.1 s 3.0 paid Nigh SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 L.
Manual Initletion 1,2,3 2(b)
J
$R 3.3.6.1.6 NA (c),(d) 2 N
SR 3.3.6.1.6 NA l
(continued)
(b) Also required to initiate the associated drywelt isolation function.
(c) Curing operations with a potentlet for draining the reactor vessel.
(d) During CORE ALTERATIONS and ckJring movement of irradiated fuel assechtles in the primary or secondary contalrwent.
(e) MCOES 1, 2, and 3 with the associated PCIVs not closed.
AmendmentNo.[
l CLINTON 3.3-57 to U-602498 LS-95-004 Prinary Containment and Drywell Isolati<fd8fnftMmdr?tation 3.3.6.1 Tebte 3.3.6.1 1 (page 4 f Primary Contalruent and Drywell Isolet natrumentation APPLICABLE CONOITIONS MODES OR REQUIRE 0 REFERENCE 0 OTNER CNANNEls FRON SPECIFIED PER REQUIRE 0 suRVEtLLANCE ALLOWAsLE FUNCTION CONotTIous FUNCT!0N ACTION F.1 REeutRENENis VALUE l
l 3.
Reactor Core Isolation Cooling (RCIC) system isolation e.
RCic Steen Line 1,2,3 2
1 SR 3.3.6.1.1 s 118.5 inches Flow - High SR 3.3.6.1.2 water SR 3.3.6.1.3 j
$R 3.3.6.1.5 j
SR 3.3.6.1.6 b.
RCic steen Line 1,2,3 2
I sa 3.3.6.1.2 s 13 seconds Flow - Nigh, SR 3.3.6.1.5 Time Detey st 3.3.6.1.6 j
c.
RCic steen supply Line 1,2,3 2
I st 3.3.6.1.1 1 52 pelo Pressure - Low
$R 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 d.
RCIC Turbine Exhaust 1,2,3 4
I wt 3.3.6.1.1 s 20 pcle Olephrepe sa 3.3.6.1.2 Pressure - Nigh SR 3.3.6.1.3 sa 3.3.6.1.5 sa 3.3.6.1.6 e.
RCic Equipment Room 1,2,3 2
I sa 3.3.6.1.1 s 207'F 1
Ashlent
$R 3.3.6.1.2 Temperature - Nish sa 3.3.6.1.5 sa 3.3.6.1.6 f.
Main steen Line Tunnet 1,2,3 2
1 SR 3.3.6.1.1 s 171*F Ashlent
$R 3.3.6.1.2 Tesperature - Nigh SR 3.3.6.1.5 sa 3.3.6.1.6 I
g.
Main steen Line Tunnet 1,2,3 2
I st 3.3.6.1.2 s 28 minutes
]
Temperature Timer st 3.3.6.1.5 SR 3.3.6.1.6 h.
RNR Neet Exchanger 1,2,3 2 per I
sa 3.3.6.1.1 s 160*F I
Ashtent room SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
]
1.
RCIC/RNR steen Line 1,2,3 2
I st 3.3.6.1.1 s 188 inches i
Flow Nigh SR 3.3.6.1.2 water j
SR 3.3.6.1.3 sa 3.3.6.1.5 i
sa 3.3.6.1.6 l
(continued)
CLINTON 3.3-58 AmendmentNo.g
.ie
.--~w w.-----
1 r-e
M acw LS-95-004 Page 10 of 13 Prinary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 5 f Primary Contaltinent and Drywett isolati natrumentation APPLICABLE CONolfl0Ns MCOEs OR REQUIRED REFERENCE 0 OTHER CHANNELS FROM SPECIFIED PER
. REQUIRE 0 SURVEILLANCE ALLOWABLE FUNCTION CONotil0NS FUNCTION ' Acil0N F.1 REQUIREMENTS VALUE 3.
RCic system Isolation (continued) 1 J. Drywell Pressure -
1,2,3 2
I st 3.3.6.1.1 s 1.88 psig High st 3.3.6.1.2 i
SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 k.
Manual Initiation 1,2,3 2
J SR 3.3.6.1.6 NA
- 4. Reactor Water Cleanup (RWCU) system Isolation a.
Offferential Flow -
1,2,3 2
1 SR 3.3.6.1.1 5 66.1 spo Nigh
$R 3.3.6.1.2 st 3.3.6.1.5 SR 3.3.6.1.6 b.
Offferentist 1,2,3 2
1 SR 3.3.6.1.2 s 47 seconds Ftow-Tleer SR 3.3.6.1.4 st 3.3.6.1.6 c.
RWCU Heat Exchanger 1,2,3 2 per room I.
st 3.3.6.1.1 s 205'F Equipment Room
$R 3.3.6.1.2 Temperature Nigh st 3.3.6.1.5 st 3.3.6.1.6 d.
RWCU Puip Rooms 1,2,3 2 per room i
SR 3.3.6.1.1 s 202'F Temperature High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 e.
Main steam Line Tunnel 1,2,3 2
I SR 3.3.6.1.1 5 171'F Ambient Tenperature-SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6 f.
Reactor Vessel Water 1,2,3 4
1 SR 3.3.6.1.1 2 47.7 inches Level-Low Low, SR 3.3.6.1.2 st 3.3.6.1.3 Level 2 SR 3.3.6.1.5 sR 3.3.6.1.6 (c) 4 0
SR 3.3.6.1.1 t 47.7 inches SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 g.
Stanchy Liquid control 1,2 2
L st 3.3.6.1.6 NA system Initiation h.
Manual Initiation 1,2,3 2
J SR 3.3.6.1.6 NA (c),(d) 2 N
SR 3.3.6.1.6 NA (continued)
(c) During operations with a potentist for draining the reactor vesset.
(d) During CORE ALTERAfl0Ns arvi daring movement of irradiated fuel assenblies in the primary or secondary contaltvoent.
CLINTON 3.3-59 AmendmentNo.JHI g
LS-95-004 Page 11 of 13 Priaary Containment and Drywell Isolation Instrumentation 3.3.6.1 l
Table 3.3.6.1 1 (page 6 J'
Prienry contaltwent and Drywett isolati notrumentation APPLICA8LE CONDITIONS MODES OR REFERENCED OTNER REQUIRtc FROM SPECIFIE0 CNANNELS PER REQUIRED
$URVEILLANCc ALLOWASLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE 5.
RM4 System Isolation a.
RNR Neat Exchanger 1,2,3 2 per room I
st 3.3.6.1.1 5 160*F Ambient SR 3.3.6.1.2 Temperature - Nigh SR 3.3.6.1.5 SR 3.3.6.1.6 l
b.
Reactor vessel Water 1,2,3(I) 4 I
sa 3.3.6.1.1 1 8.3 inches l
Level - Low, Level 3 SR 3.3.6.1.2 i
sa 3.3.6.1.3 l
sa 3.3.6.1.5 I
st 3.3.6.1.6 i
c.
Reactor Vessel Water 3(8) 4,5 4(h)
M sa 3.3.6.1.1 t 8.3 Inches Levet Low, Level 3 st 3.3.6.1.2 sa 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 l
l d.
Reactor vessel Water 1,2,3 4
I sa 3.3.6.1.1 1 147.7 l
Level Low Low Low, SA 3.3.6.1.2 inches Levet 1 sa 3.3.6.1.3 sa 3.3.6.1.5 st 3.3.6.1.6 l
e.
Reactor vesset 1,2,3 4
1 SR 3.3.6.1.1 s 150 psig l
Pressure - HIgh st 3.3.6.1.2 i
SA 3.3.6.1.3 sa 3.3.6.1.5 st 3.3.6.1.6 l
f.
Drywett Pressure-Nigh 1,2,3 8
I st 3.3.6.1.1 5 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SA 3.3.6.1.6 3 Manual Initiation 1,2,3 2
J SA 3.3.6.1.6 NA (f) With reactor steam dome pressure greater than or equal to the RNR cut In permissive pressure.
l (g) With reactor steam done pressure less than the RNR Cut in permissive pressure.
1 (h) only one trip system required In MODES 4 and 5 with RNR shutdown Cooling system Integrity malntained.
j 1
1 1
CLINTON 3.3-60 Amendment No. 95
LS-95-004 Pa8a 12 of 13 RPS Electric Power Monitoring 3.3.8.2 l
3.3 INSTRUMENTATION I
3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring l
LCO 3.3.8.2 One RPS electric power monitoring assembly shall be OPERABLE l
for each inservice RPS special solenoid power supply or alternate power supply.
APPLICABILITY:
MODES 1, 2, and 3, MO 4 and 5 with any control rod withdrawn from a core ontaining one or more fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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, inoperable.
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 Time of Condition A AND 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.
cell containing one or more fuel assemblies.
CLINTON 3.3-81 Amendment No pf
e LS-95-004 Page 13 of 13 Orywell 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
.....................................N T ES- - - - - - - - - - - - - h e 1.
Entry and exit is permissible to pe fo repairs of t components.
2.
Enter applicable Conditions and Required Actions of LCO 3.6.5.1, "Drywell," when air lock leakage results in exceeding overall drywell bypass leakage rate acceptance criteria.
(continued)
CLINTON 3.6-56 AmendmentNo.JHI
1
' a to U 602498 LS95-004 Page1of3 Technical Specifications Bases Changes i
i
MGTdRmana 2 So W%Vfi4%)
LS-95-004, Page 2 of 3 Control Rod OPERABILITY B 3.1.3 BASES (continued)
SURVEILLANCE 1R 3.1.3.1 REQUIREMENTS The position of each control rod must be determined, to ensure adequate information on control rod position is available to the operator for determining control rod OPERABILITY and controlling rod patterns. Control rod position may be determined by the use of OPERABLE position indicators, by moving control rods to a position with an OPERABLE indicator, or by the use of other appropriate methods. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR is based on operating experience related to expected changes in control rod position and the availability of control rod position indications in the control room.
h.e., the cueci
- 69. Freg un(3,npW6 SR 3.1.3.2 and SR 3.1.3.3 ge, gge
'O Control rod insertion capability is demonstrated by h
inserting each partially or fully withdrawn control rod at
)
least one notch and observing that the control rod moves.
The control rod may then be returned to its original i
position. This ensures the control rod is not stuck and is free to insert on a scram signal. These Surveillances are modified by notes identifying that the Surveillances are not 1
required to be performed when THERHAL POWER is less than or l
equal to the actual LPSP of the RPC since the notch insertions may not be compatible with the requirements of BPWS (LCO 3.1.6) and the RPC LLC 0 3.3.2.1).
These notes i
t also provide a time allowance such that the Surveillances n
are not recuired to be performed until the next scheduled control roc testing for control rods of the same category (i.e., fully withdrawn or partially withdrawn). These notes provide this allowance to prevent unnecessary perturbations in reactor operation to perform this testing on a control rodwhosesurveillancecategory(i.e.,fullywithdrawnor partiallywithdrawn)haschanged. The 7 day Frequency of SR 3.1.3.2 is based on operating experience related to the changes in CR0 performance and the ease of performing notch testing for fully withdrawn control rods.
Partially withdrawn control rods are tested at a 31 day Frequency, based on tha potential power reduction required to allow tb9 control rod movement,.and considering the large testing sample of SR 3.1.3.2.
Furthermore, the 31 day frequency takes into account operating experience related to changes in CRD performance. At any time, if a control rod is (continued)
G CL'INTON B 3.1-19 Revision No. 1 1
- to U 602498 e$, Di S LS-95-C04, Page 3 of 3 e, prode 9 c
Control Rod OPERABILITY B 3.1.3
, 4-o f ccMrMVM,
3 BASES O
SURVEILLANCE SR 3.1.3.2 and SR 3.1,l d (continued)
REQUIREMENTS immovable, a determination of that control rod's trippability (OPERABILITY) must be made and appropriate action taken.
SR 3.1.3.4 Verifying the scram time for each control rod to notch position 13 is s 7 seconds provides reasonable assurance that the control rod will insert when required during a DBA or transient, thereby completing its shutdown functions.
This SR is performed in conjunction with the control rod scram time testing of SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4.
The LOGIC SYSTEM FUNCTIONAL TEST in LCO 3.3.1.1, " Reactor Protection System (RPS)
Instrumentation," and the functional testing of SDV vent and drain valves in LC0 3.1.8, " Scram Discharge Volume (SOV)
Vent and Drain Valves," overlap this Surveillance to provide complete testing of the assumed safety function. The associated Frequencies are acceptable, considering the more frequent testing performed to demonstrate other aspects of control rod 0PERABILITY and operating ex)erience, which shows scram times do not significantly c1ange over an
/
operating cycle.
Coupling verification is performed to ensure the control rod is connected to the CRDH and will perform its intended function when necessary. The Surveillance requires verifying that a control rod does not go to the withdrawn overtravel position when it is fully withdrawn. The overtravel position feature provides a positive check on the coupling integrity, since only an uncoupled CRD can reach the overtravel position.
If the control rod goes to the withdrawn overtravel position, the control rod drive mechanism can be inserted to attempt recoupling, within the limitations of Condition C.
This verification is required to be performed anytime a control rod is withdrawn to the
" full out" )osition (notch position 48) or prior to declaring tie control rod OPERABLE after work on the control rod or CRD. System that could affect coupling. This includes control rods inserted one notch and then returned to the (continued)
CLINTON B 3.1-20 Revision No. 1-1 4