Proposed Tech Spec Replacing Pages 3/4 6-23 & 3/4 6-25 & Adding 3/4.6.1.8 & 3/4.9.14 to Reflect Addition of Safety Injection Actuation Signal to Containment Hydrogen Purge Outlet ValvesML20087M882 |
Person / Time |
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Site: |
Calvert Cliffs ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
03/26/1984 |
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From: |
BALTIMORE GAS & ELECTRIC CO. |
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To: |
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Shared Package |
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ML20087M876 |
List: |
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References |
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NUDOCS 8404020106 |
Download: ML20087M882 (9) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K0641999-09-0101 September 1999 Proposed Tech Specs,Changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2,correcting Dc Voltage & Degraded Voltage Settings in SR 3.3.6.2 & Correcting Typo in TS 5.6 ML20211G7681999-08-27027 August 1999 Proposed Tech Specs,Allowing Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities While Irradiated Fuel Assembly Movement Continues in SFP ML20196E2191998-11-30030 November 1998 Proposed Tech Specs,Allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 Repair Sleeves ML20195K3831998-11-20020 November 1998 Proposed Tech Specs Removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section XI, Subsections IWE & Iwl,Per 10CFR50.55a ML20195J7181998-11-19019 November 1998 Proposed Tech Specs 3.7.6, SWS, Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20155F7001998-10-30030 October 1998 Proposed Tech Specs Bases,Revs 1,2 & 3 Re List of Effective Pages for Plant ML20154N1961998-10-16016 October 1998 Proposed Tech Specs Pages,Revising TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20236S5621998-07-20020 July 1998 Proposed Tech Specs Providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20217D2691998-04-21021 April 1998 Proposed Tech Specs Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging ML20216H0831998-03-16016 March 1998 Rev 13 to Proposed TS Re Conversion to Improved TSs ML20199J5281998-01-28028 January 1998 Proposed Tech Specs,Converting to Improved TSs ML20198K9851998-01-12012 January 1998 Rev 11 to Proposed Tech Specs,Reflecting Conversion to Improved Sts,Per NUREG-1432 ML20198R7331997-11-0505 November 1997 Proposed Tech Specs Pages Re Rev 10 to Convert to Improved TS ML20217K6161997-10-23023 October 1997 Proposed Tech Specs Section 3.8 Re Change Request to Convert to Improved Std TSs ML20217K6671997-10-22022 October 1997 Proposed Tech Specs Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20198K3321997-10-20020 October 1997 Proposed Tech Specs Section 3.3 Re Change Request to Convert to Improved Std TSs ML20217G3571997-10-0606 October 1997 Proposed Tech Specs Section 3.6 to Reflect Conversion to Improved STS ML20217G3781997-10-0606 October 1997 Proposed Tech Specs Section 3.7 Re Change Request to Convert to Improved STS ML20211J2751997-10-0202 October 1997 Proposed Tech Specs,Reflecting New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20217C7361997-09-29029 September 1997 Proposed Tech Specs Page Omitted from 970609 License Amend Request Re Conversion to Improved TSs ML20210T8701997-09-10010 September 1997 Proposed Tech Specs Rev 5 to Section 3.4 of Original License Amend Application & Other Changes Identified by Personnel ML20210K9711997-08-14014 August 1997 Proposed Tech Specs,Reflecting Removal of TSTF-115,as Well as Other Changes Identified by Plant Personnel ML20149H5821997-07-21021 July 1997 Rev 2 to TS Sections 4.0 & 5.0,converting to Improved Std Tss,Per NUREG-1432 ML20148P7171997-06-27027 June 1997 Proposed Tech Specs Revising Wording to Support Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20135F0441997-03-0606 March 1997 Proposed Tech Specs,Superceding Previously Submitted Marked Up Pp for ABB-CE Sleeves.New Info to Be Incorporated in Updated Licensing rept,CEN-630-P,Rev 01, Repair of 3/4 OD SG Tubes Using Leak Tight Sleeves ML20134E3361997-02-0303 February 1997 Proposed Tech Specs Vol 17,Unit 2 Current Markup Improved Conversion License Amend Request ML20134E3221997-02-0303 February 1997 Proposed Tech Specs for Vol 16,Unit 1 Current Markup Improved Conversion License Amend Request ML20134D3041997-01-31031 January 1997 Proposed Tech Specs Re Requirements to Allow Increased SG Tube Plugging ML20135A5231996-11-26026 November 1996 Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20134N1831996-11-20020 November 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML20128H6031996-10-0303 October 1996 Proposed Tech Specs,Changing Provisions for Receiving, Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7991996-09-10010 September 1996 Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys ML20117L3441996-09-0404 September 1996 Proposed Tech Specs Clarifying License Amend Request Re Implementation of Changes to Radiological Effluent TSs as Proposed by GL 89-01 ML20116F8281996-08-0101 August 1996 Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation ML20116E3771996-07-26026 July 1996 Proposed Tech Specs Allowing Repair of Defective SG Tubes by Electrosleeving ML20117F6431996-05-15015 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls ML20101K6011996-03-28028 March 1996 Proposed TS Figure 3.1.1-1 Re Change to Moderator Temp Coefficient ML20096D4461996-01-16016 January 1996 Proposed Tech Specs,Adopting Option B of 10CFR50,App J to Require Type a Containment Lrt to Be Performed on performance-based Testing Schedule ML20095K2761995-12-21021 December 1995 Proposed Tech Specs,Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15 ML20095C7471995-12-0707 December 1995 Proposed Tech Spec to Add Analysis Technique to List of Approved Core Operating Limits Analytical Methods in TS for Plant ML20094S1531995-11-30030 November 1995 Proposed Tech Specs,Allowing Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20094D6171995-11-0101 November 1995 Proposed Tech Specs,Upgrading ESF Electrical Sys at Plant to Provide Addl Protection from Loss of Electrical Power ML20093M4291995-10-20020 October 1995 Proposed Tech Specs,Extending 18-month Surveillances to 960331 ML20098C0741995-10-0202 October 1995 Proposed TS 3.7.6.1,extending Action Statements a & B from 7 Days to 30 Days for Loss of Emergency Power ML20086N2551995-07-13013 July 1995 Proposed TS 5.2.1, Fuel Assemblies, Allowing Use of Cladding Matls Other than Zircaloy or ZIRLO W/Approved Temporary Exemption to 10CFR50.46,10CFR50.44 & 10CFR50,App K & Allowing Use of Lead Fuel Assemblies ML20085D5091995-06-0909 June 1995 Proposed Tech Specs,Implementing Changes to Radiological Effluent TS Per GL 89-01 ML20084R0171995-06-0606 June 1995 Proposed Tech Specs Reflecting Extension of Certain 18-month Frequency Surveillances to Refueling Interval ML20084P9741995-06-0202 June 1995 Proposed Tech Specs Re Pressurizer Safety Valves Lift Tolerance ML20087H9281995-04-28028 April 1995 Proposed Tech Specs Re Extension of Allowed Outage Time ML20081D0551995-03-15015 March 1995 Proposed Tech Specs Re Reformation of Current Administrative Controls Section of Plant TS & Relocation of Several Requirements to Other Documents & Programs 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K0641999-09-0101 September 1999 Proposed Tech Specs,Changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2,correcting Dc Voltage & Degraded Voltage Settings in SR 3.3.6.2 & Correcting Typo in TS 5.6 ML20211G7681999-08-27027 August 1999 Proposed Tech Specs,Allowing Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities While Irradiated Fuel Assembly Movement Continues in SFP ML20207F0261999-06-0101 June 1999 Third Interval Inservice Insp Program Plan for Ccnpp,Units 1 & 2 ML20195B2751999-03-31031 March 1999 Rev 0 to Rept 98-FSW-021, Corrosion Test of SG Tubes with Alloy 800 Mechanical Sleeves ML20204H6011999-01-29029 January 1999 Age Related Degradation Insp (Ardi) Program Technical Requirements Document for Mechanical Systems ML20196E2191998-11-30030 November 1998 Proposed Tech Specs,Allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 Repair Sleeves ML20195K3831998-11-20020 November 1998 Proposed Tech Specs Removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section XI, Subsections IWE & Iwl,Per 10CFR50.55a ML20195J7181998-11-19019 November 1998 Proposed Tech Specs 3.7.6, SWS, Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20155F7001998-10-30030 October 1998 Proposed Tech Specs Bases,Revs 1,2 & 3 Re List of Effective Pages for Plant ML20154N1961998-10-16016 October 1998 Proposed Tech Specs Pages,Revising TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20198A2981998-09-15015 September 1998 Technical Procedure CP-217,rev 7,PCR 98-034, Specifications & Surveillance,Secondary Chemistry ML20198A3131998-09-15015 September 1998 Technical Procedure CP-224,rev 4,PCR 97-049, Monitoring Radioactivity in Systems Normally Uncontaminated ML20236S5621998-07-20020 July 1998 Proposed Tech Specs Providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20195B2861998-06-0505 June 1998 Rev 0 to Rept 98-TR-FSW-005, Test Rept on Alloy 800 Mechanical Sleeve-Addl Qualification Testing Using Low Yield Strength Tubing ML20217D2691998-04-21021 April 1998 Proposed Tech Specs Re Change to Reactor Coolant Sys Flow Requirements to Allow Increased SG Tube Plugging ML20216H0831998-03-16016 March 1998 Rev 13 to Proposed TS Re Conversion to Improved TSs ML20198A2911998-02-23023 February 1998 Technical Procedure CP-206,rev 4,PCR 98-034, Specifications & Surveillance Component Cooling/Service Waster System ML20199J5281998-01-28028 January 1998 Proposed Tech Specs,Converting to Improved TSs ML20198K9851998-01-12012 January 1998 Rev 11 to Proposed Tech Specs,Reflecting Conversion to Improved Sts,Per NUREG-1432 ML20198R7331997-11-0505 November 1997 Proposed Tech Specs Pages Re Rev 10 to Convert to Improved TS ML20217K6161997-10-23023 October 1997 Proposed Tech Specs Section 3.8 Re Change Request to Convert to Improved Std TSs ML20217K6671997-10-22022 October 1997 Proposed Tech Specs Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20198K3321997-10-20020 October 1997 Proposed Tech Specs Section 3.3 Re Change Request to Convert to Improved Std TSs ML20217G3571997-10-0606 October 1997 Proposed Tech Specs Section 3.6 to Reflect Conversion to Improved STS ML20217G3781997-10-0606 October 1997 Proposed Tech Specs Section 3.7 Re Change Request to Convert to Improved STS ML20211J2751997-10-0202 October 1997 Proposed Tech Specs,Reflecting New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20217C7361997-09-29029 September 1997 Proposed Tech Specs Page Omitted from 970609 License Amend Request Re Conversion to Improved TSs ML20211J2981997-09-18018 September 1997 Pump & Valve IST Program Third Ten-Yr Interval for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20210T8701997-09-10010 September 1997 Proposed Tech Specs Rev 5 to Section 3.4 of Original License Amend Application & Other Changes Identified by Personnel ML20210K9711997-08-14014 August 1997 Proposed Tech Specs,Reflecting Removal of TSTF-115,as Well as Other Changes Identified by Plant Personnel ML20149H5821997-07-21021 July 1997 Rev 2 to TS Sections 4.0 & 5.0,converting to Improved Std Tss,Per NUREG-1432 ML20148P7171997-06-27027 June 1997 Proposed Tech Specs Revising Wording to Support Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20141G4471997-06-16016 June 1997 Ccnpp Unit 2 Cycle 12 Startup Testing Rept ML20141D9341997-05-0909 May 1997 Radiation Safety Procedure 1-104, Area Posting & Barricading & High Radiation Area Pre-Entry Checklist ML20135F0441997-03-0606 March 1997 Proposed Tech Specs,Superceding Previously Submitted Marked Up Pp for ABB-CE Sleeves.New Info to Be Incorporated in Updated Licensing rept,CEN-630-P,Rev 01, Repair of 3/4 OD SG Tubes Using Leak Tight Sleeves ML20134E3221997-02-0303 February 1997 Proposed Tech Specs for Vol 16,Unit 1 Current Markup Improved Conversion License Amend Request ML20134E3361997-02-0303 February 1997 Proposed Tech Specs Vol 17,Unit 2 Current Markup Improved Conversion License Amend Request ML20134D3041997-01-31031 January 1997 Proposed Tech Specs Re Requirements to Allow Increased SG Tube Plugging ML20210P3971996-12-0404 December 1996 Rev 2 to RP-2-101, Administrative Procedure Radwaste Mgt ML20135A5231996-11-26026 November 1996 Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20134N1831996-11-20020 November 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML20210P3871996-10-17017 October 1996 Rev 2,Change 0 to Offsite Dose Calculation Manual ML20128Q8041996-10-14014 October 1996 Cycle 13 Summary of Startup Testing ML20128H6031996-10-0303 October 1996 Proposed Tech Specs,Changing Provisions for Receiving, Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7991996-09-10010 September 1996 Proposed Tech Specs 3/4.3 Re instrumentation,3/4.5 Re ECCS & 3/4.6 Re Containment Sys ML20117L3441996-09-0404 September 1996 Proposed Tech Specs Clarifying License Amend Request Re Implementation of Changes to Radiological Effluent TSs as Proposed by GL 89-01 ML20116F8281996-08-0101 August 1996 Proposed Tech Specs Re Use of Blind Flanges in Place of Containment Purge Valves During Operation ML20116E3771996-07-26026 July 1996 Proposed Tech Specs Allowing Repair of Defective SG Tubes by Electrosleeving ML20117F6431996-05-15015 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls ML20101K6011996-03-28028 March 1996 Proposed TS Figure 3.1.1-1 Re Change to Moderator Temp Coefficient 1999-09-01
[Table view] |
Text
'h2M;N(; ?
I CONTAINEllT SYSTEMS CONTAte W T VENT SYSTEM LIMITINS CON 0! TION FOR OPERATION 3.6.1.8 The containment vent isolation valves MOV 6900 and MOV 6got shall be maintained closed by tagging the motor power supply breakers opes and main-taining the keyed hand switches locked in the closed position.
~
APPLICA81LITY: MODES 1. 2, 3 and 4 ACTION:
With one or both containment vent isolation valves open, close the open valve (s) within one hour or be in at least HOT STAN08Y 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 />.
SURVEILLANCE REQu!REMENTS 4.6.1.8 The containment vent isolation valves shall be determined closed at least once per 31 days by verifying that power to the motor operators is removed and the valves indicate shut.
CAlfMf cuffs ~ MIT A 3lh 4-9 b Anrenbu i No.
Ca'! :" CLITT; "r:T 1 J 3/' 0-% .txt;tE.;;
e404020106 g @g@ g PDR ADOCK 0 PDR p . . . . .
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9 TABLE' 3.6-1 (Continued) IdI
.: D G ^ TI '
'g" CONTAIN11ENT ISOLATION VALVES P ISOLATION ISOLATION VALVE ISOLATI0ft :< UA PENEIRATION NO. CilANNEL IDENTIFICATION N0. FUNCTION TIME (SECON05) pg
$Ut *
~
238-1 Fire Prot'ection MA (
e 44 NA NA 238-1 ~ NA N-.
c d
, }y
}
NA liOV-6200
,w yirf 47A NA SV-6540A Ilydrogen Sample Outlet
~
NA d p;j ,.*
- P.-
Ilydrogen Sample Outlet NA 4 N '-
SV-6540E 478 NA HA SV-6507E NA
(
DJ m
$ 'g 5?a m 47C NA SV-6540F Hydrogen Sample Outlet HA Pi[dj NA SV-6507F NA d
),y h -( ' ik
) 61 470 NA
~
SV-6540G Hydrogen Sample Return HA . ( > lf ?,1 MA SV-6507G NA 4
>l h
& &20** > -
EI 40A % blAs A n0V-6g00 "; ::;;;. " :;: h tt:t ,
itA SIAS B MOV-6901 Containment bt Jso/dien ftk 620d" g 4
,, g R . w a . 4
. - [-
a h.
l
~: ,;
e,,
- ?
TABLE _3.6-1_(Continued),
9
-@Q, 9 C0tITAlti!!EtiT ISOLA, TION VALVES
.g 9 PENETRATION ISOLATION ISOLATION VALVE ISOLATION P Pj MO. CilANNEl. tDJ,tg,,QCAT 1 QOMI,0,., rtiittiIUN TIPIE,15E,C,1)NDS)
E P.]
y~
- 61 NA 76Y-1 Refueling Pool Outlet NA q /
G NA 293M-1 tIA .
>[j
. NA 293N-1 NA 1 R
c NA 293ff-1 - NA . k h . . . _ _. :.. ..{
v.
62 S!AS A HOV-6579 Containment Ileating Outlet ~
<13 14 q;7 64 NA 238-1 Contairment lleating Inlet flA
}
43
. *.C g (1) Hanual or remote manual valve which is closed during plant operation.
-c I (2) May be opened below 300*F to establish shutdown cooling flow. .lg b andconfeinment vent di (3) Containment purgeA respectuelt .
i solation valves will be shut in MODES 1, 2. 3 and 4 per TS 3/4 6.1.7. emd up4.2 4. [.f 3
- May be open on an intermittent basis under administrative control.
fj],;
'y
- Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during which time "I these valves may be opened.
time these valves must renain closed.
Isola tion a time ls ilA for !! ODES 1. 2. 3 and 4 per TS forcentainnat piety a~d containnent vent isolohen voin f 7
and U-VY S /1C *F*CNh
_ g-8 2
"N" m, j
G ')
- x ys.
I, K y $ t? @ M f W ' " E l A n k a rs t w a o ,d A A W M s * ~^ '
- 'W^'
..CM7381Nr4ENT VEH*f T5blA7/OAl VALVt S 4/M/71Ndr dbNbf 7/od FOR OPERATibH 3.9.ILI The con +ainment vent iso /abon atives slett he closed.
APPLI CA 8ILITY: buring CoRC Al~rf/447 tons or noveHeset of arra do'a +e d . fuel u W,ih +he coala,'ament.
AC7 ton: wHf one or trore. toAtarnmen f vent isoklion valves opers, sAu t the valves within one. houe or suspend all operations involvikg consatrEMnons or prover nent of irradiated fuel withik the.
contaihmerst. 7%e provkian.s of speciAcation s.o.s are not applicable.
SU R Vt/LL ANe L M Oll/ATMTN Ts
- 4. 9. lt The con taihnen t vent hoiation nn/ves skII be de ternined to be closed withsh 7S hours prior to +As start of and at lea.rt esce per 7 days ALTERATIONS or moverten t of kred'ititd r
dunhglcoas lse Milbth.
the contaihmen t.
envenr euers - tw7.t. .s/v 9-n smendnent No.
l
- "p'y ?:n } """t "'T "
REFUELING OPERATIONS l BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WArtM LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.
The minimum water depth is consistent with the assumptions of the accident ar.alysis. ,
3/4.9.12 SPENT FUEL P00L VENTILATION $YSTEM The limitations on the spent fuel pool ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERA 8ILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
3/4.9.13 SPENT FUEL CASK HANDLING CRANE The restriction on. movement of the spent fuel shipping cask within one cask length of any fuel assembly ensures that in the event this load is dropped (1) the stored spent fuel l assemblies will not be damaged, and (2) any possible distortion of fuel in the storage racks will not result is a critical array, 2le 4A coNTmMMENf VENT 1soLA7/oM #t.VES The operabilHy an d c.losure. re.sirietions on the conia& ment vent isolaHon' valves are sa Nicient to res +ric t raa%acr%e malerdrf relense fan a l'ae i element rup ture based upon the lack sf containesent pressuriretten po ten tial aMe in the. &EfuGUNG mod 2, b reno %en/ Mo.
4 CALVERT CLIFFS - UNIT 2 8 3/4 9 3 4+
_ = =----_- _ _ - - . - - - - - - - - - _ _ _ _ _ _ _ . - _ - - - - _ _
,'q' '- -- '
~t e;~ ;- y, ; ,. _ ,,, _ ,,;'
., , % yi0 . Mr 2 pg l , ;
WAtleENT SYSTDt3 ,
llWWif VENT SYSTEM LIMIT CONDITION FOR OPERAft0N 3.6.1.8 containment vent isolation valves MOV 6900 and MOV 690 shall be estatal closed by tagging the estor power supply breakers open main-taining kqed hand switches locked in the closed position.
APPLICABILITY: M00E5 1. 2. 3 and 4 4CT!0N:
With one or both c inment vent isolation valves close the open valve (s) within one or be in at least HOT STANDS 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 within the following 30 rs.
SURVE!LLANCE REQUIREMENTS ,
s 4.4.1.8 The containment vent isola i valves shall be determined closed at least once per 31 days by verifying t power to the motor operators is removed and the valves indicate s .
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CAL'JERT CLIFF 5 - UNIT 2 . 3/4 6-23 Anendment No.
.lI l, 5 TABLE 3.6-1 (Continued)
CONTA1181ENT ISOLATION vat.VES g.
,h ISOLATION 4 PENETRATION ISOLATION ISOLATION VALVE TIME (SECONDS) ?
<s N0. CHANNEL IDENTIFICATION NO. FUNCTION C Refueling Pool Outlet NA <[
76Y-1 A 61 NA ~ NA ^
NA
g t, MOV-6579 Contalrunent Heatin3 Outlet 113 62 $1AS A 5
NA 238-1 Containment Heating Inlet NA 64 <
. j g (1) Manual or remote manual valve which is closed during plant operation. w
. ?'
. (2) May be opened below 300*F to establish shutdown cooling flow. _,-
m e rf :::ttrrt ;;;t isolation valves will be shut in MODES 1. 2. 3 and 4 >!
'" (3) Containment p ;.J per TS 3/4 6. . .;;d !; 3/0 0.I.O. r;;;;;t h;!y.
- Hay be open on an intermittent basis under administrative control.
- Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during JJ which time these valves may be opened. Isolation time for containment purge : f :::t:t z:t g .went.1 solation valves is NA for MODES 1. 2. 3 and 4 per TS 3/4 6.1.7 ::d T 2/10.1.3, g 1 g :::;::ttrb, during which time these valves must remain closed. -;i 3
n e
4 e
g
-k. .
g . . . _ ,
1.
1
f s ,, , ..
s i TABLE 3.3-9 REMOTE SHUTDOWN HONITORING INSTRUMENTATION MINIMUM k' READOUT MEASUREMENT CHANNELS
]1 . INSTRUMENT LOCATION RANGE OPFRABLE
~s HE 1. Wide Range Neutron Flux /#CY3 0.1 cps- M 1 h A
m%.
% 2. Reactor Trip Breaker
. Cable Spreading Indication Room OPEN-CLOSE 1/ trip breaker g.4
- p. ~
i; ^'
M
- 3. Reactor Coolant Cold Leg Temperature 2C43 212-7050F 1 (
L- 4. Pressurizer Pressure 2C43 0-1600 psia 1 II .
In,R L.E"* 5. Pressurizer Level 2C43 0-360 inches 1
- 6. Steam. Generator Pressure 2C43 0-1200 psig 1/ steam generator (i{W
/ 7. Steam Generator Level 2C43 -401 to +63.5 , inches 1/steamgenerator{.
,.;4 L
iN p? .
. T
- = = = = = "
l&eted ir, t;.e Axiiier, . ccdw;ter ;;eg.,. res..
mn
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Attachment No. 3 s h
- c. n,
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