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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
Af fuhment j l
- f. . , .
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- TABLE 3.3-10 (Centinuedl j ACTION STATEMENTS ,
I ACTION 31 - With the number of OPEMBLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN .
. within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 32 - With the number of OPERABLE post-accident monitoring channels one less than the minimum channel operable requirement in Table 3.3-10, operatien may proceed provided the inoperable channel is restored to OPEPABLE status at the next outage of sufficient duration. l ACTION 33 - With the number of OPEPABLE post accident monitoring channels two less than required by Table 3.3-10, qither restore one inoperable channel to OPERABLE status whhin 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ,,, ,
r ACTION 34 - With the number of OPERABLE Post-Accident Monitoring Channels one
'f less than the minimum Channel OPERABLE requirement in Table 3.3-10, either restore the system to OPERABLE status within 7 days if repairs
/ are feasible without shutting down or prepare and submit a Special l -
Report to the Commission pursuant to Specification 6.9.2 within 30 days \
following the event, out!!ning the action taken, the cause of the Inoper-Q ability and the plans and schedule for restoring the system to g OPER ABLE status.
ACTION 33 - With the number of OPERABLE Channels two less than required by l-Table 3.310, either restore the Inoperable channel (s) to OPERABLE status within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> 11 repairs are feasible without shutting down ort ,
I 1. Initiate an alternate method of monitoring for core and reactor
- coolant system voiding; f
L 2. Prepare and submit a Specla! Report to the Commission pursuant I to, Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and
\ 3.
the Restore :: :=: r JfjhWM m' to OPERABLE status at the next i
scheduled refueling.
).
k0Y.O 9008080110 900803 PDR ADOCK 050003t7 P PDC CALVERT CLIFFS - UN T 1 3/4 3 41a Amendmenc No. /.'1,I
- . - . ~ . ..._ o l_ .
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fsh 3 of 9 INSTRUMENTAi!ON_
~
,' BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTAi!0N -
l The OPERABILITY of the' post-accident instrumentation ensures that sufficient infomation is available on selected plant This parameters capabilitytoissenitor
' and assess these variables following an accident.
consistent with the reconnendations of Regulatory Guide 1.97, 'Instrumen- .
tation for Light-Water-Cooled'Ncclear Plants ^to' Assess PlantnConditions <
During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tem Reconnendations." i s
- 3/4.3.3.7 FIRE DETEC'*!ON INSTRUMENTATION i' OPERABIt. TTY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of
- fires. This capability is required in order to detect and locate fires in their early stages. Prompt detecticn of fires will reduce the poten-tial for damage to safety related equipment and is an integral element p i in the overall facility fire prctection program.
In the event that a portion of the fire detection instrumentation '
i is inoperable, the establishment of frequent fire patrols in the affected
( areas is required to provide detection capability until the inoperable l
\~ Winstr.snentation f-is restored f to operability. W
' ~-
f The Subcooled Margin Monitor (SMM). the Heated Junction Thermocouple (HJTC), and the
Core Exit Thermocouples (CET) comprise the inadequate Core Cooling (ICC
,I required by item II.F.: NUREG-0737, the Post TMI-2 Action Plan. The function of the ICC ins.rumentation is to enhance the ability of the plant operator to diagnose the approach coolant
{i from, ICC. Additionally, they aid in tracking reactor
(
f to, inventory.
and recovery These instruments are included in the Technical Specifications at the r request of NRC Generic Letter 83-37. These instruments are not required by the accident j analysis, nor to bring the plant to HOT STANDBY or COLD SHUTDOWN. 3 y
in the event more than four sensors in a Reactor Vessel Level channel are inoperable, k i
repairs may only be possible during an extended COLD SHUTDOWN, This is because the sensors . are accessible only after the plant has been cooled down and drained, and the
[
missile shield has been moved if only one chance! is inoperable, it should be restored to OPERABLE status in accordance with the schedule outlined in a Special Report. if
,)
{
both channels are inoperable, u ':- n 1._ .: shall""be restored ? - .. . ;,, m.a to OPERABLE status ;
l in the next refueling outage. 'N ^. C . "a . . . . r vs . . .. m m d u..a. _. r x. .-.
r m %pf & ' J\ /Vww Amencment No. 25, 53,7/y, g-CALYEXT C'!FFS - UNIT 1 3 '!/4 3-3 l
I
- - -- - - .--- n _ _ _ _ _ _ _
- , .. Attaskmed J
\
Pspe .9 Cf 9 TABLE 3.3-10 (Centinued) i ACTION STATEMENTS ,' .
ACTION 31 - With the number of OPEPABLE post-accident monitoring channels
> less than required by Table 3.3-10, either restore the :
inoperable channel to OPEPABLE status within 30 days or be in i
. HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, ,
' ACTION 32 - With the number of OPE?ABLE post-accident monitoring channels
- one less than the minimum channel operable requirement in I Tabic 3.3-10, o; ration may proceed provided thr., inoperable l channel is restored to OPEPAELE status at the r. ext outage of I sufficient duration.
ACTION 33 - With the number of OPEPAELE post-accident meritoring channels two less than required by Table 3.3-10, either restore one inocerable channel to OPE?ABLE status within 30 days or be in HOT SMUTDOWN within the next 12 hcurs. ,
- +
/ ACTION 34 - With the number of OPERABLE Post-Accident Monitoring Channels one
/( less than the minimum Channel OPERABLE requirement in Table 3.3-10, either restore the. system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special */s Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the Inoper- .
ability and the plans and schedule for restoring the system to m OPERABl#E status.
!N ACTION 33 - With the number of OPERABLE Channels two less than required by Table 3.3-10, either restore the Inoperable channel (s) to OPERABLE g status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without 'shuttirg down or:
- 1. Init!ste an alternate method of monitoring for core and reactor i
.( coolant system voiding;
- 2. Prepare and submit a Special Report to the Commission pursuant -
to Specification 6.9.2 within 30 days following the event; outlining the action taken, the cause of the inoperability and the plans and ,
s schedule for restoring the system to OPERABLE status; and :
- 3. Restore rYht 'r ..~Af3 ftet to OPERABLE status at the next
.......... s,. !
s scheduled refueling. I
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N
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n/ / .,/. _
a
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CALVERT CL:FFS - UNIT 2 3/4 3 als Amene.me" No. $,I
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- f 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION
' l
. The OPEPABILITY of the post-accident instrumentation ensures that 8 sufficient information is available on selected plant parameters to u' renitor and assess these variables following an accident. This capability is consistent with the rec:.mendations of Regulatory Guide 1.97, "Instru-mentation for Light-Water-cooled Nuclear Plants to Assess Plant Conditions ' 1 During and Following an Accident," December 1975, and NUREG-0578 "TMI-2 l Lessons Learned Task Force Status Report and Short-Term Recocinendations." !
, [' ,
- y l
. 3/4.3.3.7 FIRE CETECTION INSTRUMENTATION OPETA ILITY of the fire detection instr.: mentation ensures that adequate warning capability is available for the prompt detection of
- fires. This capability is required in order to detect and locate fires in their early stages. Prempt detection of fires will reduce the poten-l tial for damage to safety related equipment and is an integral ele..sent - -
in the overall facility fire protection program.
In the event that a portion of the fire detection instr'.snen+ation is inoperable, the establish:nent of frequent fire patrols in the affected
! areas is retuired to provide detection capability until the inoperable instn.snentation is rest.cre.d t.o operability.
The Subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the Core Exit Thermocouples (CET) comprise the Inadequate Core Cooling (ICC) instrumentation
/ required by item !!.F.2 NUREG-0737, the Post TM1-2 Action Plan. The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach ',
to, and recovery from, ICC. Additionally, they aid in tracking reactor coolrnt inventory. These instruments are included in the Technical Specirhations at- the request of NRC Generic Letter 83-37. These instruments are not required by the accident ,
analysis, nor to bring the plant to HOT STANDBY or COLD SHUTDOWN.
f I l In the event more than four sensors in a Reactor Vessel Level chant el are inoperable, repairs may only be possible during an extended COLD SHUTDOWN. Th.s is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield' has been moved. If only one channel is inoperable, it- shou'd be restored to OPERABLE status in accordance with the schedule outlined in a Speciel ' Report. if ,
both channels are inoperable, '-
I shall be restored to OPERABLE status
/ in the next refueling outage. i.N OTC. M .c; = "' 'h - " t'? t;-enemped-I L
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/t up CALYEXT CLIFFS - UNIT 2 S 3M 3-3 knendmen No II, ;g,7.A.
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