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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
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KITACllMENT L TECilNICAL SPECIFICATION PAGES )
TO IIE REISSUEI) !
i Unit 1. Delete Page 3/4 6 9e. i nis requires only reissuing overicaf Page 3/4 6 9d i with no changes. l r
Unit 2. Delete Page 3/4 6-9b. I Since this page has no overleaf, it can sirnply be deleted. ,
i TECilNICAL SI'ECIFICATION llASES l' AGES .
TO llE REVISEI) l Unit 1. Pages B3/412 and B3/413 Markups enclosed.
i Unit 2. Pages 03/412 and B3/413 Markups enclosed.
7 Nk kDO P
REACTIVITY CONTROL SYSTEM 5 BASES .
3/4.1.1.5 MINIMUM TTMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than SlgoF. This limitation is required to ensure 1) the moderator temperature coefficient is within its analy ed temperature range, 2) the protettive instrumentation is within its nomal operating range, 3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RTt ;g7 temperature.
3/4.1.2 B0 RATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The system also provides coolant flow following an 51A5 (e.g., during a Small Break LOCA) to supplement flow from the Safety injection System. The Small Break LOCA analyses assume flow from a single charging pump, accounting for measurement uncertainties and flow mal-distribution cffects in calculating a conservative value of :harging flow actually delivered to the RCS. The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow pathi, 4) boric acid pumps, 5) associated heat tracing systems, and 6) en emergency power supply from CPERABLE diesel generators.
With the RCS average temperature above 200 F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoper-abl e. Allowt.ble out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility _
safety from injection system failures during the repair period, pyg y The boration capability of either system is sufficien to provide a SHUT-DOWN MRGIN from all operating conditions of 3.0% ak/k a er xenon decay and cooldown to 2000F. The maximum boration capabilitv re irement occurs a_t EOL i gfull power equilibrium xenon conditions and r.4 res = s m v'l-G t r. N boric acid solution from the boric acid tanks or 55,527 gallons of 2300 J ppm borated water from the refueling water tank. However, to be consistent with the ECCS requirements, the RVT is required to have a minimum contained volume of 400.000 gallons during MODES 1, 2. 3 and 4. The maximum boron concentration of the refueling water tank shall be limited to 2700 ppm and the maximum boron concentration of the boric acid storage tanks shall be limited to 81 to preclude the possibility of boron precipitation in tie core durin.g long term ECCS cooling.
With the RCS temperature below 2000F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system bersmes inoperable.
Re visd \g NEC LcO er da4ed -.
CALVEF1 CLIFTS - UNIT 1 B 3/4 1-2 Amendment No. 27. M. M,104
' REACIVITY C0rm SYSTEMS BASES The boron caoability recuired below 200'T is8 based upon providing a 31 t.k/k SHUTDO, N MAR 31ti af ter xenon decay and cooldown froM00'T to 140'F. This condition recuiret eitherge: I M c' ' M coric acid solution from the boric acid tents.or 9.6 a gT1ons of 23no opm borated water from the refuelin; water tant ~g y g 7 6 ';
The OPERABILITY c' one boron injectier. system during REFUEL 1N3 eni,ures that tnis system is available for reactivity control while in MODE E.
3 /4.1. 3 MOVABLY COWPOL LSSEBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels.
The ACTION statements wnich pemit limited variations from the basic requirements are accorapanied by additional restrictions which ensure that the original criteria are cret.
The ACTION statements applicable to a stuck or untrippable CEA and to a large misalignment (> 15 inches) of two or more CEAs, require a prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUT-DOWN MARGIN.
For small misalignments (< 15 inches) of the CEAs, there is 1) a small degradation in the peakiiig factors relative to those assumed in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a small effect on the time dependent long tenn power distributions rela-tive to those used in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 3) a small effect on the available SHUTDOWN MARGIN, and 4) a small effect on the ejecter' CEA worth used in the safety analysis. Therefore, the ACTION statement associated with the small misalignment of a CEA permits a one hour time interval during which attempts may be made to restore the CEA to within its alignment require-ments prior to initiating a reduction in THERMAL POWER. The one hour time limit is sufficient to (1) identify causes- of a misaligned CEA, (2) I take appropriate corrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.
Revised b 3 NEC Leder dded . l CALVERT CLIFF 5 - UNIT 1 B 3/4 1-3 Amendment No. M. Myg 127
INSEl(13 For ik>th Units 1 and 2 IIASES 3/4.1.2
'Iloration Systems" INSERT 'N the concentration and volume of which are met by the range of values given in Speelfications 3.1.2.8 and 3.1.2.9, INSERT 'B' the requirements of which are met by Specification 3.1.2.73
REACTIVITY C0fl1ROL SYSTEMS
{ BASES <
3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICAllTY This specification ensures that the reactor will not be made critical
- with the Reactor C0niant System average temperature less than 515nF. This limitation is required to ensure 1) the noderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the pressurizer is capabic of being in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT NDT temperature.
3/4.1.2 BORAT!0N SYSTEMS U ~
The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The system also provides coolant fluw following a SIAS (e.g., during a Small Break LOCA) to supplement flow from the Safety Injection System. The Small Break LOCA analyses assume i
flow from a single charging pump, accounting for measuremer,t uncertainties and flow maldistribution effects in calculating a conservative value of charging flow actually delivered to the RCS. The components required to perform this I
function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid pumps, 5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200 F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure r: enders one of the systems inoper-ible. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety.from injection system failures during the repair period. jgg y' The boration capability of either system is sufficient a provide a SHUT-DOWN MARGIN frog, all operating conditions of 3.0% t.,k/k a er xenon decay and cooldown to 200 F. The maximum boration capability re irement occurs at E0L from_ full power equilibrium xenon conditions and ree res U W
% ' G boric acid solution from tne boric acid tanks or 55,627 gallons of 2300 ppm borated water from the refueling water tank. However, to be consistent with the ECCS requirements, the RWT is required to have a minimum contained volume of 400,000 gallons during MODES 1, 2, 3 and 4. The maximum boron concentration of the refueling water tank shall be limited to 2700 ppm and the maximum boron concentration of the boric acid storage tanks shall be limited to 8% to preclude the possibility of boron precipitation in the core during long term ECCS cocling.
With the RCS temperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity
! condition of the reactor and the additional restrictions prohibiting CORE l
, ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
l hvised by NRC Le ner dded .
Il CALVERT CLIFFS - UNii 2 B 3/4 1-2 Amendment No. 31, 29 123 l
REACTIVITY C0f! TROL SYSTDis I l
i BASES The boron capability reauired below 200 F is based uoon providing a 3t ak/k SHUTDOWN MARGIN af ter xenon decav_yd coolcown frotiOO*F to 140'F. This condition requires either U M = = m.
' :Jooric acid solution f rom the boric acid tanks or 9.W ea11ons of oJU ppm borated water from tne refueling water tank.
} pggg %
The OPERABILITY of one boron injection system durin; REFUELINC ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3 MOVABLECD:fRptASSEMBLIES L
The specifications of this section easure that (1) acceptable t/swer distribution limits are maintained (2) the minimum SHUT;0WN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable' levels.
The ACTION statements which permit limited variations f rom the basic recuirements are accompanied by additional restrictions wnich ensure that
'he original criteria are met.
(
The ACTION statements applicable to a stuck or untriocable CEA and to a large misali ment t (> 15 inches) of two or more CEAs, recuire a prompt shutdown of tne reactor since either of these conditions may be indicative of a possible loss of mechanical functional cacability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUT-DOWN MARGIN.
For small misalignments (< 15 inches) of the CEAs, tnere is 1) a small degradation in the pesking factors relative to those assumed in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a small effect on the* time dependent long term power districutions rela-tive to those used in generating LCOs and LSSS setooints for DNBR and linear heat rate, 3) a small effect on the available SHUTCOWN MARGIN, and 4) a small effect on the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated witn the small misalignment of a CEA permits a one hour time interval during which attempts may be made to restore the CEA to within its alignment require-ments prior to initiating a reduction in THERMAL POWER. Tne one hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs anc (3) minimize tne ef fects of xenon redistribution.
Revisd by NEC Leuer claked .
O CALVERT CLIFFS - UNIT 2 B 3/4 1-3 Arendment No. 6. 7y , /199 i23
INSElrIS For lloth Units I and 2 IIASES 3/4.1.2 "lloration Systems" INSERT 'A' the concentration and volume of which are met by the range of values given L" Specifications 3.1.2.8 and 3.1.2.9, INSERT '13' the requirements of which are met by Specification 3.1.2.7,
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