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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] |
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ATTACHMENT (1) :
f UNIT 1 -
TECHNICAL SPECIFICATION REVISED PAGES 3/45-5 BASES 3/4 5-2 t
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9311100171 931103 PDR ADDCK 05000317 D@
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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCE REQUIREMENTS (Continued)
- e. At least once per REFUELING INTERVAL by:
- 1. Verifying actsmatic i::lat4en :nd %terlock action of the Shutdc r. Occling Sysieai frem the Resctor Ccolant Syste-' when t-hs Redctoi Coviant Syaiem pre 55sre is abovc 200 pM4.-.
g
- 2. A visual inspection of the containment sump and verifying _
that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
- 3. Verifying that a minimum total of 100 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
- 4. Verifying that when a representative sample of 4.010.1 grams of TSP from a TSP storage basket is submerged, without agitation, in 3.5 + 0.1 liters of 77 + 10 F borated water from the RWT, the pH of the mixed solution is raised to > 6 _
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- f. At least once per REFUELING INTERVAL, during shutdown, by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation test signal.
- 2. Verifying that each of the following pumps str.rt automatically upon receipt of a Safety Injection Actuation Test Signal:
- a. High-Pressure Safety Injection Pump.
- b. Low-Pressure Safety Injection Pump. -
N-
\ fa;&i9 d e Shaidoux3 Coolm3 &le", @m- %ndske Meelock Meka 4 9ta%a ('colks Sys{em sacBod kokNad faldes Ctom belay ppMd l
&# a dawidd og. acM Rc5 p&ssaee sigazlol h 30ct ps;g l l
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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i
~
BASES pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
Portions of the Low Pressure Safety Injection (LPSI) System flowpath are comon to both subsystems. This includes the low pressure safety injection flow control valve, CV-306, the flow orifice downstream of CV-306, and the four low pressure safety injection loop isolation valves.
Although the portions of the flowpath are common, the system design is adequate to ensure reliable ECCS operation due to the short period of LPSI System operation following a design basis Loss of Coolant Incident prior to recirculation. The LPSI System design is consistent with the assumptions in the safety analysis. ;
The trisodium phosphate dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. The TSP provides this protection by dissolving in the sump water and causing its final pH to be raised to > 7.0.
The requirement to dissolve a representative sample of TSP in a sample of RWT water provides assurance that the stored TSP will dissolve in borated water at the postulated post LOCA temperatures.
The Surveillance Requirements provided to ensure OPERABILITY of each g component ensure that as a minimum, the assumptions used in the safety analyses are met and the subsystem OPERABILITY is maintained. The surveillance requirement for flow balance testing provides assurance that -
proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from -
exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. Minimum HPSI !
flow requirements for temperatures above 355 F are based upon small break T LOCA calculations which credit charging pump flow following an SIAS. .
Surveillance testing includes allowances for instrumentation and system !
leakage uncertainties. The 470 gpm requirement for minimum HPSI flow from i the three lowest flow legs includes instrument uncertainties but not system check valve leakage. The OPERABILITY of the charging pumps and the associated flow paths is assured by the Boration System Specification 3/4.1.2. Specification of safety injection pump total developed head ensures pump perfomance is consistent with safety analysis assumptions.
l Db IMERT A I
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'I CALVERT CLIFFS - UNIT 1 B 3/4 5-2 Amendment No./1/[ l 1
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INSERT A The surveillance requirement for the Shutdown Cooling System open permissive interlock provides assurance that the shutdown cooling suction isolation valves are prevented from .
being remotely opened when the RCS pressure is at or above the SDC System design suction pressure of 350 psia. The suction piping' a .e Low Pressure Safety Injection pumps is the SDC System component with the limiting design pressure rating. The interlock provides assurance that double isolation of the SDC System from the RCS is presened whenever RCS pressure is at or above the SDC System design pressure. The 309 psia value .
specified for this suneillance is the actual pressurizer pressure at the instrument tap elevation for PT-103 and PT-103-1 when the SDC System suction pressure is 350 psia. The -
Surveillance Test Procedure for this suneillance will contain the required compensation to be applied to this value to account for instrument uncertainties. This test is performed using a simulated reactor coolant system pressure input.
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L ATI'ACHMENT (2)
UNIT 2 TECHNICAL SPECIFICATION REVISED PAGES 3/45-5 BASES 3/4 5-2 9
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3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCE REQUIREMENTS (Continued)
- e. At least once per REFUELING INTERVAL by:
- 1. -Verifyiag entcinetic ischt4en-and-4nterlock action of-the- e Shtttdc n Cccling System fic; the Rescter Cooiani. 3ydem wiien
/ the-Reseter--Coolant Syst a-pr4ssure is above 300 psi . ;
- 2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by '-
debris and that the sump components (trash racks, screens, -
etc.) show no evidence of structural distress or corrosion.
- 3. Verifying that a minimum total of 100 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets. ,
- 4. Verifying that when a representative sample of 4.0 1 0.1 grams of TSP from a TSP storage basket is submerged, without agitation, in 3.510.1 liters of 77 1 10*F borated water from the RWT, the pH of the mixed solution is raised to > 6 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- f. At least once per REFUELING INTERVAL, during shutdown, by:
a 1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection Actuation test signal.
- 2. Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:
- a. High-Pressure Safety Injection Pump.
- b. Low-Pressure Safety Injection Pump.
Vc'R}Qyig & SWo<cdCeeb QN W 'A"1lSN'- INloelocl.
pgey& A Shu%n %6ng ysk.n 6 sacRea ice /ahM fakes feon ,
belM} /fieNec0 SA cl Sintu)2led ca aclua9 SCS feessu& slgnal
- h. 309 Psk-1 l
CALVERT CLIFFS - UNIT 2 3/4 5-5 AmencmentNo./sp_ l
/ l
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
BASES Portions of the Low Pressure Safety Injection (LPSI) System flowpath are comon to both subsystems. This includes the low pressure safety injection flow control valve, CV-306, the flow orifice downstream of CV-306, and the four low pressure safety injection loop isolation valves. Although the portions of the flowpath are comon, the system design is adequate to ensure reliable ECCS operation due to the short period of LPSI System operation following a design basis Loss of Coolant Incident prior to i recirculation. The LPSI System design is consistent with the assumptions in the safety analysis.
The trisodium phosphate dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. The TSP provides this protection by dissolving in the sump water and causing its final pH to be raised to > 7.0. The requirement to dissolve a representative sample of TSP in a sample of RWT water provides assurance that the stored TSP will dissolve in borated water at the postulated post LOCA temperatures.
The Surveillance Requirements provided to ensure OPERABILITY of each '
component ensure that at a minimum, the assumptions used in the safety analyses are met and the subsystem OPERABILITY is maintained. The surveillance requirement for flow balance testing provides assurance that a proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each' injection point is necessary to: (1) prevent total pump flow from exceeding runout conoitions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. Minimum HPSI flow requirements for temperatures above 305 F are based upon small break LOCA calculations which credit charging pump flow following a SIAS.
Surveillance testing includes allowances for instrumentation and system leakage uncertainties. The 470 gpm requirement for minimum HPSI flow from the three lowest flow legs includes instrument uncertainties but not system check valve leakage. The OPERABILITY of the charging pumps and the associated flow caths is assured by the Boration System Specifications 3/4.1.2. Specification of safety injection pump total gh ,
1 developed head ensures pump performance is consistent with safety analysis assumptions.
BERT%At temperatures of 305 F and less, HPSI injection flow is limited to less than or equal to 210 gpm except in response to excessive reactor coolant leakage. With excessive RCS leakage (LOCA), make-up requirements could -
exceed a HPSI flow of 210 gpm. Overpressurization is prevented by 1 i
)!
CALVERT CLIFFS - UNIT 2 3 3/4 3'-2 AmendmentNo.f4pj i
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i INSERT A i The surveihonce requirement for the Shutdown Cooling System open permissive interlock j provides assurance that the shutdown cooling suction isolation valves are prevented from '
l t
being remotely opened when the RCS pressure is at or above the SDC System design
(
suction pressure of 350 psia. The cuction piping to the Low Pressure Safety Injection pumps !
is the SDC System component with the limiting design pressure rating. The interlock provides assurance that double isolation of the SDC System from the RCS is preserved !
whenever RCS pressure is at or above the SDC System design pressure. The 309 psia value i
specified for this surveillance is the actual pressurizer pressure at the instrument tap i elevation for PT-103 and PT-10t1 when the SDC System suction pressure is 350 psia. The j Surveillance Test Procedure for this surveillance will contain the required compensation to . -
t be applied to this value to account for instrument uncertainties. This test is performed using !
a simulated reactor coolant system pressure input. l i
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