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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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NITACllMENT (1)
UNIT 1 TECIINICAL SPECIFICATION REVISED MARKED UP PAGES l
1 I
9403250135 940317 3 PDR pon P
ADOCK05000317]i
t INSERT A (for Technical Specification 3.4.3 Actions)
- a. If one or both PORV(s) has excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close the associated block valvc(s) and ruaintain power to the block valve (s).
- b. With one PORV inoperable due to causes other than excessive PORV seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 5 days or be in HOT STANDBY within the next E hours and at or below 365'F within the following M hours.
- c. With both PORVs inoperable due to causes other than excessive PORV seat leakace. within I hour either restore one PORV to OPERABLE status or close the associated block valve and remove power from the block valve: restore one PORV to OPERABLE status within the followinc 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and at or below 365'Fwithin the followinc 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. With one or both block valve (s) inoperable, within I hour restore the block valve (s) to OPERABLE status or place its associated PORV(s)in override closed. Restore at least one '
block valve to OPERABLE status within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if both block valves are inoperable: restore any remainine inoperable block valve to OPERABLE status within the followine 5 day; otherwise, be in at least HOT STANDBY within the next R hours and at or below 365
- F within the following M hours.
t
- - - - - -, ~. - - , ,
INSERT H (finr Technical Specification 3/4.43)
Above 365'E At or below 365'IMpecification 3/4.4.9.3 annlics :
l l
h
[
I I
~.,,._ , _ - , . - . . - - - -
r , , . . , ,
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Overpressure Protection Systems LIMITING CONDITION FOR OPERATION 3.4.9.3 The following overpressure protection requirements shall be met:
- a. One of the following three Overpressure Protection Systems shall be in place: -
- 1. Two power ..r ated relief valves (PORVs) with a setpoint t~.cc the curve in Figure 3.4.9-3*f~iIr, ShuwesoW
- 2. A single PORY with a trip setpoint below the curve in Figure 3.4.9-3Mnd a Reactor Coo ant _SyitJmysnta t I.3 square incMt, or wN4 ys oas aAle@ b'och $4c.oPN ,
- 3. A Reactor Coolant System (RCS) vent 12.6 square inches.
- b. Two high pressure safety injection DIPSI) pump ' shall be disabled by either removing (racking out) their motor circuit breakers from the electrical power supply circuit, or by locking shut their discharge valves.
- c. The HPSI loop motor operated valves (MOVs)' shall be prevented from automatically aligning HPSI pump flow to the RCS by placing their hand switches in pull-to-override.
- d. No more than one OPERABLE high pressure safety injection pump with suction aligned to the Refueling Water Tank may be used to ,
inject flow into the RCS and when used, it must be under manual !
control and one of the following restrictions shall apply:
- 1. The total high prer* + safety injection flow shall be limited to 5 210 gp. 4 l
- 2. A Reactor Coolant System vent of a 2.6 square inches shall exist.
- e. When not in use, the above OPERABLE high pressure safety !
injection pump shall have its handswitch in pull-to-lock. '
APPLICABILITY: When the RCS temperature is 5 365*F and the RCS is vented I to < 8 square inches. !
When on snutdown cooling. *he PORV trip setpoint shall be 5 429 psia. l EXCEPT wnen required for testing.
CALVERT CLIFFS - UNIT 1 3/4 4-32 Amencment :4o. MY .
3/4:4 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
ACTION: ,W n bf.5 N
- a. With one PORY inoperable? either restore the inoperable PORY to OPERABLE status within 5 days or depressurize and vent the RCS through a 1 1.3 square inch vent (s) within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; D maintain the RCS in a vented condition until both PORVs have been 948 7d56C0 @ restored to OPERABLE status.
g With both PORVs inoperable, depressurize and vent the RCS through a 2 2.6 square inch vent (s) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; maintain the RCS in a vented condition until either one OPERABLE PORY and a vent of 11.3 square inches has been established or both PORVs have been restored to OPERABLE status.
't" r t" eoev ac8 *< > e t-GB mitigate 1 t" a RCS t
pressuret"transient, a Special Report s prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the ,
PORVs or vent (s) on the transient and any corrective action ;
necessary to prevent recurrence.
h With less than two HPSI pumps' disabled, place at least two HPSI pump handswitches in pull-to-lock within fifteen minutes and _- _ 1 disable two HPSI pumps within the next four hours.
- With one or more HPSI loop MOVs' not prevented from automatically p I aligning a HPSI pump to the RCS, imediately place the MOV l handswitch in pull-to-override, or shut and disable the affected MOV or isolate the affected HPSI header flowpath within four hours, and implement the ACTION requirements of Specifications 3.1.2.1, 3.1.2.3, and 3.5.3, as applicable.
l With HPSI flow exceeding 210 gpm while suction is aligned to the l RWT and an RCS vent of < 2.6 square inches exists, j
- 1. Imediately take action to reduce flow to less than or equal to 210 gpm. l ,
- 2. Verify the excessive flow condition did not raise pressure l above the maximum allow ble pressure for the given RCS l temperature on Figure 3.4.9-1 or Figure 3.4.9-2. j i
l i
EXCEPT wnen recuired for testing.
CALVERT CLIFFS - UNIT 1 3/4 4-33 AmencmentNo.y)[
3/4.4 REACTOR COOLANT SYSTEM BASES limit includes allowances for instrumentation uncertainty, charging pump flow addition and RCS expansion following loss of decay heat removal. The HPSI flow is injected through only one HPSI loop MOV to limit !
instrumentation uncertainty. No more than one charging pump (44 gpm) is allowed to operate during the HPSI mass addition.
Three 100% capacity HPSI pumps are installed at Calvert Cliffs. Procedures will require that two of the three HPSI pumps be disabled (breakers racked out) at RCS temperatures less than or equal to 365'F and that the remaining l HPSI pump handswitch be placed in pull-to-lock. Additionally, the HPSI pump nonnally in pull-to-lock shall be throttled to less than or equal to 210 gpm when used to add mass to the RCS. Exceptions are provided for ECCS l testing and for response to LOCAs.
To provide single failure protection against a HPSI pump mass addition transient when in MPT enable, the HPSI loop MOV handswitches must be placed in pull-to-overridc so the valves do not automatically actuate upon receipt of a SIAS signal. Alternative actions, described in the ACTION statement, are to disable the affected MOV (by racking out its motor circuit breaker or equivalent), or to isolate the affected HPSI header. Examples of HPSI header isolation actions include; (1) de-energizing and tagging shut the ..
HPSI header isolation valves; (2) locking shut and tagging all three HPSI .
pump discharge valves; and (3) disabling all three HPSI pumps. !
RCS temperature, as used in the applicability statement, is determined as follows: (1) with the RCPs running, the RCS cold leg temperature is the
' appropriate indication (2) with the Shutdown Cooling System in ope ration, 1 O the shutdown cooling temperature indication is appropriate, (3) if neither l the RCPs or shutdown cooling is in operation, the core exit thermocouples '
d// are the appropriate indicators of RCS temperature.
MM /4.4.10 STRUCTURAL INTEGRITY The inspection programs for the ASME Code Class 1, 2, and 3 components !
ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life o? the plant. To the extent -
applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.
l CALVERT CLIFFS - UNIT 1 3 3/4 4-10 Amencment No. 2SF
4 NITAC11 MENT (2)
UNIT 2 TECIINICAL SPECIFICATION REVISED MARKED UP PAGES y
3/4:4 REACTOR C00 TANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Overoressure Protection S_ystems LIMITING CONDITION FOR OPERATION 3.4.9.3 The following overpressure protection requirements shall be met:
- a. One of the following three overpressure protection systems shall '
be in place:
- 1. Two power-operated p11alyalres-4BORVs-)-with-Mif_t setting of 5 430 psiat or f raeciakd dect,4hes <pJe
' W11.ih
- 2. A single PORV with a lift setting of 5 430 psiafand a q,3 ,,c;g.,p Reactor Coolant System vent of t 1.3 square inches, o y,cu pe,
- 3. A Reactor Coolant System (RCS) vent t 2.6 square inche .
- b. Two high pressure safety injection (HPSI) pumps' shall be disabled by either removing (racking out) their motor circuit breakers from the electrical power supply circuit, or by locking shut their discharge valves.
- c. The HPSI loop motor operated valves (MOVs)# shall be prevented from automatically aligning HPSI pump flow to the RCS by placing their handswitches in pull-to-override.
- d. No more than one OPERABLE high pressure safety injection pump with suction aligned to the Refueling Water Tank may be used to inject flow into the RCS and when used, it must be under manual control and one of the following restrictions shall apply:
- 1. The total high pressure safety injection flow shall be limited to 5 210 gpm OR
- 2. A Reactor Coolant System vent of 2 2.6 square inches shall exist.
- e. When not in use, the above OPERABLE HPSI pump shall have its handswitch in pull-to-lock.
APPLICABILITY: When the RCS temperature is 5 305'F and the RCS is vented to < 8 square inches. ;
l Except when required for testing. l CALVERT CLIFFS - UNIT 2 3/4 4-32 Amendment No. /,1[2/
p- ,
3/4;4 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) _
- 3. If a pressure limit was exceeded, take action in accordance with Specification 3.4.9.1.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORY shall be demonstrated OPERABLE by:
- a. Performance of 4 CHANNEL FUNCTIONAL TEST on the PORY actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORY is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE.
- b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once r 18 months.
e %k
- c. ting) valve ~ is open at least once per Verifying 72 the PORY hours when the P fRTTs being used for overpressure protection.
- d. Testing in accordance with the inservice test requirements pursuant to Specification 4.0.5.
4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- when the vent (s) is being used for overpressure protection.
4.4.9.3.3 All high pressure safety injection pumps, except the above OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the motor circuit breakers have been removed from their electrical power supply circuits or by verifying their discharge valves are locked shut. The automatic opening feature of the high pressure safety injection loop MOVs shall be verified disabled at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The above OPERA 8LE pump shall be verified to have its handswitch in pull-to-lock at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i Except when the vent pathway is locked, sealed, or otherwise secured
^
in the open position, then verify these vent pathways open at least once per 31 days.
CALVERT CLIFFS - UNIT 2 3/4 4-34 Amendment No. I J P/