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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS ML20115J0181996-07-18018 July 1996 Proposed Tech Specs 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20107H3931996-04-17017 April 1996 Proposed Tech Specs 3/4.3 Re Adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2 & Revising Table 3.3-3 by Adding Action Statements 27a & 34a ML20107E3251996-04-12012 April 1996 Proposed Tech Specs 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases,Addressing Installation of Laser Welded Tube Sleeves in Plant SGs ML20107F0791996-04-12012 April 1996 Proposed Tech Specs 3/4.4 Re Changing TS, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant SGs ML20101R4211996-04-0909 April 1996 Revised TS Pages That Adhere to Testing Methods of ASTM Std D2276-78,Method a for Diesel Fuel Oil Particulate Concentration ML20101J0381996-03-22022 March 1996 Proposed Tech Specs,Implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4351996-02-28028 February 1996 Proposed TS 3/4.8.1,ac Sources ML20106G4131996-02-23023 February 1996 Proposed Tech Specs Paragraph 1.A. Re Operating License Change to Reflect Union Electric as wholly-owned Subsidiary of Ameren Corp ML20097D5801996-02-0909 February 1996 Proposed Tech Specs Allowing Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6151996-02-0909 February 1996 Proposed Tech Specs & Bases Re Containment Systems ML20097D6341996-02-0909 February 1996 Proposed Tech Specs Re AFW Sys ML20097F8991996-02-0404 February 1996 Proposed Tech Specs 4.6.1.2.a Re Containment Sys ML20097C2791996-02-0202 February 1996 Proposed Tech Spec 3/4.6.3, Containment Isolation Valves ML20096B1891996-01-0202 January 1996 Proposed Tech Specs 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ML20094A1721995-10-23023 October 1995 Proposed Tech Specs,Relocating Audit Frequencies in Former TS 6.5.2.9 to Operational QA Manual 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20135E7351996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt One H Replacement Matl ML20135E7431996-12-11011 December 1996 Test to Determine Ampacity Derating Factor for Electrical Conductors Installed in 600mm X 101mm X 3650mm Long Cable Tray Encapsulated by KM1 Darmatt Three H Replacement Matl ML20135E7391996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt Three H Replacement Matl ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS 1999-09-08
[Table view] |
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Attachment to ULNRC-4043
- a REVISED IMPROVED TECHNICAL SPECIFCATION PAGES 3.9-1 (ULNRC-4043, dated 5/28/99) 3.9.2 B 3.9.1-1 B 3.9.1-2 B 3.9.1-3 B 3.9.1-4 5.0-29 (ULNRC-4044, dated 5/27/99) 5.0-31 l
9906080207 990528 PDR ADOCK 05000483' P PDR ,
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Boron Concentrttion s
3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of all filled portions of the Reactor Coolant System and the refueling pool that have direct access to the reactor vessel, shall be maintained sufficient to ensure that the more restrictive of the following reactivity conditions is met: ,
- a. A k, s 0.95, or
- b. A boron concentration of a 2000 ppm.
APPLICABILITY: MODE 6.
NOTE While this LCO is not met, entry into MODE 6 from MODE 5 is not permitted.
ACTIONS CONDITION REQUIRED ACTION COM ON A. Boron concentration not A.1 Suspend CORE Immediately within limit. ALTERATIONS.
M A.2 Suspend positive immediately reactivity additions.
M A.3 initiate action to restore immediately boron concentration to within limit.
CALLAWAY PLANT 3.9-1 Amendment No.133
F. .
Boron Concentretion
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3.9.1 I
. SURVEILLANCE REQUIREMENTS SUP'IEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> )
s l
1 i
l CALLAWAY PLANT 3.9-2 Amendment No.133
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Boron Concentration B 3.9.1 B 3.9 REFUELING OPERATIONS B 3.9.1 Boron Concentration BASES BACKGROUND The limit on the boron concentration of filled portions of the Reactor Coolant System (RCS) and the refueling pool that have direct access to the reactor vessel during refueling ensures that the reactor remains subcritical during MODE 6. Refueling boron concentration is the soluble boron concentration in the coolant in each of these volumes having direct access to the reactor core during refueling.
The soluble boron concentration offsets the core reactivity and is measured by chemical analysis of a representative sample of the coolant in each of the volumes. The refueling boron concentration is sufficient to maintain Shutdown Margin (SDM) with the most adverse conditions of fuel assembly and control rod position allowed by plant procedures. The .
boron concentration that is maintained in MODE 6 is sufficient to maintain k, s 0.95 with the most reactive rod control cluster assembly completely removed from its fuel assembly. )
i GDC 26 of 10 CFR 50, Appendix A, requires that two independent reactivity control systems of different design principles be provided (Ref.1). One of these systems must be capable of holding the reactor 3 core suberitical under cold conditions. The Chemical and Volume Control System (CVCS) is the main system capable of maintaining the reactor suberitical in cold conditions by maintaining the boron concentration.
The reactor is brought to shutdown conditions before beginning operations to open the reactor vessel for refueling. After the RCS is cooled and depressurized and the vessel head is unbolted, the head is slowly removed to form the refueling cavity. The refueling cavity is then flooded to form the refueling pool. Typically, the refueling pool is flooded with borated w~ater from the refueling water storage tank through the open reactor vessel by the use of the Residual Heat Removal (RHR) System pumps or gravity feeding.
The pumping action of the RHR System in the RCS and the natural circulation due to thermal driving heads in the reactor vessel and refueling pool mix the added concentrated boric acid with the water in the refueling pool. The RHR System is in operation during refueling (see LCO 3.9.5,
" Residual Heat Removal (RHR) and Coolant Circulation - High Water (continued)
CALLAWAY PLANT B 3.9.1-1 Revision O
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Boron Concantration B 3.9.1 '
, BASES-
' BACKGROUND Level," and LCO 3.9.6, " Residual Heat Removal (RHR) and Coolant (continued) Circulation - . Low Water Level") to provide forced circulation in the RCS and assist in maintaining uniform boron concentrations in the RCS and the refueling pool above the LCO limits. Administrative controls will limit the volume of unborated water that can be added to the refueling pool for decontamination activities in order to prevent diluting the refueling pool below the specified limits (Ref. 3).
APPLICABLE The boron concentration limit specified in the COLR, and consistent with SAFETY the LCO limits, is based on the core reactivity at the beginning of each ANALYSES fuel cycle (the end of refueling) and includes an uncertainty allowance.
The required boron concentration and the plant refueling procedures that verify the correct fuel loading plan (including full core mapping) ensure that the k,, of the core will remain s 0.95 during the refueling operation.
s Hence, at least a 5% Ak/k margin of safety is established during refueling.
Safety analyses assume a B-10 abundance of 19.9 atom % (Ref. 4).
Administrative controls ensure that the reactivity insertion from the reactor coolant system and the refueling pool reflects this assumption.
During refueling, the water volume in the refueling pool and the reactor vessel form a single mass. As a result, the soluble boron concentration is relatively the same in each of these volumes having direct access to the reactor vessel. a l
The limiting boron dilution accident analyzed occurs in MODE 5 (Ref. 2).
Boron dilution accidents are precluded in MODE 6 by isolating potential dilution flow paths. See LCO 3.9.2,"Unborated Water Source Isolation Valves." Unacceptable dilution from refueling pool decontamination activities is precluded by the following (Ref. 3):
- 1. The maximum allowable amount of unborated reactor makeup water that may be added to the refueling pool for decontamination activities is calculated for each refueling and will not cause the refueling pool boron concentration to fall below the LCO limits.
This maximum allowable volume it based on initial pool boron concentration and one-half the RCS volume at mid-loop. ;
- 2. The refueling pool is drained to approximately one foot above the reactor cavity seal / shield ring. The refueling pool is then drained (continued)
CALLAWAY PLANT B 3.9.1-2 Revision O
.' o Boron Conc 9ntration B 3.9.1
. BASES APPLICABLE via the reactor coolant drain tank pumps or other available means SAFETY (excluding the RHR system) until the level is below the seal / shield ANALYSES ring. This directs potentially diluted water at the top of the pool (continued) away from the reactor vessel and core.
4
- 3. After the level has been lowered to below the cavity seal / shield ring, further draining of the area enclosed by the inside diameter of the ring is performed via the RHR connection to the Chemical and Volume Controlletdown line.
The RCS boron concentration satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).
LCO The LCO requires that a minimum boron concentration be maintained in the filled portions of the RCS and the refueling pool, that have direct s access to the reactor vessel while in MODE 6. The baron concentration limit is specified in the COLR. The COLR limit ensures that a core k, of s 0.95 is maintained during fuel handling operations, and shall in all cases be 2 2000 ppm. Violation of the LCO could lead to an inadvertent criticality during MODE 6.
APPLICABILITY This LCO is applicable in MODE 6 to ensure that the fuel in the reactor vessel will remain suberitical. The required boron concentration ensures a k, s 0.95. Above MODE 6, LCO 3.1.1," SHUTDOWN MARGIN (SDM),
LCO 3.1.5, " Shutdown Bank Insertion Limits," and LCO 3.1.6," Control Bank Insertion Limits," ensure that an adequate amount of negative reactivity is available to shut down the reactor and maintain it suberitical.
The Applicability is modified by a Note stating that transition from MODE 5 to MODE 6 is not permitted while the LCO is not met. This Note specifies an exception to LCO 3.0.4 and prohibits the transition when boron concentration limits are not met. This Note assures that core reactivity is maintained within limits during fuel handling operations.
ACTIONS A.1 and A.2 Continuation of CORE ALTERATIONS or positive reactivity additions (including actions to reduce boron concentration) is contingent upon maintaining the unit in compliance with the LCO. If the boron (continued)
CALLAWAY PLANT B 3.9.1-3 Revision O
a Boron Concentration B 3.9.1 BASES ACTIONS A.1 and A.2 (continued) concentration of any coolant volume in the filled portions of the RCS and the refueling pool that have direct access to the reactor vessel, is less than its limit, all operations involving CORE ALTERATIONS or positive reactivity additions must be suspended immediately.
Suspension of CORE ALTERATIONS and positive reactivity additions shall not preclude moving a component to a safe position.
Al In addition to immediately suspending CORE ALTERATIONS or positive reactivity additions, boration to restore the concentration must be initiated immediately.
In determining the required combination of boration flow rate and concentration, no unique Design Basis Event must be satisfied. The only requirement is to restore the boron concentration to its required value as soon as possible. In order to raise the boron concentration as soon as possible, the operator should begin boration with the best source available for unit conditions.
Once actions have been initiated, they must be continued until the boron concentration is restored. The restoration time depends on the amount of boron that must be injected to reach the required concentration.
SURVEILLANCE SR 3.9.1.1 REQUIREMENTS .
This SR ensures that the coolant boron concentration in the filled portions of the RCS and the refueling pool that have direct access to the reactor vessel, is within the limit specified in the COLR and consistent with the LCO limits. The boron concentration of the coolant in each required volume is determined periodically by chemical analysis.
A minimum Frequency of once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is a reasonable amount of time to verify the boron concentration of representative samples. The Frequency is based on operating experience, which has shown 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to be adequate. l (continued)
CALLAWAY PLANT B 3.9.1-4 Revision O
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