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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20072T0521994-09-0606 September 1994 Proposed Tech Specs Modification to Append a of Operating License DPR-35 Re Maintenance of Filled Discharge Pipe ML20072S0501994-09-0606 September 1994 Proposed Tech Specs Re Instrumentation That Initiates Primary Containment Isolation & Initiates or Controls Core & Containment Systems ML20072S0081994-09-0606 September 1994 Proposed Tech Specs Re Primary Containment,Oxygen Concentration & Vacuum Relief ML20072S0861994-09-0606 September 1994 Proposed Tech Specs Re Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements ML20069M3311994-06-0909 June 1994 Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe ML20067B7111994-02-0909 February 1994 Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion BECO-93-156, Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)1993-12-10010 December 1993 Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3) ML20059A9361993-10-19019 October 1993 Proposed Tech Specs for Removal of Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint1993-10-19019 October 1993 Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint ML20046D0441993-08-0909 August 1993 Proposed Tech Specs,Proposing 24 Month Fuel Cycle ML20044G1331993-05-20020 May 1993 Proposed Tech Specs Reducing MSIV Low Turbine Inlet Pressure Setpoint from Greater than or Equal to 880 Lb Psig to Greater than or Equal to 810 Psig & Reducing Min Pressure in Definition of Run Mode from 880 Psig to 785 Psig BECO-93-016, Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively1993-02-11011 February 1993 Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively 1999-06-16
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999 Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence ML20206R8161999-05-11011 May 1999 Proposed Tech Specs Re HPCI & RCIC Surveillance Testing ML20206H9771999-05-0505 May 1999 Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs ML20205A1451999-03-23023 March 1999 Core Shroud Insp Plan ML20207F1171999-03-0303 March 1999 Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule ML20151S3851998-08-31031 August 1998 Long-Term Program:Semi-Annual Rept ML20237E0851998-08-24024 August 1998 Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT ML20236X7191998-07-31031 July 1998 Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time ML20249C7101998-06-26026 June 1998 Proposed Tech Specs Correcting Typos & Updating Bases ML20249B3231998-06-15015 June 1998 Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM ML20217F9341998-03-26026 March 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20217H2791998-03-25025 March 1998 Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A ML20203D4981998-02-20020 February 1998 Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173 ML20217K5691997-10-24024 October 1997 Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing ML20211N6871997-09-16016 September 1997 Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program ML20211G2381997-09-15015 September 1997 Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm ML20211G2311997-09-12012 September 1997 Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM ML20216C0631997-08-29029 August 1997 Semi-Annual Long Term Program Schedule ML20210K4381997-08-0808 August 1997 Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO ML20196J0041997-07-22022 July 1997 Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH ML20210K3551997-07-0101 July 1997 Rev 16 to Procedure 7.8.1, Water Quality Limits ML20136J5501997-03-0707 March 1997 Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence ML20134C9671997-01-24024 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A6511996-12-23023 December 1996 Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16
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PNPS TECHN! CAL SPECIFICATIONS List of Effective Paati East Revision Amendment PJLqt Revision ILmendment List of Effective Pages: License as Amended:
LOEP-1 148 1 0 LOEP-2 146 2 0 L0EP-3 148 3 135 LOEP-4 148 4 115 LOEP-5 146 5 134 Index of Technical Specification Order dated 09/12/80 (6 pages)
Changes: Order dated 01/09/81 (6 pages)
Order dated 01/13/81 (7 pages) i 12 Order dated 04/08/81 (3 pages) 11 23 Order dated 07/10/81 (10 pages) til 37 Order dated 01/18/82 (10 pages) iv 41 Order dated 01/19/82 (5 pages) v 45 Order dated 02/16/82 (2 pages) vi 50 Order dated 03/14/83 (10 pages) vii 57 Order dated 06/24/83 (5 pages) viii 66 Order dated 09/22/83 (5 pages) ix 72 NRC Letter datad 11/08/83 (2 pages) x 80 NRC LeMer dated 03/09/84 (2 pages) xi 88 Order dated 06/15/84 (4 pages) xii 93 Order dated 07/02/84 (4 pages) xiii 103 99 Order dated 11/27/85 (3 pages) xiv 114 111 xv 123 120 Technicel Specifications Cover Page xvi 133 125 xvii 141 129 Title Page xvili 14E 135 xix 149 --- Table of Ct,ntents:
Index of Technical Specification i 148 135 Clarifications: 11 146 133 111 146 133 C-1 141 Technical Specifications:
Clarification 87-01, 09/14/87 (1 Page)
Clarification 88-01, 11/29/88 (5 Pages) 1 146 133 Clarification 88-02, 12/02/88 (2 Pages) 2 64 Clarification 89-01, 09/16/89 (2 Pages) 3 116 113 Clarification 89-02, 10/02/89 (2 Pages) 4 15 Clarification 89-03, 10/17/89 (3 Pages) 5 0 Clarification 89-04, 11/29/89 (3 Pages) Sa 138 128 Clarification 89-05, 12/13/89 (2 Pages) Sb 138 128 Clarification 90-02, 05/16/90 (2 Pages) 6 146 133 Clarification 90-03, 06/13/90 (3 Pages) 7- 146 133 8 146 133 Materials License: 9 146 133 10 146 133 1 6 2 6 Revision 149 L0EP-1 9105140301 910507 PDR ADOCK 05000293 P pop
PNPS TECHNICAL SPECIFICATIONS List of Effective Paaes (continued)
P_ Age Revision Amendment Elge Egy111gn Amendment 185 89 206f-1 117 114 186 89 206f-2 117 114 187 89 206g 117 114 188 89 206h 117 114 189 89 2061 117 114 190 89 2061-1 117 114 191 89 2063 76 192 89 206j-1 117 114 1 193 89 206k 36 193a 89 2061 36 '
193b 89 206m 146 133 193c 89 207 91 193d 89 208 145 132 193e 89 209 145 132 193f 89 210 145 132 ,
194 117 114 211 145 132 194A 61 212 145 132 195 136 -127 213 145 132 196 136 127 214 145 132 197 136 127 215 145 132 198 0 216 146 133 199 136 127 217 146- 133 200 42 217a 146 133 201 148 135 218 145 132 202 8 219 145 132 203 108 220 145 132 203a 41 221 145 132 204 0 222 145 132 204A 149 --- 229 89 205 149 --- 230 89 205a- 146- 133 231 89 205b 146 133 232 89 205c 146 133 205d 146 133 205e 146 133 205f 146 133 206 117 114 206a 117 114 206b 117 114 206c 117 114 206c-1 117 114 206d 117 114 206e 117 114 206e-1 117- 114 206e-2 117 114 206f 117 114 i Revision 149 L0EP-4
l 3.10 PASIS: i B. Core Monitorina The SRH's are provided to monitor the core during periods of station shutdown )
and to guide the operator during refueling operations and station startup. ,
Requiring two operable SRM's in or adjacent to any core quadrant where fuel or I control rods are being moved ensures adequate monitoring of that quadrant during such alterations. The requirement of 3 counts per second provides assurance that neutron flux is being monitored and ensures startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
The limiting conditions for operation of the SRM subsystem of the Neutron Monitoring System are derived from the Station Nuclear Safety Operational Analysis (Appendix G) and a functional analysis of the neutron monitoring system. The specification is based on the Operational Nuclear Safety Requirements in subsection 7.5.10 of the Safety Analysis Report.
A spiral unloading program is one by which the fuel is in the outermost cells (four fuel bundles surrounding a control blade) is removed first. Unloading continuesbyremovingtheremagngoutermostfuelcellbycell. The center cell will be the last removed. A spiral loading program is one by which I fuel is loaded on the periphery of the previously loaded fueled region I beginning around a single SRH. Spiral unloading and reloading will preclude i the creation of flux traps (moderator filled cavities surrounded on all sides by fuel).
During spiral unloading, the SRM's shall have an initial count rate of 2 3 cps with all rods fully inserted. The count rate will diminish during fuel removal. Under the special condition of complete spiral core unloading, it is expected that the count rate of the SRM's will drop below 3 cps before all of the fuel is unloaded.
Since there will be no reactivity additions, a lower number of counts will not present a hazard. When all of the fuel has been removed to the spent fuel storage pool, the SRM's will no longer be required. Requiring the SRM's to be
! operational prior te fuel removal assures that the SRM's are operable and can be relied on even when the count rate may go below 3 cps.
During spiral reload, SRM operability will be verified by using a portable external source every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until the required amount of fuel is loaded to maintain 3 cps. As an alternative to the above, up to two fuel assemblies l
will be loaded in different cells containing control blades around each SRM to obtain the required 3 cps. Until these assemblies have been loaded, the 3 cps requirement is not necessary.
l U)During selected refueling outages, prior to initiating spiral unloading, l the central controlled cell will be removed to facilitate inspection of l
the Core Spray Spargers.
l Revision 99, 149, 204A l
$.10 BAELS:
C. Spent Fuel Pool Hattr_Lettl To ensure there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established. The minimum water level of 33 feet is established because it would be a significant change from the normal level (-l foot) and is well above the level to assure adequate cooling.
D. Epiticle Control Rod Remqyal These specifications ensure maintenance or repair of control rods or rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirement that the fuel assemblies in the cell controlled by the control rod be removed from the reactor core before the interlock can be bypassed ensures withdrawal of another control rod does not result in inadvertent criticality. Each control rod essentially provides reactivity control for the fuel assemblies in the cell associated with the control rod. Thus, removal of an entire cell (fuel assemblies plus control rod) results in a lower reactivity potential of the core.
4.10 EASES:
A. Refuelina Intellpfki Complete functional testing of all refueling interlocks before any refueling outage will provide positive indication that the interlocks operate in the situations for which they were designed. By loading each hoist with a weight equal to the fuel assembly, positioning the refueling platform, and withdrawing control rods, the interlocks can be subjected to valid operational tests. Where redundancy is provided in the logic circuitry, tests can be performed to assure that each redundant logic element can independently perform its functions.
B. Core Monitoring Requiring the SRH's to be functionally tested prior to any core alteration ensures the SRH's will be operable at the start of that alteration. The daily response check of the SRH's ensures their continued operability.
Revision 149 205 l
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