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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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LIMITVG_ CONDITION FOR OPERATION StJRVEILLAE E RE0DIREMENTS
'B. Fire Water SuDoly System B. Fire Water SuDDiv System The Fire Hater Supply System 1. The Fire Water Supply System shall be operable with: shall be tested and verified to be OPERABLE:
- 1. Two (2) 2000 gpm/125 psig fire pumps which are arranged a. by checking the volume of to start automatically, water in each fire water tank at least once every 7
- 2. Two (2) water supplies with a days.
minimum storage quantity of 240,000 gallons of water in b. by automatically starting each. each fire pump at least once every month and running each
- 3. Two (2) independent water pump for thirty minutes at flow paths from Item Nos.1 & that time.
2 above to each fire water suppression system. (3.12.C c. by visually checking every and 3.12.E) shutoff valve on the fire water supply system at least APPLICABILITY once every month for proper position.
At all times when any safety related equipment is required to be OPERABLE. d. by cycling each fire water supply system shutoff valve ACTION: through its full operation at least once per cycle.
- a. With less than the above required equipment, restore the e. by verifying at least once inoperable equipment to OPERABLE per cycle that each pump status within 7 days or prepare starts and delivers at least and submit a report to the 2000 gpm while maintaining a Commission within the next 30 system pressure of at least days outlining the plans and 125 psig.
procedures to be used to provide for the loss of redundancy in f. by performing a water flow this system. jnt on the fire water yard loop at least once every
- b. With no FIRE SUPPRESSION HATER year.
SYSTEM OPERABLE:
- g. by verifying at least once
- 1. Establish the backup Fire every month that the diesel Hater Supply System within 24 fire pump fuel storage tank hrs. contains a minimum of 175 gallons of fuel oil.
- 2. If the requirement of b.1 above cannot be met, an h. at least once per orderly shutdown of the operating cycle by reactor shall be initiated subjecting the diesel to an and the reactor shall be in inspection in accordance the cold shutdown condition with procedures prepared in within 24 hrs. conjunction with the g22bbN $ 293 e e a s for the P PDR class of service.
Amendment No. 206a l i
LXMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS B. Fire Hater Sucolv System (cont'd)
- 1. by verifying at least once per 3 months that a sample I of diesel fuel from the )
fuel storage tank, j obtained in accordance ;
with ASTM 04057-81 or D4177-82, is within the acceptable limits specified in Table 1 of ASTM 0975-81 with respect l to viscosity, water content, and sediment.
- j. by desnonstrating that the diesel starting 24-volt battery bank and charger I
l are OPERABLE as follows:
- 1. at least once per week by verifying that the electrolyte level of each battery is above the plates and battery voltage is at least 24 volts.
- 2. at least once per 3 months by verifying that the specific gravity is appropriate for continued service l of the battery.
1 1 3. at least once per operating cycle by verifying that the batteries, all plates and battery racks show no visual indication of physical damage or abnormal deterioration and the battery-to-battery and terminal connection are clean, tight, free of corrosion, and l coated with anti-corrosion material 1
s Amendment No. 206b
ILASLS
- ' 3/4.12.G Alternate Shutdown Panels The alternate shutdown system, independent of cabling and equipment in the Cable Spreading Room is provided to effect safe shutdown of Pilgrim in the event of a fire in the Cable Spreading Room. This is accomplished by installing isolation switches for safety-related equipment that will provide the capability for the plant operators to reach a safe shutdown condition.
These switches will isolate their associated equipment from the CSR cables, thus transfer control from the Control Room to the local emergency shutdown statior.s outside the CSR. These isolation switches are located in alternate shutdown panels and are located as close as practical to the equipment or switchgear they serve.
The operability of the fire suppression and detection system in the Cable Spreading Room in conjunction with the passive element of cable coating ensures that adequate fire protection / detection / suppression capability is available to quickly detect, confine and extinguish fires occurring in any portion of the room where safety-related equipment is located. The fire detection / suppression system consists of an independent smoke detection system, an automatic Halon 1301 Fire Suppression system and fire hose stations available outside the doorways to the Cable Spreading Room. The collective capability of passive protection and detection with either manual or automatic suppression is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire protection program.
An emergency shutdown procedure, which is compatible with the design modifications and plant operator availability, provides step-by-step actions to initiate safe shutdown operation. Operator actions to isolate safety-related cables passing through the CSR is initiated as soon as a fire which is not immediately extinguishable is detected and confirmed in the CSR.
Alternate shutdown panels are provided for the following systems:
l
- a. Core Spray
- b. RHR
- c. RBCCW
- d. Salt Service Water
- e. HPCI
- f. RCIC
- g. Automatic Depressurization System
- h. Diesel Generators Inoperability of the above listed systems does not require entry into LC0 action statements for the alternate shutdown panels.
A surveillance frequency of once per cycle is considered prudent and more frequent testing not warranted. The frequency of once per refueling outage for testing the diesel generators prevents unnecessarily rendering them inoperable during normal power operation. The frequency of once per refueling outage for the Automatic Depressurization System is consistent with the existing surveillance frequency for this system. Requiring this surveillance l to be performed during a refueling outage will also assure that plant conditions will allow for safe access to the ADS solenoids.
Amendment No. 206j-1
ATTACHMENT 2 to BECoJ7-200 ADDITIONAL JUSTIFICATION RE: PROPOSED SECTION 4.12.G.7 ON PAGE 206e-2 0F THF MAY 22. 1987 SUBMITTAL Section 4.9.A.1.a on page 194 of our current Technical Specifications addresses a functional check of the alternate shutdown panel for the diesel generator (DG). Language in that section contains the words "...and loaded",
which refers to manually loading the DG once it has started. Loading the DG is not, nor has ever been, required to functionally check the operation of the alternate shutdown panel. The only requirement relating to the functional check of the panel is that the DG be shown capable of starting.
BECo installed a new upgraded alternate shutdown panel during the current RF0
- 7. The old alternate shutdown panel design necessitated isolating DC control power to the DG in order to perform the functional check. As part of the upgrade, a dedicated DC control power cable was installed directly from the switchgear room to the DG. This action obviated tne old method of isolating DC power to isolate control of the DG from the control room when performing the functional check. The upgrade also included adding four switches to the new alternate shutdown panel which provide the capability to isolate startup and control of the DG from the controi room and cable spreading room without affecting the dedicated DC control cable from the switchgear room to the DG.
Using the new alternate shutdown panel, operators can isolate startup and control of the DG from the control room and cable spreading room to perform the functional check without incurring the disadvantages of starting the DG without DC control power. While one operator starts the DG from the alternate shutdown panel in the DG room, another operator goes to the switchgear room, isolates the DC control power to the switchgear, and manually loads the DG by energizing the breakers at the switchgear, as required. The starting of the DG is independent of the loading. Loading is not a necessary condition to demonstrate successful starting of the DG from the alternate shutdown panel.
Loading is only intended to verify operation of the components the DG serves, nat to functionally check the alternate shutdown panel (old or new).
BECo's May 22, 1987 submittal proposed language for Section 4.12.G.7 on page 206e-2 which duplicated the language of the current Section 4.9.A.l.a except for deleting the words". . .and loaded". Loading the DG, once it is shown capable of starting, need not be, and should not be imposed as a requirement for functionally checking the alternate shutdown panel.
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