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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures 1994-07-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D5931988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D5621988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization ML20151D6971988-06-20020 June 1988 Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl ML20151D6281988-06-10010 June 1988 Rev 1 to Procedure 3.04, Developing Written Tests ML20151D6481988-06-10010 June 1988 Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan ML20151D6791988-06-10010 June 1988 Rev 2 to Procedure 8.01, Simulator Exam Evaluation ML20151D6581988-06-10010 June 1988 Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests ML20151D5821988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding ML20151D4981988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control ML20151D5691988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling ML20151D6041988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 12, Figure ML20151D5481988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control ML20151D4471988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control ML20151D4251988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control ML20151D5971988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding ML20151D4901988-05-11011 May 1988 Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control ML20196A9081988-01-25025 January 1988 Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing ML20196A9601988-01-25025 January 1988 Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1 ML20196A9911988-01-25025 January 1988 Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1 ML20196A9471988-01-25025 January 1988 Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1 1994-07-31
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M C --1 SHOREHAM NUCLFfk POWER STATION PLANT SPECIFIC TECHNICAL CUIDELINy PSTG #6 ALTERNATE LEVEL CONTROL REVISION F0: 1 l
PREPARED BY: 7 % DATE: _ 2[ [
REVIEWED BY: hkied(/I Mer m o% A DATE: /1 h
! OPERATING ENGINEER APPROVAL: M a DATE: r' v[#
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 1 Alternate Level Control
'EPG Step:
If while executing the following steps:
o Any control rod cannot be determined to be inserted to or beyond position [02 (Maximum Suberitical Banked Withdrawal Position)] and it has not been determined that the reactor will remait. shutdown under all conditions without boron, enter (procedure developed from Contingency #5].
o RPV water level cannot be determined, enter (procedure developed from Contingency #4).
o RPV water level is increasing, enter (procedure developed from the RPV Control Guideline] at (Step RC/L).
o RPV water level drops below [-146 in. (ADS initiation setpoint)),
prevent automatic initiaticn of ADS.
SNPS PSTG Step:
If while executing the following steps:
o Any control rod cannot be determined to be inserted to or beyond position 02 and it has not been determined that the reactor will remain shutdown under all conditions without boron, enter procedure developed from Contingency #5.
o RPV water level cannot be determined, enter procedure developed from Contingency #4.
o 'RPV water level is increasing, enter procedure developed from the RPV Control Guideline at Step RC/L.
o RPV water level drops below -132 in., prevent automatic initiation of ADS, by placing the ADS Inhibit switch to INHIBIT.
Justification for Differences / References Guidance added as to how to prevent automatic initiation of ADS Hsximum Subcritical Banked Withdrawal Position: NED Appendix C Calculation No. C-NFD-200 ADS initiation setpoint: Tech Spec Table 3.3.3.2 PSTG #6 Rev. 1 Page 1
r C
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency i 1 Alternate Level Control EPG Step:
If while executing the following steps primary containment water level and suppression chamber pressure cannot be maintained below the Maximum Primary Containment Water Level Limit, then irrespective of whether adequate core cooling is assured terminate injection into the RPV from sources external to the primary containment until primary containment water level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
SNPS PSTG Step: ,
If while executing the following steps primary containment water level and suppression chamber pressure cannot be maintained below the Maximum Primary Containment Water Level Limit, then irrespective of whether adequate core cooling is assured terminate injection into the RPV from sources external to the primary containment until primary containment water
. level and suppression chamber pressure can be maintained below the Maximum Primary Containment Water Level Limit.
Justification for Differences / References Maximum Primary Containment Water Level Limit - NED Appendix C calculation No.
C-NAD-268 l
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l PSTG #6 Rev. 1 Page 2 i
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SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 1 Alternate Level Control EPG Step:
Cl-1 Initiate IC.
SNPS PSTG Step:
C1-1 Deleted.
Justification for Differences / References SNPS does not have an Isolation Condenser.
PSTG #6 Rev. 1 Page 3 <
SHOREHAM NUCLEAR POWER STATION Plant Specific Technical Guidelines Contingency # 1 Alternate Level Control EPG Step' Cl-2_ Line up for injection, start pumps, and irrespective of pump NPSH and vortex limits, increase injection flow to tie maximum with 2 or more of the
.........s tajection sybsystems:
o Condensate o HPCS o LPCI-A with injection through the heat exchanger as soon as possible.
o LPCI-B with injection throu c h the heat exchanger as soon as possible, o LPCI-C with injection through the heat exchanger as soon as possible, o LPCS-A o LPCS-B If less than 2 ef the injection subsystems can be lined up, commence lining up as many of the following alternate injection subsystems as possible.
[o RHR service water crosstie )
[o Fire System )
[o Interconnect 1ons with other units ]
6 ECCS keep-full systems ]
[o SLC (test tank) )
[o SLC (boron tank) ]
SNPS PSTG Step:
Cl-2 Line up for injection, start pumps, and irrespective of pump NPSH and vortex limits, increase injection flow to the maximum with 2 or more of the following injection subsystems:
o Condensate
! 'FCI-A with injection through the heat exchanger as soon as possible, o LPCI-B with injection through the heat exchangir as soon as possible.
PSTG #6 Rev. 1 Page 4 i
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P SHOREHAM NUCLEAR POWER STATION 1
, Plant Specific Technical Guidelines Contingency i 1 Alternate Level Control SNPS PSTG Step:
(Con't) o Core Spray A o Core' Spray B If less than 2 of the injection subsystems can be lined up, commence lining up-as many of the following alternate injection subsystems as possible:
o RHR service water crbsstie (Ultimate Cooling) o Fire Main to Ultimate Cooling l o ECCS connections from condensate transfer o SLC (test tank) o SLC (boron tank)
Justification for Differences / References Deleted HPCS (N/A to SNPS)
Deleted LPCI-C since Shoreham only has 2 LPCI loops Changed "LPCS" to Core Spray since LPCS is only a pertinent title for plants with HPCS Deleted Interconnections with other units since SNPS is a single unit plant.
. Clarified the alternate injection subsystems.
PSTG #6 Rev. 1 Page 5
e SHOREHAM NUCLEAR POWER STATION
, Plant Specific Technical Guidelines Concingency i 1 Alternate Level Control EPG Step:
Cl-3 If RPV pressu?e is above [87 psig (highest RPV pressure at which the shutoff head of a low-water-quality alternate injection subsystem (excluding SLC) is reached)]:
If while executing the following steps RPV pressure drops below [87 psig (highest RPV pressure at*which the shutoff head of a low-water-quality alternate injection subsystem (excluding SLC) is reached)), continue in this procedure at [ Step C1-4].
SNPS PSTG Step:
<.1 Cl-3 If RPV pressure is above 145 psig:
If while executing the following steps RPV pressure drops below 145 psig, d continue in this procedure at Step Cl-3.
' Justification For Differences / References Highest RPV pressure at which the chutoff head of a low-water-quality alternate injcction subsystem is reached: Service Water Pump Curve BCN 11600.02-2.23-23 through 26, Specification No. SH1-61 for Condensate Transfer Pump Information, SWEC Drcwing 11600.02-10.21-06 for Electric and Diesel driven fire pump.
PSTG #6 Rev. 1 Page 6
e
, SHOREHAM NUCLEAR POWER STATION
. Plant Specific Technical Guidelines Contingency # 1 Alternate Level Control EPO Stept Cl-3.1 If no injection subsystem is lined up for injection with at least one pump running, start pumps in alternate injection subsystems which are lined up i for injection.
C1-3.2 When RPV water level drops to [-164 in. (top of active fuel)]:
o If any system, injec, tion subsystem or alternate injection subsystem is lined up with at least one pump running, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
o If no system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, STEAM COOLING IS REQUIRED.
SNPS PSTG Step:
C1-3.1 If no injection subsystem is lined up for injection with at least one pump running, start pumps in alternate injection subsystems which are lined up for injection.
C1-3.2 When RPV water level drops to -158 in. (Top of Active Fuel):
o If any system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
o If no system, injection subsystem or alternate injection subsystem is lined up with at least one pump running. When RPV level drops to -200 l< }
in. EMERGENCY DEPRESSURIZATION IS REQUIRED.
Justification For Differences / References I;.. . svad bullet has been altered to include the Steam Cooling Contir.gency in this stop. As specified in EPG Contingency #3, Emergency Depressurization is required when RPV level drops to the Minimum Zero Injection RPV water level. The operator would enter Contingency #2 from RC/P override #3.
Top of Active Fuel: Tech Spec Figure B 3/4 3-1 Minirum Zero Injection RPV water level - NED Appendix C Cale C-NAD-270 ll (conservatively rounded up for human factors concerns),
i PSTG #6 Rev. 1 Page 7
7
<e SHOREHAM NUCLEAR POWER STATION
.. Plant Specific Technical Guidelines Contingency # 1 Alternate Level Control EPG Step:
Cl-4 When RPV pressure drops below [87 psig (highest RPV pressure at which the shutoff head of a low-water-quality alternate injection subsystem (excluding SLC) is reached)):
C1-4.1 Line up for injection, start pumps, and irrespective of pump NPSH and vortex limits, increase injection flow to the maximum with all systems and injection subsystems.
Cl-4.2 When RPV water level drops to [-164 in. (top of active fuel)),
EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; line up for injection, start pumps, and increase injection flow to the maximum with all alternate injection subsystems, If RPV water level cannot be restored and maintained above [-164 in. (top of active fuel)], PRIMARY CONTAINMENT FLOODING IS REQUIRED; enter (procedure developed from Contingency #6).
SNPS PSTG Step:
Cl-4 When RPV pressure drops below 145 psig: j'd Cl-4.1 Line up for injection, start pumps, and irrespective of pump NPSH and vortex limits, increase injection flow to the maximum with all systems and injection subsystems.
C1-4.2 When RPV water level drops to -158 in. (Top of Active Fuel),
EMERGENCY APV DEPRESSURIZATION IS REQUIRED; line up f or injection, start pumps, and increase injection flow to the maximum with all alternate injection subsystems.
If RPV water level cannot *oe restored and maintained above -158 in. (Top Of Active Fuel), PRIMARY CONTAINMF.NT FLOODING IS REQUIRED; enter procedure developed from Contingency #6.
Justification for Differences / References High2st RPV pressure at which the shutoff head of low-water-quality alternate injoction subsystem: BCN 11600.02-2.23-23 through 26 Specification No. SH1-6" for Cordsnsate Transfer Pump Information, SWEC Drawing 11600.02-10.21-06 for Electric and Discal driven fire pump.
TAF: Tech Spec Figure B 3/4 3-1 PSTG #6 Rev. 1 Page 8
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