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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20125D5071992-12-14014 December 1992
Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements
ML20086K0981991-12-0505 December 1991
Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel
ML20079P3981991-10-31031 October 1991
Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively
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....
ML20005F2481990-01-0505 January 1990
Proposed Tech Specs Re Defueled Facility OL
ML20246N9731989-07-13013 July 1989
Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process
ML20246E5891989-04-30030 April 1989
Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company)
SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988
Proposed Tech Spec Table 1.2, Operational Conditions
ML20151D7141988-07-15015 July 1988
Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators
ML20151D7421988-07-11011 July 1988
Proposed Tech Specs Clarifying Method of Demonstating Operability of Source Range Monitor Channels
ML20154M6321988-05-24024 May 1988
Proposed Tech Specs,Changing Alarm/Trip Setpoint and Measurement Range of Main Control Room Vent Radiation Monitors
ML20154H1471988-05-19019 May 1988
Proposed Tech Spec Pages 3/4 5-6 & 3/4 5-8,providing Clarification to Eliminate Possibility of Misinterpretation
ML20236C4661987-10-14014 October 1987
Proposed Tech Specs,Correcting Tupos & Tech Spec Internal Inconsistencies Re Radiological Environ Monitoring & Designation of Number of Valves in Table 3.6.3-1
ML20238C4471987-09-0404 September 1987
Proposed Tech Spec Pages 1-2,3/4 1-1,3/4 1-2,3/4 1-6, 3/4 3-4,3/4 9-3 & 3/4 9-7,changing Definition of & Footnotes Re Core Alteration
ML20206F8791987-04-10010 April 1987
Proposed Amended Tech Specs Re Surveillance Testing for B-10 Enrichment Level of Standby Liquid Control Sys Tank
ML20210C7791987-02-0404 February 1987
Proposed Tech Specs,Implementing Design Change That Will Equip Standby Liquid Control Sys W/Slightly More than Twice Equivalent Control Capacity Required by 10CFR50.62(c)(4)
ML20212J4751987-01-21021 January 1987
Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1
ML20207P9631987-01-12012 January 1987
Proposed Tech Specs Re Location of Meteorological Towers & Composition of Independent Safety Engineering Group
ML20206P2741986-06-26026 June 1986
Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept & Review of Operations Committee Responsibilities
ML20140A8101986-01-20020 January 1986
Proposed Tech Spec Correcting Error in Basis for Location of Milk Control Sample & Eliminating Sampling Analysis If No Waste Batch Released During Month
ML20137Z2941985-12-0909 December 1985
Revised Tech Spec Table 3.3.7.9-1, Fire Detection Instrumentation
ML20136B4451985-11-16016 November 1985
Proposed Tech Specs Increasing & Relocating Fire Detectors & Modifying Reactor Coolant Leakage Detection Sys Surveillance Requirement
ML20138C8791985-10-21021 October 1985
Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor
ML20128M1371985-07-31031 July 1985
Technical Specifications for Shoreham Nuclear Power Station, Unit No. 1.Docket No. 50-322.(Long Island Lighting Company)
SNRC-1181, Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD1985-06-19019 June 1985
Proposed Tech Spec 3.10.5 Suspending Provisions of Tech Spec 3.6.6.2 During Performance of Startup Test Program Until Reactor Has Operated for 120 EFPD
1992-12-14
[Table view]
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
ML20151D6081988-07-13013 July 1988
Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures
ML20151D4191988-07-13013 July 1988
Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution
1994-07-31
[Table view] |
Text
, Att:chment 1 Page 1 of 2 SNRC-1220 TABLE 3.3.7.9-l FIRE DETECTION INSTRUMENTATION SAFETY RELATED' ZONE TOTAL NUMBER OF INSTRUMENTS
- HEAT SMOKE FLAME (x/y) (x/y) (x/y)
- 1. Control Building Emergency Seitchgear Room 101 0/6 6/0 Emergency Switchgear Room 102 0/6 6/0 Emergency Switchgear Room 103 0/6 6/0 Battery Room A 0/2 3/0 Battery Room B 0/2 4/0 Battery Room C 0/3 5/0 Diesel Generator Room 101 0/9 1/0## 3/0 Diesel Generator Room 102 0/11 1/0## 3/0 Diesel Generator Room 103 0/10 1/0## 3/0 Relay Room 0/24 14/0 HVAC Equipment Roon El. 44'-0" 3/0 HVAC Equipment Room El. 63'-0" 5/0 Chiller Equipment Room El. 44'-0" 10/0 Chiller Equipment Room El 63'-0" 10/0 CRAC - FLT 2A El. 63'-0" 4/0 CRAC - FLT 2B El. 63'-0" 4/0 CRAC CR Exh El. 63'-0" 1/0 l Corridor 8 El. 25'-0" 5/0 Corridor 9 El. 25'-0" 3/0
- 2. Reactor Building Primary Containment # 4/0 Secondary Containment El. 8'-0" 30/0 Secondary Containment El. 40'-0" 38/0 l Secondary Containment El. 63'-0" 14/0 Secondary Containment El. 78'-7" El. 95'-3", & 101'-6" 4/0 42/0 Main Steam Tunnel El. 76'-5" 11/0**
Secondary Containment El. 112'-9" 2/0 55/0 Secondary Containment El. 126'-9" 7/0 Secondary Containment El. 150'-9" & 159'-9" 5/0 27/0 Secondary Containment El. 175'-9" 3/0##
MG Room 111 E1. 150'-9" 4/0 MG Room 112 El. 150'-9" 3/0 MG Room 113A El. 161'-0" 4/0 MG Room 113B El. 161'-0" 3/0 MCC West Room El. 112'-9" 2/0 MCC East Room El. 112'-9" 3/0 F512110265 DR 851209 p ADOCK 05000322 PDR
. Attach =cnt 1 Page 2 of 2-
'~
SNRC-1220 TABLE 3.3.7.9-1 (continued)
' FIRE DETECTION INSTRUMENTATION i
SAFETY RELATED ZONE TOTAL NUMBER OF INSTRLTENTS*
HEAT SMOKE FLAME (x/y) (x/y) (x/y)
Remote Shutdown Panel Enclosure El 63'-0" 0/2 HPCI Turbine El 8'-0" 0/6
, RCIC Turbine El 8'-0" 0/5
] 1TK607R Horizontal Cable' Trays 2/0
, ITX600R Vertical Cable Trays 5/0 1
RBSVS - FLT 1A El 112'-9" 2/0 RBSVS - FLT 1B El 112'-9" 2/0 MCC Room El. 40'-0" 2/0
- 3. Turbine Building i
Electrical Manhole No. IEl 5'-8" 0/2 2/0 (located in normal switchgear room)
- 4. Screenwell Pump House
, Pump Cubicle A 3/0##
Pump Cubicle B 3/0##
i
} 5. Yard
~
i Emergency Diesel F.O. Transfer Pump i House A 2/0 j Emergency Diesel F.O. Transfer Pump House B . 2/0
- Emergency Diesel F.O. Transfer Pump
- House C 2/0 i
i TABLE NOTATIONS !
- (x/y): x is number of Function A (early warning area fire detection and notification) instruments. y is. number of Function B (actuation of fire suppression system and notification) instruments.
- f. The fire detection instruments located within the primary containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.
1
- Heat detectors are non-restorable spot type fixed temperature.
- Includes projected beam type smoke detector A
1
