|
---|
Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217C8411999-10-0505 October 1999 Amend 64 to License NPF-86,revising TSs 3.7.6.1 & 3.7.6.2 to Delete Restriction to Suspend All Operations Involving Positive Reactivity Changes During Plant Conditions Specified ML20212L1071999-10-0101 October 1999 Amend 63 to License NPF-86,relocating TS 3/4.7.10, Area Temperature Monitoring, & Associsted TS Table 3.7-3.to Technical Requirements Manual ML20212D0761999-09-17017 September 1999 Amend 62 to License NPF-86,revising TS 3.7.6.2 to Increase AOT for Control Room Air Conditioning Subsystem from 30 to 60 Days to Allow Adequate Time to Replace Portions of Existing System During Current Operating Cycle ML20210Q1631999-08-12012 August 1999 Amend 61 to License NPF-86,revising TS SR 4.5.2b.1 to Delete Prescribed Method of Venting ECCS Which Would Allow Alternate Method to Verify That ECCS Piping Will Be Full of Water ML20204E3391999-03-12012 March 1999 Amend 60 to License NPF-86,revising TS Table 3.3-4 to Depict Change to Refueling Water Storage Tank low-low Level Setpoint ML20249C6401998-06-24024 June 1998 Amend 58 to License NPF-86,revises TS 4.5.2.b.1 for ECCS Subsystems to Delete Requirements to Vent Operating Chemical Volume & Control Sys Centrifugal Charging Pump Casing ML20216C7861998-04-0909 April 1998 Amend 56 to License NPF-86,revising App a TSs Re Requirements for Control Room Subsystems ML20236R9301998-03-26026 March 1998 Amend 55 to License NPF-86,modifing TS Sections 6.0, Administrative Control, to Reflect Recent Organizational Changes & Changes to Approval Title for Section Qualified Reviewer Program & Correcting Incorrect Ref in TS 6.4.3.9.b ML20216H8341998-03-17017 March 1998 Amend 54 to License NPF-86,revising App a TSs Relating to Requirements for AC Power Sources,Changing Certain Requirements Related to EDG Stated in TS 3/4.8.1, AC Sources ML20141D1391997-06-24024 June 1997 Amend 52 to License NPF-86,modifying TS 6.8.1.6.b to Include Reference to NRC W Topical Rept WCAP-12610-P-A, Vantage+Fuel Assembly Reference Core Rept, Dtd April 1995 ML20141D5901997-06-24024 June 1997 Amend 53 to License NPF-86,modifying TS to Identify Fuel Assemblies Design Features ML20141B9781997-05-13013 May 1997 Amend 51 to License NPF-86,revising TSs Re Reactor Core Fuel Assembly Design Features Requirements Contained in TS 5.3.1, Fuel Assemblies ML20135F9261997-03-12012 March 1997 Amend 50 to License NPF-86 Revising App a TSs Related to in-core Detector Sys,Seismic Instrumentation,Meteorological Instrumentation & Turbine Overspeed Protection ML20135C1561997-02-24024 February 1997 Amend 49 to License NPF-86,revising Plant App a TSs 1.7, Containment Integrity, 3/4.6.1, Primary Containment, & 3/4.6.5, Containment Enclosure Bldg, to Incorporate Provisions of Option B to 10CFR50,App J ML20117F8621996-08-30030 August 1996 Amend 48 to License NPF-86,revising TS 3.8.3.1,action A,To Increase from 8 H to 7 Days,Allowable Time That 480 Volt Bus E64 May Be Less than Fully Energized ML20108D9981996-05-0707 May 1996 Amend 47 to License NPF-86,revising App a TS 3.3.2, Engineered Safety Features Actuation Sys Instrumentation ML20095L0681995-12-21021 December 1995 Corrected Page 3/4 4-25 & 26 W/Overleaf for Completeness of Amend 46 to License NPF-86.Error Involved TS Page W/O Page & Amend Number ML20095L0641995-12-21021 December 1995 Corrected Pages 3/4 3-33,3/4 3-26 & 3/4 3-19 & 20 W/Overleafs for Completeness of Amends 45 & 46 to License NPF-86 ML20094R1741995-11-29029 November 1995 Amend 45 to License NPF-86.Amend Revises App a TS Re Relocation of Functional Unit 6.b, Feedwater Isolation - Low RCS Tavg Coincident with a Reactor Trip from TS 3.3.2 to Technical Requirements Manual ML20094P9741995-11-28028 November 1995 Amend 44 to License 44,revise App a TS Re RCS Leakage & Deletes Table 3.4-1 from TS Section 3.4.6.2 & Ref Table 3.4-1 from Limiting Condition for Operation 3.4.6.2 F ML20094F4371995-11-0202 November 1995 Amend 43 to License NPF-86,modifying App a TSs for Turbine Cycle Safety Valves ML20091Q7321995-08-31031 August 1995 Amend 40 to License NPF-86,revising App a Re Containment Bldg Penetrations ML20083Q5591995-05-19019 May 1995 Amend 39 to License NPF-86,deleting from Ts,Certain Audit Responsibilities of Nuclear Safety Audit Review Committee & Review Responsibilities of Station Operation Review Committee Re Emergency Plan,Security Plan & Procedures ML20083D0741995-05-17017 May 1995 Amend 37 to License NPF-86,revising App a TSs Re Schedule for Performing Type a Containment ILRTs ML20082H9491995-04-10010 April 1995 Amend 36 to License NPF-86,revising TS to Allow Longer Surveillance Test Intervals & AOTs for RPS & ESFAS & Removing Requirement to Perform RTS Analog Channel Operational Test on Staggered Basis ML20078R0091995-02-14014 February 1995 Amend 35 to License NPF-86,modifying TS to Rename TS 6.2.3 from Independent Safety Engineering Group to Independent Technical Reviews & Replacing Requirements for Five Person Independent Safety Engineering Group ML20078H4701995-01-26026 January 1995 Amend 34 to License NPF-86,revising App a to Specify Composition of Sorc,Implement Station Qualified Reviewer Program & to Revise Time Which Nuclear Safety Audit Review Committee Must Issue Repts & Minutes ML20080C3111994-12-0606 December 1994 Corrected Tech Spec Page 2-1 for Amend 33 to License NPF-86,including Rev to Revised Figure 2.1-1 ML20078L9021994-11-23023 November 1994 Amend 33 to License NPF-86 Revising TS to Permit Operation of Plant Core W/Expanded Axial Flux Difference Band from That Currently Permitted ML20024J2031994-10-0505 October 1994 Amend 32 to License NPF-86,revising App a Re Operability Requirements for Primary Component Cooling Water Sys & Ultimate Heat Sink ML20029E1531994-05-0505 May 1994 Corrected Page 3/4 6-13 to Amend 30 to License NPF-86, Incorporating Changes Made by Amend 29 ML20065J5491994-04-0707 April 1994 Amend 30 to License NPF-86 Supporting TS Changes in Allowable Time Intervals for Performing SR on Plant Components During Power Operation ML20063M2411994-03-0707 March 1994 Amend 29 to License NPF-86,modifies LCO of TS 3.6.1.7 by Deleting Requirements Applicable to 36-inch Containment Shutdown Purge Supply & Exhaust Isolation Valves in Containment Air Purge Sys ML20059F0611994-01-0707 January 1994 Amend 28 to License NPF-86,revising Station,Unit 1 Operating License to Reflect Transfer of VT Electric Generation & Transmission Cooperative,Inc Undivided Ownership Interest to Util ML20059L9521993-11-10010 November 1993 Amend 26 to License NPF-86,revising Tech Specs to Reduce Frequency of Surveillances Required to Verify Integrity of Condensate Storage Tank at Least Every 18 Months ML20057D7481993-09-28028 September 1993 Amend 25 to License NPF-86,modifying TS Surveillance Requirement Re RWST Narrow Range Level Transmitters ML20056H2401993-08-24024 August 1993 Amend 24 to License NPF-86,revising TS Figure of Reactor Core Safety Limit Curves ML20056G1361993-08-16016 August 1993 Amend 22 to License NPF-86,revising App a TS Re Reporting Radioactive Effluent Releases from Facility ML20056G2671993-08-16016 August 1993 Amend 23 to License NPF-86,revising Plant Operating License to Reflect Name Change of Joint Owner Following Indirect Transfer of Control of Eua Power Corp Interest in Operating License ML20045B6701993-06-14014 June 1993 Amend 21 to License NPF-86,revising App a TS Re ECCS, Specifically,Amend Modifies Acceptance Value for Surveillance Requirement Intended to Demonstrate That ECCS Capable of Delivering Adequate Flow of Cooling Water ML20035G7161993-04-26026 April 1993 Amend 20 to License NPF-86,revising TS Re Administrative Controls Applicable to Station Staff ML20106D1421992-09-30030 September 1992 Amend 17 to License NPF-86,allowing Verification of Operability of Reactor Trip Breaker Shunt Trip Circuitry Prior to First Planned or Unplanned Shutdown ML20118B0481992-09-21021 September 1992 Amend 16 to License NPF-86,revising TS to Implement Guidance of GL 90-06 Concerning Safe Plant Operation ML20099F5271992-08-10010 August 1992 Amend 13 to License NPF-86,revising TS to Decouple Loss of Offsite Power/Safety Injection Test from 24 H Diesel Generator Surveillance Run ML20099G2981992-08-10010 August 1992 Amend 12 to License NPF-86,providing Replacement of RTD Bypass Sys for Measurement of Primary Loop Temp w/fast-response thermowell-mounted RTDs ML20101B4381992-05-29029 May 1992 Amend 10 to License NPF-86,revising License to Reflect Transfer of Operations & Maintenance of Seabrook Station, Unit 1 to North Atlantic Energy Svc Co ML20092M2611992-02-18018 February 1992 Amend 9 to License NPF-86,revising Tech Spec by Relocating Cycle Specific Core Operating Limits from Tech Spec to Core Operating Limits Rept ML20086D6791991-11-18018 November 1991 Amend 8 to License NPF-86,changing Tech Spec for Facility to Redefine Fully Withdrawn Position of All Rcca Banks to Minimize Localized Rcca Wear ML20085N6951991-10-10010 October 1991 Amend 7 to License NPF-86,revising TS to Add Digital Channel Operational Test Definition to Section 1 of TS & Footnotes for TS Tables 4.3-5 & 4.5-6 ML20083D1491991-09-12012 September 1991 Corrected Amend 6 to License NPF-86,providing Overlap Pages, Instruction Sheet & TS Change Pages 1999-09-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C8411999-10-0505 October 1999 Amend 64 to License NPF-86,revising TSs 3.7.6.1 & 3.7.6.2 to Delete Restriction to Suspend All Operations Involving Positive Reactivity Changes During Plant Conditions Specified ML20212L1071999-10-0101 October 1999 Amend 63 to License NPF-86,relocating TS 3/4.7.10, Area Temperature Monitoring, & Associsted TS Table 3.7-3.to Technical Requirements Manual ML20212D0761999-09-17017 September 1999 Amend 62 to License NPF-86,revising TS 3.7.6.2 to Increase AOT for Control Room Air Conditioning Subsystem from 30 to 60 Days to Allow Adequate Time to Replace Portions of Existing System During Current Operating Cycle ML20210Q1631999-08-12012 August 1999 Amend 61 to License NPF-86,revising TS SR 4.5.2b.1 to Delete Prescribed Method of Venting ECCS Which Would Allow Alternate Method to Verify That ECCS Piping Will Be Full of Water ML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20204E3391999-03-12012 March 1999 Amend 60 to License NPF-86,revising TS Table 3.3-4 to Depict Change to Refueling Water Storage Tank low-low Level Setpoint ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249C6401998-06-24024 June 1998 Amend 58 to License NPF-86,revises TS 4.5.2.b.1 for ECCS Subsystems to Delete Requirements to Vent Operating Chemical Volume & Control Sys Centrifugal Charging Pump Casing ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C7861998-04-0909 April 1998 Amend 56 to License NPF-86,revising App a TSs Re Requirements for Control Room Subsystems ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20236R9301998-03-26026 March 1998 Amend 55 to License NPF-86,modifing TS Sections 6.0, Administrative Control, to Reflect Recent Organizational Changes & Changes to Approval Title for Section Qualified Reviewer Program & Correcting Incorrect Ref in TS 6.4.3.9.b ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20216H8341998-03-17017 March 1998 Amend 54 to License NPF-86,revising App a TSs Relating to Requirements for AC Power Sources,Changing Certain Requirements Related to EDG Stated in TS 3/4.8.1, AC Sources ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141D5901997-06-24024 June 1997 Amend 53 to License NPF-86,modifying TS to Identify Fuel Assemblies Design Features ML20141D1391997-06-24024 June 1997 Amend 52 to License NPF-86,modifying TS 6.8.1.6.b to Include Reference to NRC W Topical Rept WCAP-12610-P-A, Vantage+Fuel Assembly Reference Core Rept, Dtd April 1995 ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy-4 Fuel Cladding Matl ML20141B9781997-05-13013 May 1997 Amend 51 to License NPF-86,revising TSs Re Reactor Core Fuel Assembly Design Features Requirements Contained in TS 5.3.1, Fuel Assemblies ML20135F9261997-03-12012 March 1997 Amend 50 to License NPF-86 Revising App a TSs Related to in-core Detector Sys,Seismic Instrumentation,Meteorological Instrumentation & Turbine Overspeed Protection ML20135C1561997-02-24024 February 1997 Amend 49 to License NPF-86,revising Plant App a TSs 1.7, Containment Integrity, 3/4.6.1, Primary Containment, & 3/4.6.5, Containment Enclosure Bldg, to Incorporate Provisions of Option B to 10CFR50,App J ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20117F8621996-08-30030 August 1996 Amend 48 to License NPF-86,revising TS 3.8.3.1,action A,To Increase from 8 H to 7 Days,Allowable Time That 480 Volt Bus E64 May Be Less than Fully Energized ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20108D9981996-05-0707 May 1996 Amend 47 to License NPF-86,revising App a TS 3.3.2, Engineered Safety Features Actuation Sys Instrumentation ML20095L0681995-12-21021 December 1995 Corrected Page 3/4 4-25 & 26 W/Overleaf for Completeness of Amend 46 to License NPF-86.Error Involved TS Page W/O Page & Amend Number ML20095L0641995-12-21021 December 1995 Corrected Pages 3/4 3-33,3/4 3-26 & 3/4 3-19 & 20 W/Overleafs for Completeness of Amends 45 & 46 to License NPF-86 ML20094R1741995-11-29029 November 1995 Amend 45 to License NPF-86.Amend Revises App a TS Re Relocation of Functional Unit 6.b, Feedwater Isolation - Low RCS Tavg Coincident with a Reactor Trip from TS 3.3.2 to Technical Requirements Manual ML20094P9741995-11-28028 November 1995 Amend 44 to License 44,revise App a TS Re RCS Leakage & Deletes Table 3.4-1 from TS Section 3.4.6.2 & Ref Table 3.4-1 from Limiting Condition for Operation 3.4.6.2 F ML20094F4371995-11-0202 November 1995 Amend 43 to License NPF-86,modifying App a TSs for Turbine Cycle Safety Valves ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) 1999-09-17
[Table view] |
Text
.
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of"#%
j p
UNITED STATES j
y j
NUCLEAR REGULATORY COMMISSION I
a WASHINGTON. D.C. 30006 4 001 NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*
i DOCKET N0. 50-443 l
I SEABROOK STATION. UNIT NO. 1 l
a AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 45 i
License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission) has found that:
~
The application for amendment by North Atlantic Energy Service l
A.
i Corporation, et al. (the licensee), dated September 20, 1995, complies with the standards and requirements of the Atomic Energy i
Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;'
The facility will operate in conformity with the application, I
I
- 8..
-the provisions of the Act, and the rules and regulations of the i
Commission-L L
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health e
l and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 4
l defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Commission's regulations and all applicable requirements have been satisfied.
i
- North Atlantic Energy Service Company (NAESCO) is authorized to act as agent for the: North Atlantic Energy Corporation, Canal Electric Company, The Connecticut Light and Power Company, Great Bay Power Corporation, Hudson Light and Power Department, Massachusetts Municipal Wholesale Electric Company, i
i -
Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, and The United Illuminating Company, and has exclusive responsibility and control over the physical i
construction, operation, and maintenance of the facility, i
i 9512040305 951129 PDR ADOCK 05000443 P
PDR
4 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows:
(2) Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 45, and the Envircamental Protection Plan contained in Appendix B are incorporated into Facility License No.
NPF-86.
NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
1 FOR THE NUCLEAR REGULATORY COMISSION
~
Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i,
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 29, 1995 l
l
l ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILITY OPERATING LICENSE NO. NPF-86 i
DOCKET NO. 50-443 i
Replace the following pages of Appendix A, Technical Specifications, with the i
attached pages as indicated. The revised pages are identified by amendment number and contain yertical lines indicating the areas of change. Overleaf pages are provided.
q Remove Insert 3/4 3-19 3/4 3-19 i
4 i
3/4 3-20 3/4 3-20 3/4 3-25*
3/4 3-25*
4 3/4 3-26 3/4 3-26 3/4 3-33 3/4 3-33 l,
3/4 3-34*
3/4 3-34*
i l
4 a
t I
._.._-___.__.__....-_m._,
m 9
e-
+
4 i
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMLNTATION MINIMUM TOTAL NO.
CHANNELS CHAlelELS APPLICABLE' FUNCTIONAL UNIT OF CHAfG1ELS 10 TRIP OPERABLE MODES ACTION
. 4.
Steam Line Isolation (continued) b.
Automatic Actuation 2
1 2
1, 2, 3 20-Logic and Actuation f
Relays i
- c. ' Containment Pressure--
3 2
2 1, 2,-3 18*
i Hi-2 d.
Steam Line 3/ steam line 2/ steam line 2/ steam line' 1, 2, 3#
18*
Pressure-Low
. any steam-line e.
Steam Generator Pressure - Negative 3/ steam line 2/ steam line 2/ steam'line 3**
18*
l Rate-High any steam line i
5.
Turbine Trip
-I a.
Automatic Actuation 2
1 2
1, 2 22 Logic and Actuation Relays b.
Steam ~ Generator 4/sta. gen.
2/sta. gen.
3/sta, gen.
1, 2 18' Water Level--
High-High-(P-14).
6.
Feedwater Isolation a.
Steam Generator Water 4/sta. gen.
2/sta. gen.
3/sta. gen.
1, 2 18 Level--High-High (P-14) i b.
Safety Injection See Item 1. above for all Safety Injection initiating functions
~
and requirements.
i
.-.. -... ~.
++.ww..-...4 w..-,
a--.
-. - - -.. + +.,*
4.
4
- ~. -
- + - -
.a
4
' TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE l
FUNCTIONAL UNIT OF CHANhELS TO TRIP OPERABLE MODES ACTION t
7.
Emergency Feedwater a.
Manual Initiation (1) Motor driven pocp 1
1 1
1, 2, 3 21 (2) Turbine driven pump 2
1 2
1, 2, 3 21 b.
Automatic Actuation Logic 2
1 2
1, 2, 3 20 and Actuation Relays c.
Stm. Gen. Water Level--
Low-Low Start Motor-Driven Pump 4/sta. gen.
2/sta. gen.
3/sta. gen. 1, 2, 3 18 and Start Turbine -
Driven Pump d.
Safety Injection Start Motor-Driven Pump See Item 1. above for all Safety Injection initiating functions and and Turbine-Driven Pump requirements.
e.
Loss-of-Offsite Power Start Motor-Driven See Item 9 for loss-of-Offsite Power initiating functions and Pump and Turbine-requirements.
Driven Pump 8.
Automatic Switchover to Containment Sump a.
Automatic Actuation 2
1 2
1, 2, 3, '4 13 Logic and Actuation Relays
. TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUNENTATION TRIP SETPOINTS SENSOR TOTAL ERROR l
FUNCTIONAL UNIT y.'
ALLOWANCE iTA) 1 (S)
TRIP SETPOINT ALLWi4RLE VALUE 3.
Containment Isolation \\
a.
Phase "A" Isolgtlon
- 1) Manual Initiation N.A.
N.A.
N.A.
N.A.
N.A.
- 2) Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N.A.
and Actuation Relays
- 3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
b.
Phase "B" Isolation
- 1) Manual Initiatior N.A.
M.A.
N.A.
N.A.
N.A.
- 2) Automatic Actuation N.A.
N.A.
N.A.
N.A.
N.A.
Logic and Actuation Relays
- 3) Containment Pressure--
3.0 0.71 1.67 s 18.0 psig~
s 18.7 psig Hi-3 c.
Containment Ventilation Isolation l
- 1) Manual Initiation N.A.
N.A.
N.A.
N.A.
N.A.
- 2) Automatic Actuation N.A.
N.A.
N.A.
N.A.
N.A.
Logic and Actuation Relays
- 3) Safety Injection See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.
- 4) Containment On-Line Purge N.A.
N.A.
N.A.
<2x N.A.
Radioactivity-High
Background
4 TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE fTA) I (S)
TRIP SETPOINT ALLOWABLE VALUE 4.
Steam Line Isolation a.
Manual Initiation (System)
N.A.
N.A.
N.A.
N.A.
N.A.
b.
Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N.A.
and Actuation Relays c.
Containment Pressure--Hi-2 5.2 0.71 1.67
$4.3 psig
$5.3 psig d.
Steam Line Pressure '-Low 13.1 10.71 1.63 2585 psig 2568 psig*
e.
. Steam Generator Pressure -
3.0 0.5 0
s100 psi s123 psi **
Negative Rate--High 5.
Turbine Trip a.
Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N.A.
Actuation Relays b.
Steam Generator Water 4.0 2.24 0.55
$86.0% of s87.7% of narrow Level--High-High (P-14) narrow range range instrument instrument span.
span.
6.
Feedwater Isolation a.
Steam Generator Water 4.0 2.24 0.55 586.0% of 587.7% of narrow Level--Hi-Hi-(P-14) narrow range range instrument instrument span.
span.
b.
Safety Injection N.A.
N.A.
N.A.
N.A.
N.A.
-l
TABLE 4.3-2 (Cor.tinued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IESI IESI IS REQUIRED
- 4. Steam Line Isolation
- a. Nanual Initiation N.A.
N.A.
N.A.
R N.A.
N.A.
N.A.
1, 2, 3 (System)
- b. Automatic Actuation N.A.
N.A.
N.A.
N.A.
N(1)
N(1)
Q 1, 2, 3 Logic and Actuation Relays
- c. Containment Pressure-S R
Q N.A.
N.A.
N.A.
N.A.
1, 2, 3 Hi-2
- d. Steam Line S
R Q
N.A.
N.A.
N.A.
N.A.
1, 2, 3 Pressure-Low
- e. Steam Line Pressure-S R
Q N.A.
N.A.
N.A.
N.A.
3 Negative Rate-High
- 5. Turbine Trip
- a. Automatic Actuation N.A.
N.A.
N.A.
N.A.
N(1)
M(1)
Q 1, 2 Logic and Actuation Relays
- b. Steam Generator Water S
R Q
N.A.
N.A.
N.A.
N.A.
1, 2 l
Level-High-High (P-14)
- 6. Feedwater Isolation i
l
- a. Steam Generator Water S
R Q
N.A.
N.A.
N.A.
N.A.
1, 2 Level--High-High (P-14)
- b. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
l
- 7. Emergency Feedwater
- a. Manual Initiation
- 1) Motor-driven pump N.A.
N.A.
N.A.
R N.A.
N.A.
N.A.
1, 2, 3
- 2) Turbine-driven pump N.A.
N.A.
N.A.
R N.A.
N.A.
N.A.
1, 2, 3
l TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING N) DES CHAfMIEL DEVICE MASTER SLAVE FOR WIICH CHANNEL
. CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUN:TIONAL UNIT
.' CHECK CALIBRATION TEST TEST LOGIC TEST E
E IS REQUIRED 7.
Emergency Feedwater (Cen,tinued) 4
- b. Automatic Actuation N.A.
N.A.
N.A.
N.A.
M(1)
M(1)
Q 1, 2, 3 and Actuation Relays
- c. Steam Generator Water S
R Q
N.A.
M.A.
N.A.
N.A.
1, 2, 3 l
Level-Low-Low, Start Motor-Driven Pump and Turbine-Driven Pump
- d. Safety Injection, Start.See Item 1. above for all Safety Injection Surveillance Requirements.
i Motor-Driven Pump and Turbine-Driven Pump
- e. Loss-of-Offsite Power See Item 9. for all Loss-of-Offsite Power Surveillance Requirements.
Start Motor-Driven Pump and Turbine-Driven Pump
- 8. Automatic Switchover to Containment Sump
- a. Automatic Actuation N.A.
N.A.
N.A.
N.A.
M(1)
M(1)
Q 1, 2, 3, 4 Logic and Actuation Relays
- b. RWST Level Low-Low N.A.
R Q
Q(3)
N.A.
N.A.
N.A.
1, 2, 3, 4 l
Coincident With Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.
-