Letter Sequence Other |
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Results
Other: ML19341A422, ML19341A424, ML19341B423, ML19341C004, ML19341C007, ML19343B857, ML19343D035, ML19343D039, ML19351A069, ML19351G105, ML20003A648, ML20003A650, ML20003A653, ML20005A189, ML20008E635, ML20010B899, ML20010H761, ML20010H997, ML20030D756, ML20031B542, ML20031D162, ML20031D166, ML20031D172, ML20031D176, ML20031D178, ML20032B192, ML20032B195
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MONTHYEARML19340D1571980-12-15015 December 1980 Response to Intervenor Carolina Environ Study Group 801107 Addl Contentions Re Hydrogen Generation Control.Contentions 5 & 6 Should Not Be Admitted in Proceedings.Certificate of Svc Encl Project stage: Request ML19341A4241981-01-12012 January 1981 Proposed Tech Specs Sections 3 & 4 Changing Explosive Gas Mixtures in Tanks W/Radioactive Effluents & Deleting Requirement for Hydrogen Monitor in Waste Gas Holdup Sys Project stage: Other ML19341A4221981-01-12012 January 1981 Forwards Proposed Tech Specs,Changing Explosive Gas Mixtures in Tanks W/Radioactive Effluents & Deleting Hydrogen Monitor Requirement for Waste Gas Holdup Sys Project stage: Other ML19351G1051981-01-23023 January 1981 Unexecuted Amend 4 to Indemnity Agreement B-83,changing Amount of Financial Protection Project stage: Other ML20003A6501981-01-23023 January 1981 License NPF-9 for Facility Project stage: Other ML20003A6531981-01-23023 January 1981 Notice of Issuance & Availability of License NPF-9 for Fuel Loading & Zero Power Testing.Amend 4 to Indemnity Agreement B-83 Encl Project stage: Other ML19341B4231981-01-23023 January 1981 Memorandum & Order Affirming ASLB 801225 Order.Authorizes Director,Nuclear Reactor Regulation,To Issue License NPF-9, Permitting Fuel Loading & Zero Power Testing at Unit 1. Certificate of Svc Encl Project stage: Other ML20003A6481981-01-23023 January 1981 Informs That License NPF-9 Has Been Issued Authorizing Fuel Loading & Zero Power Testing.License & Notice of Issuance Encl Project stage: Other ML19341C0071981-01-28028 January 1981 Notice of Issuance & Availability of Amend 1 to License NPF-9 Project stage: Other ML19341C0091981-01-28028 January 1981 Safety Evaluation Supporting Amend 1 to License NPF-9 Project stage: Approval ML19341C0041981-01-28028 January 1981 Amend 1 to License NPF-9,revising Wording to Prior to Initial Criticality from Prior to Fuel Loading Project stage: Other ML19343B8571981-01-28028 January 1981 Revised App a Tech Specs Page 3/4 8-3,correcting Surveillance Requirements for Diesel Generator Project stage: Other ML20008E6351981-02-23023 February 1981 Tech Specs 3.4.7.2,3/4.5.1,3.5.1.1,4.5.1.1,3/4.5.3,3.5.5.3, 4.5.3.1,4.5.3.2,3.8.1.2,3.11.2.5,4.11.2.5 & Tables 3.4-1, 3.7-6 & 3.3-13 Re Oxygen Concentration in Waste Gas Holdup Sys,Hydrogen Monitor Requirements Et Al Project stage: Other ML20008E6331981-02-23023 February 1981 Application for Amend to License Submitted as Proposed Revision to Tech Specs Project stage: Request ML19343D0351981-04-0202 April 1981 Amend 2 to License NPF-9,correcting Typographical Errors & Revising RCS Testing Requirements Project stage: Other ML19343D0381981-04-0202 April 1981 Safety Evaluation Supporting Amend 2 to License NPF-9 Project stage: Approval ML19343D0391981-04-0202 April 1981 Notice of Issuance & Availability of Amend 2 to License NPF-9 Project stage: Other ML19351A0711981-06-12012 June 1981 Notice of Issuance of License NPF-9 Project stage: Approval ML19351A0691981-06-12012 June 1981 License NPF-9 for Facility Project stage: Other ML20004F6891981-06-17017 June 1981 Proposed Changes to Tech Specs 3/4.8.1,3/4.3.3.7 & Table 3.3-11 Re Fire Detection Instrumentation Project stage: Request ML20004F6851981-06-17017 June 1981 Application to Amend License NPF-9,consisting of Proposed Changes to Tech Specs 3/4.8.1,3/4.3.3.7 & Table 3.3-11 Re Fire Detection Instrumentation Project stage: Request ML20005A1891981-06-19019 June 1981 Notice of Issuance & Availability of Amend 1 to License NPF-9 Project stage: Other ML20005A1871981-06-19019 June 1981 Safety Evaluation Supporting Amend 1 to License NPF-9 Project stage: Approval ML20010B8991981-08-12012 August 1981 Proposed Revised Tech Specs Re Setpoints,Surveillance, Listings,Response Times & Measurements Project stage: Other ML20010B8951981-08-12012 August 1981 Application to Amend License NPF-9.Change Includes Revising Setpoints & Surveillance Requirements,Correcting Measurement Range of Unit Vent Noble Gas Effluent Monitor & Revising Surveillance Requirements.Class IV Amend Fee Encl Project stage: Request ML20030D7561981-08-28028 August 1981 Amend 3 to License NPF-9,modifying Surveillance Requirements for Auxiliary Feedwater Suction pressure-low Pressure Instrumentation Project stage: Other ML20030D7591981-08-28028 August 1981 Notice of Issuance of Amend 3 to License NPF-9 Project stage: Approval ML20030D7581981-08-28028 August 1981 Safety Evaluation Supporting Amend 3 to License NPF-9 Project stage: Approval ML20031B5421981-09-0303 September 1981 Notifies That No Known Public Correspondence Re Amend 4 to License NPF-9 Exists Project stage: Other ML20010H9941981-09-21021 September 1981 Application to Amend Ol,Changing Tech Specs by Correcting Setpoint Associated W/Reactor Trip Initiated by Turbine Trip.Class III Amend Fee Encl Project stage: Request ML20010H9971981-09-21021 September 1981 Proposed Tech Spec 2.2,correcting Setpoint Associated W/ Reactor Trip Initiated by Turbine Trip Project stage: Other ML20010H7611981-09-21021 September 1981 Requests Extension of Completion Date for Review of TMI Action Plan Item II.D.1 Re Relief & Safety Valve Tests Until 820701 Project stage: Other ML20031D1781981-09-22022 September 1981 Advises That No Known Public Correspondence or Irreversible Impact Associated W/Amend 5 to License NPF-9 Project stage: Other ML20031D1721981-09-23023 September 1981 Amend 5 to License NPF-9,correcting Setpoint Associated W/Reactor Trip Initiated by Turbine Trip Project stage: Other ML20031D1751981-09-23023 September 1981 Safety Evaluation Supporting Amend 5 to License NPF-9 Project stage: Approval ML20031D1761981-09-23023 September 1981 Notice of Issuance & Availability of Amend 5 to License NPF-9 Project stage: Other ML20031D1661981-09-30030 September 1981 Notice of Issuance & Availability of Amend 6 to License NPF-9 Project stage: Other ML20031D1621981-09-30030 September 1981 Amend 6 to License NPF-9,extending Date for Full Compliance W/Relief & Safety Valve Testing Until 820701 Project stage: Other ML20031D1641981-09-30030 September 1981 Safety Evaluation Supporting Amend 6 to License NPF-9 Project stage: Approval ML20031H5181981-10-19019 October 1981 Advises That Fee Waived for Issuance of Amend 6 to License NPF-9,per 811021 Application Requesting Extension of Completion Date for Qualification Tests for Power Operated Relief & Safety Valves Project stage: Approval ML20032B1951981-10-27027 October 1981 Notice of Issuance & Availability of Amend 7 to License NPF-9 Project stage: Other ML20032B1941981-10-27027 October 1981 Safety Evaluation Supporting Amend 7 to License NPF-9 Project stage: Approval ML20032B1921981-10-27027 October 1981 Amend 7 to License NPF-9,revising Tech Specs to Change Instrumentation Setpoints,Correct Monitor Measurement Range & Revise Snubber Listings Project stage: Other 1981-06-12
[Table View] |
Text
F Technical Specification 2.2 - Reactor Trip Instrumentation Setpoints Proposed Change Change Values on Item 12B in Table 2.2-1 to read:
12A) Low System Pressure Trip - Trip Setpoint > 45 psig Allowable Value > 42 psig Justification an.d Safety Analysis The design of the Turbine Trip / Reactor Trip circuit is based on the control oil system which is used to control DEH system oil pressure through an interface valve. When a turbine trip signal is initiated, a section of the control oil system is bled off which in turn dumps the pressure on the DEH system to close the turbine control and stop valees.
This control oil system generates a low pressure signal at 45 psig through 2 out of 3 logic to trip the reactor above the P-8 setpoint.
The DEH low pressure trip at 900 psig serves to close the turbine control and stop valves which in turn would trip the reactor through the turbine stop valve closure switch at 1% open.
However, the DEH system low pressure trip does not directly feed the reactor trip circuit.
Therefore, the setpoint specified should be for the control oil pressure switches which dir-ectly initiate the reactor ^ trip.
This proposed change corrects the current Technical Specifications to correctly specify the trip setpoint and as such does not result in any adverse safety im-plications.
8109290484 810921 PDR ADOCK 05000369 P
PDR.