Letter Sequence Request |
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Results
Other: A01658, Submits Addl Info Re Independence of Four Channels of Reactor Protection & Engineered Safeguards Actuation Sys Measurement Logic,In Response to NRC, ML17212B541, ML18047A273, ML20009C700, ML20009D105, ML20050Q900, ML20054C030, ML20054C820, ML20054C988, ML20054C994
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MONTHYEARML18046B4081977-06-28028 June 1977
Safety Evaluation Supporting Amend 15 to License DPR-67. Calvert Cliffs Sample Tech Specs Re Reactor Protection Sys & Engineered Safety Features Actuation Sys Encl
Project stage: Approval
ML20003G0471978-09-12012 September 1978
Summary of 780802 Meeting W/Utils & C-E Re Length of Time Single Failed Reactor Protection Sys Channel Should Be Bypassed Before Requiring Tripping
Project stage: Meeting
ML20238E6041978-09-15015 September 1978
Forwards Ltrs to Utils Documenting NRC Position Presented at 780802 Meeting & Requesting That STS Allowing Limited Reactor Protection Sys Channel Bypass Be Proposed
Project stage: Meeting
ML20238E6971978-09-30030 September 1978
Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls
Project stage: Meeting
ML20238E6521978-09-30030 September 1978
Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls
Project stage: Meeting
ML20238E6441978-09-30030 September 1978
Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls
Project stage: Meeting
ML20238E7021978-09-30030 September 1978
Sumarizes 780802 Meeting W/Utils & C-E in Bethesda,Md Re Action Requirements in Event of Reactor Protection Sys Channel Inoperability.Meeting Held to Clarify NRC Position on Subj as Presented in .W/O Encls
Project stage: Meeting
ML18046A5781981-04-16016 April 1981
Requests Results within 90 Days Re Review of Reactor Protection & Engineered Safety Features Actuation Sys Channel Operability.Application for License Amend Re Tech Specs Change May Be Substituted for Review
Project stage: Approval
ML20003G6471981-04-16016 April 1981
Requests Results within 90 Days Re Review of Reactor Protection & Engineered Safety Features Actuation Sys Channel Operability.Application for License Amend Re Tech Specs Change May Be Substituted for Review
Project stage: Approval
ML20009C7001981-07-15015 July 1981
Advises That Verification Results Re Adequacy of Physical & Electrical Separation & Independence of Reactor Protection Sys Instrument Channels & Engineered Safety Features Actuation Sys Subsystems Expected by End of 1982 Outage
Project stage: Other
ML20009D1021981-07-21021 July 1981
Application for Amend to License DPR-40 to Upgrade Provisions Re Operation W/Tripped or Bypassed Reactor Protection or Emergency Safeguards Feature Channel
Project stage: Request
ML20009D0991981-07-22022 July 1981
Forwards Application for Amend to License DPR-40 & Proposed Tech Specs.Amend Upgrades Provisions Re Operation W/Tripped or Bypassed Reactor Protection or Emergency Safeguards Feature Channel.Certificate of Svc Encl
Project stage: Request
ML20009D1051981-07-22022 July 1981
Proposed Tech Specs Upgrading Provisions Re Operation W/ Tripped or Bypassed Reactor Protection or Emergency Safeguards Feature Channel
Project stage: Other
ML18046A8251981-07-27027 July 1981
Informs That Applicant Will Submit Application for Tech Spec Changes by 810915 Re Reactor Protection Sys Inoperable Channel Condition.Documentation of Design Similarities to St Lucie & Calvert Cliffs Complete
Project stage: Request
A01658, Submits Addl Info Re Independence of Four Channels of Reactor Protection & Engineered Safeguards Actuation Sys Measurement Logic,In Response to NRC1981-10-23023 October 1981
Submits Addl Info Re Independence of Four Channels of Reactor Protection & Engineered Safeguards Actuation Sys Measurement Logic,In Response to NRC
Project stage: Other
ML20050Q9001982-03-31031 March 1982
Informs of Modified Staff Position on Length of Time Reactor Protection Sys or ESF Actuation Sys Channel May Be Bypassed. San Onofre Unit 2 Tech Spec & Design Criteria Encl
Project stage: Other
ML20054C8201982-03-31031 March 1982
Provides Options for Licensees Which Would Allow Flexibility in Performing Maint & Testing of Inoperable Channels,Per .San Onofre Proof & Review Tech Specs Encl
Project stage: Other
ML20054C9941982-03-31031 March 1982
Informs of Modified Position on Length of Time Reactor Protection Sys or ESF Actuation Sys Channel May Be Bypassed. Proposed Tech Specs Encl
Project stage: Other
ML18047A2731982-03-31031 March 1982
Forwards Proof & Review Copy of Tech Specs,Incorporating Changes to Permit 48-h Bypass of Reactor Protection Sys & ESF Actuation Sys Inoperable Channel.Design Criteria Permitting Bypass for Indefinite Period Encl
Project stage: Other
ML20054C0301982-03-31031 March 1982
Forwards Proof & Review Copy of Tech Specs,Incorporating Changes to Permit 48-hr Bypass of Reactor Protection Sys & ESF Actuation Sys Inoperable Channel.Design Criteria Permitting Bypass for Indefinite Period Encl
Project stage: Other
ML20054C9881982-03-31031 March 1982
Advises That NRC Position Modified Re Reactor Protection Sys & ESF Actuation Sys.Proposed Tech Specs Encl
Project stage: Other
ML17212B5411982-03-31031 March 1982
Informs of Modified Position on Length of Time Reactor Protection Sys or ESF Actuation Sys Channel May Be Bypassed. Proposed Tech Specs Encl
Project stage: Other
1981-04-16
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consumers Power company General Offices: 212 West Michigan Avenua, Jackson, Ml 49201 * (6171 788-0660 July 27' 1981 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -
LIChl~SE DPR PALISADES PLANT -
REACTOR PROTECTION SYSTEM INOPERABLE CHANNEL CONDITION NRC letter dated April 16, 1981 resumed the evaluation of the RPS inoperable channel condition for the Palisades Plant.
The referenced letter stated that long term operation of a four channel Reactor Protection System (RPS) and Engineered Safety Features Actuation System (ESFAS) in a 2 out of 3 logic configuration would be acceptable provided all four channels are sufficiently independent.
It was requested in this letter, that Consumers Power Company supply either one of the following:
- 1.
Elaboration of the physical and electrical seperation of the fo'ur channels in each system in order to judge sufficient independency cif all four channels.
- 2.
As an alternative to number one, Consumers could submit an application for Technical Specification Change that was like the Calvert Cliffs and St. Lucie Technical Specification.
Included in this application would be the documentation of design similarity to that of Calvert Cliffs and St. Lucie.
Consumers Power Company has chosen, based on its Technical review, to provide the application for change to the Palisades Technical Specifications.
At the present time the technical review work and the documentation of design similarities to Calvert Cliffs and St. Lucie have been completed.
Tne Technical Specification Change is being drafted and reviewed and should be available for su-omi ttal by September 15, 1981.
Brian D Johnson Senior Licensing Engineer CC Director, Region III, USNRC i'iRC Resident Inspector-Palisades
