Letter Sequence Other |
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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
[Table View] |
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| ML20009C700 |
| Person / Time |
|---|
| Site: |
Maine Yankee |
|---|
| Issue date: |
07/15/1981 |
|---|
| From: |
Garrity J
Maine Yankee |
|---|
| To: |
Clark R
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| FMY-81-106, JHG-81-160, TAC-7089, NUDOCS 8107210371 |
| Download: ML20009C700 (1) |
|
Text
2.C.2.1 JHG 81-160 MAIRE
%dHARHEE AmmmPMERComPAR9*
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(207) 623-3521 O
July 15, 1981 FMY 81-106 United States tbclear Regulatory Commission Washington, D. C.
20555 Attention: Offi e of tbclear Reactor Regulation Division of Licensing Operating Reactors Branch #3 Mr. Robert A. Clark, Chief
Reference:
(a) License No. DPR-36 (Docket No. 50-309)
(b) USNRC Letter to MYAPC dated April 16, 1981
Subject:
Independence of Reactor Protective System (RPS) Instrument Channels and Engineered Safety Features Actuation System (ESFAS)
Subsystems
Dear Sir:
Your letter, Reference (b), requested Maine Yanket to provide the results of a verification of the adequacy of physical and elect 11 cal separation and independence of the RPS instrument channels and ESFAS subsystems.
t In a meeting with the staff on May 4,1981, it was agreed that the schedule provided in that letter was inappropriate and could not be accommodated by Maine Yankee because of ongoing, preparations for the 1981 refueling outage, during which many of the NRC's Post TMI requirements were scheduled for implementation.
Maine Yankee intends to provide the information requested in Reference (b) by the end of the 1982 refueling outage. We anticipate tre need to discuss this matter further with your staff before that time so that the scope of our efforts can be agreed to.
W trust this schedule is acceptable.
If thare are any questions, please contact us.
(oo I Very truly yours, y
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'A, MAINE YANKEE ATOMIC POWER COMPANY
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