Letter Sequence Meeting |
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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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DISTRIBUTION:
,..Glainas l
Docket File NRC PDR DTondi Docket No.:
50-309 Rdg
..JBurdoin L PDR L
RIngram CNelson ELConner r
, OELD., _
Yankee Atonic Electric Company ATTl4:
Mr. Robert !!. Grace
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Licensing Engineer DEisenhut i
20 Turnpike Road ACRS (16) l Westboro,11 massachusetts 01581 h nan
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Gentlemen:
UTJCarter Gray File On August 2,1978, representatives front utilities using Combustion Engineering (CE) NSSS and from CE met in bothesda, Maryland to discuss the action requirements in the event of Reactor Protection System ( APS) channel inoperability. Enclosure 1 is the ninutes of this necting. The r;;eeting was held to clarify our position on this subject as presented in our letter dated October 26, 1977 and to gain an understanding of your position as indicated in your response dated December 1,1977 This sane subject had been discussed pre-viously on liarch 16, 1976.
In our previous correspondence, we requested that you submit an 'applf-cation for license anendment to change the 11aine Yankee Technical Specifications (TS) Section 3.9 to require inoperaole RPS channels to be placed in the " tripped" status within one hour after being declared
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inoperaDie. He further stated that you could request that we under-take a specific facility review of your RPS to determine the suitabil-i ity of operating the RPS in a two-out-of-three logic.
Your response requested such a specific facility RPS review and we propose that the
!!aine Yankee RPS review be schedulndfor the month of October 1976.
The exact date will be coordinated through your Operating Reactor Branch Project lianager (ORPH). Enclosure 2 is the RPS review items that will be of interest to our review team.
As you know, our staff has conducted the RPS review at the Calvert Cliffs and St. Lucie units. A copy of the resultant Safety Evaluation for St. Lucie, presenting the finding of the RPS review (pages 3 to 5),
is provided for your infonsation as Enclosure 3.
Our conclusion was I
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w=n Yankee'Atoaic Electric Co. -
1 that allowing indefinite bypass of one of -the four RPS is not
. justified,- butisince the four channel CE system does have some independence, bypassing for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during testing or. maintenance of one RPS channel > 1s justified.
As an alternative to the onsite HRC review of your RPS, we will consider issuance of the Calvert Cliffs and St. Lucie type TS of y'our RPS'if you provide an application including documentation of Lyour RPS similarity to those of Calvert Cliffs and St. Lucio. Any such. application should.be submitted within 45 days of the date of this letter.
Sincerely, Robert 11. Reid, Chief Operating Reactors Branch _ #4 Division of Operating Recctors Enlosures:
1.
. eeting Summary H
2.
Review Item-3.
Sa fety. Eva s ua tion 1 cc w/ enclosures:
See next page t-e N
ORB #4:00R ORB #4: DOR C-PSB; DOR AD-E&P: DOR
_C-0RBf4: DOR ELConner:rf CNelson Glainas _
DGrimes RReid _
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