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:
Docket File
.TJCarter flRC PDR
_ Gray File [0RB#2) l/
L PDR
.JBurdoin
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Dechet ta.:
60 4 S5 ORBf4 Rdg
.DTondi p
RIngram
. _Glainas f
RReid ELConner
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RSilver i
Consuners Power Concany Attorney, OELD I
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ATTH:
"r. David Dixel DZiemann
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l Nuclear Licensing Atininistrator HSmith j
212 West fiichigan Avenue OI&E (3) 1 I
Jaci. son, "ichigan 49201 DEisenhut J
TERA, DSB r,entl eoen:
ACRS (16)
JRBuchanan On August 2,1978, representatives from utilitics ur.ing Connustion i
Engineering (CE) HSSS and froo CE net in Bethesda, fiaryland to I
discuss the action requirements in the event of Reactor P7tection Systen (RPS) channel inoperability. Enclosure 1 is the ninutes of this necting. The aceting was held to clarify our position on this subject as presented in our letter dated January 18, 1978 and to gain an understanding of your position as indicated in your response dated March 21, 1978.
This same subject had been discussed pre-vlously on March 16, 1976.
In our previous correspondence, we requested that you subnlt an appli-cation for license anendment to change the Palisados Technical Specifications (TS) Section 3.17 to require inoperable RPS channels to be placed in the " tripped" status within one hour af ter being declared inoperable. We further stated that you coula request that i
ve undertate a specific facility review of your RPS to determine the suitability of operating the RPS in a two-out-of-three logic.
Your response requested such a specific facility RPS review ana we propcse that the Palisoces RPS review be scheduled sfor this nonth.
The exact date will oc coordinated through your Operating Reactor Branch Project Manager (ORPH). Enclosure 2 'is the RPS review itens I
that will be nf interest to our review tem.
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l As you know, our staf f has conducted the RPS review at the Calvert Clif f s and St. Lucie units. A copy of the resultant Safety Evaluation j
for St. Lucie, presenting the finding of the RP$ review (pages 3 to f>),
j is provided for your infor"ation es Enclosure 3.
Our conclusion was I
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8709150124 780910 PDR ADOCK 05000255 P
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'Consuners' Power Company-
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, that~ allowing indefinite bypass of one of the tour RPS is not justified,'but since-the four channel CE system does have sone l
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 is justified.
As an alternative to the onsite liRC review of your RPS, we will consider-issuance of the Calvert Cliffs and St. Lucie. type TS of your RPS if you provide an application including documentation i
of your RPS similarity to tNse.cf Calvert Cliffs and St. Lucie. Any such application should be submitted within 30 days of the date of this letter.
Si ncerely, Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of' Operating Reactors
.Enlosures:
1.
ficeting Sunmary 2.
Review Iteo 3.
Safety Evaluation cc w/ enclosures: See next page l
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C-0RBf4: DOR ELConner:rf RSilver Glainas DZiemann.
BGrimes.
RReid
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