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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DISTRIBl! TION:
Docket File
..Glainas NRC PDR
.DTondi i
L PDR
_JBurdoin Docket No.:
S0-336 ORBf4 Rdg l'
RReid i
RIngram MHHMX ELConner
[_
i tiertheast nuclear Energy Conpany Attorney, OELD,
ATTH: itr. W. n. Counsil, Vice President 01&E(3) fluclear Engineering 6 Operations DEisenhut P. D. idox 270 ACRS (16) l Hartford, Connecticut 06101 TERA, DSB JRBuchanan Gentlemen:
TJCarter
[
[..
Gray File Un August 2,1978, representatives from utilities using Combustion l
Engineering (CE) NSSS and frcx, CE met in Bethesda, liaryland to j
discuss the action requirements in the event of Reactor Protection i
System (RPS) channel inoperability. Enclosure 1 is the minutes of i
this necting. The raceting was held to clarify our position on this l
[
~ subject as presented in our letter dated August 3,1977 and to l
i gain an understanding of your position as inctated in your response i
dated Septeober 21, 1977 This sane subject hij been discussed pre-I viously on Maren 16, 1976.
l In our previous correspondence, we requested that you submit an appli-I cation for license amendment to change the liillstone, Unit No. 2 Technical l
Specifications (TS) Section 3.3.1.1 to require inoperable RPS channels to i
be placed in the " tripped" status within one hour after being declared I
j inoperable. We further stated thct you could request that we under-l take a specific facility review of your RPS to cetermine the suitabil-l ity of operating the RPS in a two-out-of-three logic. Your response l
requested such a specific facility RPS review and we propose that the
'1111 stone, Unit 2 RPS review be schedulelfor the month of October 1978.
i The exact date trill be coordinated through your Operating Reactor Branch Project !!anager (ORPM). Enclosure 2 is the RPS review items that will l
be of interest to our review teca.
l As you know, our staff has conducted the RPS review at the Calvert Cliffs and St. Lucit: unitr. A copy of the resultant Safety Evaluation I
for St, Lucie, presertting the finding of the RPS review (pages 3 to S),
l is proviccd for your information as Enclosure 3.
Our conclusion was l
l 8709150144 780910 PDR ADOCK 05000255 P
PDR
,y j~
,y 1
l
l
',L--
l
(
l tiortheast Nuclear Energy Co. -
i that. allowing indefinite bypass of one of the four.RPS is not justified, but since the four Ihannel CE system does have some l
indereadence, 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.
i I
1 s
l As an alternative to-the onsite NRC review of your PPS, we will
)
l
. consider issuance of the Calvert Cliffs and St. Lucie type TS of your RPS if yott provide an application including' documentation -
)
of your PPS similarity to those of Calvert Cliffs and St. Lucie.. Any such application should be submitted within 45 days of the date of l
. thi s l etter.
Si ncerely, l
' Robert W. Reid, Chief Operating Reactors Branch $4 Division of Operating Reactors Enlosures:
l 1..
Heeting Summary 2.
P.eview Itera 3.
Safety Evaluation cc w/ enclosures: See next page
")
, i ORB #4:00R C-PSB: DOR AD-E&P; DOR. _C-0RBf4:00R.
NConner:rf Glainas
-59 rimes
.RReid K
9/ /78 9/ /78 9/ /78 9/ /78
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