ML20238E697: Difference between revisions

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| number = ML20238E697
| number = ML20238E697
| issue date = 09/30/1978
| issue date = 09/30/1978
| title = 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 770803 Ltr.W/O Encls
| title = 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
| author name = Reid R
| author name = Reid R
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
Line 14: Line 14:
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 2
| page count = 2
| project = TAC:7089
| stage = Meeting
}}
}}



Latest revision as of 08:53, 19 March 2021

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
ML20238E697
Person / Time
Site: Millstone, Palisades, 05000000
Issue date: 09/30/1978
From: Reid R
Office of Nuclear Reactor Regulation
To: Counsil W
NORTHEAST NUCLEAR ENERGY CO.
Shared Package
ML20238E606 List:
References
TAC-7089, NUDOCS 8709150144
Download: ML20238E697 (2)


Text

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I i DISTRIBl! TION: , , .

Docket File . .Glainas ..

NRC PDR , .DTondi i L PDR , _JBurdoin , ,

Docket No.: S0-336 ._ ORBf4 Rdg , , , , ,

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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

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, 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 i '1111 stone, Unit 2 RPS review be schedulelfor the month of October 1978.

The exact date trill be coordinated through your Operating Reactor Branch Project !!anager (ORPM). Enclosure 2 is the RPS review items that will l l

be of interest to our review teca.

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

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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 i

of one RPS channel is justified. .

I s 1 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

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, i ORB #4:00R C-PSB: DOR AD-E&P; DOR. _C-0RBf4:00R. . .. .

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