ML19224C169
| ML19224C169 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/23/1975 |
| From: | Suhrke K BABCOCK & WILCOX CO. |
| To: | Schencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111230347 | List: |
| References | |
| NUDOCS 7906290248 | |
| Download: ML19224C169 (2) | |
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3m Babcock & Wilcox re-er ceaer w o,c,=mo P.O. Sex 1260. Lynenburg. Va. 24505 Tete;. hone: (504) 334-5111 May 23, 1975
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Lvision of Reactor Licensing ffice of Muclear Reactor Keruiation
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ear Mr. Schwencer:
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This letter is in respr.se to your letter of April 4 in which you
', ' 'e-v equested additional infor=ation on several generic topics.
Your letter
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dentified seven categories in which information was rec;uired for all urrent 3&i' plants and suggested thr: this infor.ation be provided in he fora of 35~.' topical reports.
We have reviewed the infor:ation reques:ed and while ELi? endorses he generic approach, we feel that auch of the information recuested is at generic, but depends cm sys:ces and equip =er.: provided by others.
ropose-to respond to these questions as follows:
=cordingly, we c
Itc= one was a recuest f or additional infor=ation doeurenting that he Integrated Control Sys:e= (ICS) is not safety related and providing ore detail on ICS functions, analytical assunptions and interfaces with ystems.relatei to safety.
35t* will provide an e::pansion of the intro-uction to Chapter 15 detailing what is cnd is no: taken credit for in he analyscs presented in this chapter.
It will state that we take the osition that a ni:. one failure at a tine occurs and that the consequences re less than those of one of several accidents.
'/e will submit this aterial to the :'RC in letter forn generically by the end of 1975 and sub-equently include it in the individual S/J.s.
Item two recuested a detailed listi,ng of syste=s and equipment taken redit for in the analyses in Chapter 15.
Response to this question is argely application specific as the details of the equipnent required to espond in cany accidents is provided by others (i.e. auxiliary feelwater urps, R3 sprays, building coolers, energency power supplies, etc.).
617 can and will provide a description of the functions or systees for hich credit is taken in saf ety analyses, ecuipcent details such as the articular pu=ps or valves involved will be addressed on individual plants.
response addressing B&H supplie quipo.ent and interface criteria vill c ros'ded in letter for by the end of this year.
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Ites three addressed f ailures in the main stea= and feedwater isolation yste= and non-class IE equip =ent for which credit is taken. While =uch of his equip =ent is beyond B&W scope, we intend to describe equip =ent within
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4W scope and to provide a description of the failure =ede and effects analysis o be perfor=ed on the ESFAS. This cuestion also requested a sketch of the eedwater/stea: systen with identification of actuated components.
These yste=s vary substantially fro = one plant to another; therefore specific infor-ationlsuch as this should be recuested on individual applications.
Response
o the portions of this request involvi=g B&U equir ent or systens and inter-ace crtieria vill be provided
'_n let:c: for= by July 31.
I i,Item four requested infor 2:ica on the single red withdrawal accident and aricus related cuestions.
A topicci repcrt on this subj ect has been co==itted
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j n several PSI.Es for preparation at the FSAR stage.
The outline of this report ill be cerpleted in the near future and the schedule vill be trans=itted to ou as soon as pessible. 1 L
llIte= five requested design provisions for disconnectica of RC pu=ps frc=
ha electrical grid and additional it.for=ation on accident analysis require =ents
- nd limitin; frequency decay rate.
Sp ecif ic infor=ation describing exactly her
.he RC pumps are separated frc= the gric and tr.e ecuiptent required to achieve
- his should be sought on applications.
B&U will provide RC pu=p frequency
. rip cditeria and a description of the B&U/ Architect En:ineer interface in this ra t t a r.' This will be provided in a letter by the end of 1975.
fIten six recuested a justification of the pressuricer level as a backup tignal!to trip the reactor ins:c2d of the high E3 pressure backup signal used to initiaie the ECCf.
Justification of the effectiveness of the pressuricer level
- rip sicnal vill be provided in letter for= to the Staf f by August 31, 1975.
This
- esponse vill also address provisions =ade to ensure instrumentation accuracy luring { blowd own.
Ite= seven requested a list of all safety related setpoints e d in reactor aperation, technical specification limits, safety li=its and the =argin provided.
L generic tcpical report addressing the cethodology employed for calculating these talues has previcusly been cc =it:cd for 3brch 197 6.
!bny of the ite=s identified to specific nunerical in this question vary frc= plant to plant when it ce=es values and we bel ieve that requests for specific values be =ade on individual appli-a tio n s.
Should you desire further detail information as to our intended responses and cchedules, we would be happy to.=eet with you and discuss these items further.
Very truly yours, PAECOCK & UILCOX COMPANY I
Nuclear Power Generation Ve /
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pp y n Kenneth E. Suhrke e
Manager, Licensing 257 0%
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