ML19319D938

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Discusses post-CP Review Areas Considered at 690211 Meeting W/Util in Bethesda,Md.Areas Discussed Include Qa,Reactor Vessel Neutron Fluence Considerations,Fire Protection Sys & R&D Program Results
ML19319D938
Person / Time
Site: Rancho Seco
Issue date: 06/17/1969
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Davis E
SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML19319D939 List:
References
NUDOCS 8003270614
Download: ML19319D938 (3)
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3 AEC PER LA PER SAN PLR JUN 171969 ERL Reading RPB-5 Reading P. A. Morris g

FSchroeder Docket No. 50-312 4 Assistant Directors, ERI CPPR-56 Br. Chiefs, DEL W. Butler s - w N. M. Newmark' (2)

S. G. Forbec (2)

Sacramento Municipal Utilities ACES (3)

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District

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Secremento, California 95813 1.

Attention:

Mr. E. K. Davis A

General Counsel Centlemen:

As you knew, we met with / cur representt i m at reth adr..

Iebruary 11, 1969, to discuss the contents of Supplement No.1 to de Rancho Seco Preliminary Safety Analysis Report and other Pcst-Construction Permit review areas. Our lett'er of February 27, 1969,. summaarized the j, Q

bases.cn which we find _the, design changes. described in Supplement to be seceptable. We wish to address, in' this letter, the other Post _

'V Construction Permit review areas discussed at the February,11, 1969 7%

meeting.

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Quality Assurance J-

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'N LSince issuance'of~the construction pe21 nit for'the Rancho Seco

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(CPPR-56), the Commission has developed " Quality Assurance

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E OCriteria for Nuclear Power Plants," o copy of which is enclosed.

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.We discussed. draft versions of these criteria with your representa-'

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~ 'divse'Imst' Jebruary and-snderstood that you]vould develop furthes g;g the:Bancho Seco QA Program with.these criteria as guidelines.- An ~

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' ' ' effective QA program'is' essential for allauclear power plants.

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-:We would like to meet with you to discuss this matter some two to three weeks after you have provided us with.a written description i~

1 of your current '.QA program.

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<. 2.- Beactor Vessel Neutron Fluence Considerations 5""~

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eertainties exist in;the analytical predie,tiona.. We,itherefore.%t}ly: 7 QMg 2V-t

.A Turge that careful attention be Lgiven to,the nuclear design:of the l & >"Ti $ d i & %: w $ -Y O C O.and the' associated ' evaluation program.* " ~

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Secremento Municipal Utilities JUN 171969

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uv Specific attentien should be given to the techniques that will be used and their associated uncertainties for correcting surveillance specimen data, to account for both spectral and intensity perturba tion on the field imposed by the survenlance specimens themselves and for extrapolating the data from the specimen location. to the reactor vessel wall. Submittal of information for our review on this sahject may be deferred until the ISAR is filed.

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3 Fire Protection Systems Our discussion in February included the seismic design criteria

.c for the plant's fire protection system. As a minimum, those W.f portions of the fire protection system whose failure,could damage Class I structures and components should be designed to Class I seismic standards. Please let us know how the Esucho Seco plant conforms to this requirement.

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Desults from Research & Ievelopment Programs t

We understand that several topical reports on the various research and development programs cited in the Preliminary Safety Analysis Report and related amendments will soon become available. You may y_~

wish to,incorponte these in your application.

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NP conversations with your staff, we understand that,fl construction of the' Rancho Seco plant is well under way. Wehavej-

.j:g also learned that, in the course of detailed analyses, some design 4

,,modificaticas have been made end,more are contemplated...You may._. Qg.g

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? 5eting.'...K, % % mg5:.L;:)f these design changes at our next

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DRL Reading RPB-5 Repding Docket No. 50-312 P.A. Morris CFPR-56 FSqhroeder Assistant Directors, DRL Br.,Cliie fs.,.DRL

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'N M'. Newmark (2)

S./G. Forbes (2)

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., A Attention:

Mr. E. E, Devis

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General Coun'sel

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_s, Gentlemen:

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As you know, we met with your r'epresentatives at Bethesda, Maryland on j

February 11, 1969, to' discuss thhcoatents/of Supple.aent No. I to the Rancho Seco.Freliminary Safety Ana sis Report and other Wost-Construction Fermit review areas. Our letter of bryary 27, 1969, suummarised the

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. bases on which.we find theidesign cham es described in Supplement No. I to by acceptable. We'slsh to address',

' this letter, the other Sost-Construction FermitIreview areas dis' ' s'e'& at the. February 11, 19.69 aseeting.

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Since icemance of the=eenstrue permit

'r the Rancho Seco p1' ant (WPR-56), we have.d.eveloped-

, ality Assura ce Criteria.for,Nuclea,r,_.~ _,

Fewer Plants,,, a copy 'M whia is enclosed.

.m discussed draf t--~_N

.v.e.rs.ons. _of these cri.ter.ia., wi

.your repre.s_enta-ve.s las,t_' febru..a.ry7 d<%

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and.u..nd_erstood.t. hat you.'ewou..

evelop further, t.

Ranc._he Seco.

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'as guidelines. We. lieve'sa effective Q.

JQA Program with these erite w

.;QA pr.ogram

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specimens and the associated evaluation program. Specific attention should be given ta the techniques that will be used and their l

associated uncertainties for adjun,cing the surveillance ppecimen data, e

to account for both spectral and intensity perturbation on the field imposed by the surveillance specimens themselves and for extrapolating the data from the specimen location to the reactor vessel wall. Sub-I

. mittal of infstmation for our review of this area can appropriately j

be deferred until the FSAR is filed.

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Fire Protection Systems 4

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Our discussio'n in February includ t'he seismic design criteris for

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the plant's fire protection system. As a minimum, we believe that those portions o.f the fire pgotection system whose failure could damage Class I structures and,cosiponents should be designed to Class f

I seismic standards. Please'l'et conforms to the above stated r.ehlus know how the Rancho Sece plant

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Results from Research & Develoosen (Prozrams We

  • --*and thati several to al r ports on the various research and j(

u,ced amendments will soon become avai(lable.< programaicited in We look forward to

'contentsofthesere;po(rts'woureceivingcopiesoftheserepytsatsoona they a be suitable scussion topics for our l

next Pose-Construction Permit l meeting. '

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^ In telehhone conversations wi.h your staff, we un ratand'$afc,$/$ $ t

..W hat construe-tion of the Rancho Seco plant.is well under way. W havealsojaarned i

', that, in the course of detaild analyses, some. design modifications have been made and more are contes plated. You may wish to clude ' discussion

< of these design changes at ou 7

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Enclosure:

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"Siality Assurance Criteria for $

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