ML20062N473
| ML20062N473 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000495 |
| Issue date: | 02/11/1976 |
| From: | Moeller D Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC COMMISSION (OCM) |
| Shared Package | |
| ML093450149 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8203010146 | |
| Download: ML20062N473 (5) | |
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ADVISORY COMMITTEE ON REACTOR SAFEGUARCS NUC1. EAR REGUI.ATORY CCMMISSION WASHINGTCN, D. C. 20555 February 11, 1976 Honorable William A. Arders mair nan U.S. Nuclear Regulatorf FMeica Washington, DC 20555
Subject:
REFOR'r CN SiESSAR-P1,. STCNE AND WEBSTER DXIDMKI CCRPCRATICN BAIANCE-GF-PIANT DESIGi
Dear Mr. Anders:
At'its 190th' meeting on Februarf 5-7, 1976, the Adviscrf Cemit*Je on Paactor Safeguards reviewed the application of the Stone and Webster e.gineering Corporation for a Preliminarf Design A gwval of its SWESSAR-P1, a stand -
ardized nuclear h=1=ne*-of-plant (BCP) design. S'ECSAR-P1 had previcusly
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. been reviewed at S1Wittee meetings held in Chicago, Illinois, on August 1, 1975, ard in W=*ington, DC, en January 22, 1976. Curing its review, the Cognittee had the benefit of discussions' with representatives of the Stone and Webster Engineering Corporation and the Nuclear Pagularcrj r~=4== ion
-(NBC) Staff. -te Comittee also had the benefit of the documents listed.
2e SNESSAR-P1 BCP design wculd interface with single unit pressurized-water-ceacter nuclear i=landa of standardized design such as RESAR-41 and CESSAR-80. Bis review is limited to RESAR-41. te interface requirements with other standardized nuclear island designs have not yet been established.
Se SWESSAR-P1 conemf=nt is a conventional reinforced-concrete-steel-lined building with a flat base, a cylindrical shell, and a hemis;cerical dcme.
It is surrounded by an annulus Nildig extending about one-half the height i
- of the containment building. Se containment and the annulus buildings are..
supported on a ccm m n base mat, te annulus building centains Portiens of the engineered safety features and scme auxiliaries. Se turbine generator is housed in a separate turbine buildi.m with its axis criented radially J
with respect to the con *=i - nt structure. Separate buildings are provided to house the diesel generators, the centrol facilities, and the radioactive waste disposal equiprant.
9 8203010146 010804 PDR FOIA MADDEN 80-555 PDR
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l Bor:orable Willia:n A. Anders February 11, 1976 A set of design para:neters has been established for SWESSAR-P1 '.hich
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enable it-to-be applied to a rance or sites without site-specific.desigrt
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. treat:nent.of marrf features. Se. Aa=%was. reviewed..for. a pcwer level.
..cic.
of 3800 MWt and wocid accept samm--loadings equivaient to- 0.-30;:r r"-
horizon"ar ground accelerationrfoe the-safe.shutdownie rthcuake (SSE)-
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.and 0.15g.horizental ground acceleratiert for'the operating basis earth- :
quake (CBE). SWESSAR-P1 would be imahla under meteorologic~ conditions prevailing -in 221r of the.more th n:40: sites rerMei.in. this. context by 2
2.
the NBC Staff. An optional entensiorr of the annulus building to enclose s*
the entire contaircent struct=e would permit SWESSAR-P1 to a
-iate metecrological conditions at most sites thus far 1icensed. Cther site e.'.
conditions such as tornado design requirements, :::issile resistance, ficnd design limits, and pcstulated pipe rupture effects inside and outside
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contriment are ccrr: parable to those now beiry required in licensed nuclear
. - -" - power plants. Se remainmg related. design featurer such as offsite' gwer, --".-- -
ultimate heat sink, and cordamar cooling water supply and return, would
- "" be' individually selected to suit the site on whicdt SWESSAR-P1 is used.
-<=-. Se: arrangement of SasSAR-P1 provides extensive physical separation of.. :.:
. critical safety-related equignent to protect against emmon mode failures
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===v inted with fires or other operational contingencies. However, ccm-
~plete design details for SWESSAR-P1 havernot been developed and the concept--- --
has not yet been applied to a cer::clete, nuclear power plant design.
Omar:uently',"further review of-the physical setm ation auw at should -
c.--
be mada prior to the Final Design Approval or.wnen SWESSAR-P1 is proposei., _.
for a: nuclear power plant for which a construction permi.t is being sought. -
i em Se Connittee wishes to be kept informed.
A matter of major concern in the NRC Staff's review has been the safety-relhted interfaces beraeen the SWESSAR-P1 ECP design and the RESAR-41
-- NSSS designron one hand, and the G.cdesigr:ed szte-related-str=t=es- - ~ --
and cm ponents, en the other hand. Se responsibilities and requirements related to the SWESSAR-RESAR interfacp* have been definet:1. in detail in the Safety Analysis Feperts for these two standardized designs. Se Ccanittee believes that these interface requirements are san *ctory for a Preliminar7..
. Design Approval, but expects the NBC Staff and the Applicant to centinue tar examine then further in connection with the pecoesal to use these designs --
' for an actual plant when it is reviewed for a construction pecnit. Se interfaces between SWESSAR-P1 and the site-related features are defined in the SWESSAR-P1 Safety Analysis-depcrt, but have not yet been sub3ected to the test of a emplete design for a nuclear pwer plant. S e NBC Staff should review these interfaces in greater depth when a construction permit application is received.
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p Scnorable Willi m A. Anders February 11, 1976 l
Be ('ennittee recommends that, during the design, procurement, constrac-tlan, and-startup,- timely and appropriate interdisciplinarf syste= analyses be perfocined to, assure emplete fundi==l corpatibility across each interfaceEfor~h entire spectrum of annr-trated ocerations and pcstulated.
design basis accident ccnditions.
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2e cooMihation of interdepende..t instr. nentation and controls in the nuclear-island and in the balance of plant will require attenticn at the time when
=. - - l SNESSAR-P1 is used as a portion of a nuclear pcwer plant license applicaticn.
2ese matters shculd be included in the SIC Staft!s standard review plans..:_ _ l 2e proposed orientation of the turbine-generator with respect to the nuclear island is suitable for a single unit installation. Ebr mitiple
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unit power plants, the. location and orientation of the units should be
-f such as to yield ac.eyL=bly Icw pecbabilities of damage by low-trajectorf turbinesenerator missiles,.or suitable missile shielding should be pro-
- vided, Although SNESSAR-P1 includes provisions for protection against industrial f'.
sabotage, the C mnittee believes that further steps can be taken beycnd those in SWESSAR-Pl. and in the custm. plant designs about which the AGS has ~
preNicusly expressed concern. Pfior to the use of SWESSAR-P1 as a portion
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of an ap' licatien for a nuclear Jewer plant license, the Utility-Applicant -
p should be required to deonstrate that acceptable. industrial sabotage
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provisions will be incorporated into the plant design.
y.
2e SWESSAR-P1 design should include provisions which anticipate the maintenance, inspection, and operaticnal needs of the plant throughcut its service life, including cleaning. and decontamination of the pri= arf
-l coo 1Mit system, 'and eventual decot:nissioning. In particular, the'Carmittee believes that the NIC Staff and the Applicant should review methods and procedures for removing a-lations of radioactive contamination whereby maintenance and inspection programs can be more effectively and safely carried out.
j Generic problems related to large water reactors are dim-'"=d in the Ccanittee's report dated March 12, 1975. Rose problems relevant to SWESSAR-P1 should be dealt with appecpriately by the NIC Staff and the Applicant as solutions are fcund.
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r Honorable William A. Anders February'11, 1976 h
Ihe Advisory Cemittee en Peactor Safeguards believes that the itema
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mentioned above can be resolved during the stardardized plant licensing
, process and that, if due consideration is given to the foregoing Pre-liminarf Design Appcoval for 5;ESSAR-P1 to be used In cenjunction Jith -
REEAR-41 can be granted in accord -with 'the ' spic'it and purposes set forth
- 2 in the halon's policy statement on standardization of nuclear pcwer"-
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plants as described in WASE-1341, "Programratic Information for the rhim? cf Standardized Nuclear Power Plants" and in conformance with
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the Regulations of Apoendix 0 to Part. 50 and Section 2.110 of Part 2
.of Title 10 of the Code of rederal Regulations.
Sincerely yours, ha,A t.
onde w. a m n er m i-,s j
M erences l.
Pressurized Water Paacter Paference Nuclear Power Plant Safety Analysis
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Report (SWESSAR) and Amerwhants 1 through 20.
2.
Stone and Webster Egineering, Corporation letters-April 8,1975 - Contain=ent arid 94WWEnent Analysis a.
b.
April 18,1975 - 9_Wd::nent Analysis c.
April 29,1975 - Runes d.
April 30, 1975 - Steam Pipe Break Analysis e.
June 4,1975 - I=plementation of WASE-1341 f.
June 5,1975 - Supplementary Imak Conection and Palease System g.
Septe=ber 5,1975 - Peactor Cavity Noduli:ation Study h.
September 5,1975 - Schedules
- 1.
September 11, 1975. Electrical System
- j. September 29, 1975 - Baron Recoverf System k.
October 2,1975 - Interface Data 1.
November 13,1975 - Supplementary Iaak Collection and Release System m.
Neverder 21, 1975 - Resolution of Outstanding Items.
n November 26, 1975'- Slectrical, Inst =:entatien and Centrol Systats t
c.
December 9,1975 - Soil-Structure interaction 4
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Honorable Willai:n A. Anders
~5-February 11, 1976 neference - Continued r.
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Report to the khrisory Ccanittee on Paactgr. Safeguards in the Matter of Stme tr tiebster D:gineering Corporation, SumuM. Safety Analysis Paport,c.:. l PWR Beference Nuclear Power Plant S*4ESSAR-P1 (and its relaefemhip to
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- l the RESAR-41 Standard NSSS Design) Docket !b. Sni 50-495, Published:
Q:tobec 1975, U. S.1.tclear Pegulatory c=ie= ion, Office of.14: clear."
Reactor Regulation.
4.
Supplement Ib.1 to the Paport to the Advizzy C=mittee en Peactor ~
Safeguards in the Matter of Stene & Webster Engineeri.g Corporation Standard Safety Analysis Paport IHR Reference Nuclear P::wer Plant SNESSAR-P1 (and its relatienship to the RESAR-41 Standard !GSS Design)
Docket 2b. Sri 50-495, January 1976, U. S..th: clear Regulatory F=i== ion,.....
Office of Nuclear Reactor Pagulation.
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