ML19319A801
| ML19319A801 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/13/1967 |
| From: | Harris J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Johnson, Nabrit, Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7912130749 | |
| Download: ML19319A801 (2) | |
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ADVISORY COMGTTEE ON REACTOR SAFEGU/ ADS REPO2fS TO AEC ON PROPOSED EUCISAR FI.AITfS IN SOUTH CAP.0 LINA The Atomic Energy Co=nission has received a report from its Advisory Co ittee on Reactor Safeguards concerning the Oconce Nuclear Power Station proposed by Duke Pover Co=pany near Seneca, South Carolina.
Duke ~ Power Co=pany has applied to the Co=:ission for per=its to build three nuclear power plants on the shore of future Icke Keovec in Oconee County, South Carolina, about cicht n W s northeast of Seneca. Each unit vould have a pressurised water reactor capable of an initial output of about 839,000 electrical kilovatts and an ultimate capacity of 674,000 kilowatts. All three units vou31 be designed and constructed by Dake Power Co=peny personnel. Babcock and Wilcox Corpeny would provide the nuclear steam supply syste s.
The AEC Regulatory Staff is continuing its review of the application.
A copy of the report of the Advisory Co==ittee on Reactor Safeguards is attached.
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i ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20545 JUL 1 1 1967 '
1 Honorabia Glenn T. Scaborg Chairman U. S. Atomic Energy Co=21ssion Wachington, D. C.
Subject:
REPO::T 03 OCONEE NUCLEAR STATIO:1, Ini1TS 1, 2, AliD 3 l
Daar Dr. Scaborg:
At its eighty-sixth mooting, on June 8-10, 1967, and its cinhty-ceventh meeting, on July 6-8, 1967, tha Advisory Co::::sittee on Reactor Safeguards reviewed the proposal of the Duka Powcr Co=pany to construct the Ocones Nuclear Station, Units 1, 2 and 3, at a sita near C1cason, South Carolina.
This project was rovicved by an ACRS subco=aitece on May 2,1967, at the site and at C1cason, and on May.31 and June 23, 1967, in Washington, D. C.
We Co::mittee had the benefit of discussions with representatives of the Duke Power Company and its consultants, The Babcock and Ullcox Cct::pany, Bechtel Corporation, and the AEC Regulatory Staff, and of tha docu:sents listed.
l Each unit of the Oconce Station includes a pressurized-water reactor rated
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4 at 2452 1 Hit. Each unit is to be provided with cn escrgency cora cooling system (ECCS), including two core flooding tcnks, threa high-pressure in-
-jcetion p' ps, and three low-pressura injection and rceirculation pu=ps.
i The applicant proposes not to operate a unit with a core flooding tank valved off. The Co=sittee recorcnds that tho acculatory Staff review the detailed design of the ECCS and the analysis of its perfor.~ance for the entiro spoetrum of break sizes, as soon as this infor=ation is avail--
able..In this respect:
l 1.
The Regulatory Staff should review analyses of possibio
. effects, upon pressura-vessel integrity arising from thermal shock induced by ECCS operation.*
2.
The effcets of blowdown forces on core and other primary system components should be analyzed more fully as do-tailed design proceeds.*
3.
Further evidence should be obtained to show that fual-rod failure in loss-of-coolcat accidents will not affect significantly the ability of the ECCS to provant clad colting.*
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11onorable Glenn T. Seaborg 5 JUL 1 1 1967 4.
The applicant has proposed adding swing the cora barrel to ensure obtaining -check valves in ECCS operation. cooling water in the cora under all circumstade to oncure that no new problems are i tThis featura should ances of n roduced.
5 The applicant will explora further possibili i improvement, particularly by diversificatio t es for instrumentation that initiates ECCS action n, of the Emergency power sources for the ECCS and other Oconee units (each unit can withstandother safeguards ares t
stand instantencous loss of load without a rand till be teste (a) the trip); (b) two hydroelectric units away wit eactor trip or a turbine (c) a, gash independent overhead and underEround t line, transformer, and switchyard -- all iturbina unit thirty m and n ependent transmission pie ties to the power transmission grid n addition to the usual multi-switching and sequencing of sources The applicant stated that no single failura vould impair system availability, buses, and lo s
The applicant stated that the entire prima ing the inside and outsida of the reactor ry system of each unit, inclu inspection over the life of the plaat vessel, will be accessible for The Co:xaittee continues to emphasise the i life, and reco:caends that the pplicant 1:::plin fab o
as inspection during service
-f pricary system quality that cra practical with cement those improveme the beginning of core life, for tho' firstThe moderator urrent technology.*
a culated to be positiva at detailed studios of tho effect of this core.
The applicant is making by the addition of solid poison shims to thelated ac coefficient on the course of postu-will be made more negative
, core.
Further evidence should be obtained concerni withstend expected transients at the end of its a ti ing the chility o n
The applicant is-investigating further the st bil c pated lifetime.*
oscillations.
ity margin fr..
a
':enon The containment structures are similar to tho cetors previously reviewed.
Consideration should be given to i=prov dse inspection of welds in the-steel liner of su h cceident conditions. cec:.ptance pressurization test does not stress thcont c
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, e liner to postulated v-P<
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JUL 1 1 1967 Honorable Glenn T. Seaborg.
Power for the reactor protection syste:ns and the cafeguards protection systems for all three units is provided by a syste:s cf six batteries, static inverters, and six buses. The scma batteries, via other inver-ters and buses, provide power to the control.syste:ns for all thrco units.
The Com: itten urges the applicent to review the design of thosa systems
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with respect to independance of cach unit from troubles in the others.
l The applicant propoccc to construct a submerged earthon weir in the in-taka canal to accuro a heat sink in the event Koouce Roscrvoir is drawn down encessively. The Com:sittee believes that careful attention is neces-scry in the design and construction of this voir to avoid hydraulic crosion and soil instability, particularly in casa of rapid draudown.
l The Advisory Co=nittee on Reactor Safeguards believes that the items men-tioned abovo can be resolved by th.o applicent end the Ecculatory Staff attring construction of the reactors. On the basis of the foregoing com-ments, the Cocaittec believes that the proposed Oconco nuclocr Station can be constructed uith reactsnable assurance that it can bo operated without undue risk to the health and safety of the public.
Sinecroly yours, ORIGINAL SICID 3'l N. J. PALLADIEC N. J. Palladino -
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Chairman
- The Cc=mittee believec that those catters are significant for all large water-cooled power reactors, and ucrrant careful attention.
Referonecc:
1.
Duke Power Company, Oconee Nuclocr Statica, Units 1 and 2, Preliminary Safety Analysis ncport, Volumes I and II, undated, roccived Deccaber 5, 1966.
2.
Amendment no.1, dated April 1,1967.
3.
A=andment No. 2, dated April 18, 1967.
4.
Amendment No. 3, dated April 29, 1967.
5.
A=endment No. 4 dated May 25, 1967.
6.
Amendment No.-5, dated Juna 16, 1967.
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