ML19256B547
| ML19256B547 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/09/1979 |
| From: | Falls O NUCLEDYNE ENGINEERING CORP. |
| To: | Hendrie J NRC COMMISSION (OCM) |
| Shared Package | |
| ML19256B545 | List: |
| References | |
| RTR-NUREG-0560, RTR-NUREG-560 NUDOCS 7908060486 | |
| Download: ML19256B547 (3) | |
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ICS IP*BNGZ CSP LSG9 4-003304E127002 05/07/79 1 5177874732 MGM TOBN JACKSON MI 05-07 0210P EST
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NUCLEDYNE ENGINEERING CORP 728 WEST MICHIGAN A.VE
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JACWSON MI GQ201
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THIS MAILGRAM IS A CCNCIAHATION COPY OF TWE FOLLOWING MESSAGE
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5177874742 MGM T03N JACMSON MI 187 05-07 0210P EST
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ZIP OR JOSEPH H HENDEIE, CHAIRMAN NUCLEAR
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REGULATORY COMMISSION
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WHITE HOUSE OC 20555 THIS IS A COPY OF THE MESSAGE SENT TO JIHMY CaaTER, PRESIDENT UNITED STATES OF AMERICA
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q THREE MILE ISLAND (TMI) INCIDENT NECESSITA*ES URGENT ATTENTION TO NEW DESIGN CONCEPTS THAT IMPROVE SAFETY OF PRESENT ANO FUTURE NUCLEAR P L A N T S '.
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NaC HAS KNOWN FOR uoRE THAN TWREE YEARS OF THE UNIGUE PASSIVE CONTAINuENT SYSTEM. (PCS) FOR LIGHT WATEA REACTOR (LWR) PLANTS WHICH
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WOULO.HAVE PREVENTED CORE DAMAGE AND THE QELEASE OF RADI0 ACTIVITY UNDER
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T*I CONDITIONS: PLANT RECOVERY WOULO WAVE BEEN IMMEDIATE. PCS RESPONOS TO SAFETY RESEARCH PROJECTS / TOPICS RECOMMENDED IN NRC REPORT TO CONG9ESS, NUREG-0038.
i' NRC REFUSES CONSIDERATION OF THIS NEW CONCEPT ON GROUNOS SAFETY EVALUATION IS TO DEMANDING FOR AVAILABLE NRC STAFF. RECENT ADVERSE
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EVENTS FOCUS ATTENTION ON THE NEED FOR NEW SAFETY CONCEDTS FOR NEXT q
GENEaATION OF LWR NUCLEAR PLANTS WHICH ELIMINATE POSSIBLILITY OF ANOTLER TMI TYDE INCICENT.
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WE SOLICIT YOU4 SUPDORT OF ACTION BY NRC AND OCE TO REVIEW OCS SO INDUSTRY IS ASSUGED OF TIMELY GEGULATOPY LICENSING OF DLANTS USING PCS, i MEET!NG IS GECUESTED *ITH APPROPRIATE " EMBERS CF YOUR STAFF AND
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CouMITTEES INVESTIGATING TMI INCICENT TO FULLY VALICATE CLAluS DEGA0!NG 3CS C04 NEW ALANTS ANO RETROPP0 FIT OF 3CS EMERGENCY CORE CCOLING SYSTE" ON EYISTING PLANTS, t
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A PASSIVE CONTAINMENT SYSTEM P
r for I
LIGHT-WATER NUCLEAR REACTORS t
Application of,the PCS produces the following results:
1.
Makes possible vacuum containment of the design basis j
loss-of-coolant accident (LOCA) including core.reflood and decay heat removal with no instrumentation, controls l
and interlocks and no external sources of energy required -
electrical, n achanical or otherwise; it is a completely l
automatic, hands-off system; the engineered safety l
features are entirely passive.
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2.
Flooding of the primary reactor containment above any postulated reactor coolant system pipe break provides protection for reactor vessel failure.
I 3.
Complete protection against so called Class 9 accidents including core melt, steam explosions and containment I
overpressure.
4.
Improved innovative passive protection against external events; including such extreme actions as war or sabotage; 3
a single bunkered structure 1.uses all safety related systems and components with sufficient stored heat sink capacity within primary containment for cold shutdown.
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5.
Enables cold shutdown on loss of normal and auxiliary feedwater without fuel damage or release of radioactivity to environment; plant recovery is immediate.
6.
Prevents potential fires; (a) passive systems and components not subject to burning; (b) active reactor components operate in an inert gas atmosphere; (c) separation of re-dundant control, interlock and electric cable systems and
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components provides fire damage protection in depth; (d) individual enclosures for reactor auxiliary systems can be blanketed with inert gas, water sprays or deluge systems.
7.
Major imn"svements in seismic response; particularly applica.'
n areas potentially suo3ect to high earthquake forces; only one Seismic Category I structure is required.
NucleDyne Engineering Corporation 1979 (over:
8.' Substantial volume reduction in Seismic Category I structural requirements lends itself to imbedding of the reactor building with or without a bern, or complete undergrounding.
9.
Responds to safety research projects and topics recom-mended to Congress in NRC Report, NUREG-0438, dated 4/12/78.
10.
Resolves all unresolved generic items having to do with contaihment and emergency core cooling systems (ECCS) for LWR's as identified by the Advisory Committee on Reactor Safeguards (ACRS) in Report No.
5, dated February 24, 1977.
i 11.
A substantial reduction in plant construction time; l
major equipment itens are not on the critical path.
12.
Plant construction cost studies show savinos of 10 to 15% in total plant other than the turbine-generator building.
13.
Provides substantially improved inservice maintenance and inspection for improved plant availability.
With passive systems the need is eliminated for periodically checking out instrumentation, controls, interlocks, rotating or mechanical equipment, electric or mechanical power, or operator action for -he LCCA.
In that passive systems are essentially static for the life of the plant, the maintenance is minimal.
14.
Containment permits retrofit of reactor coolant system with new and improved components making plant decom-missioning unnecessary.
15.
Double containment of all potential energy and radio-activity releases makes possible the siting of plants near load centers to make possible the use of thermal energy for residential and industrial heating (cogeneration).
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NucleDyne Engineering Corporation 1979
PASSIVE CONTAINMENT SYSTE*1 A NEW CONCEPT TO SOLVE SAFETY CONCERNS
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AMERICAN POWER CONFERENCE Chicago, Illinois April 24, 1979 Authors:
O.
B. Falls, Jr.
F. W.
'leimola
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