ML19224C909
| ML19224C909 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane  |
| Issue date: | 05/08/1979 |
| From: | Bates A Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-0108, ACRS-108, NUDOCS 7907100200 | |
| Download: ML19224C909 (1) | |
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ADVISORY COM*dlTTEE ON RE ACTOR SAFEGU ARDS g ? ?.[ f WASHINGTON, D. C. 20555 o
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May 8, 1979 ACRS Members
SUBJECT:
OCONEE RESPCNSE TO TMI-2 ACCIDENT Attached are copies of letters from Duke Power Ccmpany indicating the changes they plan to institute on Oconee Units 1, 2 and 3 in response to the TMI-2 accident and the NRC ILE bulletins.
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Bates Reactor Engineer Attachments:
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OCCNEE NUCLEAR STATICM 00CKET "CS. 50-259, 50-270 and 50-237
Dear Mr. Denton,
Supplementing my letter of April 25, 1979 and provi ing additional in-formation responsive to Staff safety concorr.s ident;fied as itsas a.
through e. on page 1-7 of the CNRR Status I.spo.-t to the Comission of April 25,1979, Duke Power Ccmpany proposts follow w.g actions:
Install autcmatic starting of the inter cnnact:.; ecargency a.
feed. tater system so that all three pumps ti;:1 cc:eive a start signal frcm any affected unit, aad tast we systcm for stability.
b.
Develop and implement operatirg procedures for initiating and centrolling emergency feedwater indepandent of ICS control, Implement a hard-wired control-grade r: actor trip on loss c.
of main feedsater and/or turbine trip.
d.
Complete analyses for potential small breaks and o':velco and implement operating instructions to define operator cction.
Statica in the control room an additienal full-time SRO (or e.
previcusi-y licensed SRO with TMI trcining) for each cperating unit to assist with guidance and possible manual action in case of transients until itcms a. thecugh d. arc cc.mpleted.
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- r for each Cconee Unit has a arbine driven emergency feedwatar -umo e
which sunclies 1501 of the rec.uired watcr to the stea generators L.
on loss of main feefuator.
The diccharges of thece pumpc haie been tied together : y al: gr.m:nt of.anual valves such that each and all of the cuar.s can sur.alv enercencv. feedwater to an-1 Cconee r nq.. <., _
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Ocoratinc. cerec-.el have been stationed at each L
e=cr~ency feedwater pung uit-a direct communication link to that s
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Administrati/c controls have been established so that in the event of lecs of both main feed.:2ter pumps on an affected unit, that unit's emercence feedwater
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D un c Pow e n Co>mun-Powem Di;nono 422 Sorrn Cat;uen S rnn.r. Ciuutciric. N. C. :n:x:
April 25, 1979 Mr. Harold R.
Denton
- Director, Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Cormission Washington, D.C.
20555
Dear Mr. Denton:
Since my presentation to the Ccrmission this afternoon, additional corrit.ents have been made by Duke Pcwer Cc=canv.
These ccr=itments have been furnished to your Staff and are presentiv being reviewed bv then.
I am confident that, uren ccmpletion of Staff review it will be determined that such cormit-ments provide you with the necessary assurance to find that the continued operation of Oconee does not endangcr the public health and safety.
I am sending copies of these cornitrents to you to assist you in your deliberation.
We feel these two cc=mit ents are fully responsive in this tin
- e to itens "a" and "c" of your Staff concerns listed en page 1-7 of the NRR Status Report to the Ccrmission this afternoon.
With recpect to iten "b" the utility industry has had 2 ears of successful experience with the ICS, first with many boilers and recently with reactors which leads us to conclude that it is the. cst ac.erce.riate systen for this acc.lication.
We feel that f rther dialogue with your Staff about this control system will result in familiarizatien, additicnal understanding and a higher level of confidence in its responsiveness and value, and we will later previde the failure a-;e s Just requested.
Re-d garding item "d", shut-down core circulation is.crovided b.v the HPI injection, backed-up by any one of the four reacter coolant pumps, and only there.s f ter followed by natural circulatica for which later analyses have been cermitted.
- ith respect to item "e",
we feel that the testimony of the I&r -
esentatives todcy ac-curatel.v.cortraved current control rcem conditions with alert, trained operatcrs that can continue safe operation of these units.
With these cermit.ents and corrents, we feel we have been prcmptly respcnsive to the enpressed concerns of your Staff and further cercit to working closely together to assure con-tinued. safe operation.
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DUKE Pomnt COMP m PowEn BUILDeiG. CHARLOTTE. N. C. 2 e 24 2 (704) 373 4120 W.
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April 25,1979 Dr Roger J Mattson, Director Divisien of Systems Division U S Nuclear Regulatory Ccenission Washington, DC 20555
Dear Dr Mattson:
As a result of the recent Three Mile Island-2 incident, Duke Pcwer Ccepany is reviewing the design and cceration of its Ocenee Nuclear Station. The review has been dcne both internally and in conjunction with Babccck & Wilccx and the Nuclear Regulatory Cem.missicn.
A,cng othe r things, this review includes the goal of improving the reliability of the normal feedwater system and added assurance of emargency feedwater supply to the s: cam generators. We feel our existing design is adequate and cccpetent; however, we have several high priority activities underway and multiple alternatives are available to achieve added margins.
A full-time, dedicated technical team was organized en April 9,1979, to evaluate the Three Mile island incident and to review all Duke nuclear stations.
This team is composed of Duke persennel with experience in design, operation, and radiological control, along with a representative f rom the vendor that supplied the Nuclear Steam Supply System. Among the items being reviewed are the design, equipment, controls, and precedures associated wi th the main condensate-feedwater and emergency feedwater systems and the resultant system reliability. This review will identify strengths and courses of action to correct any weaknesses. Primary emchasis is being placed on Oconee Nuclear Station.
One concern of NRC has been the reliance of EFV upon the Integrated Centrol System. A careful review of the systems shews that a train of EFU exists which is independent of the ICS and block valves.
An imediate improvement in both normal feedwater reliability and assurance of eme rgen cy feedwa te r i s avai l ab le.
Minor changes in existing equipment and procedures can be made to decrease the time for ocwcr to reach the main feed-water pump trains f rom the source of 2mergency pcuer, Kecwee Hyd ro S ta t i on.
This will result in an improvement in fee d'..a t e r re l i ab i ' i ty.
Also, each unit has i ts own eme rgency feedwater sys tem u ta pump.
Improvement in the starting re!ia I DUPLICATE DOCUMENT
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20555 Re:
Oconee Nuclear Station Docket Nos. 50-269, 50-270, and 50-287
Dear :
- r. Denten:
In respense to the letter of April 21, 1979 frem James P. O'Reilly, Director, NRC Region II Atlanta, concerning I.E. En11etin No.79-053 the follcwing information is provided.
Duke Power Cc=pany agrees that autcmacic anticipatory reactor tr:.p on Icss of main feed'.tacer and turbine trip is appropriate for the Oconae Nuclear Station reactors.
The trips will be
.mpic.c.an ted as ccen. as practicable.
Previcus reactor trips at Oconae Nuclear Scation, indicate that a direct reactor trip on less of main fecdwatar will provide earlier reactor shutdcwn than for the case when the reactor trips following high reactor coolant syste pressure ac a result of the transient.
Based on our in-vestigation of Incident Report No. B-8 05 Oconee Unit Or.e (copy of this incifen: report was provided to 21. Fairtile of the NIC Staff en April 24, 1979) it is concluded that the reactor trip would occur scme 50 seconds earlier when initiated by loss of main feedwater than if initiated by hi h reactor coolant system.crossure.
9 Design infcrmation and a schedule for implementation of our cc=itted anticipatory reactor trip will be previded to the NRC Scaff by ".ay 21, 1979 as requested in Bul20 tin 79-05B.
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eL h. h Willian O.
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cc:
James P.
O'Reilly, Director i
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Nuclear Regulatorv Cc= mission 10 hO 101 Marietta Street, N.W.
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