ML19257B600
| ML19257B600 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, Crane  |
| Issue date: | 08/14/1973 |
| From: | Mangelsdorf H Advisory Committee on Reactor Safeguards |
| To: | Ray D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19257B579 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001170703 | |
| Download: ML19257B600 (4) | |
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ADVISORY COMMITTEE ON REACTOR SAi EGUARDS UNITED STATES ATOMIC ENERGY COMMIGSION WAStilNGTON, D.C.
20545 August 14, 1973 llonorable Dixy Lee Ray Chairman U. S. Atomic Energy Comnission Washington, D. C.
20545
Subject:
REPORT ON /dUGNSAS NUCLEAR ONE-UNIT 1
Dear Dr. Ray:
During its 160th meetinr,, August 9-11, 1973, the Advisory Co=aittee on Reactor Safeguards completed its review of the application of the Arkansas Power and Light Compc.ny for a license to operate Arl:ansas Nuclear One-Unit 1 (formerly Russellville Nuclear Unit) at powar levels up to 2568 M1(t).
The site was visited by a Subconaittee on May 4, 1973, and the project considered during a Subcommittee meeting held in Washington, D.
C., on July 26, 1973.
In the course of the review, the Ccctittee had the benefit of discussions with representatives and con-sultants of the Arkansas Power and Light Conpany, the Babecch and Wilcox Company, th'e Bechtel Corporatica, and the AEC Regulatory Staff, and of the documents listed.
The Cemnittee last reported to the Conraission on the cons truction of this uait in its letter of September 12, 1968,.and on Unit 2 in its letter of February 10, 1972.
Arkansas Nuclear One is located about six miles from Russellville, Arkansas, on a peninsula formed by the Dardanelle Reservoir on the Arkansas River.
The application for a construction permit proposed initial operati.on at power lovels up to 2452 KJ(t), the same as the construction permit peuer 1cvel of Oconec Nuclear Station Unit I which employs a similar reactor.
Safety studies and performance analyses have been made for a power level of 2568 W(t) for Arkansas Nuclear One-Unit 1.
The Conraittee believes that review of the operation oi Oconce Nuclear Station Unit 1 by the Regulatory Staff chould be corapleted and satisfactory perfornaace of Oconec Nuclear Station t* nit 1 should be demonstrated before Arhansas Nuclear One-Unit 1 is operated at full licensed power.
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lionorable Dixy Lee Ray August 14, 1973 t.
The hot functional testing of Oconce Nuclear Station Unit I which was conducted in 1972 caused damage of some components, including reactor vessel internals.
The design changes which were made for Oconce Nuclear Station Unit I have been applied to Arkansas Nuclear One-Unit 1.
The Committee believes that these changes are acceptable.
The applicant has been responsive to the Committee's recommendation that suitable instrumentation be sought to monitor for loose parts and for vibration; such instrumentation has been designed and will be utilized.
The applicant stated that he will propose appropriate additional operating limitations if, at any time during operation, the moderator temperature coefficient of reactivity is positive.
This matter should be resolved in a manner satisfactory to the Regulatory Staff.
The Regulatory Staff has been investigating on a generic basis the problems associated with a potential reactor coolant pump overspeed in the unlikely event of a particular type of rupture at certain locations in a main co+ ' ant pipe. Some additional protective measures may be warranted and this.ma :tes should be resolved to tue satisfaction of the Regulatory Staff. The Cos-mittee wishes to be kept informed, s
The Committee reiterates its previous comments on the need for further study of means for preventing common mode failures from negating reactor scram action, and of design features to make tolerable the consequences of failure to scram during anticipated transients.
The Committee believes it desirable to expedite these studies and to implement in tLmely fashion such design modifications as are found to improve significantly the safety of the plant in this regard. The Committee wishes to be kept informed of the reso-lution of this natter.
The applicant should assure himself that instrumentation for determining the course of potentially serious accidents, on a time scale that will permit appropriate emergency action, is provided at the station and that appropriate calibration methods and calculated bases for interpreting instrument responses are available.
In view of the important role of the applicant's Safety Review Committee in providing continuing reviews, and in updating and implementing safety measures, the ACRS recommends that the Safety Review Committee include e"
additional experienced personnel from outside the corporate structure as voting members.
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Honorable Dixy Lee Ray August 14, 1973
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The applicant has proposed measures, including alarms and administrative procedures, to prevent operating under conditions which might result in exceeding acceptable fuel limits established from accident studies and other considerations. The current review has been confined to the first fuel cycle and the analyses have been based on the as-built fuel. The ACRS recommends that the Regulatory Staff establish suitable criteria for these measures, and provide suitable bases for evaluating future loadings.
Tbc Committee wishes to be kept informed.
The Committee recognizes that re-evaluation of operating limits may be necessary as a result of possible changes in the acceptance criteria for emergency core cooling systems. The Comnittee wishes to be kept inform 2d.
Other problems relating to large water reactors which have been identified by the Regulatory Staff and the ACRS and cited in previous reports should be dealt with appropriately by the Regulatory Staff and the applicant as suitable approaches are developed.
The Advisory Committee on Reactor Safeguards believes that, if due regard is given to the items mentioned above, and subject to satisfactory com-pletion of construction and preoperational testing, there is reasonable assurance that Arkansas Nuclear One-Unit 1 can be operated at power levels up to 2568 FM(t) wirbout undue risk to the health and safety of the public.
Sincerely yours, b.
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H.G.Mangelsd(f v
Chairman r
References attached.
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!!onorable Dixy Lee Ray August 14, 1973 Re fe rencen - Arkannas Nuclear One-Unit 1 1.
Final Safety Evaluation Report, Volumes I through IV 2.
Amendments 21 through 39 to the Application 3.
Arkansas Power and Light Company (AP&L) letters dated October 2 and 25, 1972, transmitting lists of BU1 Topical Reports for ANO-1 4.
AP&L letter dated February 28, 1973, notifying AEC of its intent to incorporate the Uf.nter 1972 Addenda of ASFE Sectica III into the requirements of a valve purchase order for ANO-l 5.
AP&L letter dated March 13, 1973, regarding requirements in electrical instrumentation and control systems at ANO-1 6.
AP&L letter dated April 11, 1973, furnishing information regarding enginecred safeguards control circuits 7.
AP&L report dated April 1973, " Interim Report on Fuel Densification for ANO-1" s
8.
AP&L letter dated April 23, 1973, furnishing information on stress profiles for the main steam and main feedwater lines 9.
AP&L letter dated May 11, 1973, furnishing responses to AEC require-ments for electrical instrumentation and control systecs 10.
AP&L letter dated May 11, 1973, furnishing responses to AIC require-ments to codify design of emergency cooling reservoir at ANO-1 11.
DL Safety Evaluation for ANO-1, dated June 6,1973 12.
DL Technical Report on Dens *fication of B6W Reactor Fuels, dated July 6, 1973 13.
Letter from Mrs. Robert H. Douglass, Russellville, Arkansas, dated July 17, 1973, regarding ANO-1 and Subcommittec Meeting July 26, 1973 c
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