ML19326C292
| ML19326C292 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/14/1973 |
| From: | Mangelsdorf H Advisory Committee on Reactor Safeguards |
| To: | Ray D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19326C279 | List: |
| References | |
| NUDOCS 8004220849 | |
| Download: ML19326C292 (4) | |
Text
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON D.C.
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August 14, 1973
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.?E Honorable Dixy Lee Ray fe:
Chairman
.U. S. Atomic Energy Commission Washington, D. C.
20545
Subject:
REPORT ON ARKANSAS NUCLEAR ONE-UNIT 1
Dear Dr. Ray:
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~sr During its 160th meeting, August 9-11, 1973, the Advisory Committee on
-Reactor Safeguards completed its review of the application of the Arkansas Power and Light Company for a license to operate Arkansas
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Nuclear One-Unit 1 (formerly Russellville Nuclear Unit) at power levels
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up to 2568 W (t). The site was visited by a Subcommittee on May 4, 1]
1973, and the project considered during a Subcommittee meeting held in
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Usshington, D. C., on July 26, 1973. In the course of the review, the Committee had the benefit of discussions with representatives and con-sultants of the Arkansas Power and Light Company, the babcock and Wilcox F
Company, the Ecchtel Corporation, and the AEC Regulatory Staff, and of the documents listed. The Committee last reported to the Cc= mission on the construction of this unit in its letter of September 12, 1968, and on Unit 2 in its letter of February 10, 1972.
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- i Arkansas Nuclear One is located about six miles from Russellville,
. Arkansas, on a peninsula formed by the Dardanelle Reservoir on the j
h Arkansas River.
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The application for a construction permit proposed initial operation at pcwer levels up to 2452 W(c), the sa se as the construction permit power level of Oconee Nuclear Station Unit I which employs a similar reactor.
Safety studies and performance analyses have been made for a power level of 2568 NW(t) for Arkansas Nuclear One-Unit 1.-
The Committee believes that review of the operation of Cconee Nuclear Station Unit 1 by the Ragulatory Staff should be completed and satisfcetory perfornance of
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Oconen Nuclear Station Unit 1 should be demonst.rared before Arkansas E
Nuclear one-Unit 1 is operated at full licensed power.
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- .4 Honorable Dixy Lee Ray August 14, 1973 h
The hot functional testing of Oconee Nuclear Station Unit I which,was conducted in 1972 caused damage of some components, including reactor vessel internals. The design enanges which were made for Oconee Nuclear Station Unit 1 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 recom endation that suitable instrumentation be sought to monitor for loose parts and for vibration; such instrumentation has been designed and will be utilized.
p The applicant stated that he will propose appropriate additional operatinE ti 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 proble%s associated with a potential reactor coolant pump overspeed in the unlikely event of a particular type of rupture at certain locations in a main coolant F
pipe. Some additional protective measures may be warranted and this. natter
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should be resolved to the satisfaction of the Regulatory Staff. The Com-i.
mittee wishes to be kept informed.
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The Committee reiterates its previous comments on the need for further study of means for preventing common mode failures from negating rt setor t
scram action, and of design features to make tolerable the consequences of
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f ailure to scram during anticipated transients. The Committee believes it desirable to expedite these studies and to implement in timely fashion such design modifications as are found to improve significantly the safety of the
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plant in this regard. The Committee wishes to be kept informed of the reso-I' lution of this matter.
The applicant should assure himself that instrumentation for determining h
the course of potentially serious accidents, on a time scale that will
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permit appropriate emergency action, is provided at the station and that appropriate calibration methods and calculated bases for interpreting i
instrument responses are available.
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In view of the important role of the applicant's Safety Review Committee j
in providing continuing reviews, and in updating and implementing safety i
measures, the ACRS recommends that the Safety Review Committee include additional experienced personnel from outside the corporate structure as voting members.
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O Honorable Dixy Lee Ray
-J-August 14, 1973 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.
The Committee wishes to be kept informed.
The Committee recognizes that re-evaluation of operating lLnits may be necessary as a result of possible changes in the acceptance criteria for
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emergency core cooling systems. The Committee wishes to be kept informed.
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
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up to 2568 MR(t) without undue risk to the health and safety of the public, i
.L Sincerely yours, we i
H.G.Mangelsdjff Chairman References attached.
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llenorable Dixy Lee Ray 4-August 14, 1973 References - Arkansas Nuclear One-Unit 1 1.
Final Safety Evaluation Report, Volumes I through IV
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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 B&R Topical Reports for ANO-1 4.
AP&L letter dated February 28, 1973, notifying AEC of its intent I-to incorporate the Winter 1972 Addenda of ASNE Section III into the requirements of a valve purchase order for ANO-1 5.
AP&L letter dated March 13, 1973, regarding requirements in electrical instrumentation and control systems at ANO-1
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AP&L letter dated April 11, 1973, furnishing information regarding
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cngineered safeguards control circuits i-7.
AP&L report dated April 1973, " Interim Report on Fuel Densification i
for ANO-1" 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 systers
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ments to modify design of emergency cooling reservoir at ANO-1 D
- 11. DL Safety Evaluation for ANO-1, dated June 6, 1973 12.
DL Technical Reporc on Densification of BGR Reactor Fuels, dated f
July 6, 1973 i
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Letter from Mrs. Robert E. Douglass, Russellville, Arkansas, dated
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July 17, 1973, regarding ANO-1 and Subcommittee Meeting July 26, 1973 i
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