ML19326E170

Tech Spec Change Request to Allow Continued Operation of Plant.Qualified Radiation Monitors Will Not Be Available in Time to Meet Existing Tech Specs Effective 800801.Class II Fee Encl

ML19326E170
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/21/1980
From:	Steel C ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19326E171	List: ML19326E170 ML19326E173
References
2-070-22, 2-70-22, NUDOCS 8007280222
Download: ML19326E170 (4)

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e ARKANSAS POWER & LIGHT COMPANY SUITE 2900/THE FIRST NATIONAL BUltDING/P.O. box 551/UTTLE ROCK ARKANSA3 722o3/t5o11371-4282 CHARLES L STEEL July 21, 1980 Vice President Assistant to President 2-070-22 Director of Nuclear Reactor Regulation ATTN: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Technical Specification Change Request -

Post Accident Radiation Monitors (File: 1510, 1510.6)

Gentlemen:

By letters dated June 23, 1978, and August 31, 1978, we informed you of difficulties we were encountering in environmentally qualifying the Post Accident Containment Radiation Monitors. Asyou9reaware, the proposed radiation monitors for ANO-2 are the first 10 R/hr monitors proposed to be used and qualified in containment. As such, a detector had to be specifically designed and qualified.

Following our above letters and several conversations with the staff, we proposed (by letters dated August 31, 1978, and September 14,1978) an interim method for determining post accident radiation levels in containment.

This proposed interim method was verbally approved by the staff for use through the first cycle of operation of AN0-2 while testing efforts of the detectors continued.

By l'etter dated October 10, 1978, we submitted Technical Specification revisions to you addressing this issue. As mutually agreed, we chose the effective end date of the interim method as July 31, 1980. This particular date was chosen as it was conservatively past the then (October 1978) projected first refueling outage. Due to problems en-countered during the ANO-2 startup, the current schedule for the first AN0-2 refueling outage is March 1981.

80,9728o MEMBER MIODLE SOUTH UTIUTIES SYSTEM j L

2-070-22 Mr. Robert A. Clark July 22,1980 Although we have been actively pursuing the qualification of the detectors (several unsuccessful tests have been performed since October 1978), we have not been successful to date in qualifying the detectors. Currently, a modified version of the detector has just reentered qualification test-ing and is scheduled for completion in late September 1980. If this test-ing is successful, new detectors will have to be manufactured and installed in ANO-2.

To further expedite installation of qualified detectors, we have recently learned of another vendor who is attempting to qualify detectors to our specifications. We have now placed a purchase order with this second vendor to assure we have access to the first available qualified detector.

Subsequent to the development of this issue on the AN0-2 Docket, Item 2.1.8.B of NUREG-0578 has now required all containments to be equipped with the same detectors as ANO-2.

Paragraph 3 on page 2 of the Safety Evaluation Supporting Amendment No. 7 to NPF-6 states that the currently used interim method for post accident in containment radiation monitoring is acceptable for use through the first cycle of operation of AN0-2. However, as the implementation date of NUREG-0578 is sooner than the first scheduled refueling outage for ANO-2, we re-quest the Technical Specifications be modified to allow continued use of the interim method (as was the original inter.t of the specification) until such time as NUREG-0578 Item 2.1.8.B becomes effective.

As continued operation of ANO-2 beyond July 31, 1980, would result in a Technical Specification violation, we request your expedited approval of this change request prior to that date.

As this issue has previously been evaluated by NRC and addressed in the above referenced Safety Evaluation, we have determined this change request to be a Class Il change in accordance with 10 CFR 170.22. Accordingly, a check in the amount of $1,200.00 is attached.

Very truly yours, M ._ .

Charles L. Steel CLS:0TE:skm 4

STATE OF ARKANSAS )

) SS COUNTY OF PULASKI )

Charles L. Steel, being duly sworn, states that he is Vice President and Assistant to the President for Arkansas Power &

Light Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

u (JCharles L. Steel SUBSCRIBED AND SWORN T0 before me, a Notary Public in and for the County and State above named, this J/ day of 3 , 1980.

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Y) 1 Notary Pubiic sA l My Commission Expires:

Ahr. Commiss:en Dpires 9/1/,81

BASIS FOR CHANGE Change is' required to allow continued operation of the plant as qualified radiation monitors will not be available in time to meet the existing Tech. Spec. when it goes into effect August 1,1980.

EVALUATION OF EFFECT ON PLANT OPERATION There will be no effect on plant operation as a result of this change.

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