IR 05000313/1987004

Ack Receipt of Informing NRC of Steps Taken to Correct Deficiencies Noted in Insp Repts 50-313/87-04 & 50-368/87-04

ML20215M512
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/11/1987
From:	Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Campbell G ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8705130286
Download: ML20215M512 (1)

Text

3 h MAf I-l 196T In Reply Refer To:

Dockets: 50-313/87-04-50-368/87-04

^rkansas Power & Light Company ATTN: Mr. Gene Campbell Vice President, Nuclear Operations-P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:

Thank you for your letter of April 13, 1987, in response to our letter and NRC Inspection Report 50-313/87-04; 50-368/87-04 dated March 6, 1987. We have reviewed your reply and find it responsive to our concerns. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine

Sincerely, ORIGINAL SIGNED BY:

J. E. Gagliardo, Chief Reactor Projects Branch cc:

J.>M. Levine, Director Site. Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director bec to DMB (IE35)

bec distrib. by RIV:

RPB Resident Inspector R. D. Martin, RA R&SPB Section Chief (RPB/B) D. Weiss, RM/ALF RIV File DRSP RSB MIS SYSTEM RSTS Operator Inspector Section Chief W. L. Fisher R. L. Bangart R. E. Hall Project Inspector, RPB D. B. Matthews, NRR

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ARKANSAS POWER & LIGr4T COMPANY POST OFFICE box 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000

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U. S. Nuclear Regulatory Commission _ d__ , _ _

Region IV 611 Ryan Plaza Drive, Suite 1000 - - - __ _ _ .

Arlington, TX 76011 ATTN: Mr. Robert D. Martin Regional Administrator SUBJECT: Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Emergency Preparedness Inspection 87-04

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Gentlemen: -

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The Arkansas Power and Light Company (AP&L) is in receipt of your correspondence of March 6, 1987 (SCNAD38701) concerning the routine, unannounced inspection conducted by Mr. Nemen Terc during the dates of January 11-16, 1987.

,

During this inspection, one emergency preparedness deficiency (313-368/8704-01) was identified based upon the following five (5) findings:

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, The Unit 1 Abnormal Operating Procedure A0P-1203.19, "High Activity in the Reactor Coolant," does not include a follow-up action requirement for sampling the primary coolant. This is necessary to evaluate actions according to Technical Specification requirements.

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l The EPIPs do not contain a flow diagram equivalent to that of IE Information Notice No. 83-28 dated May 4, 1983. As a consequence, the teams interviewed did not consider evacuation before a release had occurred during General Emergency conditions with extensive fuel damage l and large amounts of radioactivity in the containment.

!

l There is no direct correlation between the example initiating I conditions of NUREG 0654, Appendix I, and the EALs found in the Plan.

l In a few cases, it was shown that the departure from NUREG 0654 is in a

nonconservative direction. For example, no EALs based upon installed

! instrumentation are listed in the Plan that correspond to a severe loss l

of fuel cladding.

l

' EALs in the Plan are not always equivalent to those in NUREG 0654 in promptness of notification or in establishing the severity of the emergency clas pg 7 NN N b h5 m ~. e=1- ur,ume .reo i

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-2- April 13, 1987 t Form 1904.02A, " Emergency Class /Offsite Dose Projection Worksheet,"

does not provide for computing an integrated dose based upon expected release duration and projected dose rat Item (1) has been addressed by revising the Unit 1 Abnormal Operating ~

Proceduro A0P-1203.19 "High Activity in the Reactor Coolant" to include the requirement for primary coolant sampling as part of follow-up ' action. This revision was effective as of March 5, 198 Item (5) will be addressed by developing and implementing a revision to procedure 1904.02, Form 1904.02A " Emergency Class /0ffsite Dose Projection Worksheet" to record the necessary information to calculate a projected

- total dose. This total dose value can then be compared to protective action guides to arrive at a protective action recomendation. This procedure change will be incorporated by May 31, 198 Items (2), (3), and (4) relating to the methodology of Inspection and Enforcement (I&E) Information Notice 83-28 and the correlation of the AN0 Emergency Action Levels (EAL) to those listed in NUREG 0654, Appendix I will be approached in two (2) phase Phase I will be to reexamine our EAL structure with emphasis on addressing

- ' incorporation of the intent of the I&E Information Notice 83-28 methodology and to identify where, if possible, EALs could be based upon installed -

. . instrumentation. This effort will also include a review of current industry activity in this area to determine if an approach applicable to the ANO case has been developed elsewher The end product of Phase I will be to determine what action can be taken to address the concerns identified in the January,1987 inspection. Once these actions are identified, a schedule for implementation will be developed and Phase II of the effort will be to implement the identified changes in accordance with that schedule. Phase I is currently scheduled to be

. completed by June 30, 198 If you have any questions regarding this item, please contact my offic < Very truly yours, M

. Ted Enos, fianager Nuclear Engineering and Licensing JTE:MT:lw

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