IR 05000282/1997007

Requests to Complete Engineering Analysis of Portion of Section S1.1b(1)(a) of Insp Repts 50-282/97-07 & 50-306/97-07,dtd 970430,as Required by 10CFR73.55(c)(7) & (8)

ML20217C691
Person / Time
Site:	Prairie Island
Issue date:	09/24/1997
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Wadley M NORTHERN STATES POWER CO.
References
50-282-97-07, 50-282-97-7, 50-306-97-07, 50-306-97-7, NUDOCS 9710020022
Download: ML20217C691 (3)

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September'24, 1997

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Mr. MJ.Wadley -

Vice Piesident, Nuclear Generation ~

- Northern States Power Company -

414 Nicollet Mall 2 Minneapolis,MN 55401 SUBJECT: PRAIRIE ISLAND VEHICLE BARRIER SYSTEM UNRESOLVED ITEM

Dear Mr. Wadley:

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L Section S1.1.b(1)(a) cf Inspection Reports 50-282/97007; 50-306/9700/, dated April 30,1997, noted that a portion of the Prairie Island Vehicle Barrier System (VBS) did not appear to have

= an engineering analysis completed, as requirsd by_10 CFR Part 73.55(c)(7) and (8), to assure y that the barrier could meet the maximum parameters of the design basis vehicle (the exact-

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l- location and construction characteristics of that portion of the barrier system is considered .

! - safeguards information until resolved). = During the inspection, plant engineering representatives Indicated that they believed that the NRC determined that " engineered structures * did not have -

[ to be' analyzed for barrier effectiveness and such structures were considered as acceptable for VBS purposes without an analysis being performed.

Based upon our discussions with the NRC Office of Nuclear Reactor Regulation (NRR),

Safeguards Branch; Division of Reactor Program Management, it was determined that an:

engineering analysis is required. You are requested to complete an engineering analysis of the portion of the VBS in question, and provide _us 'he conclusions pertaining to that portion of the VBS 's ability to meet the maximum parameters of the design basis vehicle threat, zThis issue has been discussed with Mr. M. Sleigh of your staff and responsc is requested -

p within 30 days of receipt of this letter. You will be advised of the resolution of this unresolved

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item by separate corresponcence after we have reviewed your analysis.

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Thank you for your assistance in this matter.

Sincerely, ociginal signed by J. .M . JacobsonN *

John A. Grobe, Acting Director Division of Reactor Safety Docket NosJ 50-282,50-306 I

See Attached Distnbution i L DOCUMENT NAME: G:DRS\PRA092 a. . -, .c..co._7.DRS

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OFFICE Rill l Rill l Rill l- Rill - /bfl NAME GPirtle:Jp JCreed JMcCormick-B JGrobh '\ V M^

DATE- 09/ /97 09/ /97 09/ /97 09/p\/9N ~

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OFRCIAL RECORD COPY Y-9710020022 970924 2 /

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'. Mr.! M.- Wadley? _ _ _.

Vice President. Nuclear Generation Nodhem States Power Company -

414 Nicollet Mall; Minneapolis, MN 55401 SUBJECT: VEHICLE BARRIER SYSTEM UNRESOLVED ITEM Dear Mr. Wadleyi -

. Section S1.1.b(1)(a) of Inspection Reports No. 50-282/97007; 50-306/97007, dated April 30 -

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r 1997, noted that a portion of the Vehicle Barrier System (VBS) did not appear to have an

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erigineering analysis completed, as required by CFR 73.55(c)(7)and (8), to assure that the

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barrier could meet the maximum parameters of the design basis vehicle ( the exact location and construction characteristics of that portion of tho barrier system is considered safeguards (information until resolveo).- During the inspection, the licensee engineering representatives L -- indicated that they believed that the NRC determined that " engineered structures" did not have -

D to be analyzed for barrier effectiveness and such structures were considereo as acceptable for t

?/BS purposes without an analysis being performed.

Based upon our discussions with the NRC Office of Nuclear Reactor Regulation (NRR), ,

Safeguards Branch, Division _of Reactor Program Management,- it was determined that an '

engineo-ing analysis is required.- You are requested to complete an engineering analysis of the portion of the VBS in question, and provide us the conclusions pertaining to that portion of the VBS 's effectiveness to meet the maximum parameters of the design basis vehicle threat ~

within 30 days after receipt of this letter. -You will be advised of the resolution of this unresolved Item by separate correspondence after we have reviewed your analysis conclusions.

. We discussed this issue with Mr. M. Sleigh of your staff and he was advised that the '

engineering analysis would be requested.

Thank you for your assistance in this matter.

Sincerely, John A. Grobe, Acting Director Division of Reactor Safety _

-1 Docket Nos. 50-282.,50-306 '

See Attached Distnbution

DOCUMENT NAME: G DRS\PRA092 7 DRS. (See Previous Cmncu

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OFFICE- Rill = _ - [J Ril! : Tj d l Rlli d A/ Rlli l NAME- GPirtle:Jp 3R@ JCreed JMcComE-t - JGrobe -

DATE- 09/23/97- 09/;d197 09/p3/97 09/ /97 OFRCIAL RECORD COPY -

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. September 24, 1997 cc: Plant Manager, Prairie Island State L.laison Officer, State of Minnesota State Liaison Officer, State of Wisconsin Tribal Council, Prairie Island Dakota Community

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Distribution:

Docket File Rlli PRR J. L. Caldwell, Rlli PUBLIC IE-01 SRI, Prairie Island Rlli Enf. Coordinator OC/LFDCB TSS DRP LPM,NRR DOCDESK DRS A. B. Beach, Rlil CAA1 l

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