ML20206G632

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SER Supporting Employee Concern Element Rept OP 31208-SQN, Security at Plant Entrances
ML20206G632
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/04/1988
From:
NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20206G037 List: ... further results
References
NUDOCS 8811220329
Download: ML20206G632 (2)


Text

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[g n ue, UNITED STATES '

!' fi NUCLEAR REGULATORY COMMISSION

f. ^' / , ' E W A SHING TON. D. C. 20655 l ,

SArETY EVAtt'ATION DEDO T Rv THE OrrtCE OF SPECIAL PDOJECTS  !

EvegvEE CONCERN ELEPENT CEPOPT OP 3120P-SON, "SECUPITY AT PLANT ENTDANCES" TENNESSEE VALLEY AUTHORITY g

SEOUOYAu NUCLEAR POWEP PLANT UNITS 1 & 2 r

00CKET NOS. 50-327 AND 50-328 .

Subiect 1.

C ate go r;, : Operations (Plant Operations Su: pert)

Subcate;ory: Security (31208)

Element: "Security at Plant Entrances" ,

Employee Cencern: SQN-56-010 001 The basis for Element Re: ort No. 312.08-50N, dated October 21, 1985, relates to inaceovate searches cf items leaving the site during the afternoons.  !

This concerr aas evaluated by TVA as being site soecific but not nuclear safety related.  ;

Su-.ary Tnis individual voiced a concern that many Public Safety Service Officers do ,

not recuire female employees to sutsmit to a search of their purses during the afternoons wnen lunch boxes are to be searched. j III. Evaluatic. (

The licensee incor ectly refers to 10 CFR 73.46,1erformance Capabilities i for Fixed Site Physical Protection Systems" as t*e NRC's requirements for protecting nuclear po.er plants. Additionally, tre licensee erroneously -

references NRC Regulatory Guide 5.7 "Entry / Exit Control for Protected Areas, Vital Areas and Material Access Areas" as further NRC requirements for power plants. The licensee then discusses searches at emit points of Material Access Areas for Strategic Special Nuclear Materials. l 1

The licensee did revie= appropriate procedures, did conduct intervie s and i did witness exit searches of hanc-carried items. l IFe evaluat0r c0reluded that tre coa.cern c0uld not te validated.

8811220329 891104 PDR ADOCK 05000327 p PDC

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3 IV. Conclusion ir.e licensee initiated its investigation predicated upon erroneous information, i.e. ,10 CFR 73.46 is not the NRC regulation for power plants,

egulatory Guice 5.7. is not a regulation nor does it offer guidance for cower plants, tnere are no Mate <'al Access Areas at power plants nor is there any Strategic Scecia' Nuclear Ma.erial available at power plants.

Tne licensee terminated its investigation based upon a review of the correct crocedure even though the procedure does not irrplement any NRC commitment.

The licensee concluced that there was no NRC requirement for the exit search. The issue was resolved and no open items nor corrective action is outstanding.

The NRC Staf f concurs with the final resolution of this concern, but not w'thcut first .r.ak.ing note of the above listed errors. These errors were discussed with the licensee during Inspection Report Hos. 50-327/B6-72 and 50-328/26-72.

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