IR 05000348/1997013

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Partially Withheld Insp Repts 50-348/97-13 & 50-364/97-13 on 971021-24 (Ref 10CFR73.21).Major Areas Inspected:Physical Security Program for Power Reactors
ML20199H247
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 11/20/1997
From: Belisle G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20199H230 List:
References
50-348-97-13, 50-364-97-13, NUDOCS 9711260058
Download: ML20199H247 (2)


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U.S. NUCLEAR REGULATORY COMMISSION REGION 11 Docket Nos:

50 348 and 50-364 License Nos:

NPF-2 and NPF 8 Report Nos:

50-348/97-13 and 50 364/97-13 Licensee:

Southern Nuclear Operating Company. Inc.

Facility:

Joseph M. Farley Nuclear Plant Units 1 and 2

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Location:

600 North 18th Street Birmingham. AL 35291-0400 Dates:

October 21-24, 1997 Inspector:

L. Stratton. Safeguards Inspector. Region II Approved by:

George A. Belisle. Chief Special Inspection Branch Division of Reactor Safety

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SAFEGUARDS INFORMATIOIL,__

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EXECUTIVE SUMMARY _-

l Farley Nuclear Plant

- NRC Inspection Report 50-348/97-13, 50-364/97 13

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This routine announced inspection was conducted in the area of plant suyoort

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by a regional safeguards specialist.

The specific area evaluated was tie

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Physical Security Program for Power Reactors.

An Inspector followup Item was identified in that a portion of the

licensee's planned implementation of the newly installed biometrics i

granted June 5 ppear to meet the intent of an NRC exemption which was

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system did not a 1995 (Section 52.1).

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i The licensee had initiated action to obtain more substantial locking

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devices,for the active barriers of the Vehicle Barrier System.

However.

Inspector Followup Item 50 348. 50 364/97-02-01 will remain open pending I

the procurement and installation of the new locks and their respective covers (Section S2.5).

s The licensee added a requirement to post a degraded Vehicle Barrier

System component in Revision 0 of the NRC approved Physical Security

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Plan (Section 52.5).

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Three structures were added to the Vehicle Barrier Calculation that

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were originally omitted.

The licensee concluded those structures met the requirements specified in NUREG/CR 6190 and Regulatory Guide 5.68

(Section S2.5).

Revisions to the Physical Security Plan reviewed by the inspector were

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appropriate and did not decrease the effectiveness of the plan (Section S3.1).

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Thelicenseeaddedthe'longtermcomkensatorypostattheServiceWater

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Intake Structure into Revision 0 of he Physical Security Plan.

This

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addition incorporated the Service Water intake Structure post as a part

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of the licensee's physical protection strategy to protect the facility (Section S3.1).

.The licensee was conducting security audits in accordance with the

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regulatory requirements specified in the Physical Security Plan (Section 7.1).

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l Documentt*ansmmed herewith ;;;;='=;1 6nclosure(s) this document le decontroikd

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