NRC Generic Letter 1982-23

NRC Generic Letter 1982-023: Inconsistency Between Requirements of 10 CFR 73.40(d) & Standard Technical Specifications for Performing Audits of Safeguards Contingency Plans (Security Plan)

ML031080482
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000514, 05000000, 05000496, 05000497, 05000515, Zimmer, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Bailly, Atlantic Nuclear Power Plant, Perkins, Cherokee, Clinch River, Skagit, Marble Hill, Hartsville, Phipps Bend, Yellow Creek, Crane
Issue date:	10/30/1982
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:
References
GL-82-023, NUDOCS 8210290108
Download: ML031080482 (1)

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Docket Fir( FMIragl ia NRC PDR - DElsenhut L PDR PAnderson NSIC

PRC

OCT 3 0 1982 SSPB R/F

FAnderson DBrinkman CThomas TO ALL LICENSEES AND APPLICANTS FOR OPERATING POWER REACTORS

AND HOLDERS OF CONSTRUCTION PERMITS FOR POWER REACTORS

Gentlemen:

SUBJECT: INCONSISTENCY BETWEEN REQUIREMENTS OF 10 CFR 73.40(d) AND

STANDARD TECHNICAL SPECIFICATIONS FOR PERFORMING AUDITS OF

SAFEGUARDS CONTINGENCY PLANS (SECURITY PLAN)

(Generic Letter No. 82-23)

Section 73.40(d) of Title 10 of the Code of Federal Regulations requires that each nuclear power reactor licensee provide for an independent review

-if its safeguards contingency plan at least every 12 months.

It has come to our attention that the Standard Technical Specifications in use by a number of licensees and some existing plant-specific Technical Speci- fications require that this independent audit be carried out every 24 months.

All licensees are required to meet the requirements of 10 CFR 73.40(d), not- withstanding any provision that may have been in their Technical Specifications prior to the issuance of 10 CFR 73.40(d) or that have been added since its issuance.

Accordingly, you are requested to assure that your provisions for carrying out an independent audit of your safeguards contingency plan is in accordance with 10 CFR 73.40(d). If your Technical Specifications contain a provision that is less frequent than the regulations, you should request the staff to modify your technical specifications to conform to the rule.

Because this Technical Specification is clarifying and made at the request of the Commission, you are not required to remit a license fee for the change.

This request has been approved by OMB Clearance Number 3150-00 ., which expires May 31, 1983.

Sincerely, Darrell G. Eisenhut, Director Division of Licensing

8210290108 I P D SSPB .DL iD:

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OFFICIAL RECORD RECORD COPY

USOPO. 1981-335-960

FORM 318 NRC FORM

NRC 318 (10-80) NRCM 0240

(10-80) NRCM 0240

OFFICIAL COPY MSGMO 1981t35960