NRC Generic Letter 1982-23

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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 G
Office of Nuclear Reactor Regulation
To:
References
GL-82-023, NUDOCS 8210290108
Download: ML031080482 (1)


It , '- L I I OCT 3 0 1982 DISTRIBUTION

r Docket Fir(NRC PDR -L PDR NSIC PRC SSPB R/F FAnderson DBrinkman CThomas POWER REACTORS REACTORS FMIragl ia DElsenhut PAnderson TO ALL LICENSEES

AND APPLICANTS

FOR OPERATING AND HOLDERS OF CONSTRUCTION

PERMITS FOR POWER 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 of the Commission, you Specification is clarifying and made at are not required to remit a license fee the request 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: OFFICE ..n.t....s.I

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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USOPO. 1981-335-960

NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY MSGMO 1981t35960

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