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

It , '- LI IOCT 3 0 1982DISTRIBUTION rDocket Fir(NRC PDR -L PDRNSICPRCSSPB R/FFAndersonDBrinkmanCThomasPOWER REACTORSREACTORSFMIragl iaDElsenhutPAndersonTO ALL LICENSEES AND APPLICANTS FOR OPERATINGAND HOLDERS OF CONSTRUCTION PERMITS FOR POWERGentlemen:SUBJECT: INCONSISTENCY BETWEEN REQUIREMENTS OF 10 CFR 73.40(d) ANDSTANDARD TECHNICAL SPECIFICATIONS FOR PERFORMING AUDITS OFSAFEGUARDS CONTINGENCY PLANS (SECURITY PLAN)(Generic Letter No. 82-23)Section 73.40(d) of Title 10 of the Code of Federal Regulations requiresthat 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 inuse 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 Specificationsprior to the issuance of 10 CFR 73.40(d) or that have been added since itsissuance.Accordingly, you are requested to assure that your provisions for carryingout an independent audit of your safeguards contingency plan is in accordancewith 10 CFR 73.40(d). If your Technical Specifications contain a provisionthat is less frequent than the regulations, you should request the staff tomodify your technical specifications to conform to the rule.Because this Technicalof the Commission, youSpecification is clarifying and made atare not required to remit a license feethe requestfor the change.This request has been approved by OMB Clearance Number 3150-00 ., which expiresMay 31, 1983.Sincerely,Darrell G. Eisenhut, DirectorDivision of Licensing8210290108I P D SSPB .DL iD:OFFICE ..n.t....s.I DB -..n --s -.. ....... j 1 ....... .............................n a W A nk an' FM M a ..B.... .......................n M.z8. t 2i.udlt2 8 ........................SU N M W .~ O 7 " ~ I f / g 1 2 10/ ~ /82 10 r 4 ' /82DATE................DATE ........................ ........................ .... .... .. ........ ............ ......... ....... ... ........................NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USOPO. 1981-335-960NRC FORM 318 (10-80) NRCM 0240OFFICIAL RECORD COPYMSGMO 1981t35960