NRC Generic Letter 1985-17

NRC Generic Letter 1985-017: Availability of Supplements 2 and 3 to NUREG-0933, a Prioritization of Generic Safety Issues

ML031140418
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, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, 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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill
Issue date:	08/23/1985
From:	Thompson H L Office of Nuclear Reactor Regulation
To:
References
GL-85-017, NUDOCS 8508210259
Download: ML031140418 (5)

N L f.. -.UNITED STATESI\l 0 {NCLAR REGULATORYCOMMISSION -* 0 WASHINGTON, D. C. 20555August 23, 1985TO ALL LICENSEES OF OPERATING REACTORS, APPLICANTS FOR OPERATING LICENSES,AND HOLDERS OF CONSTRUCTION PERMITS (GENERIC LETTER 85-11)Gentlemen:SUBJECT: AVAILABILITY OF SUPPLEMENTS 2 and 3 TO NUREG-0933, "A PRIORITIZATIONOF GENERIC SAFETY ISSUES"This letter is to inform you that Supplements 2 and 3 to NUREG-0933, "APrioritization of Generic Safety Issues," were published in January andJuly 1985, respectively. These supplements present the priority rankings forgeneric safety issues related to nuclear power plants. The purpose of theserankings is to assist in the timely and efficient allocation of NRC resourcesfor the resolution of those safety issues that have a significant potentialfor reducing risk. The safety priority rankings of HIGH, MEDIUM, LOW, andDROP have been assigned on the basis of risk significance estimates, theratio of risk to costs and other impacts estimated to result if resolutionsof the safety issues were implemented, and the consideration of uncertaintiesand other quantitative or qualitative factors, as discussed in theIntroduction of NUREG-0933. To the extent practical, estimates arequantitative. Although changes to nuclear power plant designs or operationare assumed, the sole purpose in prioritizing the issues is to estimate costsand other impacts that might result if such changes were implemented.The priority rankings in the report are based on generic assessments, i.e.,assessments of plants thought to be typical of a class of plants. Thus, thesafety significance of an issue might be greater (or less) for a specificplant because of features of the design or operation that are different fromthose assumed in the generic assessments.The supplements contain: (1) the issues that have been resolved since thepublication of NUREG-0933 Supplement 1 in July 1984; (2) the issues thathave been removed from further consideration by the NRC (i.e., those issueswith LOW or DROP priority rankings); and (3) the issues that are in theprocess of resolution (i.e., those issues nearly-resolved or with HIGH orMEDIUM priority rankings).NUREG-0933 and its 3 supplements may be purchased by calling (202) 275-2060or (202) 275-2171 or by writing to the Superintendent of Documents, U.SGovernment Printing Office, Post Office Box 37082, Washington, D.C. 20013-7082, or the National Technical Information Service, Department of Commerce,5258 Port Royal Road, Springfield, VA 22161.AIIpD AOC J53bb cl)C99fZ<41) 0227>

.1 I: %. ; .wI -:a .i ..I ;:K-4A\ This letter does not contain any new requirements or guidanceof operating reactors, applicants for operating licenses, andconstruction permits. No reply is required. If you have anythe subject, please contact Ronald Emrlt on (301) 492-4960.for licenseesholders ofquestions onRugt '.Tho ~on, .baorDi v on of LicensingOffice of Nuclear Reactor Regulationcc: List of Generic Letters/ 't r/

-s I D4-cv§ I.-/9TO ALL LICENSEES OF OPERATING REACTORS, APPLICANTS FOR OPERATING LICENSES,AND HOLDERS OF CONSTRUCTION PERMITSGentlemen:SUBJECT: AVAILABILITY OF SUPPLEMENT 2 TO NUREG-0933, "A PRIORITIZATION OFGENERIC SAFETY ISSUES"This letter is to inform you that Supplement 2 to NUREG-0933, "APrioritization of Generic Safety Issues," will be published in January 1985and may be purchased by calling (301) 492-9530 or writing the NRC/GPO SalesProgram, Division of Technical Information and Document Control, U.S.Nuclear Regulatory Commission, Washington, D.C. 20555, or the NationalTechnical Information Service, Department of Commerce, 5258 Port Royal Road,Springfield, VA 22161.The Supplement presents the priority rankings for generic safety issuesrelated to nuclear power plants. The purpose of these rankings is to assistin the timely and efficient allocation of NRC resources for-the resolutionof those safety issues that have a significant potential for reducing risk.The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have beenassigned on the basis of risk significance estimates, the ratio of risk tocosts and other impacts estimated to result if resolutions of the safetyissues were implemented, and the consideration of uncertainties and otherquantitative or qualitative factors, as discussed in the Introduction ofNUREG-0933. To the extent practical, estimates are quantitative. Althoughchanges to nuclear power plant designs or operation are assumed, the solepurpose-in prioritizing the issues is to estimate costs and other impactsthat might result if such changes were implemented.The priority rankings in the report are based on generic assessments, i.e.,assessments of plants thought to be typical of a class of plants. Thus, thesafety significance of an issue might be greater (or less) for a specificplant because of features of the design or operation that are different fromthose assumed in the generic assessments.The Supplement contains: (1) the issues that have been resolved since thepublication of NUREG-0933 Supplement 1 in July 1984; (2) the issues thathave been removed from further consideration by the NRC (i.e., those issueswith LOW or DROP priority rankings); and (3) the issues that are in theprocess of resolution (i.e., those issues nearly-resolved or with HIGH or 00MEDIUM priority rankings).85082102- -WOr nateR ..... ;................... .... ............... ...... ..,,,,........ ....,........... ...... ,,,..................... ............... ......... .............SURNAM Ei ........................ ........................ ................ ........ ........................ ........................ ........................ ........................DATt ................. .......................... ......................... .....I.. ........................ .........................t4RC FORM 316 (10 80) NRCM 0240 OFFICIAL RECORD COPY NAC FORM 316 (10 K0) NRCM 0240O FFICIA L R EC O RD C OPYUSGPO 1961-335-964 I" -b1-Of 0LIST OF RECENTLY.ISSUED GENERIC LETTERStGENERICLETTER NO.85-0185-0285-0385-0485-0585-0685-0785-08SUBJECT DATE,Fire Protection Policy Steering.Committee, , .Report; -/9/8S;Staff Recommended Actions .itemmninq From NRCIntegrated Program for the Resolution ofUnresolved Safety Issues Regarding SteamGenerator Tube Integrity 4/15/85Clarificationrof Equivalent Control Capacity V128/85For Standby Liquid Control SystemsOperator Licensing Examinations1/29/85Inadvertent Boron Dilution Events ...-,, '1/31/85Quality Assurance Guidance for ATWSEquipment that is not Safety-RelatedImplementation of Integrated Schedulesfor Plant Modifications10 CFR 20.408 Termination Reports -Format4/16/855/02/855/23/8585-0985-1085-1185-1285-1384-1485-1585-1685-17Technical Specifications for GenericLetter 83-28, Item 4.3-Technical Specifications for GenericLetter 83-28, Items 4.3 and 4.4Completion of Phase II of "Control ofHeavy Loads at Nuclear Power Plants"NUREG-0612Implementation of TMI Action Item II.K.3.5,"Automatic Trip of Reactor Coolant Pumps"Transmittal of NUREG-1154 Regarding theDavis Besse Loss of Main and AuxiliaryFeedwater EventCommercial Storage at Power Reactor Sitesof Low Level Radioactive Waste notGenerated by the Utility5/23/85 ---5/23/856/28/856/28/858/5/858/1/85Information Relating to the Deadlines forCompliance with 10 CFR 50.49, "EnvironmentalQualification of Electric Equipment Importantto Safety for Nuclear Power Plants 8/6/85High Boron ConcentrationsAvailability of Supplements 2 & 3 toNUREG-0933, "A Prioritization ofGeneric Safety Issues8/23/858/23/85

IC ' / efK)-2-This letter does not con'tain any new requirements or guidance for licenseesof operating reactors, applicants for operating licenses, and holders ofconstruction permits. No reply is required.m signed bFWugh L-Thmnson, Jr.Hugh L. Thompson, Jr, DirectorDivision of LicensingOffice of Nuclear Reactor Regulationcc

List of Generic LettersVr.ikjbl r(D/OFFCE S p .E B W p ... ......... ................ ..... .. ..................REmrit:s.-J Wners F owsp e TSpei ' ES4s tSU Ai 85 l/8 ................ ..........ArA .... .. 0 '-'.' . 0240 OFFIC'AL RECORD COPY '. . ..... ..H4RC FOAM~ 31t (10 0) NRCM 0240O FFICIA L R EC O RD C OPYUSGPO 19NI-335-960