NRC Generic Letter 1978-17
| ML031280393 | |
| Person / Time | |
|---|---|
| Issue date: | 06/12/1978 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| GL-78-017 | |
| Download: ML031280393 (5) | |
UNITED STATESNUCLEAR REGULATORY COMMISboUNWASHINGTON, D. C. 20555June 12, 197861- 7j-'/7Licensees for all Plants in the SystematicEvaluation ProgramGentlemen:Due to an administrative error, the wrong May 17, 1978, letterregarding information on heavy loads over spent fuel was sent to you.Accordingly, please disregard that letter. The correct letter isattached.
Sincerely,-_ 7Viictr Stell DirectorDivision of pera ing ReactorsOffice of Nuclear Reactor Regulation
Enclosure:
Letter to Systematic EvaluationProgram Licensees dtd. 5/17/78) 11 I ejLJ,
--so -1 UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON. D. C. 20555May 17, 1978Licensees for all Plants in the SystematicEvaluation ProgramIn January, 1978, the NRC published NUREG-0410 entitled "NRC Program forthe Resolution of Generic Issues Related to Nuclear Power Plants." Aspart of this program, the Task Action Plan for Category A TechnicalActivity No. A-36, "Control of Heavy Loads Near Spent Fuel", was approved.As you are aware,overhead handling systems are used to lift heavy objectsin the vicinity of spent-fuel in both PWRs and BWRs. If a heavy object,e.g., a spent fuel shipping cask or a shielding block, were to fall ortip onto spent fuel in the storage pool or the reactor core during refuel-ing and damage the fuel, there could be a release of radioactivity to theenvironment and a potential for radiation over-exposures to inplant personnel.If the dropped object is large, and the damaged fuel contained a large amountof undecayed fission products, radiation releases to the environment couldexceed 10 CFR Part 100 guidelines. These concerns are currently consideredin licensing reviews. We believe there is a need to systematically reviewNRC requirements, facility designs and technical specifications regardingthe movement of heavy loads, to assess safety margins and to improve thosemargins where warranted.The staff efforts currently underway commenced with a detailed evaluationof current NRC requirements and licensee procedures for the movement ofheavy loads near spent fuel. Based on the results of that evaluationassessments will be performed of the probabilities and consequences ofheavy loads damaging spent fuel. A determination will then be made of theneed for revising the Standard Review Plan, the Standard Format andContent of Safety Analysis Reports for Nuclear Power Plants and theStandard Technical Specifications.All licensees except those in the Systematic Evaluation Program are beingrequested to provide information regarding the movement of heavy loadsnear spent fuel at their facilities. A copy of the information requestis enclosed for your use. You need not submit this information for yourfacility at the present, however, it will be required and reviewed duringthe SEP program for your plant. This request has been reviewed by theGeneral Accounting Office and approved under Clearance No. B-180225(R0522).This clearance expires February 28, 198 May 17, 1978In the interim, while these efforts are ongoing, you should review yourcurrent procedures for the movement of heavy loads over spent fuel toassure that the potential for a handling accident which could result indamage for spent fuel is kept to a minimum.
Sincerely,V o ctorDivision of Oper ing ReactorsOffice of Nuclear Reactor Regulation
Enclosure:
Information Request Approved by GAOB-180225 (R0522)Expires 2-28-81EnclosureINFORMATION REQUESTED1. Provide a diagram which illustrates the physical relation betweenthe reactor core, the fuel transfer canal, the spent fuel storagepool and the set down, receiving or storage areas for any heavyloads moved on the refueling floor..2. Provide a list of all objects that are required to be moved over thereactor core (during refueling), or the spent fuel storage pool. Foreach object listed, provide its approximate weight and size, a diagramof the movement path utilized (including carrying height) and thefrequency of movement.3. What are the dimensions and weights of the spent fuel casks that areor will be used at your facility?4. Identify any heavy load or cask drop analyses performed to date foryour facility. Provide a copy of all such analyses not previouslysubmitted to the NRC staff.5. Identify any heavy loads that are carried over equipment required forthe safe shutdown of a plant that is operating at the time the load ismoved. Identify what equipment could be affected in the event of aheavy load handling accident (piping, cabling, pumps, etc.) and discussthe feasibility of such an accident affecting this equipment. Describethe basis for your conclusions.6. If heavy loads are required to be carried over the spent fuel storagepool or fuel transfer canal at your facility, discuss the feasibilityof a handling accident which could result in water leakage severe enoughto uncover the spent fuel. Describe the basis for your conclusions.7. Describe any design features of your facility which affect the potentialfor a heavy load handling accident involving spent fuel, e.g., utilizationof a single failure-proof crane.8.. --Provide copies of all procedures currently in effect at your facilityfor the movement of heavy loads over the reactor core during refueling,the spent fuel storage pool, or equipment required for the safe shut-down of a plant that is operating at the time the move occurs.9. Discuss the degree to which your facility complies with the eight (8)regulatory positions delineated in Regulatory Guide 1.13 (Revision 1,December, 1975) regarding Spent Fuel Storage Facility Design Basi ICommonwealth Edison CompanyccMr. John W. RoweIsham, Lincoln & BealeCounselors at LawOne First National Plaza, 42nd FloorChicago, Illinois 60603Mr. B. B. StephensonPlant SuperintendentDresden Nuclear Power StationRural Route #1Morris, Illinois 60450Morris Public Library604 Liberty StreetMorris, Illinois 60451