Resolution of Generic Safety Issues: Item A-36: Control of Heavy Loads near Spent Fuel (Rev. 2) ( NUREG-0933, Main Report with Supplements 1–35 )

DESCRIPTION

At all nuclear plants, overhead cranes are used to lift heavy objects in the vicinity of spent fuel. If a heavy object such as a spent fuel shipping cask or shielding block were to fall onto spent fuel in the storage pool or reactor core during refueling and damage the fuel, there could be a release of radioactivity to the environment. Such an occurrence also has the potential for overexposing plant personnel to radiation. If the dropped object were large and the damaged fuel contained a considerable amount of undecayed fission products, radiation releases to the environment could exceed 10 CFR Part 100 guidelines. With the advent of increased and longer-term storage of spent fuel, the NRC determined that there was a need for a systematic review of requirements, facility designs, and TS regarding the movement of heavy loads to assess safety margins and improve them where necessary. This item was originally identified in NUREG-0371² and was later determined to be a USI in NUREG-0510.¹⁸⁶

CONCLUSION

This USI was RESOLVED in December 1980 with the issuance of GL 80-113, ¹⁸⁴² following publication of the report on the NRC review of nuclear power plant load-handling operations in NUREG-0612. ⁷⁴⁷ GL 80-113 ¹⁸⁴² requested licensees to review their controls for the handling of heavy loads to determine the extent to which guidelines in NUREG-0612 ⁷⁴⁷ were being satisfied, and to identify the changes and modifications that would be required in order to fully satisfy the guidelines. GL 81-07 ¹⁸⁴³ was subsequently issued to correct errors in GL 80-113. ¹⁸⁴²

Licensee responses to NUREG-0612⁷⁴⁷ were requested in two parts: Phase I (6-month response); and Phase II (9-month response). For operating plants, MPAs C-10 and C-15 were established by NRR/DL to track the implementation of Phases I and II, respectively.⁶⁰ For future plants, SRP¹¹ Section 9.1.5. was revised. At the completion of Phase II, the results of the NRC findings were published in GL 85-11.¹⁸⁴⁴ However, in April 1999, Issue 186 was identified to address the NRR concern that licensees operating within the GL 85-11¹⁸⁴⁴ regulatory guidelines were not taking adequate measures to assess and mitigate the consequences of dropped heavy loads.

REFERENCES

0002. NUREG-0371, "Task Action Plans for Generic Activities (Category A)," U.S. Nuclear Regulatory Commission, November 1978. 0011. NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," U.S. Nuclear Regulatory Commission, (1st Ed.) November 1975, (2nd Ed.) March 1980, (3rd Ed.) July 1981. 0060. NUREG-0606, "Unresolved Safety Issues Summary," U.S. Nuclear Regulatory Commission, Vol. 7 No. 3, August 1985. 0186. NUREG-0510, "Identification of Unresolved Safety Issues Relating to Nuclear Power Plants," U.S. Nuclear Regulatory Commission, January 1979. 0747. NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants Resolution of Generic Technical Activity A-36," U.S. Nuclear Regulatory Commission, July 1980. 1842. Letter to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits from U.S. Nuclear Regulatory Commission, "Control of Heavy Loads (Generic Letter 80-113)," December 22, 1980. 1843. Letter to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits from U.S. Nuclear Regulatory Commission, "Control of Heavy Loads (Generic Letter 81-07)," February 3, 1981. 1844. Letter to All Licensees for Operating Reactors from U.S. Nuclear Regulatory Commission, "Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants," NUREG-0612 (Generic Letter 85-11)," June 28, 1985. [ML031150689]