ML20058E298

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Forwards Briefing Slides from Congressional Staff Briefing on 931105
ML20058E298
Person / Time
Issue date: 11/19/1993
From: Rathbun D
NRC OFFICE OF CONGRESSIONAL AFFAIRS (OCA)
To: Rogers, Selin I, The Chairman
NRC COMMISSION (OCM)
References
NUDOCS 9312060243
Download: ML20058E298 (14)
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Text

{{#Wiki_filter:9 p* 8f Cg i.'dRI E UNITED STATES (lyg ; j NUCLEAR REGULATORY COMMISSION y e WASHINGTON, D.C. 20555-0001 g '.gs j November 19, 1993 MEMORANDUM FOR: The Chairman Commissioner Rogers Commissioner Remick Commissioner de Planque FROM: Dennis K. Rathbun, Director 3 Office of Congressional Affairs

SUBJECT:

BRIEFING SLIDES FROM CONGRESSIONAL STAFF BRIEFING Attached for your information are slides used by the NRC staff on November 5, 1993, during a briefing for the staff of the Subcommittee on Energy and Mineral Resources, House Committee on Natural Resources. Attachments: As Stated

Contact:

Mike Callahan, 504-1776 cc: EDO OGC SECY PA PDR e 9312060243 931119 PDR ORG NRCC ye l, m,

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4 b { 4 Environmental Qualification May 28,1993 Briefing on Bonded-Jacket Electrical Cables Sandia National Laboratories Testing Safety Significance of Test Failures Information Notices 92-81 and 93-33 issued 3 =.s3

l WHY EQ IS A CONCERN As a result of license renewal activities, the staff 7 determined that the differences between the qualification requirements for older plants and newer plants should be reassessed for current operating plants. Sandia National Laboratory tests results raised questions with respect to accident performance capability of certain artificially aged equipment. A preliminary risk scoping assessment indicated that inadequate EQ could be a significant contributor to core damage frequency. The Fire Protection Reassessment Report concluded that EQ should be reviewed to identify and correct any - programmatic weaknesses that may exist. 3 Nov-93 1 m m m m w .wwem m , -.w, v-e t.... -.,.. ,,.+,,<e

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THE PURPOSES OF THE EQ TASK ACTION PLAN ARE TO: 1. EVALUATE DIFFERENCES THAT CURRENTLY EXIST IN EQ REQUIREMENTS BETWEEN OLDER AND NEWER PLANTS. 2. ASSESS THE ADEQUACY OF ACCELERATED AGING PRACTICES THAT ARE CURRENTLY USED FOR DEMONSTRATING EQUIPMENT QUALIFICATION. 3. PERFORM A PROGRAMMATIC REVIEW ~OF EQ REQUIREMENTS TO IDENTIFY AND RESOLVE ANY OTHER EQ ISSUES THAT-MAY EXIST. 3 Nov-93 l l

MAJOR ELEMENTS OF EQ TASK ACTION PLAN: 1. INFORM COMMISSION 2. MEET WITH INDUSTRY i 3. PROGRAMMATIC REVIEW 4. DATA COLLECTION / ANALYSIS 5. RISK ASSESSMENT l 6. TECHNICAL ISSUES 7. OPTIONS FOR RESOLUTION 8. IMPLEMENTATION I 3 Nov 93 5-m. .mm. . m.-- c .m m. m w e .-r.e w mmr., 3-*,erew, -.e,e-- ., - ---.. --., - +.,.--.-

e d LOSS OF SPENT FUEL POOL COOLING 4 U. S. NUCLEAR REGULATORY COMMISSION NOVEMBER 5,1993 d w --,--------2 <.--,v---e - ~ ~-- w.- .,v. -s

LOSS OF SPENT FUEL POOLlSFP? COOLING ISSUE AT SUSO.UEHANNA r e 10 CFR PART 21 Notification - November 27,1992

  • LOCA/ LOOP results in loss of SFP cooling e NRC View - Low Safety Significance
  • Low probability of concurrent events

~ [LOCA/ Extended LOOP / Full Core Offload] 9 e PP&L View-

  • Low probability. event
  • Fuel pool can be cooled e Meeting with.Part 21 Authors - October 1,1993
  • LOCA hydrodynamic loads can cause loss of SFP cooling
  • Review issue at Susquehanna
  • Determine generic. impact

=. NRC ACTIONS i j t e Met with PP&L March 18, and July 8,1993 e Met with Part 21 Authors March 18, and October 1,1993 i i t

  • Issued Information Notice No. 93-83 October 7,1993 e Visited PP&L October 20-21,1993 t
  • Established Task Action Plan October 29,1993
  • Sent Letter to BWR Owners Group October 30,1993 r

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MAJOR TECHNICAL ISSUES o POTENTIAL DIRECT LOSS OF NORMAL SPENT FUEL POOL COOLING POST-LOCA LOCA-induced hydrodynamic effects on piping o Extended loss of offsite power o o Automatic load shed o Environmental effects of LOCA o POTENTIAL LOSS OF ACCESS TO REACTOR BUILDING POST-LOCA Inability to reset load shed of normal spent fuel pool cooling system o 'o Inability to align spent fuel pool cooling and makeup systems Inability to monitor spent fuel pool temperature and level o o POTENTIAL LOSS OF SAFETY-RELATED EQUIPMENT FOLLOWING SPENT FUEL POOL BOILING Temperature and humidity effects within the reactor building o Basement flooding from condensation of water vapor o .m..m m.

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