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Category:ARCHIVE RECORDS
MONTHYEARML20248J9151998-05-20020 May 1998 Rev 0 to Calculation NSD-024, ANO-1 N560 Consequence Evaluation ML20248J9511998-05-20020 May 1998 Rev 0 to Calculation EPRI-116-310, Degradation Mechanisms Evaluation for ANO-1 ML20217N8641998-03-27027 March 1998 Rev 0 to NSD-023, Consequence Evaluation of ANO-2 Svc Water Sys ML20217E9501997-08-15015 August 1997 Rev 0 to A-PENG-CALC-015, Implementation of Espri Risk- Informed ISI Evaluation for Containment Spray Sys at ANO-2 ML20217E9871997-08-15015 August 1997 Rev 0 to A-PENG-CALC-017, Implementation of EPRI Risk- Informed ISI Evaluation for Emergency Feedwater Sys at ANO-2 ML20217F0071997-08-15015 August 1997 Rev 0 to A-PENG-CALC-018, Implementation of EPRI Risk- Informed ISI Evaluation for Main Feedwater Sys at ANO-2 ML20217F0291997-08-15015 August 1997 Rev 0 to A-PENG-CALC-019, Implementation of EPRI Risk- Informed ISI Evaluation for Main Steam Sys at ANO-2 ML20217F0921997-08-14014 August 1997 Consequence Evaluation of ANO-2 Efw,Containment Spray & Main Steam & Feedwater Sys Piping ML20217E9211997-08-0808 August 1997 Rev 00 to A-PENG-CALC-010, Implementation of EPRI Risk- Informed ISI Evaluation for High Pressure Safety Injection Sys at ANO-2 ML20217E9291997-08-0808 August 1997 Rev 0 to A-PENG-CALC-012, Implementation of EPRI Risk- Informed ISI Evaluation for RCS at ANO-2 ML20217E9381997-08-0808 August 1997 Rev 0 to A-PENG-CALC-014, Implementation of EPRI Risk- Informed ISI Evaluation for Chemical & Volume Control Sys at ANO-2 ML20217E9671997-08-0808 August 1997 Rev 0 to A-PENG-CALC-016, Implementation of EPRI Risk- Informed ISI Evaluation for Low Pressure Safety Injection & Shutdown Cooling Sys at ANO-2 ML20135B6161996-12-0404 December 1996 Press Release IV-96-61, NRC Staff Authorizes Loading of Spent Fuel Into Dry Casks at Arkansas Plant ML20117H9671996-08-23023 August 1996 Rev 1 to NEAD-SR-95/125, Summary of ANO-2 Criticality Safety Analysis for Fuel Enrichments Up to 5.0 Weight % U-235 ML20133B5581996-07-16016 July 1996 Alternative Calculations for 32-1245917-00 ML20133B5521996-07-0808 July 1996 Adjusted Reference Temperatures for 21 & 32 EFPY for ANO-1 ML20128H4911996-05-23023 May 1996 Fuel Assembly Drop ML20202G1641995-03-0808 March 1995 Rev 1 to Design Calculation ANO-109.001.003, MCNP 1-D & 2-D Shielding Analyses for ANO MSB Transfer Cask (Mtc) ML20056E2821993-08-13013 August 1993 RB Penetration Overcurrent Protection Study ML20105B8911992-09-0303 September 1992 Rev 0(2) to Loop Error,Setpoint & Time Response Analysis for Low Pressurizer Wide Range Pressure ESFAS & RPS Trip Functions ML20099B2111992-07-24024 July 1992 ANO Unit 2 Degraded Voltage Study for Startup 2 ML20101G1831992-06-19019 June 1992 Calculation 92-E-0064-01, Arkansas Nuclear One Unit 1 Degraded Voltage Study for Startup 2 ML20105B8771992-05-0808 May 1992 Rev 0 to Loop Error,Setpoint & Time Response Analysis for Narrow-Range Containment Bldg Pressure ESFAS & RPS Trip Functions ML20085E9811992-01-20020 January 1992 100 Ton Cask Drop Analysis for Concrete Floor Above ANO-1 Control Room ML20079M9231991-11-11011 November 1991 Response to NUMARC Survey Re Aquatic Resource Questions, Socioeconomic Questions & Waste Mgt Questions in Support of NRC License Renewal Rulemaking ML20091D6621991-10-15015 October 1991 17 Ton Cask Drop Analysis for Concrete Floor Above ANO-1 Control Room ML20079N8521991-09-24024 September 1991 17 Ton Cask Drop Analysis for Concrete Floor Above AN0-1 Control Room ML20082K6211991-08-22022 August 1991 17 Ton Cask Drop Analysis for Concrete Floor Above ANO-1 Control Room ML20106C6581991-03-26026 March 1991 Rev 1 to Calculation 91-E-0019-01, Loop Error Analysis for Naoh Tank T10 Level ML20091L0241990-12-29029 December 1990 Pressurizer Nozzle Level Tap LBB Assessment ML20059B5851990-08-24024 August 1990 1 HPI Flow Rate ML20150C0781988-07-0101 July 1988 Proposed Amends 1 & 2 to Licenses DPR-51 & NPF-6, Respectively ML20079M9731988-04-25025 April 1988 Response to NUMARC Survey Re Questions on Aquatic Resource Questions in Support of NRC License Renewal Rulemaking ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20235B7461987-01-0505 January 1987 Package Consisting of Statement by G Campbell Re Complaints Filed by Two Former Employees & Five Related News Articles ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20050D1531982-04-0505 April 1982 Leaking Fuel Investigation ML20030B9101981-08-14014 August 1981 Slide Presentation Entitled Severe Accident Sequence Analysis (Sasa) Program at Id Natl Engineering Lab,Egg Id ML19350E5451981-04-10010 April 1981 Viewgraphs Entitled, CPC Design Bases Events, Backup Trip Function for CPC Design Bases Events, & Ak Nuclear One, Unit 2 Milestone,Rating & History ML20040C5251980-10-22022 October 1980 Slide Presentation from NRC 801022 Meeting W/Util Re Svc Water Sys Fouling ML19318C5071980-05-19019 May 1980 Slide Presentation for 800519 Meeting Re Core Protection Calculation Sys Software ML20125C0051979-08-22022 August 1979 Viewgraph Presentation Entitled, Middle South Svcs,Inc Analysis Support Program for Arkansas Nuclear One & Waterford Unit 3 ML20082K6331978-10-11011 October 1978 AP&L Miscellaneous Re Spent Fuel Shipping Cask Drop ML19326C8041968-09-20020 September 1968 Press Release Notifying That 681030 Public Hearing Will Consider CP Application 1998-05-20
[Table view] Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20135B6161996-12-0404 December 1996 Press Release IV-96-61, NRC Staff Authorizes Loading of Spent Fuel Into Dry Casks at Arkansas Plant ML19326C8041968-09-20020 September 1968 Press Release Notifying That 681030 Public Hearing Will Consider CP Application 1996-12-04
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U.S. Nuclear Regulatory Commission Office of Public Affairs, Region IV Walnut Creek Field Office j
1450 Maria Lane, Walnut Creek, CA 94596-5378 CONTACT: Mark Hanunond December 4,1996 Office: (510) 975-0254 FOR IMMEDIATE RELEASE Home:
(415) 674-1024 RIV-9661 Pager: (800) 916-4952 e-mail: mfh2@nrc. gov NRC STAFF AUTHORIZES LOADING OF SPENT FUEL INTO DRY CASKS AT ARKANSAS PLANT The Nuclear Regulatory Commission staff has lifted a restriction that prevented Entergy Operations Inc., operator of the Arkansas Nuclear One (ANO) power plant, from loading spent reactor fuel into a type of spent fuel storage cask that experienced a problem earlier this year at a plant in Wisconsin.
This action permits Entergy to begin transferring fuel assemblies from the ANO Unit I spent fuel pool into the casks. They will be mounted on a concrete pad foundation at the plant site near Russellville, Arkansas.
A pair of inspectors dispatched from NRC's Region IV office in Arlington, Texas, as well as an NRC resident inspector stationed at the plant, will provide 24-hour observation of loading activities. The project began after the restriction was lifted and will continue for several days. A total of 24 assemblies will be stored in the first dry cask; other casks will be filled in the coming months.
In lifting the restrictions, the NRC staff determined that changes in procedures proposed by Entergy would prevent a recurrence of hydrogen gas as occurred on May 28 at the Point Beach nuclear plant near Two Rivers, Wisconsin.
After a thorough evaluation, an NRC inspection team and the operator of the Point Beach plant, the Wisconsin Electric Power Co., concluded that hydrogen was generated by a chemical reaction between the zine coating on the cask interior and acidic borated water from the plant's spent fuel pool. Some water was inside the cask.
The hydrogen ignition occurred as Point Beach technicians welded a shield lid onto the storage cask. Pressure from the ignition displaced the 6,390-pound lid, leaving it slightly l
tipped. No one was injured and no radioactive materials were released.
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4 But as a result of the event, the NRC staff issued Confirmatory Action Letters j
to Entergy, Wisconsin Electric and Consumers Power Co., operator of the Palisades nuclear power plant near South Haven, Michigan. Those three utilities have used or plan to j
use the same type of cask that experienced the problem at Point Beach. The Confirmatory j
Action Letters documented agreements by the utilities that they would not use the casks until 1
NRC concerns were adequately addressed.
1 The cask in question is the VSC-24 model, manufactured by Sierra Nuclear Corp. of j
Scotts Valley, California. The Palisades plant has loaded 13 casks of the same type and plans to load others. Arkansas will use the VSC-24 for the first time.
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The Confirmatory Action Letters were followed by an NRC Bulletin in early July that required licensees to assess the potential for chemical, electro-chemical or other reactions l
within the casks and propose additional safety measures.
Among t'le measures proposed by Entergy and approved by the NRC staff is the 4
establishment of an air flow during welding operations that is designed to assure that i
hydrogen concentrations are kept very low.
j "The staff agrees that continuous venting of the [ cask] will effectively l
prevent the accumulation of a combustible concentration of hydrogen during welding and cutting operations," the NRC's Office of Nuclear Material Safety and Safeguards said in a i
report. "The staff concluded that Entergy's procedural controls, correctly implemented, I
would effectively prevent ignition of hydrogen during cask operations."
The restrictions imposed by the Confirmatory Action Letters affecting Point Beach j
and Palisades remain in effect pending conclusion of the NRC staff review. The l
manufacturer of the VSC-24 cask, Sierra Nuclear, has informed the NRC that it is investigating substitute coatings for the interior of the cask that would not generate hydrogen 1
upon contact with water from a spent fuel
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