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Category:COMMISSION PAPER
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20029D3561994-03-31031 March 1994 Update of 1991 Decommissioning Cost for Rancho Seco Nuclear Generating Station ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual ML20029A7511991-02-28028 February 1991 Suppl to Special Rept 90-13:on 901224,25,29 & 910113,listed Meteorological Instrumentation Inoperable for More than 7 Days.Work Request Initiated & Instrumentation Channels Declared Operable on 910116 ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station 05000312/LER-1990-002, :on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.21990-07-20020 July 1990
- on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.2
ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station NL-90-355, Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20033G6011990-03-30030 March 1990 Rev 1 to Defueled Requalification Training Program for NRC Licensed Operators ML20042E6921990-03-30030 March 1990 Special Rept 90-06:on 900301,06 & 14,listed Fire Barrier Penetrations That Failed Surveillance Test Not Restored to Operable Status within 7 Days as Required by Tech Spec 3.14.6.2.Operability of Fire Detectors Verified ML20033G6031990-03-30030 March 1990 Rev 1 to Defueling Training Programs for NRC License Candidates ML20042E6931990-03-30030 March 1990 Special Rept 90-07:on 900228,high Temp Detector Circuit for Zone 53 Not Restored to Operable Status within 14 Days When Circuit Failed Surveillance Test SP.345 & Would Not Alarm. Fire Watch Established.Detector Found Operable on 900316 NL-90-054, Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station1990-02-28028 February 1990 Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station ML20006F4181990-02-0909 February 1990 Special Repts 90-1,90-2,90-3 & 90-4:on 900110,16,18,19,30 & 31,fire Barriers Breached for More than 7 Days.All Fire Barrier Penetrations & Fire Doors Returned to Operable Status NL-90-035, Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station1990-01-31031 January 1990 Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 1999-08-13
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POLICY ISSUE SECv-93-023 February 2, 1993 (Information)
[g:
The Commissioners from:
James M. Taylor Executive Director for Operations Sub.iec t :
QUARTERLY REPORT ON THE STATUS OF PREMATURELY SHUT DOWN PLANTS furpose:
To inform the Commission of the status of open issues and the progress of the specified facilities toward decommissioning.
Backgrouad:
In COMJC-92-002 of March 23, 1992, the Commission directed the staff to submit quarterly reports on the status of prematurely shut down plants.
[Li_3g311gn:
The following is the status of plants in the decommissioning process.
1.
SHOREHAM Price-Anderson Exemption The staff and the Office of the General Counsel (0GC) are reviewing this issue and expect to make recommendations for resolution by February 1993.
11.
RANCHO SEC0 A,
Decommission 1na Plan The Atomic Safety and Licensing Board (ASLB) in its order (LBP-92-23, 35 NRC) of August 20, 1992, denied the Petitioner, Environmental and Resources Conservation Organization (ECO), standing in its NOTE:
TO BE MADE PUBLICLv AVAILABLE UPON ISSUANCE.
THIS PAPER WILL BE SERVED ON THE PARTIES TO CONTAC1:
ONGOING DECOMMISSIONING S. Weiss, ONDD/NRR
1 The Commissioners e.
request for a hearing on the decommissioning plan.. On September 8, 1992, ECO filed an appeal of the ASLB ruling with the Commission for its consideration.
The staff has nearly completed reviewing the licensee decommissioning plan. The staff schedule for action on the licensee decommissioning plan will depend on the Commission action on the ECO appeal.
B.
Decommissionina Fundina Plan The staff has evaluated the Rancho Seco funding plan and will include its findings in the safety evaluation supporting the Rancho Seco decommissioning order.
C.
Price-Anderson Exemotion 1
The staff and OGC are reviewing this issue and expect i
to make recommendations for resolution by February 1993.
111.
FORT ST. VRAIN A.
Decommissionina Plan in an order of November 23, 1992, the Commission ~
authorized the decommissioning (DECON option) of the i
Fort St. Vrain facility (FSV). The Commission also-issued Amendment 85 to establish the decommissioning technical specifications (TS).
Public Service Company 4
of Colorado is dismantling FSV in accordance with.the plan.
B.
Transfer of Responsibility In a memorandum of December--17, 1992, the staff transferred the regulatory responsibility of licensing-a'nd project management for the Fort St. Vrain (FSV).
facility from the Non-Power Reactors and Decommissioning Project Directorate _of the' Office of-Nuclear Reactor Regulation. (NRR) to the -
Decummissioning and_ Regulatory _lssues Branch of the.
t Office of Nuclear Material Safety and Safeguards (NMSS). The transfer is consistent with the agreement.
between NRR and NMSS,'as documented in a memorandum of-March ;1,- 1988, from Thomas E. Murley' and -
Hugh:L.-Thompson,.Jr., to Victor Stello.
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The Commissioners,
C.
Vodates Discontinued Unless new issues arise on Fort St. Vrain which should be brought to the attention of the Commission, this is the last update in the quarterly report for matters related to Fort St. Vrain. This is in accordance with COMJC-92-002.
IV.
YANKEE R0WE A.
Decommissionina Plan The licensee is now scheduled to submit the decommis-sioning plan in the f all of 1993.
The staff estimates needing one year to review the plan, with approval by fall of 1994.
B.
Completed Actions The staff issued six license amendments and five exemptions and approved a Certified Fuel Handler Program.
The major amendments and exemptions dealt-with 10 CFR Part 50 Appendix J, emergency planning, the FSAR Update Rule, operator staffing, the fire protection program, radiological effluent technical specifications, and the safeguards program.
The staff also reviewed miscellaneous administrative changes for the permanently shut down condition.
C.
Actions ir vroaress The staff is processing (1) exemption requests for property insurance onder 10 CFR 50.54(w), (2) the Price-Anderson indemnity agreement under 10 CFR Part 140, and (3) two license amendment requests for wate chemistry and "defueled" technical specifications. On the Price-Anderson indemnity issue, the staff and 0GC expect to make iecomnendations for resolution by February 1993.
D.
Public Interest The NRC received two letters from the Citizen's Awareness Network, a local group, expressing concern that local residents did not have a voice in the decision making process for issuing the license.
amendments and exemptions. The Network requested that the NRC rescind the _ exemptions and hold a public hearing on decommissioning issues.
The NRC has
The Commissioners,
responded to both letters and has proposed a public meeting near the site in early 1993 to discuss the Yankee Rowe decommissioning process.
E.
Etmoval of larae Comoonents Under 10 CFR 50.52 in a letter of flovember 25, 1992, Yankee described its proposed program to remove the four steam generators, the pressurizer, and reactor vessel internals from the site to Barnwell prior to tiRC approval of the decommissioning plan for Yankee.
At a meeting with the licensee on December 8,1992, the staff requested further information on pre-decommissioning activities.
The staff documented these questions in a meeting summary of December 23, 1992, and responses were received on January 12, 1993.
Further guidance on activities which might be performed prior to approval of a decommissioning plan was received from the Commission in a staff requiraments memorandum of January 14, 1993.
The staff will review the licensee proposed actions using this guidance.
V.
SAti OfiOFRE, UtilT 1 A.
Epssession-Only license On 0ctober 23, 1992, the staff issued a possession-only license for San Onofre liuclear Generating Station, Unit 1 (50t4GS-1).
The possession-only license will not become effective until the licensee certifies that all fuel has been removed from the core and stored in the_ spent fuel pool.
The licensee permanently shut down 5014GS-1 on tiovember 30, 1992.
As allowed by the existing license, the licensee has begun removing spent fuel from the Unit I spent fuel pool to the Unit 3 pool to make room for the Unit I core.
The licensee expects that the Unit I core will be transferred to the spent fuel pool by March 30, 1993.
B.
ESAR Update Exemotien On October 1, 1992. the Commission promulgated a rule change to 10 CFR 50.71(e) which extended the interval between submissicns of FSAR updates, Therefore, the exemption requested by the licensee is no longer necessary.
Accordingly, the licensee has withdrawn its request for an exemption.
l The Commissioners VI.
TROJAN TerminatiRD of Ontrations On January 4,1993, officials at Portland General Electric Company announced that they will permanently cease operation of the Trojan Nuclear Plant.
Trojan has been shut down since November 9, 1992, because of steam generator tube leaks that resulted from an improperly sleeved tube.
Vll.
INDIAN P0lt(T 1 AND DRESDEN 1 After issuing the Fort St. Vrain decommissioning order, the staff was able to apply resources to continue reviewing the decommissioning plans for Indian Point Unit 1 and Dresden Unit 1.
The staff anticipates completing both reviews by the spring of 1993.
)y h ' /
'llimes ti. TaY1or c, txecutive Director for Operations DISTRIBUTION:
Commissioners OGC OCIG OIG OPP EDO ASLDP SECY
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