|
|---|
Category:ARCHIVE RECORDS
MONTHYEARML20216J6041999-09-23023 September 1999
Evaluation of New Surveillance Data on Chemistry Factor for Weld Wire Heat 61782,Point Beach Unit 1
ML20198A9011998-11-23023 November 1998
Rev 1 to Calculation PBNP-IC-33, 4.16KV Rt UV Matrix Relays Uncertainty/Setpoint Calculation
ML20196F2321998-11-21021 November 1998
Rev 0 to NSP-31Q-302, Evaluation of Limiting Flaws for Structural Adequacy on Lower Full Length CRDM Canopy Seal Weld
ML20154J2731998-10-0202 October 1998
Audit Rept on Implementation of GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants, on 980915-17
ML20154B8101998-09-23023 September 1998
Rev 0 to 98-0132, Evaluation of 23.6 EFPY P-T Limit & LTOP Applicability Date & Pressurized Thermal Shock at 32 Efpy
ML20236L2781998-07-0606 July 1998
Rev 0 to Calculation ENG-ME-170, Flooding of Unit 2 Loop a Msn Actuation Equipment
ML20249C0121998-06-22022 June 1998
Audit Rept Commitment Mgt Southern Nuclear Operating Co Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20206S1181998-05-11011 May 1998
Rev 2 to NSP-21Q-302, Charpy V-Notch (Cvn) Test Data Files for Monticello RPV Plates,Curve Fits of Cvn Data & Calculation of Plant Specific Chemistry Factors
ML20216H4021998-04-0707 April 1998
Rev 5 to 98-106, Evaluation for LOCA Aging at 1880 Mwt
ML20206S1331998-04-0606 April 1998
Rev 1 to NSP-21Q-304, Pressure Test,Non-Critical Core Operation & Critical Core Operation P-T Curve Development
ML20249C5241998-04-0303 April 1998
Rev 2 to Calculation 96C2913-C016, HP & LP Turbine Condenser Anchorage Capacity Evaluations
ML20248C6841998-03-30030 March 1998
Rev 1 to 09334281-01, RCS Internal Voltage Decay on Loss of A01/A02 4 Kv Bus
ML20217D2451998-03-17017 March 1998
Rev 0 to ENG-ME-355, Intake Canal Available Water Volume Comparison Analysis
ML20202F8931998-02-12012 February 1998
Rev 0 to SIC-98-009, Evaluation of Limiting Flaws for Structural Adequacy in CRDM Repair Adapter Plug Fillet Weld Evaluation at Prairie Island Unit 2
ML20205Q0041998-02-12012 February 1998
Rev 00 to NSP-27Q-301, CRDM Repair Adapter Plug Fillet Weld Evaluation
ML20217D2001998-02-0606 February 1998
Rev 0 to ENG-ME-347, Min Required Intake Bay Volume
ML20199J2281998-01-29029 January 1998
Rev 1 to Calculation NSP-26Q-302, Evaluation of Limiting Flaws for Structural Adequacy in Canopy Seal Repairs at Prairie Island Nuclear Plant
ML20249C5211998-01-13013 January 1998
Rev 0 to Calculation 96C2913-C20, Monticello Unit 1 Limited Analysis for Baseplate Qualification,Computer Analysis & Hand Calculations
ML20199G9951997-12-19019 December 1997
Rev 0 to Calculation 97C2999-C-001, T-44 Seismic Displacement Evaluation
ML20236L9931997-09-0404 September 1997
Rev 1 to SMNH-97-008, Unit 1 Core Spray NPSH Margin Calculation. W/Two Oversize Drawings
ML20236L9901997-09-0404 September 1997
Rev 1 to SMNH-97-007, Unit 1 RHR Pump NPSH Margin Calculation
ML20198H3261997-07-29029 July 1997
Rev 0 to FAI/97-88, Verification Experiments for Waterhammer Events in Power Plant Svc Water Sys
ML20198H3771997-07-28028 July 1997
Rev 0 to FAI/97-68, Prairie Island Fan Coil Unit Analysis Using Tremolo 1.01. W/30 Oversize Drawings
ML20149J4351997-06-30030 June 1997
Event Tracking Sheet of 950123 Event Re Failure of 10 Inch Valve at Weld Joining & Adapter Plate & More Catastrophic Failure to Other Parts Due to Inclusion of Shims Contrary to Drawing
ML20149J4871997-06-30030 June 1997
Event Tracking Sheet of 960408 Event Re Crane Valves. Provides Update on Continuing Efforts to Evaluate Whether Erroneous Data to Set Torque Switches for MOVs Supplied to Licensees During mid-1980s.No Contractural Evidence Found
ML20141B9341997-06-18018 June 1997
Rev 0 to Calculation V75100.NSP97.00501, Determination of Containment Overpressure Required for Adequate NPSH of Low Pressure ECCS Pumps
ML20249C5221997-06-10010 June 1997
Rev 0 to Calculation 96C2913-C015, Gang Hangar Support
ML20140D7001997-05-0101 May 1997
Delay Times for Containment Spray & Containment Accident Fans for Containment Integrity Accident Analysis (Tscr 192)
ML20210U3261997-04-23023 April 1997
Rev 0 to FAI/96-107, Experimental Data to Simulate Possible Water-Hammer Loads in Prairie Island Svc Water Sys for DBA Conditions
ML20148S6531997-04-0808 April 1997
RHR Room Temp Response to GE Ltrs GLN-97-017 & GLN-97-019, Rev 0
ML20134C2491997-01-24024 January 1997
Determination of Pbnp LTOP Setpoint Using ASME Code Case N-514 (Applicable Through Appx. Jan 2001)
ML20133M5921997-01-22022 January 1997
Press Release III-97-06, NRC Meetings W/Wi Electric Planned for 970124 & 31 on Recent Insp Findings & Point Beach Unit 2 Startup
ML20133E2341997-01-0909 January 1997
Press Release III-97-03, NRC Staff Postpones Meeting W/ Wiep to Discuss Recent Insp Findings & Point Beach 2 Startup Activities
ML20133L1191997-01-0303 January 1997
Determination of Pbnp LTOP Setpoint Using ASME Code Case N-514 (Applicable Through Appx Jan 2001)
ML20136B5431997-01-0202 January 1997
Low Pressure ECCS Net Positive Suction Head
ML20133B1781997-01-0202 January 1997
Press Release III-97-01, NRC Staff to Meet W/Wisconsin to Discuss Recent Insp Findings & Point Beach 2 Startup Activities
ML20134D3941996-12-27027 December 1996
Uncertainty Associated W/Instrumentation Use in IT-12 & IT-13 for CCW Pumps
ML20134D3811996-12-27027 December 1996
Uncertainty Associated W/Instrumentation Used in IT-17 & IT-18 for Bat Pumps
ML20134D2951996-12-27027 December 1996
Uncertainty Associated W/Instrumentation Used in IT-14 for Fuel Oil Transfer Pumps
ML20134D3731996-12-20020 December 1996
Uncertainty Associated W/Instrumentation Used in IT-21 & IT-22 for Charging Pumps
ML20134D3311996-12-18018 December 1996
Instrument Uncertainty Associated W/Flow Instrumentation Used for IT-15 Chill Water Pumps Inservice Test
ML20132C0551996-12-17017 December 1996
Press Release III-96-73, Postponement of Meeting to Discuss Preliminary Findings of NRC Team Insp at Point Beach Nuclear Plant
ML20134D4011996-12-12012 December 1996
Instrument Uncertainty Associated W/Flow Instrumentation Used for IT-11 SFP Cooling Pump Inservice Test
ML20135B6151996-12-0404 December 1996
Press Release III-96-072, NRC Staff Proposes $325,000 Fine Against Wisconsin Electric Co for Violations of NRC Requirements at Point Beach Nuclear Plant
ML20135A7991996-12-0202 December 1996
Press Release III-96-71, Special NRC Team Insp Beginning at Point Beach Nuclear Power Station
ML20198H3381996-10-31031 October 1996
Evaluation of Possible Water-Hammer Loads in Prairie Island Svc Water Sys for DBA Conditions
ML20134D2231996-10-17017 October 1996
Press Release III-96-63, Aerial Radiation Measurements Planned for NPPs in Wisconsin & Minnesota
ML20129F8191996-09-26026 September 1996
Rev 0 to SG Replacement Rept
ML20129F8431996-09-17017 September 1996
Rev 0 to SG Narrow Range Level Instrument Uncertainty & Setpoint Calculation
ML20129C0891996-09-16016 September 1996
Rev 1 to Determination of Pbnp LTOP Setpoint Through an Inside Surface Fluence of 2.05x10 19m/cm (Appx Jan 2001)
1999-09-23
[Table view]
Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20133M5921997-01-22022 January 1997
Press Release III-97-06, NRC Meetings W/Wi Electric Planned for 970124 & 31 on Recent Insp Findings & Point Beach Unit 2 Startup
ML20133E2341997-01-0909 January 1997
Press Release III-97-03, NRC Staff Postpones Meeting W/ Wiep to Discuss Recent Insp Findings & Point Beach 2 Startup Activities
ML20133B1781997-01-0202 January 1997
Press Release III-97-01, NRC Staff to Meet W/Wisconsin to Discuss Recent Insp Findings & Point Beach 2 Startup Activities
ML20132C0551996-12-17017 December 1996
Press Release III-96-73, Postponement of Meeting to Discuss Preliminary Findings of NRC Team Insp at Point Beach Nuclear Plant
ML20135B6151996-12-0404 December 1996
Press Release III-96-072, NRC Staff Proposes $325,000 Fine Against Wisconsin Electric Co for Violations of NRC Requirements at Point Beach Nuclear Plant
ML20135A7991996-12-0202 December 1996
Press Release III-96-71, Special NRC Team Insp Beginning at Point Beach Nuclear Power Station
ML20134D2231996-10-17017 October 1996
Press Release III-96-63, Aerial Radiation Measurements Planned for NPPs in Wisconsin & Minnesota
ML20116C3471996-05-29029 May 1996
Press Release Re Explosion Rocks Nuclear Waste Silo at Point Beach Nuclear Plant
ML20212Q9221987-03-17017 March 1987
Press Release Discussing Proposed $50,000 Fine Against Util for Violations of Security Requirements at Plant
ML20002E1071981-01-20020 January 1981
Press Release Requesting Comment by Persons in Two Creeks, Manitowoc County,Wi Affected by Purchase & Installation of Spare Steam Generators at Facility
ML20127N9251970-01-16016 January 1970
Press Release Discussing Util Intention to Seek License to Operate Plant.Acrs Rept Encl
1997-01-09
[Table view] |
Text
_..
U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenville Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT:
RIII-96-63 October 17, 1996 CONTACT: Jan Strasma 630/829-9663 Angela Dauginas 630/829-9662 E-mail:
opa3@nrc. gov 4
AERIAL RADIATION MEASUREMENTS PLANNED l
FOR NUCLEAR POWER PLANTS IN WISCONSIN AND MINNESOTA A blue-and-white helicopter, flying at low altitudes, will conduct routine background radiation surveys for the Nuclear Regulatory Commission near four nuclear power stations in Wisconsin and Minnesota.
The surveys are part of an ongoing NRC program to monitor radiation levels around facilities producing, using, or storing radioactive materials.
The surveys are performed by Bechtel Nevada, a Department of Energy contractor 4
in Las Vegas, Nevada.
The helicopter surveys will be performed in the area of the Kewaunee and Point Beach Nuclear Power Stations north of Two Rivers Wisconsin: at the Prairie Island Nuclear Power Station near Red Wing, Minnesota: and at the Monticello Nuclear Power Station in Monticello, Minnesota.
The tentative schedule for the Wisconsin survey is to begin setup activities on Friday (October 18) with the survey to be performed over the next several days.
The Prairie Island survey will begin about October 26 with the Monticello survey to follow, beginning about October 29.
The actual survey schedules will depend on weather conditions.
The surveys are performed at several commercial nuclear power stations each year.
They include the plant site itself and about a 10-square mile area around the plant.
Nuclear Regulatory Commission news announcements are issued by fax and by internet e-mail.
If you wish to receive Region III news releases by e-mail, send a message to opa3@nrc. gov. To receive news announcements issued by NRC Headquarters and all NRC regional offices by e-mail, send an e-mail message to listproc@nrc. gov with the message: subscribe pr-opa followed by your name. A weekly printed summary of news releases is available by writing Office of Public Affairs. Nuclear Regulatory Commission Washington DC 20555.
News releases are also available on the NRC's internet web site at the address: <http://www nrc gov /0PA>
961018o096 961017
)
ph
-III O
N oh r'-T' r't
+
W N
