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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
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
ML20248C6841998-03-30030 March 1998
Rev 1 to 09334281-01, RCS Internal Voltage Decay on Loss of A01/A02 4 Kv Bus
ML20140D7001997-05-0101 May 1997
Delay Times for Containment Spray & Containment Accident Fans for Containment Integrity Accident Analysis (Tscr 192)
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)
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
ML20134D2951996-12-27027 December 1996
Uncertainty Associated W/Instrumentation Used in IT-14 for Fuel Oil Transfer Pumps
ML20134D3811996-12-27027 December 1996
Uncertainty Associated W/Instrumentation Used in IT-17 & IT-18 for Bat Pumps
ML20134D3941996-12-27027 December 1996
Uncertainty Associated W/Instrumentation Use in IT-12 & IT-13 for CCW 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
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)
ML20116G5121996-07-31031 July 1996
Low & High Pressurizer Pressure Reactor Trip Instrument Uncertainty Calculation
ML20116B1571996-07-19019 July 1996
Svc Water Through Wall Flaw Evaluation
ML20115H3241996-07-0101 July 1996
Rev 1 to Evaluation of SI-860,SI-857 & RC-515/516 Bonnet Pressurization
ML20116C3471996-05-29029 May 1996
Press Release Re Explosion Rocks Nuclear Waste Silo at Point Beach Nuclear Plant
ML20115H3301996-02-0808 February 1996
Rev 0 to Verification of Pressure Locking Analysis Program Preslok
ML20058P1751993-09-0707 September 1993
Package Consisting of Attachment to Employee Concerns Programs
ML20086Q1211991-12-16016 December 1991
Audit Rept A-V-89-02, QA Audit Rept,Teledyne Isotopes Midwest Lab,Northbrook,Il 890208-09
ML20085M6101991-11-11011 November 1991
Response to NUMARC Survey Re Waste Mgt,Aquatic Resource & Socioeconomic Questions in Support of NRC License Renewal Rulemaking
ML20086U0791989-12-20020 December 1989
Pbnp Containment Tendon Prestress Acceptance Limits
ML20245J2691989-06-23023 June 1989
Rev 2 to Calculation AC-601R-2-R38, Evaluation of Pipe Support
IA-87-166, Partially Withheld Excerpt from NRC 870713 Operations Ctr Log Re Major Loss of Physical Security Effectiveness at Facility.Door W/O Guard Accessed by Central Alarm Security Sys Operator.Area Checked & No Adverse Consequences Noted1987-05-18018 May 1987
Partially Withheld Excerpt from NRC 870713 Operations Ctr Log Re Major Loss of Physical Security Effectiveness at Facility.Door W/O Guard Accessed by Central Alarm Security Sys Operator.Area Checked & No Adverse Consequences Noted
ML20216J0831987-05-18018 May 1987
Partially Withheld Excerpt from NRC 870713 Operations Ctr Log Re Major Loss of Physical Security Effectiveness at Facility.Door W/O Guard Accessed by Central Alarm Security Sys Operator.Area Checked & No Adverse Consequences Noted
ML20212Q9221987-03-17017 March 1987
Press Release Discussing Proposed $50,000 Fine Against Util for Violations of Security Requirements at Plant
ML20203H2851986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
ML20135H3531984-06-19019 June 1984
Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2
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
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
1997-01-09
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Text
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D U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenville Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT: RIII-96-71 December 2, 1996 CONTACT: Jan Strasma 630/829-9663 Angela Dauginas 630/829-9662 ,
E-mail: opa3@nrc. gov l SPECIAL NRC TEAM INSPECTION BEGINNING AT POINT BEACH NUCLEAR POWER STATION l
The Nuclear Regulatory Commission is conducting a special two-week team inspection to evaluate operational safety at the l Point Beach Nuclear Power Station. The plant, operated by '
Wisconsin Electric Power Co., is at Two Creeks, Wisconsin.
The inspection begins today (December 2), and will conclude Friday, December 13. The team will present its preliminary !
findings in a meeting with utility officials on Friday, December 20.
That meeting will be at 10 a.m. in the Two Creeks Town Hall, located at State Highway 42 and Tapawingo Road north of Two Rivers, Wisconsin. The meeting will be open to public observation.
The inspection was scheduled to provide a broad review of plant activities following problems earlier this year with control room operations and with the equipment testing program.
These issues were the subject of a predecisional enforcement conference between the NRC staff and the utility in September. A decision on the enforcement action is still pending.
The team inspection will include around-the-clock surveillance of routine activities in the plant's control room for several days. Inspectors will also review maintenance, testing, and engineering activities.
The 10-person team is headed by Melvyn Leach, Chief of the NRC's Region III Operator Licensing Branch. Steven Ray, Senior Resident Inspector at the Prairie Island Nuclear Power Station in Minnesota, is the assistant team leader.
Other team members include engineering and reactor operations specialists from the Region III office in Lisle, Illinois; another senior resident inspector and a resident inspector from other sites; and a human factors specialist from NRC Headquarters in Rockville, Maryland.
r 9612040048 961202 1
PDR PRESS R l RG-III-96-071 PDR
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