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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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U.S. NUCLEAR REGULATORY COMMISSION a Region III Office of Public Affairs j 801 Warrenville Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT: RIII-96-72 December 4, 1996 l l CONTACT: Jan Strasma 630/829-9663 '
i Angela Dauginas 630/829-9662 l E-mail: opa3@nrc. gov NRC STAFF PROPOSES $325,000 FINE AGAINST WISCONSIN ELECTRIC CO.
FOR VIOLATIONS OF NRC REQUIREMENTS AT POINT BEACH NUCLEAR PLANT The Nuclear Regulatory Commission staff has proposed a ,
$325,000 fine against Wisconsin Electric Power for violations of {
NRC safety requirements at the Point Beach Nuclear Power Station.
The plant is located at Two Creeks, Wisconsin.
"The issues we identified reflect significant weaknesses in the areas of operations, maintenance, and engineering...which involve all levels of your organization," said A. Bill Beach, NRC Regional Administrator in notifying the utility of the fine.
He continued, "While these issues are of significant regulatory concern, we are also concerned by-the inadequate l response (and sometimes lack of a response) by your staff to most of these issues."
J The company was cited: '1) for instances when reactor i operators were inattentive to their duties; (2) for starting up Point Beach Unit 2 in April with a safety system -- an auxiliary feedwater pump -- inoperable and for failing to adequately test i the plant's safety injection system; (3) for failing to take adequate steps to increase the minimum number of pumps required in the equipment cooling water system; and (4) for violations associated with the hydrogen burn in a spent fuel storage cask after it was loaded in May. (Additional details on the violations are attached.]
Fines of $100,000 each were proposed for the first three items. A-fine of $25,000 was proposed for the violations associated with the spent fuel storage cask.
Wisconsin Electric has until January 2 to pay the fine or to protest it. If the fine is protested and subsequently imposed by the NRC staff, the utility may request a hearing.
The NRC's letter to the utility and the Notices of Violation are available on the NRC's internet web site at:
<http://www.nrc. gov /OPA/ reports >.
9612050076 961204 POR PRESS R R 2 -I I I-96-072 PDR 050011 fitM o//
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I l ADDITIONAL DETAILS ON VIOLATIONS Point Beach Nuclear Power Station
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- 1. Control room inattentiveness l
! I j On July 15 an NRC inspector observed on-shift control room '
- . operators viewing a training videotape in the control room. On i July 31 an NRC inspector. observed a control room operator leave l i his watch station to get a cup of coffee without the required '
- short-term watch relief by another operator. On August 14 an NRC i inspector observed a control room operator fail to respond to a
- control board alarm until he was prompted by a senior reactor i operator. On August 14 the utility found that its on-duty Technical Adviser left the site in violation of NRC requirements
{ I i and that being offsite but nearby had been an accepted practice j for the past five years.
- 2. Auxiliary Feedwater System ooerability and Safety Iniection
! System testinq
! The utility started up Unit 2 in April with a safety system -- an j auxiliary feedwater pump -- inoperable. The pump provides water j to the plant's steam generators when the main feedwater pumps are ,
4 not available. Valves in the pump's discharge line had been left i closed following maintenance, and the utility did not conduct a l required post-maintenance test which would have found that the l valves remained closed, l i I j The' testing program to measure the discharge pressure of pumps in '
j the~ Safety Injection System did not have the correct pressure
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criterion and used gauges which where found to be out of ,
j calibration. The Safety Injection System is one of the plant's I j emergency reactor cooling systems. From December 1992 to July of 3 this year, _the gauges were found to be within their required j accuracy only once in 20 calibrations.
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- 3. Inadeauate Corrective Action -- Service Water Pumos j Wisconsin Electric did not take adequate corrective action after determining in April that it needed to increase the minimum
- number of service water system pumps required to be operable.
1 The service water system supplies cooling water to various plant
} equipment. There are six pumps in the system. The existing i requirement called for a minimum of two pumps, and the utility j did not take adequate steps to increase the minimum when it i determined that three would be needed in some accident conditions j to provide the desired flow and pressure.
i 4. Violations Associated with Dry Cask Soent Fuel Storace i On May 28 welding on a shield lid for a loaded spent fuel storage i cask ignited hydrogen gas which had accumulated under the lid.
j There was no apparent damage to the cask or the spent fuel, and 4
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there were no injuries. The hydrogen was generated by an unexpected chemical reaction between a zinc coating inside the cask and boric acid in water temporarily in the cask.
The company was cited for failing to determine the suitability of the zinc coating for use in the dry cask storage system and for failing to take proper action on earlier indications of a gas build up in the cask.
The company was also cited for failing to appropriately transfer the weight of the cask shield lid into several procedures and for inadequate safety evaluations of the rigging used to lift the cask shield lid and of the procedure to weigh the lid.
Attachment to News Announcement RIII-96-72 December 4, 1996 i
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