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Category:QUALITY ASSURANCE PROGRAM
MONTHYEARML20210A6361999-04-30030 April 1999
Rev 13 to Quality Assurance Program Description
ML20206J3751999-04-29029 April 1999
Rev 13 to QA Program Description
ML20196A9241998-07-31031 July 1998
Rev 12 to LACBWR QA Program Description (Qapd)
ML20237E2701998-07-31031 July 1998
Rev 12 to QA Program Description
ML20134M2531996-02-20020 February 1996
Revised Rev 11 to QA Program Description
ML20151B2351987-10-20020 October 1987
Revised Rev 5 to QA Program Description
ML20234C3931987-10-20020 October 1987
Rev 5 to QA Program Description
ML20212B2931986-10-29029 October 1986
Rev 4 to QA Program Description
ML20133C6781985-09-11011 September 1985
Rev 3 to QA Program Description
1999-04-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20210A6361999-04-30030 April 1999
Rev 13 to Quality Assurance Program Description
ML20206J3751999-04-29029 April 1999
Rev 13 to QA Program Description
ML20207A9591999-01-31031 January 1999
Revised LACBWR Decommissioning Plan
ML20196G0751998-12-31031 December 1998
1998 Annual Rept for Dairyland Power Cooperative
ML20204D8371998-12-31031 December 1998
Annual Rept for 1998 - Rept of Changes,Tests & Experiments for Lacbwr. with
ML20237E2701998-07-31031 July 1998
Rev 12 to QA Program Description
ML20196A9241998-07-31031 July 1998
Rev 12 to LACBWR QA Program Description (Qapd)
ML20202J0691998-01-31031 January 1998
Revised LACBWR Decommissioning Plan
ML20202J0781998-01-31031 January 1998
Revised LACBWR Initial Site Characterization Survey for Safstor
ML20203K0041997-12-31031 December 1997
Annual Operating Rept for 1997 - Rept of Changes,Tests & Experiments
ML20249B7101997-12-31031 December 1997
Navigating for Our Future Dairyland Power 1997 Annual Rept. W/O Ltr
ML20138B7771997-04-25025 April 1997
Corrected Page 8 of SE for Amend 69 to La Crosse Boiling Water Reactor License
ML20137R7731997-04-11011 April 1997
Safety Evaluation Approving Changes to QAP Description
ML20149K2071996-12-31031 December 1996
Conquering New Frontiers,Dairyland Power Cooperative 1996 Annual Rept
ML20135C3901996-12-31031 December 1996
Annual Rept for 1996 - Rept of Changes,Tests & Experiments
ML20132F8721996-10-31031 October 1996
Revised LACBWR Decommissioning Plan
ML20134M2531996-02-20020 February 1996
Revised Rev 11 to QA Program Description
ML18012A9001995-12-31031 December 1995
Annual Rept - 1995 of Changes,Tests & Experiments. W/ 960220 Ltr
ML18011B1461995-04-20020 April 1995
LER 95-001-00:on 950417,noted That HPSW to Containment Building Isolated.Caused by Momentary LOP Due to Operational Test of 1A Edg.Procedures for Test Being Modified to Include Instructions to Verify Value Being open.W/950420 Ltr
ML20056E2631993-08-10010 August 1993
LACBWR Containment Bldg Structural Analysis. W/One Oversize Drawing
ML20056E2621993-07-31031 July 1993
Nonproprietary Analysis of Potential Blast Effects on LACBWR Reactor Bldg Due to 16 Inch Natural Gas Pipeline Failure,Suppl Analysis for Fast Closing Valve
ML20127D3901993-01-13013 January 1993
SE Supporting Amend 67 to License DPR-45
ML20128K6011992-12-31031 December 1992
Corrected App a Re Std Format for Reporting Number of Personnel & man-rem by Work & Job Function,To Annual Rept for 1992 - Rept of Changes,Tests & Experiments
ML20128D3421992-12-31031 December 1992
LACBWR Annual Rept 1992
ML20062B4761990-09-30030 September 1990
Monthly Operating Rept for Sept 1990 for LACBWR
ML20248D0941989-08-31031 August 1989
Monthly Operating Rept for Aug 1989 for LACBWR
ML20245G6571989-07-31031 July 1989
Monthly Operating Rept for Jul 1989 for LACBWR
ML20245F9681989-06-30030 June 1989
Monthly Operating Rept for June 1989 for LACBWR
ML20245J7351989-04-26026 April 1989
Safety Evaluation Supporting Amend 65 to License DPR-45
ML20245F8241989-02-28028 February 1989
Monthly Operating Rept for Feb 1989 for La Crosse Bwr.W/
ML20235S2441989-02-16016 February 1989
Suppl to 880104 Special Rept Re Inoperability of High Pressure Svc Water Diesel 1B.Fuel Supplu Sys Was Source of Problem.Fuel Supply Sys Will Be Replaced W/Above Ground Tanks for Both Diesels
ML20245F7771989-01-31031 January 1989
Monthly Operating Rept for Jan 1989 for LACBWR
ML20246H8771988-12-31031 December 1988
1988 Dairyland Power Cooperative Annual Rept
ML20205T1271988-10-31031 October 1988
Monthly Operating Rept for Oct 1988 for La Crosse Bwr.W/
ML20151T0991988-08-0808 August 1988
Safety Evaluation Supporting Approval of Util Rev 10 to Emergency Plan
ML20150D7051988-07-0808 July 1988
Safety Evaluation Supporting Rev 10 to Emergency Plan
ML20155F9161988-05-31031 May 1988
Safety Evaluation Supporting Amend 62 to License DPR-45
ML20151G0591988-04-11011 April 1988
Safety Evaluation Supporting Amend 60 to Provisional License DPR-45
ML20148C3941988-03-15015 March 1988
Safety Evaluation Supporting Amend 59 to License DPR-45
ML20149G0711988-01-0404 January 1988
Safety Evaluation Supporting Amend 58 to License DPR-45
ML20147A9731987-12-31031 December 1987
Decommissioning Plan
ML20149J3441987-12-31031 December 1987
LACBWR Annual Rept 1987
ML20195D7811987-12-31031 December 1987
1987 Dairyland Power Cooperative Annual Rept
ML20237C6781987-11-30030 November 1987
Special Rept:On 871118,internal Portion of Fire Suppression Water Sys Removed from Svc to Replace Section of Piping.On 871120,piping Successfully Hydrostatically Tested & Fire Suppression Sys Returned to Svc
ML20236W2731987-11-23023 November 1987
Special Rept:On 871028,following Initiation of 24 H Run for 18-month Diesel Generator Test,Emergency Diesel Generator 1B Stopped Running.No Cause for Trip Determined.Procedure Will Be Revised So Alarm Conditions Tested Before Run
ML20236X0081987-11-18018 November 1987
Special Rept Re Inoperability of Fire Suppression Water Sys. Internal Portion of Sys Removed from Svc on 871118 to Replace Section of Piping.Initially Reported on 871118.Plant Permanently Shut Down & Reactor Defueled
ML20234C3931987-10-20020 October 1987
Rev 5 to QA Program Description
ML20151B2351987-10-20020 October 1987
Revised Rev 5 to QA Program Description
ML20235R0531987-09-30030 September 1987
Determination of Potential Radiological Consequences to Members of Public from Fuel Handling Accident at La Crosse Nuclear Facility
ML20235B5711987-09-15015 September 1987
Safety Evaluation Supporting Amend 57 to License DPR-45
1999-04-30
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Text
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0 4 DAIRYLAND POWER COOPERATIVE SECTION I REV. NO. 11 LACBWR ORGANIZATION I QUALITY ASSURANCE
! PROGRt'f DESCRIPTION DATE 02/20/96 PAGE 4 OF 8 t
5 (9) Review of the Contingency Plan, the Plant Security Plan, and implementing procedures.
(10) Review of the Emergency Plan and implementing procedures.
(11) Review the waste n.onagement process control program, which includes the transportation packaging program.
(12) Review of the Decommissioning Plan,
- h. The Operations Review Committee shalt:
(1) Recommend in writing to the Plant Manager approval or disapproval of items considered under f (1) through (4) above.
(2) Render determinations in writing with~ regard to whether or not each item considered under f (1) through (5) above constitutes an unreviewed safety question.
(3) Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the General 1 Manager and the SRC of disagreement between the ORC and I the Plant Manager; however, the Plant Manager shall have j responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.
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- i. The Operations Review Committee shall maintain written minutes of each ORC meeting that, at a minimum, document the results of all ORC activities performed under the responsibility and authority provisions. Copies shall be provided to the General Manager and the SRC.
- 7. The Safety Review Committee ir an advisory committee responsible to the General Manager for independent reviews and audits to verify that the facility is being maintained consistent with company safety, administrative, and licensing provisions.
- a. The Safety Review Committee shall function to provide independent review and audit of all aspects of plant nuclear safety.
- b. The SRC shall be composed of a Chairman and a minimum of three members who are appointed by either the Dairyland Power Cooperative (DPC) Genc.al Manager or the Assistant General m 9611220208 961105 PDR ADOCK 05000409 W PDR
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. ,- 1 DAIRYLAND POWER COOPERATIVE SECTION I REV. NO. 11 !
l LACBWR ORGANIZATION I QUALITY ASSURANCE PROGRAM DESCRIPTION DATE 02/20/96 PAGE 5 OF 8 l
Manager, Generation. The Chairman shall be appointed by the I General Manager. In addition, the Plant Manager is also a member )
of the SRC. SRC members appointed by the General Manager or 1 Assistant General Manager, Generation, shall not be members of I the plant staff.
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- c. All SRC alternate members shall be appointed in writing by the DPC l General Manager or Assistant General Manager, Generation, to i serve on a temporary basis; however, no more than two alternates i shall participate as voting members in SRC activities at any one time.
- d. Membership to the SRC requires that an individual meet one or more of the academic and/or experience reauirements listed below.
The majority of the SRC members shall moet the requirements of 7.d.(1).
(1) Bachelor Degree in Engineering or the physical sciences, plus five years' total experience in one or more of the below listed disciplines. 1 (2) Nine years' combined total experience in one or more of the below listed disciplines.
- Nuclear Power Plant Technology )
- Facility Operations
- Power Plant Design
- Engineering / Nuclear Engineering
- Radiation Safety
. Safety Analysis Instrumentation and Control
. Quality Assurance
- e. Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
- f. The SRC shall meet at least once per year, and as deemed necessary by the SRC Chairman or the Plant Manager.
- g. The minimum quorum of the SRC necessary for the performance of the SRC review and audit functions shall consist of the Chairman, or his designated alternate, and at least three SRC members, including litternates.
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