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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20138B7771997-04-25025 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 ML20127D3901993-01-13013 January 1993 SE Supporting Amend 67 to License DPR-45 ML20245J7351989-04-26026 April 1989 Safety Evaluation Supporting Amend 65 to License DPR-45 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 ML20235B5711987-09-15015 September 1987 Safety Evaluation Supporting Amend 57 to License DPR-45 ML20206G6421987-04-0808 April 1987 Safety Evaluation Supporting Amend 55 to License DPR-45 ML20214N3921986-09-10010 September 1986 Safety Evaluation Supporting Amend 54 to License DPR-45 ML20209E9241986-09-0505 September 1986 Safety Evaluation Rept Supporting Amend 53 to License DPR-45.Neither EIS Nor Environ Assessment Necessary ML20209D9681986-09-0202 September 1986 Safety Evaluation Supporting Amend 52 to License DPR-45 ML20212N6121986-08-22022 August 1986 Safety Evaluation of Util 840530 Response to Generic Ltr 84-11, Insp of BWR Stainless Steel Piping. Response Did Not Meet Requirements NUREG-0827, Safety Evaluation Supporting Proposed Installation of remotely-operated Solenoid in Pipe Tunnel Outside Containment for Offgas Vent Line1986-08-0606 August 1986 Safety Evaluation Supporting Proposed Installation of remotely-operated Solenoid in Pipe Tunnel Outside Containment for Offgas Vent Line ML20204J2601986-07-30030 July 1986 Safety Evaluation Supporting Amend 51 to License DPR-45 ML20203H3161986-07-15015 July 1986 Safety Evaluation Supporting Amend 50 to License DPR-45 ML20207G2791986-07-15015 July 1986 Safety Evaluation Supporting Amend 49 to License DPR-45 ML20199K3891986-06-26026 June 1986 Safety Evaluation Supporting Exemption from Certain Requirements of 10CFR50.54(w) Re Primary Onsite Property Damage ML20141F4271986-04-14014 April 1986 Safety Evaluation Supporting Amend 48 to License DPR-45 ML20141D6331986-03-31031 March 1986 Safety Evaluation Denying 821029 Request for Amend to License DPR-45,eliminating Four Type B Tests ML20154S4771986-03-27027 March 1986 Safety Evaluation Supporting Amend 47 to License DPR-45 ML20140F3571986-03-25025 March 1986 Safety Evaluation Supporting Amend 46 to License DPR-45 ML20140D7311986-03-20020 March 1986 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Testing IR 05000409/19840091986-03-10010 March 1986 Safety Evaluation Supporting Util 850208 Proposed Installation of Two Check Valves in Series in Sample Line to Improve Capability to Isolate Containment Atmosphere from Environ,Per Insp Rept 50-409/84-09 ML20141F9831986-01-0606 January 1986 Safety Evaluation Supporting Amend 45 to License DPR-45 ML20133F6491985-10-0808 October 1985 Safety Evaluation Supporting Amend 44 to License DPR-45 ML20205B7701985-09-0606 September 1985 SER Supporting Stability of Containment & Stacks Under Flood Conditions ML20126E5121985-06-0707 June 1985 Safety Evaluation Supporting Amend 43 to License DPR-45 ML20125D2041985-06-0505 June 1985 Safety Evaluation Supporting Amend 42 to License DPR-45 ML20138K0751984-12-12012 December 1984 Safety Evaluation on 831025 & 850918 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program & Procedures. Program & Procedures Acceptable ML20062D9761982-07-30030 July 1982 Safety Evaluation Supporting Amend 29 to License DPR-45 ML20062B9961978-10-11011 October 1978 Safety Evaluation Supporting Amend 14 to License DPR-45 1997-04-25
[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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SAFETY EVALUATION RY THE OFFICE OF NUCLEAR REACTOR REGillATION SUPPORTING AMENDMENT NO. 55 TO PROVISIONAL OPERATING LICENSE NO. DPR-45 DAIRYLAND POWER COOPERATTVE LA CROSSE BOTLING WATER REACTOR (LAC 8WR1
! DOCKET NO. 50-409 i
1.0 INTRODUCTION
By application dated March 20, 1984, and modified by letter dated August 24, 1984, Dairyland Power Cooperative (DPCI (the licenseel requested a change to Provisional Operatino License No. DPR-45 of the la Crosse Boiling Water Reactor (LAC 8WRI.
This amendment would incorporate the reporting requirements of 10 CFR 50.73 and would also add details on the reouirements of the report to be submitted to the NRC on each failure of a diesel generator. Th'roughout the Technical Specifications (TS) references to Reportable Occurrences would be changed to reflect the terminology and reporting requirements of 10 CFR 50.73. There are changes to the Definitions section, Action Statennts Surveillance Requirements, and Administrative Controls of the LACnWR Appendix A TS.
7.0 EVALUATION In Generic letter (GL) 83-43, dated December 19, 1983, the Commission stated that Section 50.7? of Title 10 of the Code of the Federal Regula-tions was revised and a new Section 50.73 was added, effective January 1, 1984 Section 50.72 revises the immediate notification requirement for operating nuclear power reactors and Section 50.73 provides for a revised License Event Report System.
The Comission requested licensees to propose revisions to the "Adminis-trative Controls" and " Definitions" sections of th ir plant's TS to implement the 50.73 requiation changes. The Commission also stated that there may be other changes to the TS reouired to reflect the revised reporting requirements (e.g., TS requiring a Licensee Event Report instead of a Special Reporti.
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8704150072 870408 PDR ADOCK 05000409 P PDR k_.
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The licensee proposed to add the following definition to Section 4.0.1, Definitions: Reportable Event, a REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. A Licensee Event Report shall be submitted for REPORTABLE EVENTS. The first sentence of the licensee proposed definition is the NRC recomended definition. Since the second sentence is accurate and provides continuity for the use of the term " Licensee Event Report," this definition is acceptable to the staff.
The Commission requested in Generic Letter 83-43 that the licensee revise the responsibilities of the Unit Review Group and Company and Puclear >
Review and Audit Group to include review of all Reportable Events. The licensee proposed to revise the responsibilities of its respective ,
, Operations Review Comittee and Safety Review Comittee to do this.
The Comission requested in GL 83-43 that the licensee revise TS Section l 6.6, Reportable Event Action, to implement the regulation changes to 10 CFR 50.73. The licensee proposed words which are consistent with guidance in GL 83-43 for this section.
The Comission requested in GL 83-43 that the licensee delete the TS '
Section on Reportable Occurrences, with its references to prompt notification with written followup and thirty-day written reports. .The licensee has proposed to delete this section.
The Comission requested in GL P3-43 that TS Section 6.10.1, Record Retention, item c, be revised to state "All Reportable Events." This was requested to maintain the new nomencisture of Reportable Events of 10 CFR 50.72 and 50.73 throughout the TS. The licensee proposed to revise the item accordingly.
The licensee also r.-: posed changes to other sections to reflect the terminology and reporting requirements of 10 CFR 50.73, as requested by Generic letter 83 43. The sections modified were: 4.2.2.22, 4.2.17, 4.2.18.1, 4 4.2.18.2, 4.2.18.3, 4.2.18.5, 5.2.10.1.4, 4.2.21 and Bases 4/5.2.18. These l chances are acceptable to the staff as they implement the request of the l Generic Letter.
j One of the affected sections was 5.7.10.1.4 on diesel generator failure reports. The licensee's existing wording did not correctly identify the ,
i basis for the reporting requirement. The licensee submitted a proposed a revision to 5.2.10.1.4 in its August 24, 1984 letter which included this
! information. The staff finds the wording in the August 24, 1984 submittal j to be acceptable.
In submitting a change to Section 4.2 21, Emergency Service Water Supply System..due to Generic Letter 83-43, the licensee also clarified wording in the Limiting Condition for Operation (LCO). The wording change was minor, but better reflects the actual system and how it is described in the Bases. The staff finds this minor word change acceptable.
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Based on the above, the staff concludes the changes proposed by the licensee to implement the 50.73 regulation changes are acceptable. The addition of detail in the report requirements for diesel generator failures and the minor wording change in the Emergency Service Water Supply System LCO are also acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes recordkeeping, reporting, and administrative procedures. The Comission has previously published a proposed finding that this amendment involves no significant hazards consideration and there has been no pubite comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in the 10 CFR 51.22(c)(101 Pursuant to 10 CFR 51.?2(b) no environmental impact statement nor environ-mental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security nor to the health and safety of the public.
5.0 ACKNOWLEDGEMENT This evaluation was prepared by John Stang and Roby Bevan.
Dated: April 8, 1987
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