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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20198K6611998-12-24024 December 1998 Safety Evaluation Supporting Amend 120 to License DPR-6 ML20154E0371998-09-30030 September 1998 Safety Evaluation Accepting Request for Exemption from Certain Portions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities & Reduce Scope of Onsite EP as Result of Permanently Shutdown ML20154E0581998-09-30030 September 1998 Safety Evaluation Accepting Licensee Request from Exemption from Certain Portions of 10CFR50.47(b) ML20198K0091998-09-18018 September 1998 SER Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Big Rock Nuclear Plant ML20216K0011998-04-16016 April 1998 Safety Evaluation Approving Licensee Request Re Plant Training Program for Certified Fuel Handlers ML20141J8731997-08-14014 August 1997 Safety Evaluation Supporting Amend 119 to License DPR-6 ML20137X0161997-04-18018 April 1997 Safety Evaluation Accepting Changes to Rev 17 of CPC Quality Program Description for Operational NPPs (CPC-2A) ML20137J9381997-04-0202 April 1997 Safety Evaluation Supporting Amend 118 to License DPR-6 ML20058F3441993-11-22022 November 1993 Safety Evaluation Concurring W/Contractor Findings Presented in Technical Evaluation Rept EGG-RTAP-10816, Evaluation of Utility Responses to Suppl 1 to NRC Bulletin 90-01;Big Rock Point ML20058A1601993-11-15015 November 1993 Safety Evaluation Supporting Amend 112 to License DPR-6 ML20057E1981993-10-0505 October 1993 Safety Evaluation Supporting Amend 111 to License DPR-6 ML20056E1661993-08-16016 August 1993 Safety Evaluation Supporting Amend 110 to License DPR-6 ML20128C9621992-11-27027 November 1992 Safety Evaluation Accepting Response to Suppl 1 to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20059H6051990-09-11011 September 1990 Safety Evaluation Approving Util 891229 Application for Disposal of Discharge Canal Dredging Spoils at Site ML20059F2581990-08-31031 August 1990 Safety Evaluation Approving Licensee Proposal to Dispose of Discharge Canal Dredgings Onsite in Manner Described in Util ML20246D2391989-08-16016 August 1989 Safety Evaluation Supporting Amend 100 to License DPR-6 ML20245G5211989-08-10010 August 1989 SER Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Domestic Operating Reactors NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-61989-07-31031 July 1989 Safety Evaluation Supporting Amend 99 to License DPR-6 ML20245H8421989-07-28028 July 1989 Safety Evaluation Supporting Amend 98 to License DPR-06 ML20248C0621989-05-31031 May 1989 Safety Evaluation Supporting Amend 97 to License DPR-6 ML20246L8251989-05-0202 May 1989 Safety Evaluation Supporting Amend 96 to License DPR-6 ML20245F8391989-04-14014 April 1989 Safety Evaluation Supporting Amend 95 to License DPR-6 ML20235J0251989-02-15015 February 1989 Safety Evaluation Supporting Amend 94 to License DPR-6 ML20205T5911988-11-0404 November 1988 Safety Evaluation Supporting Requested Relief from Inservice Testing Requirements ML20205S1271988-10-14014 October 1988 Safety Evaluation Supporting Amend 93 to License DPR-6 ML20154G1131988-09-14014 September 1988 Safety Evaluation Supporting Amend 92 to License DPR-6 ML20154C1381988-09-0707 September 1988 Revised Safety Evaluation Accepting Continued Use of Hafnium Hybrid Control Blade & Proposed Surveillance Program ML20155F3511988-06-0606 June 1988 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification ML20154H4051988-05-17017 May 1988 Safety Evaluation Supporting Continued Use of Present Six Nucom Rods,Insertion of Two Similar Rods for Cycle 23 & Use of Surveillance Program ML20154H5341988-05-17017 May 1988 Safety Evaluation Supporting Amend 90 to License DPR-6 ML20154J1981988-05-17017 May 1988 Safety Evaluation Supporting Amend 91 to License DPR-6 ML20211P1411987-02-19019 February 1987 Safety Evaluation Supporting Issuance of Amend 89 to License DPR-6 ML20211N5401987-02-17017 February 1987 Safety Evaluation Supporting Issuance of Amend 88 to License DPR-6 ML20207S1681987-02-12012 February 1987 Safety Evaluation Concluding That Portions of Util 861205 Application to Amend License DPR-6,revising Tech Spec Section 5.2.1,Tables 1 & 2 Re Defining Operating Limits for New Reload I-2 Fuel Unacceptable ML20209H0651987-01-28028 January 1987 Safety Evaluation Supporting Amend 87 to License DPR-6 ML20212L9441987-01-16016 January 1987 Safety Evaluation Supporting Original Exemption from 10CFR50,App R Requirements Re Oil Collection Sys to Be Installed on Recirculation Pumps ML20198A3911986-05-12012 May 1986 Safety Evaluation Supporting Amend 85 to License DPR-6 ML20210P1761986-05-0606 May 1986 Safety Evaluation Supporting Amend 84 to License DPR-6 ML20155D7161986-04-11011 April 1986 Safety Evaluation Supporting Util 840730 Proposed Amend to License DPR-6,changing Tech Specs to Add Definition for Reportable Event & to Delete Specific Reporting Requirements Included in 10CFR50.72 & 50.73 ML20141N6571986-03-10010 March 1986 Safety Evaluation Supporting Amend 83 to License DPR-6 ML20154A1011986-02-12012 February 1986 Safety Evaluation Supporting Amend 82 to License DPR-6 ML20138K8001985-12-12012 December 1985 Safety Evaluation Supporting Util 850410 Request for Relief from Inservice Testing Requirements for Valves in Feedwater & Reactor Depressurization Nitrogen Backup Sys ML20136D1451985-11-19019 November 1985 Safety Evaluation Re Response to Generic Ltr 83-28,Items 3.1.1-3,3.2.1-3 & 4.5.1 Concerning post-maint & Reactor Trip Sys Functional Testing.Response Acceptable ML20138R2071985-11-15015 November 1985 Safety Evaluation Re Environ Qualification of Electric Equipment Important to Safety.Util Program Complies w/10CFR50.49 & Resolution of 830426 SER & Technical Evaluation Rept Acceptable ML20209J2401985-11-0505 November 1985 Safety Evaluation Supporting Util 831107 & 850816 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review Program & Description ML20198A9621985-11-0101 November 1985 Safety Evaluation Supporting Request for Relief from Inservice Insp Requirements ML20205F6051985-11-0101 November 1985 Safety Evaluation Supporting Amend 81 to License DPR-6 ML20205E9721985-10-29029 October 1985 Safety Evaluation Supporting Amend 80 to License DPR-6 ML20133N3931985-10-22022 October 1985 Safety Evaluation Supporting Amend 79 to License DPR-6 ML20137W3231985-10-0202 October 1985 Safety Evaluation Supporting Amend 78 to License DPR-6 1998-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C3031999-09-28028 September 1999 Annual Rept of Facility Changes,Tests & Experiments ML20199A6621999-01-0505 January 1999 Special Rept:On 981230,hi Range Noble Gas Monitor Was Inoperable for Greater than Seven Days.Cause Unknown. Preplanned Alternate Method of Monitoring Appropriate Parameters within 72 H Was Established ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML20198K6611998-12-24024 December 1998 Safety Evaluation Supporting Amend 120 to License DPR-6 ML20154E0371998-09-30030 September 1998 Safety Evaluation Accepting Request for Exemption from Certain Portions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities & Reduce Scope of Onsite EP as Result of Permanently Shutdown ML20154E0581998-09-30030 September 1998 Safety Evaluation Accepting Licensee Request from Exemption from Certain Portions of 10CFR50.47(b) ML20198K0091998-09-18018 September 1998 SER Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Big Rock Nuclear Plant ML20217N2131998-04-24024 April 1998 Brpnp Zircaloy Oxidation Analysis ML20216K0011998-04-16016 April 1998 Safety Evaluation Approving Licensee Request Re Plant Training Program for Certified Fuel Handlers ML20217H4641998-03-26026 March 1998 Rev 2 to Post Shutdown Decommissioning Activities Rept (Psdar) ML20202G1941998-02-12012 February 1998 Rev 7 to Updated Final Hazards Summary Rept for Big Rock Point Plant ML20154A7591997-10-0808 October 1997 10CFR50.59 Annual Rept of Facility Changes,Tests & Experiments, Since 971008 ML20216E4731997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Big Rock Point Plant ML20141J8731997-08-14014 August 1997 Safety Evaluation Supporting Amend 119 to License DPR-6 ML20210H5601997-07-31031 July 1997 Monthly Operating Rept for July 1997 for Brpnp ML20148T4901997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Big Rock Point Nuclear Plant ML20148N9251997-06-0606 June 1997 Rev 18 to CPC-2A, Quality Program Description for Operational Nuclear Plants ML20140C8981997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Big Rock Nuclear Power Plant ML20138J0121997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Big Rock Point ML20137X0161997-04-18018 April 1997 Safety Evaluation Accepting Changes to Rev 17 of CPC Quality Program Description for Operational NPPs (CPC-2A) ML20137J9381997-04-0202 April 1997 Safety Evaluation Supporting Amend 118 to License DPR-6 ML20137P0391997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Big Rock Point Nuclear Plant ML20135F2361997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Big Rock Nuclear Plant ML20148N9181997-02-0101 February 1997 Rev 17 to CPC-2A, Quality Program Description for Operational Nuclear Plants ML20134H3691997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Big Rock Point Nuclear Plant ML20137F2101996-12-31031 December 1996 1996 Annual Financial Rept CMS Energy ML20133C5421996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Big Rock Point Nuclear Plant ML20135E5101996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Big Rock Point Nuclear Plant ML20134H3381996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Big Rock Point Nuclear Plant ML20211N1561996-10-0808 October 1996 Annual Rept of Facility Changes,Tests & Experiments, Consisting of Mods & Miscellaneous Changes Performed Since 961008 ML20128F9821996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Big Rock Point Nuclear Plant ML20059E8321993-12-31031 December 1993 Monthly Operating Rept for Dec 1993 for Big Rock Point Nuclear Plant ML20058K0931993-11-30030 November 1993 Monthly Operating Rept for Nov 1993 for Big Rock Point Nuclear Plant ML20058E8961993-11-29029 November 1993 1993 ISI Rept 3-1 Big Rock Point Plant, for 930626-0905 ML20058F3441993-11-22022 November 1993 Safety Evaluation Concurring W/Contractor Findings Presented in Technical Evaluation Rept EGG-RTAP-10816, Evaluation of Utility Responses to Suppl 1 to NRC Bulletin 90-01;Big Rock Point ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20058A1601993-11-15015 November 1993 Safety Evaluation Supporting Amend 112 to License DPR-6 ML20059J4531993-10-31031 October 1993 Monthly Operating Rept for Oct 1993 for Big Rock Point Nuclear Plant ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20057E1981993-10-0505 October 1993 Safety Evaluation Supporting Amend 111 to License DPR-6 ML20057E8341993-09-30030 September 1993 Monthly Operating Rept for Sept 1993 for Big Rock Point Nuclear Plant ML20056G9171993-08-31031 August 1993 Monthly Operating Rept for Aug 1993 for Big Rock Point Nuclear Plant ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20056E1661993-08-16016 August 1993 Safety Evaluation Supporting Amend 110 to License DPR-6 ML18058B8821993-06-15015 June 1993 Rev 13 to Quality Program Description for Operational Nuclear Power Plants. ML20128P5501993-02-18018 February 1993 Section 2.5 of Big Rock Point Updated Final Hazards Summary Rept ML20128F3511993-01-31031 January 1993 Monthly Operating Rept for Jan 1993 for Big Rock Point Nuclear Plant ML20128C4341993-01-29029 January 1993 Forwards Rev 3 to Updated Final Hazards Summary Rept ML20058L8721992-12-31031 December 1992 1992 Annual Rept,Cpc ML20127K8941992-12-31031 December 1992 Revised Pages to Graybook Rept for Dec 1992 for Big Rock Point Nuclear Plant 1999-09-28
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4 001 l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGUL ATION l
l REGARDING CERTIFIED FUEL HANDLER TRAINING PROGRAM l CONSUMERS ENERGY COMPANY l
l FOR BIG ROCK POINT NUCLEAR PLANT
! DOCKET NO. 50-155 l i I
l
1.0 INTRODUCTION
l By letter dated September 19,1997, Consumers Energy Company (Consumers or licensee) requested amendment to Facility Operating License DPR-6 and Appendix A, Technical l
Specifications, of DPR-6 to reflect the permanc.itly shutdown and defueled condition of the
! Big Rock Point (BRP) Nuclear Plant. Within this submittal, Consumers included their l proposed " Training Program for Certified Fuel Handlers." Nuclear Regulatory Commission (NRC) staff approval of CFH training programs is required in accordance with 10 CFR 50.2.
NRC staff review and approval of the licensee's request for amendment of DPR-6 and associated technical specifications continues.
2.0 BACKGMOUND By letter dated June 28,1997, Consumers certified to the NRC their intentione to permanently cease power operations at BRP on August 30,1997. On August 29,1997, Consumers permanently shut down the BRP plant. By letter dated September 19,1997, Consumers requested amendment to Facility Operating License DPR-6 and Appendix A, Technical Specifications, of DPR-6 to reflect the permanently shutdown and defueled condition of the BRP facility. Within this submittal, Consumers included their proposed
" Training Program for Certified Fuel Hand:ers," wisich consisted of two main parts: initial certification training and recertification training. The proposed CFH program described, in part, the training, testing, program administration, and certification requirements for CFHs at the BRP facility. The licensee's proposed amendment to technical specifications includes, in part, changes to operator licensing and staffing requirements. This license amendment is still undergoing NRC staff review.
On September 23,1997, Consumers certified, in accordance with 10 CFR 50.82(a)(1)(ii),
that on September 20,1997, all fuel was permanently removed frum the reactor vessel ENCLOSURE 2 980422005B 980416 PDR ADOCK 05000155 W PDR
- 1 1
2-and placed in the spent fuel pool for interim storage. D' aber 29,1997, l representatives from Consumers and NRC staff met at Nn. _.2adquarters to discuss
, planned activities regarding the decommissioning of the BRP facility. This meeting included .
discussions of licensee-proposed operator staffing changes, including CFHs. On l
January 21,1998, the NRC staff visited the BRP facility and discussed the BRP CFH I training program with licensee representatives. Subsequently, on February 10,1998, during a telephone conversation with the NRC staff, the licensee confirmed that NRC staff questions regarding the CFR training program had been resolved and implemented, as l
appropriate, into the BRP " Training Program for Certified Fuel Handlers."
2.0 EVALUATION i l
The proposed " Training Program for Certified Fuel Handlers," composed of the CFH Initial Training Program and the CFH Recertification Training Program, establish CFH training and program requirements for the BRP Nuclear Plant. These programs ensure that the qualifications of the CFH personnel are commensurate with the tasks to be performed and l the conditionc requiring personnel resnonse. Furthermore, these programs are to be i performed on a Systams Approach to Training (SAT) that appropriately reflects the approach that was used to determine the content of the BRP operator training programs
.during plant operation. The SAT process provides for the development, maintenance, and modification of the BRP " Training Program for Certified Fuel Handlers" to ensure continued ;
successful performance on the job by trained individuals,' as plant conditions change ;
! throughout the decommissioning of the DRP facility.
l 1 3.0 .QONCLUSION l
l The proposed BRP " Training Program for Certified Fuel Handics' is consistent with current l licensing practices and provides adequate confidence that a >propriate SAT-based training l of personnel, who perform CFH duties, is conducted to ensure that the facility is l raaintained in safe condition while spent nuclear fuelis stored in the spent fuel pool. There i is no regulation that requires NRC approval of changes to the CFH training program and the licensee shall follow all licensee and technical specification requirements until properly amended by the Commission.
Principal Contributor: Jesse A. Arildsen Date: March 25,1998