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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 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20056G9171993-08-31031 August 1993 Monthly Operating Rept for Aug 1993 for Big Rock Point Nuclear Plant 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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+ oq[3, ' UNITED STATES 1 [ ), NUCLEAR REGULATORY COMMISSION i
s r. 8 WASHINGTON, D. C. 20655
'+,*....,o SAFETY EVALUATION I Y THE OFFICE OF NUCLFAR REACTOR REGULATION
- SUPPORTING AMEl$NEP
- T FO. 81 TO FACILITY OPEPAT!!!G LICENSE NO. DPR-6 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155
1.0 INTRODUCTION
Py letter dated August 16, 1985 as revised by letter dated Septerber 24,
! 1985, Censurers Power Company (CPC, the licensee) requested changes to the Big Rock Point (the facility) Technical Specifications (TS) related to i'
the upcorning fuel reloading. Specifically, the changes wculd incorporate' Maximum Average Planar Linear Heat Generation Rate (P/PLHGP) and Pinimum Critical Power Petic (f:CFR) limits for the reload 11 fuel supplied by j Exxon Nuclear Company (ENC) into the facility TS.
Netices of Consideration of Issuance of Amendment to License and Prepcted Fo Sienificant Hazards Consideration Determination and Opportunity fer Heartre refeted to the requested action were published in the Federal Reaf ster on Septertber 11,1985 (50 FR 37078) and on Cctrber 1,1985 (50 FR 40076). P.o public coments or requests for hearing were received.
j 2.0 EVALUATION o >
2.1 PAPLHGR Limits 4
- The proposed P)PLHGR limits are based on the loss-of-coolcnt eccident (LOCA) arelysis required by 10 CFR 50.46. In support of this application, the licensen made reference to Exxon reports XN-NF-78-53 erd 7F-FF-79-?I, Revision 1, which describe the LOCA analysis methods presently used for ,
Exxon fuel reloads at Big Rock Point. On the basis of these two reports, the staff previcusly issued Amendment 44 to the Big Rock Point operating license. That arrer.dment revised MAPLHGR limits for gli feel supplied by Exxon te thet reint in time including the Exxon Reload G3/G4 fuel. .
The present reload !! fuel is identical to the previous G3/Gd fuel in all respects, except as described below:
- 1. In reload II, the fuel has a smaller pellet-to-clad gap than previous fuels, and
- 2. The funi red is prepressurfred while the previously used fuel rods were non-prepressurized.
' B511120322 B51101 PDR ADOCK 05000155 Y PDR
m These two differences cause an improved heat transfer in the fuel gap, which results in lower stored energy. The MAPLHGR limits maintain the peak cladding temperatures (PCT) less than 2200'F during LOCA. Since the methods used by the licensee to analyze the behavior of the core remain valid for the reload Il fuel and since PCT remain below 2200*F, we conclude that the MAPLHGR limits for the reload Il fuel are acceptable.
Previous safety evaluations for Big Rock Point fuel reloadings described a reduction in the MAPLHGR limits for General Electric fuel for burnups beyond 30,000 MWD /t to account for the effects of enhanced fission gas release.
This limitation was imposed as part of the staff's approval of Amendment 44 for General Electric Type F and Modified Type F fuel. Since none of the GE fuel will reside in the core (i.e., the core now contains only ENC fuel which is covered by ENC analyses), this reduction in the MAPLHGR limits is no longer applicable.
2.2 MCPR Limits The operating limit MCPR is established to protect the fuel from damage during any limiting transient. In the September 24, 1985 submittal, the licensee indicates that the gap conductance increases by about 50% compared with the existing fuel designs. The increase results from the smaller gap distance and prepressurized fuel design for the reload Il fuel. Based on the results of a sensitivity study performed by the licensee, MCPR increases by 0.012 and 0.022 for cases with increases in gap conductance of 25% and 300%, respectively.
The licensee proposes an increase of 0.02 from the existing operating MCPR limit of 1.59 to conservatively account for an increased conductance of 50%
in the reload II fuel.
, The staff has reviewed the proposed operating MCPR limit and has found that the analytical results support the proposed MCPR limit. This new MCPR limit provides sufficient margin for the Ifmiting transient. On this basis, the staff concludes the proposed MCPR limit is acceptable.
2.3 Summary Based on our review of the licensee's proposed TS changes for the reload Il fuel, the staff finds the MAPLHGR and MCPR limits to be acceptable. We also find that the proposed TS changes correctly reflect the analytical results for the proposed MAPLHGR and MCPR limits and, therefore, are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has detennined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational J
- - - - - - - - , - - - - _ _ _ - - - _ _ - , - - , - - . - - - - - , - - - - - - - - - - - . - - _ _ a .---__-- _-._ _ - _ - - - - - _ - - - _ - - - - _ _ - - _ _ _ - - - _ _ - _ - - - - -
radiation exposure. The Commission has previcusly issued a proposed finding that this amendment involves no significant hazards censideration and there has been no public comment on such finding. Accordirgly, this anendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or envirenrental assessment need be prepared in connection with the issuarre of this amendment.
4.0 CONCLUSION
, The staff has concluded, based on the consideratior.s discussed above, that: (1) there is reasonable assurance that the Fealth 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 Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ACKNOWLEDGEMENT This evaluatien was prepared by S. B. Sun and T. S. Potella.
Dated: November 1,1985 4
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