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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 ML20058G2141993-11-29029 November 1993 Safety Evaluation Accepting Category 3 Qualification in Lieu of Category 2 Qualification for post-accident Monitoring of SIT Volume & Pressure 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 ML20141M2351992-03-31031 March 1992 Safety Evaluation Granting Util 910909,920116 & 0318 Requests for Relief from Section XI of ASME Code for Making non-code Repairs to Three Containment Air Coolers at Plant ML20058E0871990-10-29029 October 1990 Safety Evaluation Approving Closeout of IE Bulletin 79-15, Deep Draft Pump Deficiencies 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 ML20197A9421986-10-20020 October 1986 Nonproprietary SER Supporting Util 860611 Submittal Re Inadequate Core Cooling Instrumentation Sys for Plant.Util Approach to Reactor Vessel Level Monitoring Sys Based on Radcal Gamma Thermometer Probes Acceptable 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 ML20205F6051985-11-0101 November 1985 Safety Evaluation Supporting Amend 81 to License DPR-6 1998-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML20217C3031999-09-28028 September 1999 Annual Rept of Facility Changes,Tests & Experiments ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr 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 ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML20198K6611998-12-24024 December 1998 Safety Evaluation Supporting Amend 120 to License DPR-6 ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant 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 ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML20217N2131998-04-24024 April 1998 Brpnp Zircaloy Oxidation Analysis ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. 1999-09-30
[Table view] |
Text
- - _ - -_ - - . - - - - - ~
b p ur
'. p k UNITED STATES g y NUCLEAR REGULATORY COMMISSION
' o & WASHINGTON, D.C. 20666-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ,
1 l OVALITY ASSURANCE PROGRAM DESCRIPTION CHANGE CONSUMERS POWER COMPANY BIG ROCK POINT AND PALISADES PLANTS l DOCKET NOS. 50-155 AND 50-235
1.0 INTRODUCTION
By letter dated February 20, 1997, Consumers Power Company, the licensee, i transmitted proposed changes to Revision 17 of its Quality Program Description for Operational Nuclear Power Plants (CPC-2A) in accordance with 10 CFR i 50.54(a)(3)(ii). Specifically, the proposed changes identify alternatives to i the previously approved provisions related to lead auditor qualifications and annual supplier evaluation. The staff has reviewed the submittal in accordance with 10 CFR 50.54(a) and determined that the proposed changes to CPC-2A are acceptable in that the quality assurance program continues to meet the requirements of Appendix B to 10 CFR Part 50.
2.0 EVALUATION 2.1 Lead Auditor Qualification Process Section 2.3.4, " Audit Participation," of ANSI N45.2.23-1978, " Qualification of QA Program Audit Personnel for Nuclear Power Plants," as endorsed by Regulatory Guide (RG) 1.146, " Qualification of Quality Assurance Audit Personnel for Nuclear Power Plants," dated August 1980, states that:
The prospective Lead Auditor shall have participated in a minimum of five (5) quality assurance audits within a period F time not to exceed three (3) years prior to the date of qualificatiot one audit of which shall be a nuclear quality assurance audit within W year prior to the individual's qualification.
As described in its submittal the licensee has proposed the followino alternative to the requirements contained in Section 2.3.4 of ANSI N45.2.23-1978:
The prospective lead auditor shall demonstrate his ability to properly implement the audit process defined by this Standard and Consumers Power Company program / procedure, to effectively lead an audit team, and to effectively organize and report results, including participation in at least one nuclear quality assurance audit within the year preceding date of certification.
, Enclosure 9704210126 970418 PDR ADOCK 05000150 P PDR s..
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1 Based on the staff's review it was determined that the alternative proposed by Consumers Power Company represents an acceptable option to Section 2.3.4 of ANSI N45.2.23-1978. This determination was based on the licensee's program controls which require that (1) prospective lead auditors effectively demonstrate their ability to lead an audit team and effectively implement the audit process and (2) that the licensee describe this demonstration process in written procedures and that the results of these activities are evaluated and documented. The alternative also requires that the prospective lead auditor shall have participated in at least one nuclear quality assurance audit within l the year preceding the individual's effective date of qualification and that having met the other provisions of Section 2.3 of ANSI N45,2.23-1978, the ;
j individual may be certified as being qualified to lead audits. i l
2.2 Annual Supplier Evaluation l ANSI N45.2.12-1977, " Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants," as endorsed by NRC RG 1.144, " Auditing of Quality Assurance Programs for Nuclear Power Plants," Revision 1, dated September 1980, describes a method acceptable to the NRC staff for complying with regulations concerning auditing of quality assurance programs for nuclear power plants. Specifically, Section 3.5.2 of ANSI N45.2.12-1977 requires that ,
audits of quality assurance activities be regularly scheduled to ensure that i the quality assurance program is adequate and that activities are being performed in accordance with the quality assurance program. Regulatory Position C.3, of RG 1.144, discusses acceptable audit scheduling. In particular, Regulatory Position C.3.b(2), which addresses the auditing of a supplier's quality assurance program, permits an audit frequency of up to 3 years, provided that the licensee performs an annual evaluation of the supplier's performance in accordance with the following requirements:
A documented evaluation of the supplier should be performed annually. Where applicable, this evaluation should take into account (1) review of supplier furnished documents such as certificates of conformance, non-confermance notices, and corrective actions, (2) results of previous source verifications, audits, and receiving inspections, (3) operating experience of identical or similar products furnished by the same supplier, and (4) results of audits from other sources (e.g., customer, ASME, or NRC audits). !
)
As described in its submittal the licensee has proposed the following i alternative to the requirements contained in Regulatory Position C.3.b(2), of RG 1.144:
Consumers Power Company will review the information described in the second paragraph of section C.3.b(2) of Regulatory Guide 1.144, ,
Revision 1,1980, as it becomes available through its ongoing receipt I inspection, operating experience and supplier evaluation programs, in lieu of performing a specific evaluation on an annual basis. The '
results of the reviews are promptly considered for effect on a supplier's continued qualification and adjustments made as necessary (including corrective actions, Lijustments of supplier audit plans, and i
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4 input to ti.ird party auditing entities as warranted). In addition, the i results- are reviewed periodically to determine if, as a whole, they
- . constitute a significant condition adverse to quality requiring additional action.
l- Based on the staff's review it was determined that the alternative proposed by I t Consumers Power Company represents an acceptable option to Regulatory Position j C.3.b(2) of RG 1.144. Specifically, the alternative to the preceding position ,
! provides' for a documented ongoing evaluation of the supplier's performance, ;
1 rather than a delayed annual evaluation. Where applicable, this evaluation takes into account the review of supplier-furnished documents such as certificates of conformance, non-conformance notices, and corrective actions, 4 as well as-evaluating the results of previous source verifications, audits, )
, , and receiving inspections. The proposed alternative also provides for the !
review of operating experience information pertaining to equipment failures
. and evaluation of the results of audits from other sources (e.g., customer,
- ASME, or NRC audits) for their effect on supplier qualification status. As l described in the licensee's program, the results of these evaluations are 1
reviewed and appropriate corrective.actirn taken. Furthermore, adverse
- findings resulting from these evaluations are periodically reviewed to determine if, in the aggregate, they result in a significant condition adverse to quality. Additionally, the results of these evaluations are used to
! provide input to support supplier audit activities conducted by Consumers
! Power Company or third party auditing organizations.
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3.0 CONCLUSION
- The staff has determined that the proposed changes to Revision 17 of Consumers
. Power Company's Quality Program Description for Operational Nuclear Power l Plants (CPC-2A), related to. lead auditor qualifications and annual supplier i evaluation represent an acceptable alternative to the review criteria
!. contained in Section 17.2 of NUREG-0800, the Standard Review Plan, and that
[ these changes continue to meet the requirements of Appendix B to 10 CFR l Part.50.
Principal contributor: R. Latta Date: April 18, 1997