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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
[Table view] |
Text
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- o g UNITED STATES 8 p, NUCLEAR REGULATORY COMMISSION O j WASHINGTON, D. C. 20555
SAFETY EVALUATIOi! BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING RELIEF FROM INSERVICE INSPECTION REQUIREMENTS CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET NO. 50-155 INTRODUCTION
', Technical Specification 9.3.a for the Big Rock Point Plant states that inservice examination of ASME Code Class 1, 2, and 3 ccmponents shall be performed in accordance with Section XI of the ASME Boiler and Pressure .
Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Commission. Certain requirements of later editions and addenda of Section XI are impractical to perform on older and materials plants because of the plants' design,(component geometry,Thus, 10 of construction.
Comission to grant relief from those requirements upon making the necessary findirgs.
By letter dated December 19, 1983, Consumers Power Company (CPC) submitted its inservice inspection program and additional information related to requests for relief from certain Code requirements detemined to be impractical to perform on the Big Rock Point Plant during the inspection interval. The program is based on the requirements of the 1977 Edition i through Sumer 1978 Addenda of Section XI of the ASME Code, and remains in f effect until January 1,1992 unless the program is modified or changed
. prior to the interval end date.
EVALUATION Requests for relief from the requirements of Section XI which have been i determined to be impractical to perfom have been reviewed b
- contractor, Science Applications International Corporation (y the SAIC). The Staff's contractor's evaluations of the licensee's requests for relief and his recomendations are presented in the Technical Evaluation Report (TER) attached (ATTACPMENT1). The staff has reviewed the TER and agrees with i
the evaluations and recomendations. A sumary of the determinations made by the staff is presented in the following tables:
0511060262 PDR ADOCK e5 M 55 PDR G
L
%e 2 O
- ?- .. { ,
CONCLUSION Based on the review summarized, the staff cercludes that relief granted from the examination and testirg rro,uirements and alternate methods and provisions imposed through this document oive reasnnable assurance of the piping and component pressure boundary and support structural integrity, that granting relief where the Code requiremsots aresimpractical is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering
. the Lurden that could result if they were imposed on the facility.
ACKNOWLEDGEMENT This Safety Evaluation was prepared by Mr. B. Turovlin and Mr. T. Rotelle.
Dated: November 1,1985 s
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TABLE 1 . .
~
CLASS 1 COMPONENTS LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS 81.11 B-A Reactor Circumferential Volumetric Each refuel- Granted Bl.12 Vessel - and Longitudinal outage perform Shell Welds prestartup hydro at I.1 times operating pressure B.21 B-A Reactor Circumferential Volumetric During next Granted B.22 Vessel and Meridional interval Bottom Head Welds examine Head accessible 90 degrees of 793-1 weld and hydro test.
83.90 B-D Reactor Nozzle-to- Volumetric Visual of Granted 83.100 Vessel Vessel accessible provided Nozzle in- surfaces of SEP Topic side radius nozzles V-4 is per-formed.
B5.10 B-F Reactor Nozzle-to- Volumetric Visual of Granted Vessel safe ends Surface accessible provided SEP welds surfaces Topic V-4 in plus volu- performed.
metric, visual and surface of accessible 20 in. recirc.
nozzles.
TABLE 1 . .
CLASS 1 COMPONENTS (CONTINUED) .
LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS
, B3.90 B-D Reactor 3 in. Nozzle Volumetric Remote visual Granted B3.100 B-F Vessel to-Vessel Welds, Surface of accessible provided SEP B5.10 to safe ends, internal sur- Topic V-4 is nozzle inside faces and hydro performed.
radius B5.10 B-F Reactor 6 ea. 14 in. Volumetric Mechanized UT Granted Vessel steam outlet Surface Visual VT-1 provided nozzles Hydro volumetric expanded to include 100%
of each weld.
88.10 B-H Reactor Suspension Volumetric Limited Remote Granted Vessel Rod Brackets or Surface Visual provided Vessel Hanger Hydro general area Lugs of shield Stabilizer annulus in-Brackets spected for leak during hydro B2.51 B-B Steam Drum Shell Welds Volumetric Shell welds Granted B2.52 within 30 arc either side of upper longi-tudinal centerline B3.150 B-D Steam Drum Nozzle-to Volumetric Upper One-Half Granted B3.160 Vessel welds -
of all full nozzle inside penetration radius nozzles
o 1 TABLE 1 . .
CLASS 1 COMPONENTS (CONTINUED) ,
LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B8.40 B-H Steam Drum Welds in Volumetric 4 supports Granted Supports or Surface in upper portion per code.
B3.160 B-D Clean-up Nozzle inside Volumetric None Granted Regenera- radius tive and Nonregen-erative Heat Exchangers B3.150 B-D Clean-up Nozzle-to- Volumetric Visual VT-1 Granted Nonre- vessel welds and surface generative Hydro Heat Ex-changer B3.160 B-D Clean-up Nozzle Volumetric None Granted Deminer- inside alizer radius Tank B5.50 B-F Shutdown Dissimilar Volumetric Visual Granted cooling Metal Fitting Surface system to pipe weld weld 6-SCS-101-7 B5.50 B-F Piping Dissimilar Volumetric - Surface Only Granted B9.11 B-J Metal Fitting Surface 89.21 to Pipe Welds B9.40
TABLE 1 . .
CLASS 1 COMPONENTS (CONTINUED) .
LICENSEE PROPOSED IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS B9.11 B-J Piping Dissimilar Volumetric None Granted B9.21 Metal Pipe Surface 89.40 to Safe End We lds. 7 Welds B10.10 B-K-1 Main Recir Integrally Volumetric Visual Granted System Welded Piping or Surface Attachments 20 attachments B10.10 B-K-1 Reactor Integrally Volumetric None Granted ,
depressuri- welded piping or Surface zation attachments system 2 attachments B11.10 B-K-2 Component W e lds, settings Visual Remote Visual Granted Supports, of snubbers, Piping shock absorbers, spring-type hangers.
B12.10 B-L-1 Clean up Pump Casing Volumetric Surface on Granted B12.20 B-L-2 and main Welds accessible areas provided recirc. Pump Internal Visual visual during pump interior pumps surface hydro examined if pump is dis-assembled B12.40 B-M-2 Valves Interior Surface Visual Visual during Granted pro-of 6 valve hydro vided any valve categories '. disassembled have visual examination m -
TABLE 2 - .
CLASS 2 COMPONENTS ,
LICENSEE PROPOSED IWC-2500 IWC-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNA~i1VE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STW'IJS C5.11 CF (See Circumferential Surface None No Relief C5.21 Attach- piping weld C5.11 required ment 1 to surface and Table 2) volumetric C5.21 C5.11 CF Regenera- Vent and Surface and None Granted C5.21 tive and drain lines volumetric piping to ,
heat ex- be reclass- !
changers ified. I l
1 l
8
_ _ _ . . _ _ - . _ _ _ _ _ _ _ _ _ _ e
~
TA8LE 2 . ,
ATTACHMENT 1 Penetrations affected:
- Penetration Piping on Either Side i Number P&ID No. of Penetration H-12 M-111 Class 3
- H-13 M-111 Class 3 j H-15 M-108 Non-classed / Class 3 i H-17 M-108 Non-classed
, H-18 M-110 Class 3 H-21 M-108 Non-classed H-22 M-107 Non-classed / Class 3
. H-23 M-107 Non-classed H-31 M-121 Non-classed t
n
't a
TABLE 3 - .
PRESSURE TESTS , .
IWA-5000 .
IWB-5000 IWC-5000 IWD-5000 LICENSEE PROPOSED SYSTEM OR PRESSURE TEST ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST STATUS All systems IWB, IWC, IWD-5000 No system leakage Granted Class 1,2,3 require system test during outage leakage test each when hydrostatic refueling outage. test is scheduled.
IWB, IWC, IWD-5000 require system hydrostatic test each interval.
TABLE 4 VOLUMETRIC EXAMINATION METHODS LICENSEE SYSTEM OR PROPOSED ALTERNATIVE RELIEF REQUEST COMPONENT REQUIREMENT TEST STATUS Class 1 Ultrasonic examina- Calibration block Denied In-and 2 tion of class 1 and with side drilled sufficient B5.50 class 2 ferritic holes justification B9.12 steel piping systems for declaring l 89.31- shall be conducted Code require-C5.21 and in accordance with ments impracti-C5.22 Appdx. III, amended: cal.
For examination of welds, reflectors that produce a response greater -
than 50% of the
! reference level l shall be recorded.
l