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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20203H8331998-02-20020 February 1998 SE Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds for Prairie Island Nuclear Generating Plant,Unit 2 ML20148D5441997-05-16016 May 1997 Safety Evaluation of Prairie Island Nuclear Generating Plant Individual Plant Exam ML20138J9961997-05-0606 May 1997 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of CRD Mechanism Canopy Seal Welds ML20058N8021993-12-0808 December 1993 Safety Evaluation Approving Third 10-yr IST Program Requests for Pumps & Valves,Per 10CFR50.55a(f)(6)(i) & 10CFR50.55a(a)(3)(i) ML20127C0071993-01-0404 January 1993 Supplemental SE Accepting Changes & Additions Described in Rev 1 to Design Rept for Station Blackout/Electrical Safeguards Upgrade Project ML20127C0291993-01-0404 January 1993 Safety Evaluation Accepting pressure-retaining Components of safety-related Auxiliary Fluid Sys Associated W/Edgs ML20127C0241993-01-0404 January 1993 Safety Evaluation Re Audit of Load Sequencer Implementation. Four of Five Items Reviewed Acceptable & Closed.One Open Item Remained Re Electromagnetic Environ Qualification for Lower Frequency Range of 30 Hz to 10 Khz ML20127C0151993-01-0404 January 1993 Safety Evaluation Accepting Instrumentation & Control Sys Aspects of Unit 2 Load Sequencer Sys in Station Blackout/ Electrical Safeguards Upgrade Project ML20128A7301992-11-30030 November 1992 Safety Evaluation Accepting Licensee 920921 120-day Response to Suppl 1 to GL 87-02 Re in-structure Response Spectra ML20128A7171992-11-30030 November 1992 Safety Evaluation Accepting Licensee 920921 120-day Response to Suppl 1 to GL 87-02 as Commitment to Entire GIP-2, Including Both SQUG Commitments & Implementation Guidance. In-structure Response Spectra Addressed in Separate SE ML20151U1181988-08-17017 August 1988 Safety Evaluation Re Compliance W/Atws Rule (10CFR50.62). Design Acceptable Contingent Upon Successful Completion of Human Factors Engineering Studies & Qualification of Isolation Devices ML20235Y4791987-07-13013 July 1987 Supplemental Safety Evaluation Accepting Util 870120 Requests for Relief from ASME Code Requirements Re Inservice Insp & Testing Program for Second 10-yr Interval ML20205Q8071987-03-30030 March 1987 SER Accepting Util 861104 & 840706 Responses to Generic Ltr 83-28,Item 4.5.2 Re ATWS Requirements for on-line Testing of Reactor Trip Sys ML20205M5261987-03-27027 March 1987 Safety Evaluation Denying Util 860819 Proposal to Reproduce Radiographs on Microfilm ML20211Q2971987-02-18018 February 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 ML20209C2151987-01-21021 January 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys Challenges ML20214S4131986-11-26026 November 1986 Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Licensee Actively Pursuing Improvements in Auxiliary Feedwater Sys Reliability & in Reducing Challenges to Sys ML20214C9231986-11-14014 November 1986 Safety Evaluation Supporting Amends 80 & 73 to Licenses DPR-42 & DPR-60,respectively ML20212K8801986-08-15015 August 1986 Corrected Safety Evaluation Accepting Util 860110 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20203B1551986-07-11011 July 1986 SER Re Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification. Program Acceptable. Exemption of Turbine Trip Component from Listing Also Acceptable ML20202A7531986-06-23023 June 1986 Safety Evaluation Supporting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20199L4491986-06-23023 June 1986 Safety Evaluation Re Util 860110 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Response Acceptable ML20211A3791986-05-30030 May 1986 Safety Evaluation Re Use of VIPRE-01 Subchannel Thermal Hydraulic Code & WRB-1 Critical Heat Flux Correlation W/Min DNBR Limit of 1.17.Code & Correlation Acceptable ML20211A2111986-05-27027 May 1986 SER Supporting Util Response to Generic Ltr 83-28,Item 1.2, Post-Trip Review (Data & Info Capability) ML20141N0961986-02-25025 February 1986 Safety Evaluation Accepting K(Z) Curve & Current Tech Spec Fq Value of 2.32 ML20138H1951985-10-18018 October 1985 Safety Evaluation Re Util 850422 & 0830 Ltrs Concerning Removal of Rod Cluster Control Guide Tube Thimble Plugs. Plan Acceptable ML20133N2021985-10-18018 October 1985 Safety Evaluation Accepting Util 830415,0915,850118 & 0606 Responses to Generic Ltr 82-33 Re Conformance of post- Accident Monitoring Instrumentation W/Rev 2 to Reg Guide 1.97 ML20138P6301985-10-17017 October 1985 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Concerning Reactor Trip Breaker Automatic Shunt Trip.Licensee Position on Items Acceptable ML20138E1661985-10-11011 October 1985 Safety Evaluation Re 850809 Inservice Insp of Components Relief Requests 29 & 66.Alternative Acceptable & Relief Should Be Granted ML20133P0521985-08-0505 August 1985 Safety Evaluation Accepting Util post-trip Review Program & Procedures.Nrc Action on Item 1.1 of Generic Ltr 83-28 Completed ML20128M9091985-05-13013 May 1985 Safety Evaluation Supporting Util 831104 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 ML20062B6451982-07-0909 July 1982 Safety Evaluation Supporting Thermal Hydraulic Margins for Exxon Toprod for Cycle 7 ML20062B6361981-10-20020 October 1981 Safety Evaluation Supporting Thermal Hydraulic Margins for Exxon Toprod for Cycle 7 1999-08-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30
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I SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
.' NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT
?- UNIT NOS. 1 AND 2 PROPOSED MICROFILM REPRODUCTION OF RADIOGRAPHS l f
Principal Contributor:
William J. Collins, Sr. Metallurgist Office of Inspection and Enforcement ho04020422870327 p ADOCK 05000282 PDR
INTRODUCTION By lett-r dated August 19, 1986, Northern States Power Company (NSP) requested NRC to review and concur with their proposal to microfilm radiographs of the piping system welds of the subject plants in accordance with paragraph IWA-6320ofASMECodeSectionXI(1980 Edition, Winter 1981 addenda) requirements.
In response to this request, a meeting was held on December 17-18, 1986 4
between representatives of NSP and NRC at Micro Media Inc., Minneapolis, Minnesota, to review the proposed microfilming activities and quality assurance program. Enclosure 1 identifies the attendees of this meeting.
EVALUATION ,
Micro Media Inc., is a small local microfilming company who has been
- , assisting NSP efforts to develop a suitable method of radiograph reproduction
- g by microfilming. Their facilities essentially consist of comercial photographic equipment and automated film processing systems that are designed and primarily being used for microfilming medical x-ray records. No formal quality control system is employed by Micro Media. Rather, the final product is directly dependent on the skill and experience of trained technicians and line supervision.
Following a tour of the MMI facility, the procedure NSP proposed to use in microfilming the subject weld radiographs was discussed. Briefly, the procedure would employ a multiple exposure technique to provide five microfilm images, in 35 nun format, of each radiograph to accommodate the expected film density range of 1.5 to 4.0. Using this approach, NSP anticipated that at least one microimage would feature the actual density and equivalent sensitivity level of the original radiographs. The resulting microfilms would then be reviewed against the respective radiographs tc assure that all ASME Code requirements are met.
To demonstrate the methodology proposed, Micro Media was asked to microfilm a representative sample of 12 industrial radiographs furnished by the NRC staff. These radiographs were of carbon steel and austenitic stainless steel piping welds ranging from 0.5 to 1.3 inches in wall thickness, respectively.
Measured film density ranged from 1.8 to 3.5 across the areas of interest.
Plaque type penetrameters shimmed to simulate weld thickness were present on each film. A 4T penetrameter sensitivity as required by code specifications
, was visible on the majority of films. For the radiographs of the thin-wall pipe samples of carbon steel, a 2T sensitivity index was also visible, i Collectively, the sample radiographs featured various code rejectable indications in the weldments. These included porosity, root burn through,
- inclusions, weld undercut, lack of fusion, cracking and various film artifacts. The indications varied from being very obvious and easily seen to very subtle, requiring expert interpretation. In order words, the visibilit
' of the indications and penetrameter sensitivity (i.e., image quality index) y ranged from marginal to excellent depending on the contrast and resolution achieved.
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Five microfilm images were made of each radiograph in 35 mm format as described above. A standard film density strip was required by the NRC staff to be microfilmed with each radiograph to aid in interpretation. In microfilming, no automated circuitry was used to vary the light intensity or relative exposure to acconnodate the density gradient inherent in the 1 radiographs. Hence, the microfilm images merely showed different levels of density of which only one appeared interpretable.
Two viewers were made available by Micro Media for microfilm review by the task group (Messrs. Nelsen, Martinson, Dahlman and Collins). Unfortunately, the equipment was designed for viewing medical x-ray film and as a result proved inadequate for evaluating details of the microfilm images of the industrial radicaraphs.
The reproductions were then placed on an industrial radiograph viewer and i [~ *,
compared directly with the original radiographs utilizing a hand-held optical
. loupe (8x mag.) as a visual aid. As expected four of the five microfilm images were uninterpretable due to excessive film density. The remaining image was quite comparable to the original radiograph on the bases of film density strip estimates. However, the image showed no penetrameter sensitivity index (complete loss of 2T and 4T hole visibility) and relatively low resolution of certain flaw details. This was particularly evident in the microfilms of the heavy pipe thickness and was attributed to light scatter bridging the density gradients of the radiographs during microfilming. In certain film, image aberrations occurred due to improper camera focusing which also degraded image quality and clarity of details. The lack of a capability to properly enlarge the microfilm and absence of a calibrated scale precluded further evaluation of the reproductions in accordance with code specifications.
CONCLUSION Based on the above, the group concluded that the microfilming techniques as presently proposed were not an acceptable alternative for the original radiographs. The group also concluded that several critical constraints in the existing methods and procedures need to be resolved by NSP. Specifically, these include:
- 1. The microfilm viewer must be designed with sufficient operational capability in terms of variable focusing, lighting, calibrated scale and image enlargement to permit definitive interpretation of microfilm against code specifications.
- 2. Special film types need to be evaluated to ensure equivalent sensitivity, contrast, and resolution characteristic of the original radiograph.
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- 3. Camera equipment designed with finite focusing, spatial alignment and variable lighting controls are necessary to optimize filming conditions. This must be accomplished in con,iunction with item 4.
- 4. During the filming of a target film, the standard film density strip and the calibrated scale need to be filmed with the radiographs to aid interpretation and more importantly, verification that the microfilms are accurately reproduced from the original radiographs.
- 5. A photographic film stability test, such as provided for in ANSI PH 4.8, 1978, needs to be considered as a means.to control film processing parameters and ensure archival quality of microfilms.
., 6. The quality control program for microfilming radiographs is the .
(; responsibility of NSP and is currently in draft form. The program procedures need to be finalized before microfilming can commence. The y procedure (s) must provide for control of all microfilming activities and final review processes to ensure the final product meets code specifications.
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. is Enclosure 1 LIST OF MEETING ATTENDEES t a R. I. Nelson NSP, Quality Control Supervisor a
L. C. Dahlman NSP, Materials and Special Processes Division K. B. Martinson NSP, Quality Control Supervisor G. Eckholt NSP, Nuclear Support Services J. McMerty Micro Media Inc.
N. Giannaccini Micro Media Inc.
]
fik; W. J. Collins U.S. NRC, IE, DEPER .
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