Package Consisting of Questions & Comments Re PBAPS Submittal,Dtd 980813,in Support of Discussion on Listed ItemsML20210A495 |
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Peach Bottom ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
07/22/1999 |
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From: |
NRC |
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To: |
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References |
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NUDOCS 9907220118 |
Download: ML20210A495 (2) |
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Category:ARCHIVE RECORDS
MONTHYEARML20210A4951999-07-22022 July 1999 Package Consisting of Questions & Comments Re PBAPS Submittal,Dtd 980813,in Support of Discussion on Listed Items ML20151X8811998-06-23023 June 1998 Rev 2 to PM-1011, Core Spray Pump Npsh ML20151X8721998-06-23023 June 1998 Rev 2 to PM-1010, RHR Pump Npsh ML20151X8621998-06-22022 June 1998 Rev 1 to PM-1013, Min Containment Pressure Available ML20195E3151998-04-27027 April 1998 Non-proprietary Version of Rev 1 to Calculation MISC-PENG- CALC-064, Verification of ECCS Strainer Pressure Drops for Peach Bottom,Units 2 & 3 ML20195E3551997-11-28028 November 1997 Non-proprietary Version of Rev 1 to Calculation MISC-PENG- CALC-062, Evaluation of Predictions & Data for Prototype Strainer ML20216E6891997-08-0404 August 1997 Calculation 0067-000-84-C-020 (PS-0920), Clipped A-46 Spectra for Radwaste/Turbine Building. W/14 Oversize Drawings ML20216E7491997-07-24024 July 1997 Calculation CTLAR-01 PS-0939, LAR of Raceway Supports for PBAPS Units 2 & 3 ML20216E7161997-04-28028 April 1997 Calculation 0067-00084-C-011 PS-0912, LAR of Raceways ML20134D5471996-10-28028 October 1996 Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened ML20058P0931993-09-17017 September 1993 Package Containing Attachment to Employee Concerns Programs ML20086C4921991-10-0404 October 1991 Design of Full Structural Weld Overlay on Pbaps,Unit 3 Reactor Water Cleanup Weld No 12-I-1C ML20247H9431989-07-25025 July 1989 Summary of ASME Repairs & Replacement Completed (N1S-2) for Peach Bottom Atomic Power Station Unit 2,870401-890426 ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys IA-87-759, Annotated Slides of NRC 870909 Briefing on Pipe Replacement Project1987-09-0909 September 1987 Annotated Slides of NRC 870909 Briefing on Pipe Replacement Project ML20236X0061987-09-0909 September 1987 Annotated Slides of NRC 870909 Briefing on Pipe Replacement Project IA-87-209, Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant1987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20235Y5381987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20235N6621987-07-15015 July 1987 Package of Partially Withheld Investigation Status Records, Draft Synopsis,Handwritten Notes & Util Personnel Policy Re Case 1-85-019 Concerning Alleged Threats to Employees to Prevent Disclosure of Possible Overexposure to NRC ML20235A1861987-07-0101 July 1987 Partially Withheld Package Consisting of Radiation Work Permit 3-1-003,discrepancy Rept,Radiation Contamination - Airborne Survey & Radiation Work Permit Access & Exposure Control ML20206N8911987-04-14014 April 1987 Revised Viewgraphs to 870410 Transcript on Commission Briefing Re Status of Facility ML20214E4881987-04-0606 April 1987 Press Release Re Util Plan to Investigate Reasons for NRC Order Suspending Plant Operation IA-87-185, Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance1986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance ML20216F4841986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities1986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities ML20137Q6671986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities ML20154B8891985-10-0101 October 1985 Slide Presentation Entitled, Performance of L Grade Stainless Steel Recirculation Outlet Safe Ends at Peach Bottom-3. List of Attendees Encl ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1999-07-22
[Table view] Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARML20210A4951999-07-22022 July 1999 Package Consisting of Questions & Comments Re PBAPS Submittal,Dtd 980813,in Support of Discussion on Listed Items ML20058P0931993-09-17017 September 1993 Package Containing Attachment to Employee Concerns Programs ML20247H9431989-07-25025 July 1989 Summary of ASME Repairs & Replacement Completed (N1S-2) for Peach Bottom Atomic Power Station Unit 2,870401-890426 ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys IA-87-209, Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant1987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20235Y5381987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20235N6621987-07-15015 July 1987 Package of Partially Withheld Investigation Status Records, Draft Synopsis,Handwritten Notes & Util Personnel Policy Re Case 1-85-019 Concerning Alleged Threats to Employees to Prevent Disclosure of Possible Overexposure to NRC ML20235A1861987-07-0101 July 1987 Partially Withheld Package Consisting of Radiation Work Permit 3-1-003,discrepancy Rept,Radiation Contamination - Airborne Survey & Radiation Work Permit Access & Exposure Control IA-87-185, Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance1986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance ML20216F4841986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance ML20137Q6671986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities1986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1999-07-22
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/zo/M Questions and Comments Regarding the Peach Bottom Atomic Power Station Submittal Dated 8/13/98
- 1. The Peach Bottom ISI Program identifies numerous Code Cases adopted by the utility that have not been approved for use. Although approval may be pending per Rev.12 of Reg. Guide 1.147, the licensee must submit a Request for Alternative for each Code Case that has not been approved by inclusion in Reg. Guide 1.147.
The Request for Alternative must also include the licensee's basis for the proposed alternative, which demonstrates that the proposed alternative provides an '
acceptable level of quality and safety in accordance with the requirements of 10CFR50.55a(a)(3)(i).
- 2. The licensee's basis for Proposed Alternative RR-17 does not state the hardship of compliance, it is not clear how the licensee's proposed alternative (to monitor acoustic and temperature instruments on the relief valve tail pipes) provides any -
assurance of structuralintegrity. Therefore, the proposed alternative will not be authorized. The licensee should revise and resubmit this request providing more ;
detailed information which demonstrates: (a) that the proposed alternative provides an acceptable level of quality and safety in accordance with 10CFR50.55a(a)(3)(i) or, (b) that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in quality and safety in i accordance with 10CFR50.55a(a)(3)(ii).
- 3. In Request for Alternative RR-27, the licensee proposed that the Code required sampling rate be applied to all Category C-F-2 welds regardless of nominal piping wall thickness, except that only surface examinations will be performed on welds in piping <3/8 inch nominal wall thickness. The staff believes that examinations should be performed on welds < 3/8 inch nominal wall thickness. The licensee's proposed alternative would result in fewer volumetric examinations being performed. Also, the licensee has not provided a basis for performing only surface examinations. The licensee needs to address whether or not volumetric examinations can be performed on welds <3/8 in nominal wall thickness? The licensee also needs to address how performing only surface examinations would provide adequate assurance of structuralintegrity since most degradation mechaniams occur from the ID.
- 4. In conference call of 5/13/99, the licensee was asked why the inaccessible welds in penetrations listed in Request for Relief RR-28 were selected for examination.
The licensee stated that they were selected because they consider the containment penetration to be an anchor point, therefore these welds are at terminal ends. The licensee's proposed alternative states that examinations will be performed on the first accessible pipe weld outside each penetration that has an inaccessible weld inside. Please document the selection criteria for welds to be examined in lieu of inaccessible welds as discussed in the conference call.
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Questions and Comments Regarding the Peach Bottom Atomic Power Station Submittal Dated 8/13/98
- 5. In Request for Alternative RR-32, the licensee proposed performing visual VT-3 i
examinations of bolts removed from leaking bolted connections. However, since there are no Code acceptance criteria for VT-3 examinations, the staff requires that a VT-1 examination be performed on the bolt selected for examination. The licensee needs to revise and resubmit the relief to conform to Code case N-566-1 and the additional commitment to perform a VT-1 examination as described above.
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