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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20211H6791997-09-18018 September 1997 Safety Evaluation Authorizing Licensees Request for Alternative from Augmented Insp of Reactor Pressure Vessel Circumferential Weld in Plant,Unit 1 ML20211A5881997-09-11011 September 1997 Safety Evaluation Supporting Evaluation of First 10-yr Interval ISI Program Plan Requests for Relief PT-004,PT-005 & PT-006 for Plant,Unit 1 ML20217K9061997-08-12012 August 1997 Safety Evaluation Accepting Plant First 10-yr Interval ISI Program Plan Relief Request PT-007 ML20141L9131997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for First 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1 ML20147H4211997-04-0101 April 1997 Safety Evaluation Accepting Changes to USAR Sections,Which Continue to Satisfy Criteria of App B of 10CFR50 ML20134D1061997-01-27027 January 1997 Safety Evaluation on Revised EALs for Plant.Proposed EALs Changes Are Consistent W/Guidance in NUMARC/NESP-007,with One Exception,& Meets Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20058M6761993-09-29029 September 1993 Safety Evaluation Accepting Rev 10 to Plant Emergency Plan for NRC Review Under 10CFR50.54(q) ML20246F6481989-08-23023 August 1989 Safety Evaluation Accepting Proposed Turbine Sys Maint Program ML20246Q0291989-07-14014 July 1989 Safety Evaluation Re Updated Safety Analysis Rept Appendix 1B,license Commitment Revs ML20244D6351989-06-0707 June 1989 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance1989-06-0505 June 1989 Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance ML20246Q0771989-05-0909 May 1989 Safety Evaluation Supporting Proposed Mod to Delete K74B & K74D Relays from Electrical Control Circuitry of MSIV to Resolve Spurious Opening of MSIV on Loss of Reactor Protection Sys Bus a or B ML20248G2921989-03-30030 March 1989 Safety Evaluation Accepting Util 840406 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing ML20236E0141989-03-15015 March 1989 Safety Evaluation Supporting Util Implementation of 10CFR50.62 ATWS Rule ML20196D4311988-12-0606 December 1988 Safety Evaluation Documenting NRC Review of Licensee Response to Generic Ltr 83-28.Evaluation Concludes That Licensee Adequately Meets Provisions of Part 1 of Item 2.2 to Generic Ltr 83-28 ML20213A5661987-04-20020 April 1987 Safety Evaluation Supporting Amend 4 to License NPF-58 ML20205Q9771987-04-0101 April 1987 Safety Evaluation Supporting Amend 3 to License NPF-58 ML20203N6981986-10-10010 October 1986 Sser Supporting Util Request for Relief from Preservice Insp Program Requirements ML20203N6951986-10-10010 October 1986 Safety Evaluation Supporting Request for Relief from ASME Code Exam Requirements in Preservice Insp Program ML20202G4321986-07-0808 July 1986 SER Approving Tdi Diesel Generator Owners Group Program to Validate & Upgrade Design & Mfg Quality of Tdi Diesel Generators for Nuclear Emergency Standby Svc ML20198C3951985-11-0505 November 1985 Safety Evaluation Re Reliability of Tdi Standby Emergency Diesel Generators for Application at Domestic Nuclear Plants.Diesel Generators Will Provide Reliable Standby Source of Onsite Power,W/Listed License Conditions ML20138N7461985-10-28028 October 1985 SER Supporting Reliability of Tdi Standby Emergency Diesel Generators.Viewgraphs & Final Draft Tech Specs Encl 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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[ 4 UNITED STATES
't s* j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 4
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- 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOUR CHANGES OF THE INDEPENDENT SAFETY ENGINEERING GROUP ElRST ENERGY (TAC NO. MA3325) i j E2RRY NUCLEAR POWER PLANT DOCKET NO. 50-440
1.0 INTRODUCTION
i
- By letter datad July 22,1998 and supplemented on September 1,1998, pursuant to 50.54(a),
FirstEnergy submitted proposed revisions to the quality assurance program for the Perry 4
Nuclear Power Plant (PNPP). The proposed changes included (1) The reporting point of the Independent Safety Engineering Group (ISEG) will change from the Director, Perry Nuclear l
- Services Department to the Manager, Quality Assurance Section; (2) the ISEG function to l review and assess operation and maintenance audits will be transferred to the Company l Nuclear Review Board; (3) ISEG membership will be reduced from five to four members; and l l (4) the ISEG qualifications wll be revised.
3
.0 EVALUATION l The transfer of the ISEG reporting point from the Director, Perry Nuclear Services Department 1
to the Manager, Quality Aswrance Section (QAS) modifies the Updated Final Safety Analysis
- Report (USAR) Section 17.2.1.3.2.2 which describes responsibilities of the Manager, QAS. The j remaining changes alter the current descriptions of the functions and responsibilities of the ISEG made in USAR Appendix 1A, item I.B.1.2, and Sections 13.4.3 and 17.2.1.3.2.2.3.
2.1 Reoortina Point Transfer from the Director. Perry Nuclear Service Deaartment (oNSD) to the Manaaer. QAS In the current USAR, the ISEG reports to the Director, Perry Nuclear Serv.ces Department. However, in the proposal, ISEG will report to the Manager, Quality Assurance Section (QAS), who is also the manager of the Quality Assurance and Quality Control Units. As part of this organization, ISEG will still maintain a separation and independence from the o -site enginerring and technical organization. The QAS manager has a direct reporting relationship to the site Vice President. Although the staff wC report to the QAS manager, ISEG will not report to a supervisor responsible for quality assurance audits or surveillances. The reduction in commitnient is acceptable because ISEG will maintain a separate schedule and the full-time, dedicated ISEG staff has adequate freedom to perform the quality a:surance oversight function.
9809230252 900916 PDR ADOCK 05000440 P PDR
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! l 2.2 ISEG Function to Review and Assess Ooeration and Maintenance Audits USAR Appendix 1 A, item 1.B.1.2 states that the ISEG should perform independent review and assessment of plant operation and maintenance audits. This oversight function is l being deleted as an ISEG function. There is no NRC requirements for 9EG to perform this function. However, the function will continue to be performed by an independent organization. USAR Section 17.2.1.3.5, " Company Nuclear Review Board (CNRB),"
states the review board is required to perform independent review and audit of plant operations, instrumentation and control (maintenance function), and other activities.
USAR Section 17.2.1.3.5.2 states the CNRB is required to audit various activities including conformance of unit operations to the provisions of the Technical Specifications (TS), and audit the results of actions taken to correct deficiencies occurring in unit equipment. The CNRB comprises eight members and reports directly to the site Vice President. A CNRB member (USAR Section 17.2.1.3.5) shall hold a bachelor's degree in an engineering or physical science field, or equivalent experience, and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the various engineering disciplines listed in USAR Section 17.2.1.3.5. The reduction in commitment is acceptable because the oversight audit function is being performed by another independent group composed of members that meet or exceed the qualifications for the ISEG personnel.
2.3 Reduction of ISEG Membershio NUREG-0737 states that ISEG will comprise five individuals. The licensee proposes to reduce the ISEG membership from five to four individuals to perform the requisite tasks described in USAR Appendix 1 A. Item 1.B.1.2, and Sections 13.4.3 and 17.2.1.3.3.2 '2.3.
Currently, the ISEG manager is considered one of the members, however, the proposal will not consider the QAS manager as cne of the members. As discussed in section 2.2 of this evaluation, the ISEG will no longer perform a review of plant operation and maintenance auditc. In addition to ISEG staffing expectations, one of ISEG's tasks is to obtain and evaluate " industry and regulatory information." However, since the issuance of NUREG-0737, computerized databases and websites have become more readily available. ISEG staff can now more readily access this information. Also, properly trained station personnel can perform their own review of " industry experience ar.d regulatory information" utilizing the same databases that ISEG uses. The use of modern information retrieval tools has reduced the need for routine retrieval of " industry experience and regulatory information" by an ISEG member. The four ISEG individuals will still perform the ISEG functions in NUREG-0737. The reduction in commitment is acceptable as the ISEG staff will continue to perform the ISEG functions described in NUREG-0737 b a more efficient manner.
2.4 ISEG Qualifications l
l The proposal requests that the USAR be changed to match the qualifications at stated in
! Perry's Operations Requirements Manual (ORM), Revision 0, Section 7.2.2.2. Tha ORM is controlled under 10 CFR 50.59 provisions. The ISEG qualifications were relocated from Perry's TS 6.2.3.2 to its ORM Section 7l2.2.2 by Centerior Energy's letter dated i
i l
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d i
4 l December 16,1993. Currently, the ISEG qualifications in the USAR state that the ISEG is l staffed by engineers and other technically oriented personnel, all of whom have
)
l qualifications comparable to the requirements set forth in ANSI /ANS 3.1, Sections 4.1 and
' l 4.2 (December 1981). However, the licensee proposes to ch.me the qualifications to the l following -
i Each shall have either (1) a bachelor's degree in engineering or related l science and at least 2 years professional experience in their field, at least i 1 year of which experience shall be in the nuclear field, or (2) equivalent l work expcrience as described in Section 4.1 of ANSI /ANS 3.1, December '
1981. The evaluations of the equivalent work experience and its basis
, will be documented and approved by the Manager, Quality Assurance Section. At least half of the ISEG members shallpossess the qualifications described in item 1 above.
L The proposed qualifications are equivalent to the ORM Section 7.2.2.2 (formerly TS
- 6.2.3.2) requirements with the added restriction of at least half the ISEG having the L qualifications described in Item 1. The reduction in commitment is acceptable because l the proposed qualifications match the last approved ISEG qualifications in Perry's TS and the also match the current ORM ISEG qualifications.
3.0 CONCLUSION
The staff has reviewed the July 22,1998 and the September 1,1998 50.54(a) submittals,'in accordance with NUREG-0800," Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants" Chapters 13 and 17. The staff has determined that the changes to the USAR Section 13.4.3,17.2.1.3.2.2,17.2.1.3.2.2.3 and Appendir 1 A, item 1.B.1.2 continues to satisfy the criteria of Appendix B of 10 CFR 50 and, therefore, the changes are found to be acceptable.
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