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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 ML20211A7641999-08-11011 August 1999 Safety Evaluation Supporting Amends 190 & 195 to Licenses DPR-24 & DPR-27,respectively ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20206A5031999-04-23023 April 1999 Safety Evaluation Supporting Amends 189 & 194 to Licenses DPR-24 & DPR-27,respectively ML20207L3471999-03-0202 March 1999 Safety Evaluation Supporting Amends 187 & 192 to Licenses DPR-24 & DPR-27,respectively ML20207K2751999-03-0202 March 1999 Safety Evaluation Supporting Amends 188 & 193 to Licenses DPR-24 & DPR-27,respectively ML20207D5691999-03-0101 March 1999 Safety Evaluation Supporting Amends 186 & 191 to Licenses DPR-24 & DPR-27,respectively ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 ML20236U7201998-07-21021 July 1998 Safety Evaluation Supporting Amend 190 to License DPR-27 ML20236T1761998-07-17017 July 1998 Safety Evaluation Supporting Amends 185 & 189 to Licenses DPR-24 & DPR-27,respectively ML20236S0161998-07-13013 July 1998 Safety Evaluation Supporting Amends 184 & 188 to Licenses DPR-24 & DPR-27,respectively ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6061998-07-0808 July 1998 Safety Evaluation Granting Request for Relief RR-2-23,from Performing ASME Code,Section XI Volumetric Coverage Requirements for SG nozzle-to-safe End Welds & Associated Safe end-to-pipe Welds During Third 10-yr ISI Interval ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20217K4721998-03-24024 March 1998 Safety Evaluation Supporting Amends 183 & 187 to Licenses DPR-24 & DPR-27,respectively ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant ML20248L8641998-03-17017 March 1998 Safety Evaluation Supporting Amends 182 & 186 to Licenses DPR-24 & DPR-27,respectively ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 ML20198L4671998-01-0202 January 1998 SER Approving Request for Relief VRR-4B to Inservice Testing Program Wisconsin Electric Power Co,Point Beach Nuclear Plant,Units 1 & 2 ML20197J9341997-12-12012 December 1997 Safety Evaluation Accepting Licensee Request for Relief from Performing Inservice Volmetric Exam of Inaccessible Portions of RPV Lower Shell to Lower Head Ring Weld During 10-yr ISI Interval of Plant,Unit 2 ML20217D7111997-09-29029 September 1997 Safety Evaluation Supporting Amends 181 & 185 to Licenses DPR-24 & DPR-27,respectively ML20236R9571997-09-23023 September 1997 Safety Evaluation Supporting Amends 180 & 184 to Licenses DPR-24 & DPR-27,respectively ML20210S9821997-09-0404 September 1997 Safety Evaluation Supporting Amends 179 & 183 to Licenses DPR-24 & DPR-27,respectively ML20216G5781997-09-0303 September 1997 Safety Evaluation Supporting Amends 178 & 182 to Licenses DPR-24 & DPR-27,respectively ML20210Q0231997-08-25025 August 1997 Safety Evaluation Supporting Amends 177 & 181 to Licenses DPR-24 & DPR-27,respectively ML20217H4241997-08-0606 August 1997 Safety Evaluation Supporting Amends 175 & 179 to Licenses DPR-24 & DPR-27,respectively ML20198F0261997-08-0606 August 1997 Safety Evaluation Supporting Amends 176 & 180 to Licenses DPR-24 & DPR-27,respectively ML20149E8331997-07-16016 July 1997 Corrected Pages 9 & 20 to SER for Amends 174 & 178 to Licenses DPR-24 & DPR-27,respectively ML20217N3741997-07-0909 July 1997 Safety Evaluation Supporting Amends 174 & 178 to Licenses DPR-24 & DPR-27,respectively ML20148U4811997-07-0101 July 1997 Safety Evaluation Supporting Amends 173 & 177 to Licenses DPR-24 & DPR-27,respectively ML20137U4991997-04-10010 April 1997 Safety Evaluation Accepting Proposed Alternatives Contained in Requests for Relief RR-1-17 & RR-2-21 ML20138M0571997-02-20020 February 1997 Safety Evaluation Supporting Amends 172 & 176 to Licenses DPR-24 & DPR-27,respectively ML20133G3111997-01-0808 January 1997 Safety Evaluation Supporting Amends 170 & 174 to Licenses DPR-24 & DPR-27,respectively ML20128P4731996-10-0909 October 1996 Safety Evaluation Supporting Amends 169 & 173 to Licenses DPR-24 & DPR-27,respectively ML20129G6901996-10-0303 October 1996 SER Accepting Request for Relief from ASME Code Repair Requirements for ASME Code Class Three Piping at Plant ML20133N4281996-07-16016 July 1996 Safety Evaluation Supporting Amends 171 & 175 to Licenses DPR-24 & DPR-27,respectively ML20101E1851996-03-20020 March 1996 Safety Evaluation Supporting Amends 168 & 172 to Licenses DPR-24 & DPR-27,respectively ML20095K6471995-12-27027 December 1995 Safety Evaluation Supporting Amends 167 & 171 to Licenses DPR-24 & DPR-27,respectively ML20094P3741995-11-22022 November 1995 Safety Evaluation Supporting Amends 166 & 170 to Licenses DPR-24 & DPR-27,respectively ML20094M3101995-11-17017 November 1995 Safety Evaluation Supporting Amends 165 & 169 to Licenses DPR-24 & DPR-27,respectively ML20093E9591995-10-12012 October 1995 Safety Evaluation Supporting Amends 163 & 167 to Licenses DPR-24 & DPR-27,respectively ML20093H7051995-10-12012 October 1995 Safety Evaluation Supporting Amends 164 & 168 to Licenses DPR-24 & DPR-27,respectively ML20086E6271995-07-0505 July 1995 Safety Evaluation Supporting Amends 162 & 166 to Licenses DPR-24 & DPR-27,respectively ML20080R4731995-03-0606 March 1995 Safety Evaluation Supporting Amends 161 & 165 to Licenses DPR-24 & DPR-27,respectively ML20078C2571995-01-18018 January 1995 Safety Evaluation Supporting Amends 160 & 164 to Licenses DPR-24 & DPR-27,respectively ML20079A1071994-12-21021 December 1994 Safety Evaluation Supporting Amends 159 & 163 to Licenses DPR-24 & DPR-27,respectively 1999-09-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with 05000266/LER-1999-007, :on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier1999-09-30030 September 1999
- on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier
ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 05000266/LER-1999-004, :on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated1999-09-0202 September 1999
- on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated
NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with ML20211A7641999-08-11011 August 1999 Safety Evaluation Supporting Amends 190 & 195 to Licenses DPR-24 & DPR-27,respectively NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with 05000301/LER-1999-003-01, :on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created1999-05-28028 May 1999
- on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created
05000266/LER-1999-004, :on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG1999-05-20020 May 1999
- on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG
05000266/LER-1999-003, :on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With1999-05-0606 May 1999
- on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With
ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20206A5031999-04-23023 April 1999 Safety Evaluation Supporting Amends 189 & 194 to Licenses DPR-24 & DPR-27,respectively 05000301/LER-1999-002-01, :on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction1999-04-16016 April 1999
- on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction
NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with 05000301/LER-1999-001-01, :on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output1999-03-10010 March 1999
- on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output
ML20207K2751999-03-0202 March 1999 Safety Evaluation Supporting Amends 188 & 193 to Licenses DPR-24 & DPR-27,respectively ML20207L3471999-03-0202 March 1999 Safety Evaluation Supporting Amends 187 & 192 to Licenses DPR-24 & DPR-27,respectively ML20207D5691999-03-0101 March 1999 Safety Evaluation Supporting Amends 186 & 191 to Licenses DPR-24 & DPR-27,respectively NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20236U7201998-07-21021 July 1998 Safety Evaluation Supporting Amend 190 to License DPR-27 ML20236T1761998-07-17017 July 1998 Safety Evaluation Supporting Amends 185 & 189 to Licenses DPR-24 & DPR-27,respectively 05000266/LER-1998-015, :on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed1998-07-17017 July 1998
- on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed
05000266/LER-1998-019, :on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating1998-07-14014 July 1998
- on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating
ML20236S0161998-07-13013 July 1998 Safety Evaluation Supporting Amends 184 & 188 to Licenses DPR-24 & DPR-27,respectively ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6061998-07-0808 July 1998 Safety Evaluation Granting Request for Relief RR-2-23,from Performing ASME Code,Section XI Volumetric Coverage Requirements for SG nozzle-to-safe End Welds & Associated Safe end-to-pipe Welds During Third 10-yr ISI Interval ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 1999-09-30
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ME:o UNITED STATES
[,
j NUCLEAR REGULATORY COMMISSION g
t WASHINGTON, D.C. 2066H001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO NUCLEAR QUALITY ASSURANCE PROGRAM CHANGES WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT. UNITS 1 ANDJ, DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
In letters dated November 16,1998, and November 30,1998, the Wisconsin Electric Power Company (WE), in accordance with requirements in 10 CFR 50.54(a)(3), submitted two letters transmitting revisions to Section 1.4 of the Final Safety Analysis Report (FSAR) for Point Beach Nuclear Plant, Units 1 and 2 (PBNP). Section 1.4 of the FSAR describes the current Nuclear Quality Assurance (OA) Program implemented at PBNP. The proposed changes consist of reassigning the reporting requirements of the Non-Destructive Examination (NDE) Services group from the Nuclear Assurance Manager to the Engineering Programs group in the corporate offices in Milwaukee. Another proposed change would revise Quality Verification's (OV) responsibilities for tracking deficiencies identified during audits, surveillances, and work monitoring reports to be required only for QA program deficiencies. FSAR page 1.4-4 and Figure 1.4-1 have already been changed from the current FSAR page 1.4-4 and Figure 1.4-1 because they were determined not to be a reduction in commitment by the licensee, and therefore were not submitted to the NRC for approval.
2.0 EVALUATION 2.1 Reassionina the Reportina Reauirements of NDE Services Group The proposed changes would consist of replacing the phrase "The OA section is divided into five groups (see Figure 1.4-1) three of which have specific OA responsibilities, summarized as follows:" on FSAR page 1.4-4 with the phrase "The Nuclear Assurance section organization is depicted in Figure 1.4-1." The proposed change would also delete the discussion of the NDE Services responsibilities of the Nuclear (Quality) Assurance Manager on FSAR page 1.4-6 and would revise FSAR Figure 1.41 to reflect that the NDE Services group no longer reports to the Nuclear Assurance Manager.
The changes would eliminate the engineering and administrative duties of the Nuclear Assurance Manager related to managing the NDE Services group. This change is a reduction in commitment because the NDE Services group would no longer report to the Nuclear Assurance section, which is independent of the line organization. The NDE Services group is ENCLOSURE 9901200443 990113 PDR ADOCK 05000266 P
PDR
2 currently identified as having' specific OA responsibilities on FSAR page 1.4-6. Although the NDE Services group is no longer organizationally independent of the line organization, the NDE Services group will still be independent of those groups actually performing or directly supervising the work being inspected. This is permitted by ANSI Standard N18.7-1976, j
Section 3.2, which states, "(2) Verification of conformance to established requirements is j
accomplished by a qualified person who does not have responsibility for performing or directly j
supervising work."
l Control of NDE services performed by the NDE Services group will continue to be described in FSAR Sections 1.4.9 and 1.4.10. FSAR Section 1.4.9, " Control of Special Processes," states, j
" Procedures and practices are established and documented to assure that special processes, such as welding, heat treating, and nondestructive examinations are controlled and i
accomplished by qualified personnel using qualified procedures or process sheets in accordance with applicable codes and standards." FSAR Section 1.4.10 " Inspection," states, j
"All nondestructive examination personnel are required to be qualified in accordance with the appropriate sections and editions of ASNT [American Society for Nondestructive Testing]
Recommended Practice No. SNT-TC-1 A." The Quality Verification group, under the Nuclear Assurance section, will continue to provide independent oversight of the NDE Services group as pad of the independent quality verifying activities prescribed by FSAR Section 1.4.
2.2 Trackina Deficiencies Another proposed change would consist of revising Quality Verification's (QV) responsibilities for tracking deficiencies identified during audits, surveillances, and work monitoring reports to s
i be required only for OA program deficiencies. This proposed change would consist of deleting j
the word " deficiencies" and replacing it with "QA program deficiencies" and deleting the word "not" and adding " including those initiated as a result of quality assessments which are not QA program deficiencies"in the first and second sentences respectively of the FSAR Section 1.4.1, Quality Verification (item 8). The proposed changes would also delete " deficient areas" and add "QA program deficiencies" under FSAR 1.4.18.
ANSI Standard N45.2.12-1977, to which WE is committed, defines, in part, in Section 1.4 a OA program deficiency as a " Failure to develop, document, or implement effectively any applicable element of the quality assurance program...." It then establishes in Section 3.2.4-5 that the objectives of QA assessments are to identify both nonconformances and QA program deficiencies, but to (only] verify correction of identified QA program deficiencies. ANSI Standard N45.2.12-1977 Section 4.3.2.4-7 states, "When a nonconformance or quai!ty assurance program deficiency is identified as a result of an audit, further investigation shall be conducted by the audited organization in an effort to identify the cause and effect and to determine the exterit of the corrective action required. Nonconformances or quality assurance program deficiencies should be acknowledged by a member of the audited organization.
Conditions requiring immediate corrective action shall be reported immediately to management of the audited organization. Specific attention should be given to corrective action on program deficiencies identified during previous audits." Also, ANSI Standard N18.7-1976, Section 5.2.14, " Nonconforming items," to which WE is committed, states in part, " Measures shall be provided to control items, services or activities which do not conform to requirements.
These procedures shall include as appropriate, instructions for identification, documentation, segregation, disposition and notification to affected organizations. Nonconforming items shall be reviewed and accepted, rejected, repaired or reworked in accordance with documented
3 procedures.' The responsibility and authority for the disposition of nonconforming items shall be defined. Repaired and reworked items shall be reinspected in accordance with applicable procedures."
3.0 CONCLUSION
The staff has reviewed the November 16,1998, and November 30,1998,10 CFR 50.54(a) submittals in accordance with NUREG-0800, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," Chapters 17.1 and 17.2, and determined that the changes to the FSAR Section 1.4 continue to satisfy the criteria of Appendix B to 10 CFR Part 50. PBNP states that the nonconformances discovered during the audit process will be entered into the corrective action program as a Condition Report and tracked or monitored by other Nuclear Power Business Unit groups to closure within the corrective action program. This is acceptable because (1) PBNP continues to fully implement ANSI Standard N45.2.12-1977 and ANSI Standard N18.7-1976, and (2) the QV organization will continue to audit the overall corrective action program under its Appendix B,10 CFR Part 50 QA program as described in FSAR Sections 1.4.16 and 1.4.18.
Principal Contributor: M. Bugg Date: January 13, 1999 i