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Category:QUALITY ASSURANCE PROGRAM
MONTHYEARML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20107K2741996-04-12012 April 1996 Rev 20 to Operational QA Plan ML20085J7661995-05-19019 May 1995 Rev 19 to Operational QA Plan ML20069D1531994-04-26026 April 1994 Rev 18 to Operational QA Plan ML20105D0561992-05-18018 May 1992 Rev 16 to Operational QA Plan ML20248A9311989-05-25025 May 1989 Rev 13 to Operational QA Plan ML20150F8091988-05-26026 May 1988 Rev 12 to Operational QA Plan ML1129903921980-02-28028 February 1980 Changes to QA Program for Operations Phase of Facility ML20127N9151977-11-15015 November 1977 Rev 2 to, Operational QA Plan ML20091A2381976-09-24024 September 1976 Operational QA Plan, Rev 1 ML20091A8401976-06-17017 June 1976 Rev 0 to Operational QA Plan 1998-03-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203G1431998-02-10010 February 1998 Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531 ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20202F9161998-01-29029 January 1998 Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 ML20216D2071997-12-31031 December 1997 1997 Annual Rept for Northern States Power Co ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199G7051997-11-19019 November 1997 Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump 1999-09-30
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REPORT OF CHANGES TO THE NSP OPERATIONAL QUALITY ASSURANCE PLAN Northern States Power Company (NSP) submitted its Operational Quality Assurance Plan, Rev 2, to NRC Division of Operating Reactors for review by letter dated November 22, 1977. A letter from D K Davis, NRC Operating Reactors Branch #2, dated December 29, 1977, stated that the Operational Quality Assurance Program, Rev. 2, is acceptable for the operations phase of the Monticello and Prairie Island Nuclear Generating Plants.
By letter dated June 27, 1978, NSP submitted its Operational Quality Assurance Plan, Rev. 3, to the Director, Office of Nuclear Material Safety and Safeguards (with copy to Division of Operating Reactors). Revision 3 incorporated Quality Assurance requirements for the use of packages for transport of radioactive materials, pursuant to 10 CFR 71.51, and included minor editorial, organization and title changes. A letter from the NRC Transportation Branch, Division of Fuel Cycle and Material Safety, dated April 2, 1979, transmitted Quality Assurance Program Approval for Radioactive Packages, No. 0083, Rev. 0.
Revision 4 to the NSP Operational Quality Assurance Plan was internally re viewed and approved on January 24, 1980. We have concluded that the changes do not decrease the effectiveness of NSP's Operational Quality Assurance Program.
Although the changes became effective in 1980, a summary of the changes is included with this report of 1979 changes, tests and experiments for convenience and more timely documentation. Copies of the Operational Quality Assurance Plan, Rev 4, are available at the Monticello and Prairie Island Nuclear Generating Plants and at the NSP corporate office for review by IE-III personnel.
Summary of Changes
- 1. Page 1; NSP Fire Protection Program Outline has been added to Section 1.0 to provide a basis for incorporating fire protection QA requirements into the Operational Quality Assurance Program.
- 2. Page 2; ANSI N 45.2.9 has been deleted. Record requirements have been explicitly identified in Section 19 and Section 5.
- 3. Page 2; Changed commitment to the current revision of ANSI N 45.2.12.
- 4. Page 3; Revised the exceptions to ANSI N18.7-1976. Eliminated environmental monitoring since it is not a safety-related activity. Referenced the section of the Q.A. plan that explicity identifies records management.
- 5. Page 4; Revised the exceptions to ANSI N18.7-1976. Provided explicit references to the sections of the Operational Quality Assurance Plan or the Construction Quality Assurance Program with regard to various 5.0 subsections of ANSI N18.7-1976.
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- 6. Section 2.0; Full implementation of the Operational Quality Assurance Programs was changed from "Commercial Operation" to "satisfactory com pletion of the pre-operational and startup test program". Commercial Operation" is not an easily identified point in plant history.
- 7. Section 3.0; Numerous changes were made in this section due to NSP organiza tional changes including the following:
(a) Promotion of the General Manager Power Production to Vice President Power Production (the Vice President Power Production reports to the Executive Vice President - D W Angland).
(b) Transfer of Nuclear Support Services to Power Production.
(the Manager Nuclear Support Services reports to the Vice President Power Production).
(c) Transfer of Supplier Inspection responsibility from the Plant Engineering & Construction Department to the Quality Assurance Section of Power Production.
(d) Promotion of the Plant Quality Engineer to Superintendent Quality Engineering (the Superintendent Quality Engineering reports to the Plant Manager).
- 8. Section 4.2; The Power Production & System Operation Level of the Program has been deleted due to reorganization. The requirements associated with the following organizations will be incorporated into the Corporate Level Administrative Control Directives:
(a) Maintenance & Testing Department (b) System Operation (c) Fuel Supply
- 9. Page 30; The Spent Fuel Bridge Crane has been added to Table 4-2 (Item 18).
- 10. Section 5.2.2; The responsibility for major modifications has been assigned to the Plant Engineering & Construction Department, (PE&C). Such modifica tions are required to be performed in accordance with the provision of the0 PE&C Quality Assurance Program. The required provisions of the PE&C Quality Assrance Program are identified.
- 11. Section 7.3; Inspection Procedures have been added to the list of required procedures.
- 12. Section 9.2; The applicable elements associated with vendor's Quality Assurance Programs have been changed from 10CFR 50 Appendix B to ANSI N 454.2-1976 to establish program consistency.
- 13. Section 11.2; Brazing has been added.
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- 14. Section 12; This section has been revised to explicitly identify the inspection program. The intent is to explicitly identify the scope of the inspection program in a manner consistent with the inspection require ments of ANSI N 18.7 - 1976.
- 15. Section 13.2; Inservice Inspection function testing of pumps and valves has been added.
- 16. Section 16.4; Independent verification of safety tagging has been added.
- 17. Section 16.6; Independent verification of bypasses and requirements asso ciated with fire protection bypasses has been added.
- 18. Section 19; The following changes have been made:
(a) Record retention periods have been added.
(b) Records management requirements have been added.
- 19. All Sections; The references included in each section have been deleted.
The Administrative Control Directives and Administrative Work Instructions utilized to implement the requirements of the Operational Quality Assurance Plan will be identified in the index required by Section 4.8.