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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20202B9791997-11-26026 November 1997 Safety Evaluation Accepting Relief Requests 2VR-7 VR-8 from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Inservice Testing Program ML20198Q2821997-10-24024 October 1997 Safety Evaluation Granting Relief for Second 10-yr Interval ISI Program Plan & Associated Requests for Plant ML20217J7071997-10-0909 October 1997 Safety Evaluation Accepting Second 10-yr ISI Interval Relief Request I2R-22 ML20141D0501997-06-23023 June 1997 Safety Evaluation Supporting Requests for Relief to Use ASME Code Case N-508-1 for Plant ML20147C1561997-01-31031 January 1997 Safety Evaluation Accepting Licensee Structural Integrity & Operability ML20247N1811989-09-20020 September 1989 Safety Evaluation Supporting Plant Inservice Testing Program & Request for Relief ML20236C7501989-03-0909 March 1989 SER Supporting Util 880801 Request for Relief from ASME Code Pump & Valve Inservice Testing Program Requirements for Bearing Temp for Safety Injection Pumps ML20153E6921988-09-0101 September 1988 Safety Evaluation Accepting Licensee Program for Equipment Classification & Vendor Interface ML20151H1411988-07-19019 July 1988 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.3 Re Reactor Trip Breaker Automatic Shunt Trip ML20151G5121988-07-15015 July 1988 Safety Evaluation Supporting Amend 17 to License NPF-42 ML20195K0801988-06-17017 June 1988 Safety Evaluation Supporting Amend 16 to License NPF-42 ML20155G1041988-06-0101 June 1988 Safety Evaluation Re Diesel Generator Circuit Breaker Manual Close Capability.Final Design Acceptable ML20153F8471988-05-0202 May 1988 Safety Evaluation Granting Util Relief from Section XI of ASME Code Re Replacement of Parts on Two Code Classed Components ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 ML20148J7351988-01-15015 January 1988 SER of First 10-yr Inservice Testing Program Plan & Requests for Relief from Requirements Concluding That Program as Modified by SER Provides Reasonable Assurance of Operational Readiness of safety-related Pumps & Valves ML20237D7591987-12-16016 December 1987 Safety Evaluation Concluding That Util Proposed ATWS Design in Compliance w/10CFR50.62 & Acceptable,Subj to Final Resolution of Tech Spec Issue & Completion of Certain Human Factors Engineering Reviews ML20236R3241987-11-12012 November 1987 Safety Evaluation Supporting Util Submittal of Rev 2 to First 10-yr Interval Inservice Insp Program Plan ML20205Q7131987-04-0101 April 1987 Safety Evaluation Re Util 861001 Submittal of Analysis of Large Break LOCA in Response to License Condition 2.C.(12). Analysis Acceptable & License Condition 2.C.(12) Satisfied ML20211P1991986-12-15015 December 1986 Safety Evaluation Supporting Util 860123 Response to PTS Rule.Matl Properties & Fast Neutron Fluence Calculations Acceptable Until End of Current License.Reevaluation of Rt (PTS) Required by 10CFR50.61 ML20214W8821986-12-0202 December 1986 Safety Evaluation Supporting Util 850524,1104 & 861105 Submittals Re Process Used to Identify Deviations from Emergency Response Guidelines.Justification Provided for Identifying Deviations Acceptable ML20215K9841986-10-22022 October 1986 SER Supporting Util 831115 & 860812 Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements for safety-related Components,Based on Plans to Address Diesel Generator Testing Concerns ML20236N9221986-10-0707 October 1986 SER Accepting Util 840229 & 860529 Responses to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Re post-maint Testing of Reactor Trip Sys Components ML20215D8321986-10-0707 October 1986 SER Re Util 840229 & 860529 Responses to Generic Ltr 83-28, Items 3.2.1 & 3.2.2 Re post-maint Testing of safety-related components.Post-maint Testing Program Acceptable ML20215D6221986-10-0707 October 1986 SER Re Licensee Response to Generic Ltr 83-28,Item 4.5.1, Reactor Trip Sys Reliability (Sys Functional Testing). Reactor Trip Sys Functional Testing Acceptable ML20203G5361986-07-24024 July 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability ML20211P9321986-07-21021 July 1986 Safety Evaluation Supporting Util Preventive Maint Program for Reactor Trip Breakers in Response to Generic Ltr 83-28 Items 4.1,4.2.1 & 4.2.2 ML20134F5061985-08-16016 August 1985 Safety Evaluation Supporting Util 850522 Description of Mods to Low Temp Overpressure Protection Sys of Rcs.Requirements of License Condition 2.C.(13) Met ML20134F5191985-08-16016 August 1985 Safety Evaluation Supporting Rev 12 to Facility Site Addendum Re Removal of 345 Kv Offsite Transmission Line to West Gardner Switching Station from Design ML20128Q8371985-07-0303 July 1985 SER Supporting Deletion of Pseudo Rod Cluster Control Assembly Drop Test at 50% Power.No Useful Info Would Be Gained from Performance of Test ML20128C8321985-06-26026 June 1985 SER Supporting Licensee Programs Re Generic Ltr 83-28,Item 1.1, Post-Trip Review 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
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4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
RELATED TO REQUESTS FOR RELIEF TO USE ASME CODE CASE N-508-1 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
The Code of Federal Regulations.10 CFR 50.55a, requires that inservice inspection (ISI) of certain ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code applicable Edition and Addenda, except where s)ecific written relief has been requested by the licensee and granted by t1e Commission pursuant to paragraph 10 CFR 50.55a(g)(6)(1), or alternatives approved pursuant to 10 CFR 50.55a(a)(3). In proposed alternatives. the licensee must demonstrate that: (i) the proposed alternatives provide an acceptable level I of quality and safety; or (ii) compliance would result in hardship or unusual '
difficulty without a compensating increase in the level of quality and safety. I In requesting relief, pursuant to 10 CFR 50,55a(g)(5), the licensee must i demonstrate that the requirement is impractical for their facility.
Section 50.55a of Title 10 of the Code of Federal Regulations authorizes the Commission to grant relief from, and authorize alternatives to ASME Code requirements upon making the necessary findings. The NRC staff's finding with respect to whether to grant the relief request as part of the licensee's ISI program or authorize an alternative is contained in this Safety Evaluation (SE).
This SE covers a request for approval to use the ASME Boiler and Pressure Vessel (B&PV) Code Case N-508-1, for Wolf Creek Generating Station (WCGS), as an alternative to the ASME B&PV Code,Section XI, requirements submitted by the Wolf Creek Nuclear Operating Corporation (WCNOC) letter dated January 2, 1997. The licensee's ISI program for the current interval is based on the repair and replacement requirements of Section XI of the ASME B&PV Code.
Section XI. 1989 Edition for the second ten-year ISI program at WCGS,
2.0 BACKGROUND
l ASME Code Section XI Reauirement: Article IWA-7000 Replacement, specifies l the rules and recuirements to be used when replacing, among other items, l relief valves anc snubbers. In th6t article the owner's responsibilities are
! defined and require the owner to develop a replacement program that meets the
- requirements of Section IWA-7130. Replacement Program. When a component is replaced under this program, IAW-7000 requires the preparation of a 9706260249 970623 PDR ADOCK 05000482 P PDR
t l
replacement plan and Form NIS-2, performance of specific Section XI reviews and evaluations, and review and concurrence of the Authorized Nuclear Inspector. These requirements a) ply even when removing and installing relief valves and snubbers solely for t1e purpose of testing.
Code Case N-508-1. " ROTATION OF SERVICED SNUBBERS AND PRESSURE RELIEF VALVES FOR THE PURPOSE OF TESTING. SECTION XI. DIVISION 1" Reauirements: Code Case N-508-1 provides an alternative to Article IWA-7000 when pressure relief valves and snubbers are rotated from stock and installed on components (including piping systems) within the Section XI boundary. Specific requirements, that are detailed in Code Case N-508-1, must be met when rotating components from stock for the purpose of testing. These requirements include: the items must be of the same design and construction:- the items shall have no evidence of failure at the time of removal; items being rotated shall be removed and installed only by mechanical means: items being installed shall previously have been in service: preservice inspections and pressure tests shall be performed as required by IWA-7000; traceability of inservice inspection and testing shall be maintained: the use of an NIS-2 form is not required except for repair or replacement of the rotated item: testing of removed snubbers and pressure relief valves, including required sample expansions, shall be in accordance with the owner's test program: and repair or replacement of removed items shall be performed in accordance with IWA-7000.
Staff Review of Code Case N-508-1: The staff has reviewed Code Case N-508-1 for acceptability and inclusion in Regulatory Guide 1.147. The staff concluded that it would not approve the generic use of the Code Case. The staff's concern was the Code Case did not provide assurance that its application would not adversely impact the existing snubber service life monitoring program. Specifically, when snubbers are rotated between stock and installation, without involving the preparation of a Section XI repair / replacement plan and the subsequent submittal of a Form NIS-2, traceability of the snubbers service life could be compromised.
3.0 RELIEF REQUEST The licensee requests ap3roval to use Code Case N-508-1 for snubbers and pressure relief valves tlat are rotated from stock for the purposes of testing as an alternative to the requirements of ASME Section XI Article IWA-7000, 3.1 Licensee's Basis for Reauested Relief When a snubber or relief valve is removed for the purposes of testing and when -
adequate spares are available. WCNOC rotates a replacement item into its place and tests the removed item at a later time. However, WCNOC could declare the system inoperable, remove the component, perform the test, reinstall the component and then declare the system operable. By rotating the components, WCNOC minimizes the time that the system is inoperable or out-of-service.
Currently, the activity of rotating components is required to be treated as a Section XI replacement activity meeting the requirements of Article IWA-7000.
The requirements of Article IWA-7000 are detailed above. The provisions of I
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3-Article IWA-7000 are appropriate when items are replaced because of a design i change or a nonconformance, but they are excessive for the removal and l
i installation of snubbers and relief valves solely for the purpose of testing.
I The licensee has stated that when performing the rotation of the item in accordance with IWA-7000 or Code Case N-508-1, the following will be required:
(1) a work package will be prepared to control the effort of removing and installing the replacement component from spares: (2) upon installation, the replacement component will receive the recuired inspections and tests: (3) the removed component will be tested in accorcance with required WCNOC test programs for snubbers and relief valves: (4) the work package for relief valves will provide the method for tracking the required inspections and tests: (5) for snubbers the managed maintenance data base will provide the method of tracking the required inspections and tests; and (6) if the removed component requires repair or replacement, these activities will be performed in accordance with Section XI, IWA-4000 or IWA-7000. As required by Code Case f1-508-1, if the item being removed shows evidence of failure, use of the Code !
Case is not acceptable and the removal will be performed and documented in l accordance with IWA-7000. The use of the Code Case only eliminates i unnecessary administrative controls and documentation requirements associated with a Section XI replacement when an item is rotated from stock.
The snubber service life monitoring program is contained in the WCGS Updated Safety Analysis Report (USAR) (previously contained in the technical specifications) which requires inspection and testing of snubbers. Snubbers l are tracked by serial number and are tracked independently from the Section XI l Repair / Replacement Program. Use of Code Case N-508-1 will have no impact on l the implementation of that program. The snubber program will continue to meet '
all requirements contained in the USAR.
3.2 Evaluation Code Case N-508-1 provides an alternative to the current ASME B&PV Code,Section XI, Article IWA-7000 requirement to generate a Repair / Replacement Program when removing snubbers or 3ressure relief valves from a system for testing. The Code Case allows snu)bers and pressure relief valves to be rotated from stock and installed on components and piping systems within the Section XI boundary, provided all the requirements stated in the Code Case are met. The use of the Code Case eliminates only certain administrative controls and docu,nentation requirements associated with a Section XI replacement.
The licensee has agreed to meet all of the Code Case requirements. Further, if the component being removed shows evidence of failure, the licensee will not use Code Case N-508-1, but will use Section XI Article IWA-7000 of the ASME B&PV Code for repair or replacement activities.
In response to the staff's concern about the impact of the use of Code Case 1 N-508-1 on the snubber service life monitoring program, the licensee has I
stated the snubber service life monitoring program as contained in the WCGS USAR will be continued. Snubbers will continue to be tracked by serial number independently of the Section XI Repair / Replacement Program. Further, the
s t
-licensee states that. "Use of Code Case N-508-1 will have no impact on the implementation of the snubber service life monitoring program,"
The licensee's proposed alternative to use the Code Case for the purpose of testing snubbers and pressure relief valves will eliminate unnecessary administrative and documentation requirements, minimize the time during which the affected system is out-of-service, and component reliability will be maintained in that previously tested components will be used for rotation.
In considering the proposed use of Code Case N-508-1 for the WCGS, and the licensee's argument in addressing the staff's concerns with regard to an adverse impact on the existing snubber service life monitoring program, the staff has determined that the application is acceptable. The use of Code Case N-508-1, with the provision that the snubber service life monitoring program is not changed. provides and acceptable level of quality and safety.
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3.0 CONCLUSION
S The staff concludes that the licensee's proposed alternative to use Code Case N-508-1 for rotation of serviced snubbers and pressure relief valves for the purpose of testing in lieu of ASME B&PV Code,Section XI, Article IWA-7000 requirements provides an acceptable level of quality and safety for Wolf Creek i Generating Station in that it only affects the administrative and l documentation requirements of Section XI. Therefore, the licensee's proposed alternative with the clarification of the snubber service life monitoring program contained in the request for approval, is authorized by law, pursuant to 10 CFR 50.55a(a)(3)(i), for the first and second 10-year ISI interval, provided that all requirements of Code Case N-508-1 are satisfied. Use of Code Case N-508-1 is authorized until such time as the Code Case is published in a future revision of Regulatory Guide 1.147. At that time, if the licensee intends to continue to implement this Code Case, the licensee is to follow all provisions in Code Case N-508-1 with the limitations issued in Regulatory Guide 1.147, if any.
l Principal Contributor: F. Grubelich I J. Stone l
Date: June 23, 1997 I
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