Letter Sequence Approval |
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EPID:L-2018-LLR-0381, Relief Requests Associated with Sixth Ten-Year Lnservice Testing Interval (Approved, Closed) |
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MONTHYEARML18347B0362018-12-13013 December 2018 Relief Requests Associated with Sixth Ten-Year Lnservice Testing Interval Project stage: Request ML19205A4532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives PR-01 and PR-02 for Sixth 10-Year Inservice Testing Program Project stage: Approval 2018-12-13
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Similar Documents at Ginna |
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Category:Code Relief or Alternative
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Ginna Nuclear Power Plant Relief Requests VR-1, VR-2 and VR-13 for the Fourth 10-Year Interval of the Pump and Valve Inservice Testing Program ML0330401202003-11-21021 November 2003 R. E. Ginna Nuclear Power Plant, Relief Request Review, Inservice Testing Program Relief Requests VR-4 and VR-8 ML0329603222003-10-20020 October 2003 Submittal of Relief Request VR-4 Related to the Requirements of 10CFR50.55a(f), Inservice Testing Requirements. ML0304202642003-02-10010 February 2003 R. E. Ginna Nuclear Power Plant, Relief, Inservice Testing Program Relief Request PR-2, MB7232 ML0314205202003-01-0909 January 2003 Enclosure - R.E. Ginna, Inservice Testing Program Relief Request PR-2 2023-03-16
[Table view] Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23258A1382023-09-18018 September 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000244/2023010 IR 05000244/20230052023-08-31031 August 2023 Updated Inspection Plan for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report IR 05000244/20234012023-08-15015 August 2023 LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only) IR 05000244/20230022023-08-0303 August 2023 LLC - Integrated Inspection Report 05000244/2023002 ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 IR 05000244/20234022023-07-19019 July 2023 R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only) RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23135A0412023-05-15015 May 2023 2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report ML23121A0482023-05-0101 May 2023 R. E. Ginna Nuclear Power Plant Core Operating Limits Report Cycle 44, Revision 0 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000244/20230012023-04-26026 April 2023 LLC - Integrated Inspection Report 05000244/2023001 ML23100A0302023-04-10010 April 2023 2023 10 CFR 50.46 Annual Report ML23114A1152023-03-29029 March 2023 Electronic Reporting of Exposure Data for 2022 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23075A0872023-03-15015 March 2023 R. E. Ginna Nuclear Power Plant - Project Manager Assignment ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000244/20220062023-03-0101 March 2023 Annual Assessment Letter for R.E. Ginna Nuclear Power Plant, LLC (Report 05000244/2022006) ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23060A1622023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators ML22287A0692023-02-0808 February 2023 R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23031A2992023-02-0707 February 2023 R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request ML23010A0112023-02-0101 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000244/20223012023-01-20020 January 2023 Initial Operator Licensing Examination Report 05000244/2022301 IR 05000244/20220122023-01-12012 January 2023 LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012 ML22362A0382022-12-28028 December 2022 R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML22348A2062022-12-14014 December 2022 Re. 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[Table view] Category:Safety Evaluation
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Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22094A1072022-06-22022 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 151 Adopt 10 CFR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22119A0942022-06-21021 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 150 Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21250A3822021-09-29029 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request I6R-06 Alternate Inspection for Reactor Vessel Internals ML21246A1062021-09-22022 September 2021 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Alternative Request GR-03, Valve Position Verification Testing Extension Sixth 10-Year Inservice Testing Program Interval ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21175A0012021-07-27027 July 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 145 Regarding Technical Specifications Change to Make a One-Time Exception to the Steam Generator Tube Inspection Requirements ML21166A1682021-06-25025 June 2021 ML20353A1262021-03-11011 March 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20090D2912020-06-0202 June 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval (EPID L-2019-LLR-0071). Supersedes ML20056D559 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20057E0912020-04-0303 April 2020 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method ML20056D5592020-03-13013 March 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-02 for the Sixth 10-Year Inservice Inspection Interval ML20055F8862020-03-13013 March 2020 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternative I6R-01 for the Sixth 10-Year Inservice Inspection Interval ML19325D8242019-12-23023 December 2019 R. E. Ginna Nuclear Power Plant Issuance of Amendment No. 136 to Revise Technical Specification 5.5.15, Containment Leakage Rate Testing Program, to Extend Containment Integrated Leak Rate Test Frequency ML19318E0802019-12-0202 December 2019 R. E. Ginna Nuclear Power Plant - Safety Evaluation of Alternative Request SR-1 Related to Snubber Program Aligned with Sixth 10-Year Inservice Testing Interval Program ML19252A2462019-10-29029 October 2019 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 134 to Revise the Emergency Response Organization Staffing Requirements ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19205A4532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives PR-01 and PR-02 for Sixth 10-Year Inservice Testing Program ML19205A3532019-08-0505 August 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Alternatives GR-01, VR-01, and VR-02 for the Sixth 10-Year Inservice Testing Program (EPID L-2018-LLR-0382; EPID L-2018-LLR-0383) ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19100A0042019-04-22022 April 2019 R. E. Ginna Nuclear Power Plant - Issuance of Relief Request ISI-18 Regarding Fifth 10-Year Inservice Inspection Program Interval ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18213A3692018-11-13013 November 2018 Issuance of Amendment No. 132 Revise Technical Specifications 3.3.1, Reactor Trip System Instrumentation, and 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML18295A6302018-10-31031 October 2018 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 131 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF 547, Clarification of Rod Position Requirements ML18214A1762018-08-31031 August 2018 Issuance of Amendment No. 130, Revise Technical Specification Surveillance Requirement 3.8.4.3, DC (Direct Current) Sources - Modes 1, 2, 3, and 4 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18190A4722018-07-12012 July 2018 R.E Ginna - Correction to Amendment No. 127 Related to Request to Delete a Modification Associated with the Risk-Informed, Performance Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (CAC No. MF9948; EPID L-2017-LLA-0253) ML18137A6142018-06-26026 June 2018 Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes ML18114A0252018-06-25025 June 2018 Issuance of Amendment No. 127, Modify License Condition 2.C.(3) Related to Commitment Associated with Implementation of National Fire Protection Association Standard 805 (CAC MF9948; EPID L-2017-LLA-0253) 2023-08-30
[Table view] |
Text
August 5, 2019 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
R. E. GINNA NUCLEAR POWER PLANT- ISSUANCE OF RELIEF REQUEST ASSOCIATED WITH ALTERNATIVES PR-01 AND PR-02 FOR THE SIXTH 10-YEAR INSERVICE TESTING PROGRAM (EPID L-2018-LLR-0381)
Dear Mr. Hanson:
By letter dated December 13, 2018 (Agencywide Documents Access and Management System Accession No. ML18347B036), Exelon Generation Company, LLC (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) associated with pump inservice testing for the R. E. Ginna Nuclear Power Plant.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use the proposed alternatives in requests PR-01 and PR-02 on the basis that the ASME OM Code requirements present an undue hardship, without a compensating increase in the level of quality or safety.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
Therefore, the NRC staff authorizes the use of these alternative requests for the sixth 10-year inservice testing program interval, which begins on January 1, 2020, and is scheduled to end on December 31, 2029.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable.
B Hanson If you have any questions, please contact the R. E. Ginna Nuclear Power Plant Project Manager, V. Sreenivas, at 301-415-2597 or V.Sreenivas@nrc.gov.
Sincerely,
/RA/
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUESTS PR-01 AND PR-02 FOR SIXTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM EXELON GENERATION COMPANY, LLC R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
1.0 INTRODUCTION
By letter dated December 13, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18347B036), Exelon Generation Company, LLC (the licensee) submitted alternatives to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) associated with pump inservice testing (IST) at R.E. Ginna Nuclear Power Plant (Ginna).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use the proposed alternatives in requests PR-01 and PR-02 on the basis that the ASME OM Code requirements present an undue hardship, without a compensating increase in the level of quality or safety.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(f), states, in part, that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations.
The regulation in 10 CFR 50.55a(z) states that alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC), if the licensee demonstrates (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
3.0 TECHNICAL EVALUATION
3.1 Licensees Alternative Request PR-01 The licensee requested an alternative to the pump testing requirements of the ASME OM Code.
Enclosure
ISTB-3550, Flow Rate, states, in part, When measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall include the method used to reduce the data.
The licensee has requested to use the proposed alternative described below for the fuel oil transfer pumps listed in Table 1.
Table 1 Component Description ASME Code Class ASME OM Pump Category PDG02A Diesel Fuel Oil Transfer 3 B Pump A PDG02B Diesel Fuel Oil Transfer 3 B Pump B The Ginna sixth 10-year IST program interval begins on January 1, 2020, and is scheduled to end on December 31, 2029. The applicable ASME OM Code edition for the Ginna sixth 10-year IST program interval is the 2012 Edition.
Reason for Request
The licensee stated:
The diesel fuel oil transfer pumps are required to transfer fuel oil from the storage tank to the day tank. This function ensures a continuous fuel supply to support long term operation of the diesel during accident conditions.
There are no installed instruments on the diesel fuel oil transfer system that allow a direct measurement of the flow rate when testing the diesel oil fuel transfer pumps. The pump flow rate can be calculated by measuring the change in day tank level or volume and the pump operation time required to make that change.
The accuracy of this method is documented in design analysis Engineering Work Request (EWR) 4526-ME-20. This method determines a flow rate for a pump that can be used to evaluate the pump's hydraulic performance.
Proposed Alternative The licensee stated:
Ginnas diesel fuel oil transfer pumps, PDG02A & PDG02B, are positive displacement pumps. The flow rate for these pumps is determined by measuring the indicated level change in the diesel generator fuel oil day tank during a timed pump run and converting this data into fuel oil transfer pump flow rate for both the Group B and comprehensive pump tests.
Level gauges LG-2044 (A Emergency Diesel Generator) and LG-2045 (B Emergency Diesel Generator) are utilized to measure the change in indicated level while the fuel oil transfer pump is running and restoring fuel oil day tank level. Both LG-2044 and LG-2045 (sight glasses equipped with a reference
scale in inches of level) have a range of indicated level of 9 inches (2.5 inches to 11.5 inches).
The respective day tank is drained to an initial indicated level of 5.0 to 5.5 inches before initiating the fuel oil pump start. This level is logged as the initial level.
The pump is then started coincident with starting the stopwatch and the system allowed to stabilize. A minimum 2-minute stabilization period is observed for the comprehensive test.
Following a total minimum run time of 5 minutes (or exceeding an indicated tank level of 11 inches), the pump is stopped coincident with stopping the stopwatch and the day tank level is read in inches to the nearest 0.25 inch. This level is logged as the final level.
The change in day tank level is determined in inches and then converted to total gallons pumped using the constant conversion factor of 24.76 gallons per inch.
The constant of 24.76 gallons per inch of indicated level on the day tank sight glass was established by EWR 4526-ME-20 based on the tanks geometrical dimensions. The total gallons pumped is then divided by the total pump run time to arrive at the pump test flow rate in gallons per minute (gpm). This calculation is documented in the pump test procedures.
The test circuit for each pump is a fixed flow path from the storage tank (pump suction) to the day tank (pump discharge). Pump suction pressure is nearly constant because of the very small change in storage tank level. This change in suction pressure during pump operation is considered negligible. The normal rise in day tank level is approximately 5.5 inches, which corresponds to a quantity of approximately 136 gallons pumped during the 5 minutes of pump operation, resulting in a typical flow rate of approximately 27 gpm.
The small rise in day tank level during pump operation does not affect pump discharge pressure or flow rate. This conclusion is supported by the discussion in NUREG-1482, Revision 2, Section 5.5.2, Use of Tank Level to Calculate Flow Rate for Positive Displacement Pumps, where the NUREG states: Pump discharge pressure will match system pressure up to the shutoff head of the positive displacement pump. Because of the characteristics of a positive displacement pump, there should be virtually no change in pump discharge flow rate as a result of the rising tank level. Therefore, rising tank level will not have an impact on test results. By having approximately the same level in the tank at the beginning of each test, licensees can achieve repeatable results.
The accuracy of level gauges, LG-2044 and LG-2045, is determined using the 9-inch indicated range of level and the constant of 24.76 gallons per inch. This yields a total volume change of 222.84 gallons. Based on a readability uncertainty of +/-0.125 inch (0.25-inch scaling), which is equivalent to 3.10 gallons, divided by the total indicated volume of 222.84 gallons, the overall accuracy of the sight glass is +/- 1.39%.
In addition, the stopwatch used to measure the time the pump is operating and pumping fuel oil is now accurate to within +/-3 seconds per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (formerly
+/-0.6 second per minute) [the licensees submittal stated +/-0.6% second per
minute, which they have stated is incorrect] for a calibrated accuracy of +/-0.004%
(formerly +/-1.0%). Combining the accuracy of the stopwatch with the level gauge sight glass, using the square root of the sum of the squares method, results in an insignificant decrease with an overall indicated accuracy of +/-1.39% (formerly
+/-1.71%). This overall accuracy has been improved from that which was provided in the alternative previously authorized for use during the fifth 10-year interval IST program.
Therefore, the pump flow rate can be accurately calculated by measuring the change in day tank level or volume and the pump operation time required to make that change. This method determines a flow rate for these pumps that can be used to evaluate the pumps hydraulic performance and provide reasonable assurance of pump operational readiness. Therefore, relief is requested pursuant to 10 CFR 50.55a(z)(2) based on the determination that compliance with the Code pump testing requirements regarding pump flow rate cannot be achieved without resulting in a hardship or unusual difficulty without a compensating increase in the level of quality and safety; and the proposed alternative of using the tank level change vs. time to calculate the flow rate provides reasonable assurance of operational readiness and provides an acceptable level of quality and safety.
NRC Staff Evaluation
The licensee proposes alternative testing for the diesel fuel oil transfer pumps. The current configuration does not meet the requirements of ISTB-3550, which states that when measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. The licensees proposed alternative test shall determine the flow rate by calculation of day tank level versus time. The diesel fuel oil transfer pumps PDG02A and PDG02B are positive displacement pumps.
There are no installed instruments in the diesel fuel oil transfer system that allow a direct measurement of the flow rate when testing the diesel fuel oil transfer pumps. The pump flow rate can be calculated by measuring the change in day tank level or volume and the pump operation time required to make that change. The accuracy of this method is documented in the licensees design analysis EWR 4526-ME-20, Evaluation of Instrument Setpoints for EDG Fuel Oil System. This method determines a flow rate for a pump that can be used to evaluate the pump hydraulic performance.
The licensees alternative is consistent with NRC guidance in NUREG-1482, Revision 2, Guidelines for Inservice Testing at Nuclear Power Plants, Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants, Final Report, Section 5.5.2, as an acceptable alternative for measuring positive displacement pump flow rate without using an installed flow rate instrument. The licensee has verified via design analysis EWR 4526-ME-20 that the alternative testing accuracy meets the requirements of ISTB-3510(a). The combined accuracy of the tank level gauge and the stopwatch is +/-1.39 percent, which is an improvement over the combined accuracy of
+/-1.71 percent that the licensee stated is the accuracy in the current Ginna fifth 10-year IST program interval. The NRC staff concludes that the proposed alternative of using the change in tank level to calculate the flow rate provides reasonable assurance of operational readiness of diesel fuel oil transfer pumps PDG02A and PDG02B, and provides an acceptable level of quality and safety.
It is noted that the NRC staff authorized the use of this alternative for the current Ginna fifth 10-year IST program interval.
3.2 Licensees Alternative Request PR-02 The licensee requested an alternative to the pump testing requirements of the ASME OM Code.
Table ISTB-3000-1, Inservice Test Parameters, provides the parameters for flow rate (Q) and differential pressure (P) for the Group A pump test and Q and P for the Group B pump test.
ISTB-3550, Flow Rate, states, in part, When measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall indicate the method used to reduce the data.
ISTB-5121, Group A Test Procedure, states, in part, Group A tests shall be conducted with the pump operating as close as practical to a specified reference point and within the variances from the reference point as described in this paragraph. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph.
ISTB-5121(c) states, Where it is not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values.
ISTB-5122, Group B Test Procedure, states, in part, Group B tests shall be conducted with the pump operating as close as practical to a specified reference point and within the variances from the reference point as described in this paragraph. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph.
ISTB-5122(c) states, in part, System resistance may be varied as necessary to achieve a point as close as practical to the reference point. If the reference point is flow rate, the variance from the reference point shall not exceed +2% or -1%.
The licensee has requested to use the proposed alternative described below for the pumps listed in Table 2.
Table 2 Pump ID Pump Description ASME Code Class ASME OM Pump Group PAF01A A Preferred Motor 3 A Driven Auxiliary Feedwater (AFW) Pump PAF01B B Preferred Motor 3 A Driven AFW Pump PSF01A C Standby Motor Driven 3 B AFW Pump PSF01B D Standby Motor Driven 3 B AFW Pump
The Ginna sixth 10-year IST program interval begins on January 1, 2020 and is scheduled to end on December 31, 2029. The applicable ASME OM Code edition for the Ginna sixth 10-year IST program interval is the 2012 Edition.
Reason for Request
The licensee stated:
Pursuant to 10 CFR 50.55a, Codes and Standards, paragraph (z)(2), an alternative is proposed to the pump testing requirements regarding pump flow rate in the ASME OM-2012 Code. The basis of the request is that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The AFW pumps each have a minimum flow path that can be utilized for the respective Group A and Group B pump tests. The minimum flow lines provide a fixed resistance flow path from the pump discharge to the condensate storage or demineralized water storage tank, as applicable, then back to the suction of each pump. However, the minimum flow lines are not provided with flow instrumentation.
Compliance with the Code is an undue burden due to existing design limitations in that a flow rate measuring device is not installed in the associated pump minimum flow recirculation line being employed as the pump test circuit. Costly major hardware modifications would be required to provide a permanent flow measuring device in each affected line. It has been estimated that the cost would exceed $75,000 annually to install and maintain temporary flow measuring devices or more than $375,000 to install permanent flow measuring devices into the minimum flow recirculation lines in order to meet the ASME OM Code requirements and support the quarterly testing of the four AFW pumps.
Additionally, flow is not variable since an installed flow orifice establishes a 40 gpm flow rate when the pump is operated in the recirculation mode.
The flow path to the steam generators has flow instrumentation; however, this flow path has the potential for service water intrusion and requires a reactivity change. This flow path is used for the biennial comprehensive pump test.
Therefore, the instrumented flow path which has the potential for service water intrusion into the steam generators and requires a reactivity change, and the cost of installing either temporary or permanent flow instrumentation in the minimum flow recirculation lines imposes an undue burden without a compensating increase in the level of quality or safety.
Proposed Alternative The licensee stated:
The performance of pump tests using a fixed resistance flow path is an acceptable alternative to the Code requirements per NUREG-1482, Revision 2, Section 5.9, Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices. During the performance of quarterly pump testing,
pump differential pressure will be measured and trended. This provides a reference value for differential pressure that can be duplicated during subsequent tests. This methodology provides for the acquisition of repeatable differential pressure, which is an adequate means of monitoring for pump degradation.
Concerns identified in NRC Bulletin 88-04, Potential Safety-Related Pump Loss, with regard to minimum recirculation flow line sizing were assessed and verified to not be of concern during pump testing.
Quarterly testing of the designated Group A AFW centrifugal pumps (PAF01A, PAF01B) will be performed on minimum flow recirculation measuring differential pressure across the pump and measuring vibration per ASME OM-2012 Code, paragraph ISTB-5121 and using NUREG-1482, Revision 2, Section 5.9 for guidance.
Quarterly testing of the designated Group B Standby AFW centrifugal pumps (PSF01A, PSF01B) will be performed on minimum flow recirculation measuring differential pressure across the pump per ASME OM-2012 Code, paragraph ISTB-5122 and using NUREG-1482, Revision 2, Section 5.9 for guidance.
Therefore, relief is requested pursuant to 10 CFR 50.55a(z)(2) based on the determination that compliance with the Code required Groups A and B centrifugal pump test requirements cannot be achieved without resulting in a hardship or unusual difficulty without a compensating increase in the level of quality and safety; and the proposed alternative testing provides reasonable assurance of the AFW pumps' operational readiness.
NRC Staff Evaluation
Motor-driven AFW pumps PAF01A and PAF01B are Group A centrifugal pumps. Inservice testing requirements for Group A centrifugal pumps are specified in ISTB-5121.
Motor-driven AFW pumps PSF01A and PSF01B are Group B centrifugal pumps. Inservice testing requirements for Group B centrifugal pumps are specified in ISTB-5122.
The licensee proposes alternative quarterly testing for the motor-driven auxiliary feedwater pumps. The current configuration does not meet ISTB-3550, which states that when measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. The licensee stated that the estimated cost to install and maintain temporary flow measuring devices in the pump minimum flow recirculation lines would exceed $75,000 annually, and the cost to install permanent flow measuring devices in the pump minimum flow recirculation lines would exceed
$375,000. The licensees proposed alternative quarterly test shall use the minimum flow path lines, which have a flow orifice installed. These minimum flow path lines provide a fixed resistance flow path without installed flow rate instrumentation. Measurements will include differential pressure across the pump in accordance with ISTB-5121 for the Group A pumps and ISTB-5122 for the Group B pumps, and vibration measurements in accordance with ISTB-5121 will be taken during the Group A pump tests.
The NRC staff has reviewed the licensees proposed alternative and has determined that the testing is consistent with the guidance in NUREG-1482, Revision 2, Section 5.9, Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices, and Generic
Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs, Position 9.
The NRC staff finds that compliance with the ASME OM Code-required Group A and Group B pump test requirements cannot be achieved without major system modifications and would result in hardship or unusual difficulty. The NRC staff also finds that the alternative described in the licensees proposal provides reasonable assurance of pump operational readiness.
It is noted that the NRC staff authorized the use of this alternative for the current Ginna fifth 10-year IST program interval.
4.0 CONCLUSION
As set forth above, the NRC staff determined that for alternative requests PR-01 and PR-02 for Ginna, the proposed alternatives provide reasonable assurance that the pumps listed in Tables 1 and 2 are operationally ready. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2) for requests PR-01 and PR-02. Therefore, the NRC staff authorizes the use of the alternative requests PR-01 and PR-02 for Ginna for the sixth 10-year IST program interval, which begins on January 1, 2020, and is scheduled to end on December 31, 2029.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
Principal Contributor: R. Wolfgang Date: August 5, 2019
ML19205A453 *by memorandum OFFICE DORL/LPL1/PM DORL/LPL1/LA DE/EMIB/BC* DORL/LPL1/BC DORL/LPL1/PM NAME VSreenivas KEntz; SBailey JDanna VSreenivas LRonewicz (MMarshall for)
DATE 07/26/2019 07/29/2019 07/18/2019 08/02/2019 08/05/2019