Letter Sequence Approval |
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EPID:L-2023-LLR-0059, ASME OM Code Inservice Testing Program Alternative Request V-01, Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing Supplemental Information (Approved, Closed) |
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MONTHYEARML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests Project stage: Request ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps Project stage: Approval 2023-10-12
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Similar Documents at Surry |
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Category:Code Relief or Alternative
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[Table view] Category:Letter
MONTHYEARML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2862024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - 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U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - 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[Table view] Category:Safety Evaluation
MONTHYEARML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times 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Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23061A0122023-05-0909 May 2023 Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23100A0652023-04-25025 April 2023 Issuance of Amendment Nos. 310 and 310, Regarding Turbine Building Tornado Classification ML23102A2832023-04-25025 April 2023 ASME OM Code Inservice Testing Program Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML23030B8472023-03-10010 March 2023 Issuance of Amendment Nos. 309 and 309, License Amendment Request Regarding a 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines ML21201A1172021-08-0606 August 2021 Proposed Alternative Requests S1-I5-ISI-05 and S2-I5-ISI-06 to Eliminate Examination of Threads in Reactor Pressure Vessel Flange ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML20293A1602020-12-0808 December 2020 Issuance of Amendment Nos. 301 and 301 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20148M3592020-12-0808 December 2020 Issuance of Amendment Nos. 302 and 302 to Revise Technical Specifications Figure 3.1 1, Surry Units 1 and 2 Reactor Coolant System Heatup Limitations, and Figure 3.1-2, Surry Units 1 and 2 Reactor Coolant System ML20321A2322020-11-20020 November 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20301A4522020-10-28028 October 2020 Non-Proprietary, Issuance of Amendment Nos. 300 and 300 to Revise Technical Specifications 6.2.C, Core Operating Limits Report ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI ML20085G9642020-05-19019 May 2020 Issuance of Amendments Nos. 298 and 298 to Revise Technical Specifications Table 3.7-1, Reactor Trip Instrument Operating Conditions, for an Addition of 24-Hour Completion Time for an Inoperable Rector Trip Breaker ML20115E3522020-05-12012 May 2020 Alternative Request S2-I5-ISI-05 ASME Section XI Inservice Inspection Program Proposed Alternative Request to Use a Mechanical Clamping Device for a One-Inch Main Steam Line Repair ML20115E2372020-05-0707 May 2020 Issuance of Exigent Amendments Nos. 299 and 299, to Revise TS 6.4.Q, Steam Generator (SG) Program, to Allow a One-Time Deferral of the Inspection of Surry Unit 2 Sg B Spring 2020 Refueling Outage ML20058F9662020-03-16016 March 2020 Issuance of Amendment Nos. 297 and 297 to Revise Technical Specifications 3.16, Emergency Power System, to Allow a One Time 14-Day Allowed Outage Time for Replacement of 5-KV Cables Associated with Reserve Station ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19028A3842019-06-12012 June 2019 Issuance of Amendment Nos. 295 and 295 to Adopt TSTF-490, Revision 0, and Update Alternative Source Term Analyses (EPID-L-2018-LLA-0068) ML19043A8242019-03-15015 March 2019 Relief Requests Examination Coverage for Pressurizer Nozzle Inner Radius Sections and Certain Stainless Steel Piping Welds (S2-15-LMT-CO1 and S2-15-LMT-P01) ML18331A0602019-02-28028 February 2019 Relief Requests Regarding Examination Coverage for Pressurizer Nozzle Inner Radius Section and Certain Stainless Steel Piping Welds (S1-I5-LMT-C01 and S1-I5-LMT-P01) ML19031B2272019-02-27027 February 2019 Issuance of Amendment Nos. 281, 264, 294, and 294 to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes ML18318A0622018-12-10010 December 2018 Review of Reactor Vessel Material Surveillance Capsule Withdrawal Schedules (CAC Nos. MG0098 and MG0099; EPID L-2017-LLL-0021) ML18261A0992018-10-0505 October 2018 Issuance of Amendments. Request to Revise Technical Specifications Section 3.16 Emergency Power System Regarding a Temporary 21 Day Allowed Outage Time ML18236A2362018-09-26026 September 2018 Relief from the Requirements of the ASME Code - Proposed Alternatives S1-I5-ISI-04 and S2-I5-ISI-04 ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 ML18166A3292018-06-29029 June 2018 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML18106A0072018-05-0303 May 2018 Issuance of Amendments Regarding Open Phase Protection Per NRC Bulletin 2012 01 (CAC Nos. MF9805, MF9806; EPID L-2017-LLA-0238) ML17326A2252018-02-0909 February 2018 Issuance of Amendments Regarding License Amendment Request to Revise Residual Heat Removal and Component Cooling System Technical Specifications Requirements (CAC Nos. MF9124 and MF9125; EPID L-2017-LLA-0166) ML18019A1952018-01-24024 January 2018 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination (CAC Nos. MF9923, MF9924, MF9925, MF9926, MF9927, and MF9928; EPID L-2017-LLR-0060) ML17303A0682017-12-20020 December 2017 Nonproprietary Relief from the Requirements of the ASME Code (CAC Nos. MF8987 and MF8988; EPID L-2016-LLR-0019) 2024-08-23
[Table view] |
Text
June 18, 2024
Eric S. Carr President - Nuclear Operations and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2 - PROPOSED ALTERNATIVE RELIEF REQUESTS P-3 AND P-4 INSERVICE TESTING OF BORIC ACID, COMPONENT COOLING WATER PUMPS (EPID L-2023-LLR-0059)
Dear Eric Carr:
By letter dated October 12, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23285A092), Virginia Electric And Power Company (licensee) submitted relief requests (RRs) P-3 and P-4 to the U.S. Nuclear Regulatory Commission (NRC) for authorization of proposed alternatives to certain inservice testing (IST) requirements in the 2020 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants Division 1, OM Code: Section IST (OM Code) as incorporated by reference in Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) at the Surry Power Station (SPS), Units 1 and 2.
Specifically, pursuant to 10 CFR 50.55a(z)(1), the licensee asserted that the alternatives in RRs P-3 and P-4 provide an acceptable level of quality and safety in lieu of certain ASME OM Code requirements for specific pumps at SPS, Units 1 and 2.
Accordingly, the NRC staff concludes that the li censee has adequately a ddressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the use of RRs P-3 and P-4 at SPS, Units 1 and 2, for the sixth interval IST program, which is scheduled to begin on August 10, 2024.
All other ASME OM Code requirements for which r elief or an alternative was not specifically requested and granted or authorized (as applicable) in the subject requests remain applicable.
E. Carr
If you have any questions, please contact me at (301) 415-5136, or via email at John.Klos@nrc.gov.
Sincerely,
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-280 and 50-281
Enclosure:
Safety Evaluation
cc: Listserv SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELIEF REQUESTS P-3 AND P-4
RELATED TO THE SIXTH INTERVAL INSERVICE TESTING PROGRAM
VIRGINIA ELECTRIC AND POWER COMPANY
SURRY POWER STATION, UNITS 1 AND 2
DOCKET NOS. 50-280 AND 281
EPID L-2023-LLR-0059
1.0 INTRODUCTION
By letter dated October 12, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23285A092), Virginia Electric And Power Company (licensee) submitted relief requests (RRs) P-3 and P-4 to the U.S. Nuclear Regulatory Commission (NRC) for authorization of proposed alternatives to certain inservice testing (IST) requirements in the 2020 Edition of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) as incorporated by reference in part 50 of Title 10 of the Code of Federal Regulations (10 CFR) at the Surry Power Station (SPS), Units 1 and 2.
Specifically, pursuant to 10 CFR 50.55a(z)(1), the licensee asserted that the alternatives in RRs P-3 and P-4 provide an acceptable level of quality and safety in lieu of certain ASME OM Code requirements for specific pumps at SPS, Units 1 and 2.
2.0 REGULATORY EVALUATION
The NRC regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, state, in part, that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the IST requirements (exce pt design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The NRC regulations in 10 CFR 50.55a(z) state, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the NRC, if the licensee demonstrates (1) the proposed alternatives would provide an acceptable level of quality and safety, or (2) that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Enclosure
3.0 TECHNICAL EVALUATION
The information provided by the licensee in support of RRs P-3 and P-4 have been evaluated and the bases for disposition are documented below.
3.1 Licensees Relief Request P-3
Applicable OM Code Edition
The IST Code of Record for the sixth interval IST program at SPS, Units 1 and 2, is the 2020 Edition of the ASME OM Code as incorporated by reference in 10 CFR 50.55a. The sixth interval IST program at SPS, Units 1 and 2, begins on August 10, 2024.
ASME OM Code Components Affected
The plant equipment within the scope of this request are:
Component ID Component Description ASME Pump Class Group
1-CH-P-2A Boric Acid Transfer Centrifugal Pump 2 A
1-CH-P-2B Boric Acid Transfer Centrifugal Pump 2 A
1-CH-P-2C Boric Acid Transfer Centrifugal Pump 2 A
1-CH-P-2D Boric Acid Transfer Centrifugal Pump 2 A
Function: The boric acid transfer pumps supply boric acid to the suction of the charging pumps for emergency boration.
Applicable ASME OM Code Requirements
ASME OM Code, subsection ISTB, Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants - Pre-2000 Plants, paragraph ISTB-3510, General, subparagraph (b), Range, item (1), requires that the full-scale range of each analog instrument shall be not greater than three times the reference value.
Licensees Proposed Alternative
The licensee proposes that the inlet pressure for the Group A and Comprehensive Pump Tests for the specified boric acid transfer pumps at SPS, Units 1 and 2, will be measured with gauges that have a full-scale range of 0 to 15 pounds per square inch gauge (psig).
Licensees Reason for Request
The licensee indicates that the installed inlet pressure gauges for the Group A and comprehensive pump tests for the specified pumps have a full-scale range of 0 to 15 psig.
These instruments were sized by evaluating the static pressures present at the suction side of the pumps and applying the three times rule of ISTB-3510(b)(1). When the pumps are
started, the pressure at the suction side of the pumps drops to approximately 2 psig; therefore, the inlet pressure gauges do not meet the three times rule for dynamic inlet pressure. Using a lower range temporary gauge on a quarterly basis presents a hardship because the process fluid contains boric acid and is contaminated. The gauges could also be exposed to an over-range condition (static pressures in excess of 6 psig) which may damage the lower range temporary instruments.
The licensee asserts that the difference in the error between the 0 to 15 psig gauges and gauges that would meet the three times full-scale rule are so small that the 0 to 15 psig gauges can be considered equivalent in terms of accuracy for determining differential pressure. Some historical readings show a suction pressure as low as 0.5 psig which would lead to a range of 0-1.5 psig to meet the three times rule. A 0.5 percent accuracy for the 1.5 psig gauge translates to an error of 0.0075 psig. A 0.5 percent accuracy for the 15 psig gauge translates to an error of 0.075 psig. The difference in error of 0.0675 psig is insignificant when determining the differential pressures for these pumps which range between 90 and 110 psid (pounds per square inch differential). Therefore, the licensee considers that the gauges can be considered equivalent in terms of accuracy for determining differential pressure.
Licensees Basis for Use
The licensee states that using the provisions of this request as an alternative to the specific requirements of ISTB-3510(b)(1) for the applicable pumps will provide adequate indication of pump performance and continue to provide an acceptable level of quality and safety.
Therefore, pursuant to 10 CFR 50.55a(z)(1), the licensee requests authorization to use the proposed alternative to the specific ASME OM Code requirements identified in this request.
NRC Staff Evaluation
The boric acid transfer pumps at SPS, Units 1 and 2, supply boric acid to the suction of the charging pumps for emergency borati on. The ASME OM Code, subsection ISTB, paragraph ISTB-3510(b)(1), requires that the full-scale range of each analog instrument not be greater than three times the reference value. The licensee indicates that the installed inlet pressure gauges for the Group A and comprehensive pump tests for these pumps have a full-scale range of 0 to 15 psig. When the pumps are started, the pressure at the suction side of the pumps drops to approximately 2 psig; therefore, the inlet pressure gauges do not meet the three times requirement for dynamic inlet pressure. To meet the ASME OM Code requirements, the licensee would be required to install temporary instruments at the inlet of the boric acid transfer pumps prior to each quarterly test. Therefore, the licensee proposed in RR P-3 that the inlet pressure for the Group A and comprehensive pump tests for the applicable boric acid transfer pumps be measured with gauges that have a full-scale range of 0 to 15 psig.
Under 10 CFR 50.55a(z)(1), the licensee asserts that the alternative described in RR P-3 provides an acceptable level of quality and safety because t he difference in the error between the 0 to 15 psig gauges and gauges that would meet the three times full-scale rule is very small.
The difference to be insignificant when determining the differential pressures for the boric acid transfer pumps, which range between 90 and 110 psid. Therefore, the gauges can be considered equivalent in terms of accuracy for determining differential pressure.
The NRC staff has reviewed the licensees proposed alternative in RR P-3 for SPS, Units 1 and
- 2. ASME OM Code, subsection ISTB, paragraph ISTB-3510(b)(1), is intended to provide reasonable assurance that the range used for pressure instrumentation allows meaningful monitoring of potential pump degradation. The licensees proposed alternative meets the intent of the ASME OM Code requirements because the difference resulting from the use of the
proposed instrumentation is very small. Theref ore, the NRC staff finds that the licensee's proposed alternative in RR P-3 provides an acceptable level of quality and safety pursuant to 10 CFR 50.55a(z)(1) for the testing of the specified boric acid transfer pumps at SPS, Units 1 and 2.
3.2 Licensees RR P-4
Applicable OM Code Edition
The IST Code of Record for the sixth Interval IST program at SPS, Units 1 and 2, is the 2020 Edition of the ASME OM Code as incorporated by reference in 10 CFR 50.55a. The sixth Interval IST program at SPS, Units 1 and 2, begins on August 10, 2024.
ASME OM Code Components Affected
The plant equipment within the scope of this request are:
Component ID Component Description ASME Class Pump Group
1-CC-P-2A Unit 1 Component Cooling Water Charging Pump Centrifugal Pump 3 A
1-CC-P-2B Unit 1 Component Cooling Water Charging Pump Centrifugal Pump 3 A
2-CC-P-2A Unit 2 Component Cooling Water Charging Pump Centrifugal Pump 3 A
2-CC-P-2B Unit 2 Component Cooling Water Charging Pump Centrifugal Pump 3 A
Applicable ASME OM Code Requirements
ASME OM Code, subsection ISTB, Inservice Testing of Pumps in Water-Cooled Reactor Nuclear Power Plants - Pre-2000 Plants, paragraph ISTB-3510, General, subparagraph (b), Range, item (1), requires that the full-scale range of each analog instrument shall be not greater than three times the reference value.
Licensees Proposed Alternative The licensee proposes that the inlet pressure for the Group A and comprehensive pump tests of the specified component cooling water charging pump centrifugal pumps will be measured with gauges that have a full-scale of 0 to 3.5 psig.
Licensees Reason for Request
The licensee indicates that the installed inlet pressure gauges used for the Group A and comprehensive pump tests of the specified pumps have a full-scale range of 0 to 3.5 psig. The readings from these inlet pressure gauges over the past year indicate that the dynamic pressures fall within the bottom third of full-scale. However, the difference in the error between the 0 to 3.5 psig gauges and gauges that would meet the three times full-scale rule are so small that the 0 to 3.5 psig gauges can be considered equivalent in terms of accuracy for determining differential pressure.
As an example, the licensee states that inlet pressures as low as 0.65 psig have been recorded for pump 1-CC-P-2B. A gauge that meets the three times full-scale rule would have a full-scale of 0 to 1.95 psig or less. A 0.5 percent accuracy for the 1.95 psig gauge translates to an error of 0.00975 psig. A 0.5 percent accuracy for the 3.5 psig gauge translates to an error of 0.0175 psig. The difference in error of 0.00775 psig is insignificant when determining the differential pressures for these pumps which range between 50 and 60 psid. Therefore, the gauges can be considered equivalent in terms of accuracy for determining differential pressure.
Licensees Basis for Use
The licensee states that using the provisions of this request as an alternative to the specific requirements of ISTB-3510(b)(1) for the applicable pumps will provide adequate indication of pump performance and continue to provide an acceptable level of quality and safety.
Therefore, pursuant to 10 CFR 50.55a(z)(1), the licensee requests authorization to use the proposed alternative to the specific ASME OM Code requirements identified in this request.
NRC Staff Evaluation
The component cooling water charging pump centrifugal pumps at SPS, Units 1 and 2, supply cooling water to transfer heat from the charging pump mechanical seals. The ASME OM Code, subsection ISTB, paragraph ISTB-3510(b)(1), requires that the full-scale range of each analog instrument not be greater than three times the reference value. The licensee indicates that the installed inlet pressure gauges used for the Group A and comprehensive pump tests for these pumps have a full-scale range of 0 to 3.5 psig. As an alternative to the ISTB-3510(b)(1) requirement, the licensee proposed in RR P-4 that the installed gauges be used to measure the differential pressure for the applicable component cooling water charging pump centrifugal pumps.
Under 10 CFR 50.55a(z)(1), The alternative in RR P-4 provides an acceptable level of quality and safety because the difference in the error between the 0 to 3.5 psig installed gauges and gauges that would meet the three times full-scale requirement is very small. The difference is insignificant when determining the differential pressures for the component cooling water charging pump centrifugal pumps which range between 50 and 60 psig. Therefore, the gauges can be considered equivalent in terms of accuracy for determining differential pressure.
The NRC staff has reviewed the licensees proposed alternative in RR P-4 for SPS, Units 1 and
- 2. ASME OM Code, subsection ISTB, paragraph ISTB-3510(b)(1), is intended to provide reasonable assurance that the range used for pressure instrumentation allows meaningful monitoring of potential pump degradation. The licensees proposed alternative meets the intent of the ASME OM Code requirements because the difference resulting from the use of the proposed instrumentation is very small. Theref ore, the NRC staff finds that the licensee's proposed alternative in RR P-4 provides an acceptable level of quality and safety pursuant to
10 CFR 50.55a(z)(1) for the testing of the specified component cooling water charging pump centrifugal pumps at SPS, Units 1 and 2.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that RRs P-3 and P-4 for SPS, Units 1 and 2, as described in the licensees submittal dated October 12, 2023, provide an acceptable level of quality and safety for the proposed testing for the specified pumps for the sixth interval IST program at SPS, Units 1 and 2. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes the use of RRs P-3 and P-4 at SPS, Units 1 and 2, for the sixth interval IST program, which is scheduled to begin on August 10, 2024.
All other ASME OM Code requirements as incorporated by reference in 10 CFR 50.55a for which relief or an alternative was not specifically requested, and granted or authorized (as appropriate), in the subject requests remain applicable.
Principal Contributors: Nicholas Hansing, NRR Thomas Scarbrough, NRR
Date: June 18, 2024
ML24166A062 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DEX/EMIB/BC NAME JKlos SRohrer SBailey DATE 6/11/2024 6 /17/2024 6/11/2024 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley (EMiller for) JKlos DATE 6/18/2024 6/18/2024