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Category:Letter type:L
MONTHYEARL-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-027, Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2023-10-0303 October 2023 Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency 2024-08-23
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, Xcel Energym MAR 3 O 2fl10 L-PI-10-023 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN. Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9 (TAC Nos. ME0086, ME00871
Reference:
- 1. Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, letter to US Nuclear Regulatory Commission (NRC), "License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9", dated November 4, 2008, Accession Number ML083110125.
In Reference 1, NSPM submitted an LAR for the Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2 requesting revisions to the Technical Specifications (TS) for PINGP to increase the 24 month test load for the Unit 1 EDGs, D l and D2, reduce the monthly test load for the Unit 2 EDGs, D5 and D6, and reduce the 24 month test loads for the Unit 2 EDGs. NSPM requests that the LAR be split with some portions continuing in NRC review and other portions withdrawn from further NRC review.
NSPM submits this supplement in accordance with the provisions of 10 CFR 50.90.
The LAR to revise EDG test loads in SR 3.8.1.3 and SR 3.8.1.9 proposed four testing changes for the EDGs: (1) reduce the Unit 2 EDG monthly test load requirements in SR 3.8.1.3.b; (2) reduce the lower test limit in the two hour portion of the Unit 2 EDG 24-month test load requirements in SR 3.8.1.9.a; (3) increase the test load in the remaining hours test portion of the Unit 1 EDG 24-month test in SR 3.8.1.9.b; and, (4) reduce test load in the remaining hours test portion of the Unit 2 EDG 24-month test in SR 3.8.1.9.b.
NSPM requests withdrawal of proposed changes (1) and (4) from further NRC review.
NSPM also requests the NRC to continue reviewing proposed changes (2) and (3).
Specific guidance on the portions of the LAR on which continuing review is requested and the portions withdrawn is provided in Enclosure 1 to this letter.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121
Document Control Desk Page 2 The supplemental information provided in this letter does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the November 4,2008 submittal as supplemented August 10, 2009.
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and Enclosure 1 to the designated State Official.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
Summaty of Commitments The commitment proposed in the Reference 1 cover letter is withdrawn. This letter contains no new commitments.
I declare under penalty of ury that the foregoing is true and correct.
Executed on MAR 3 ,0 ,I fie#
Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant, Units 1 and 2 Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
Enclosure I In Reference 1, Northern States Power, a Minnesota corporation (NSPM), proposed four changes to the Prairie Island Nuclear Generating Plant (PINGP) Technical Specifications (TS) related to emergency diesel generator (EDG) testing: (1) reduce the Unit 2 EDG monthly test load requirements in surveillance requirement (SR) 3.8.1.3.b to 4000 kW; (2) reduce the lower test limit in the two hour portion of the Unit 2 EDG 24-month test load requirements in SR 3.8.1.9.a to 5400 kW; (3) increase the test load in the remaining hours test portion of the Unit 1 EDG 24-month test in SR 3.8.1.9.b to 2500 kW; and, (4) reduce test load in the remaining hours test portion of the Unit 2 EDG 24-month test in SR 3.8.1.9.b to 4000 kW.
NSPM proposes to split the license amendment request in Reference 1 by requesting the NRC to continue review of changes (2) and (3) and withdrawing changes (1) and (4). Attachments 1, 2 and 3 to this enclosure provide a marked up TS page, a marked up Bases page, and a final TS page, respectively, for the NRC continuing review of proposed changes (2) and (3) and supersede in their entirety the TS and Bases changes proposed in Reference 1.
The enclosure to Reference 1 provided the licensee's evaluation of the four proposed changes. With the split of the Reference 1 license amendment request (LAR), NSPM requests the enclosure to Reference 1 to be considered modified as follows.
Section 1.
SUMMARY
DESCRIPTION Disregard the discussion of SR 3.8.1.3 and reduction of the remainder of the 24-hour test load for Unit 2 EDGs.
Section 2. DETAILED DESCRIPTION Subsection 2.1 Proposed Changes Disregard the first and fourth inset paragraphs.
Subsection 2.2 Background Disregard the discussion of testing at 4000 kW or testing greater than or equal to 4000 kW in the fifth paragraph (next to last paragraph in this section on page 4 of 30).
Section 3. TECHNICAL EVALUATION Under subheading: Proposed Surveillance Requirement changes and benefits Page 1 of 3 NSPM Disregard the discussion of SR 3.8.1.3 starting at the bottom of page 7 of 30 and ending on page 8 of 30.
Under SR 3.8.1.9, starting on page 8 of 30 and ending on page 9 of 30, disregard discussions of testing at 4000 kW (see Attachments 1 and 3 to this enclosure for the proposed TS changes for which continuing review is requested).
Under subheading: Technical basis for changes Disregard the discussion of Changes to SR 3.8.1.3 starting on page 10 of 30 and ending on page 16 of 30.
Under Changes to SR 3.8.1.9, in the third paragraph on page 17 of 30, disregard the discussion of continuous run load of greater than or equal to 4000 kW Disregard the first paragraph at the top of page 18 of 30.
Under subheading: Conclusions Disregard the first and second paragraphs. Disregard the discussion and considerations in the fourth paragraph (last paragraph on page 18 of 30) relating to testing at or above 4000 kW.
Section 4. REGULATORY SAFETY ANALYSIS Subsection 4.1 Applicable Requlatory Requirementslcriteria Under subheading: Title 10 Code of Federal Regulations 50.36, "Technical specifications" Disregard discussions of SR 3.8.1.3 and testing at 4000 kW in the first, second (on page 19 of 30) and third (top of page 20 of 30) paragraphs.
Under subheading: Title 10 Code of Federal Regulations 50.63, "Loss of all alternating current power" Disregard discussions of SR 3.8.1.3 and testing at 4000 kW in the fourth paragraph (top of page 21 of 30).
Under subheading: General Design Criteria Disregard discussions of SR 3.8.1.3 and testing at 4000 kW in the third inset paragraph (bottom of page 21 of 30 continuing to top of page 22 of 30).
Page 2 of 3 NSPM Under subheading: Renulatow Guide 1.9, Revision 4, "Application and Testinn of Safety-Related Diesel Generators in Nuclear Power Plants", March 2007 (RG 1.9)
In the first paragraph, disregard the discussion of a commitment. With the LAR split proposed in this letter and enclosure, a testing commitment is not needed and is withdrawn.
Under subheading: NUREG-1431 Standard Technical Specifications, Westinnhouse Plants, Revision 3.0. Surveillance Requirement 3.8.1.3 D~sregardall discussion.
Subsection 4.2 Precedent Disregard all discussion Subsection 4.3 Significant Hazards Consideration Disregard the discussion of reducing Unit 2 EDG monthly test loading and the remainder of the 24-hour test at or above 4000 kW in the first paragraph under each question. The considerations and conclusions of this subsection remain applicable.
Section 6. REFERENCES Disregard references 5 and 6.
References
- 1. NSPM letter to the NRC, "License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9", dated November 4, 2008, Accession Number ML083110125.
Page 3 of 3
ENCLOSURE, ATTACHMENT 1 Technical Specification Pages (Markup) 3.8.1-9 1 page follows
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY Sji 3.8.1.9 ............................ NOTES ..........................
- 1. Momentary transients outside the load and power factor ranges do not invalidate this test.
- 2. If performed with DG synchronized with offsite power, it shall be performed at a power factor
< 0.85. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.
24 months Verie each DG operates for 2 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
- a. For 2 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded:
Unit 1 1 2 8 3 2 kW, and
< 3000 kW Unit 2 2 $40()5%2kW, and
< 5940 kW; and
- b. For the remaining hours of the test loaded:
Unit 1 >2500%75 kW, and Unit 2 > 4860 kW; and
- c. Achieves steady state voltage 2 3740 V and 5 4580 V; and frequency 2 58.8 Hz and 5 61.2 Hz.
Prairie Island Unit 1 - Amendment No. 4423 4-89 Units 1 and 2 3.8.1-9 Unit 2 - Amendment No. 1-49 4 7 4
ENCLOSURE, ATTACHMENT 2 Bases Pages (Markup)
(For Information Only)
B 3.8.1-20 1 page follows
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1 .8 (continued)
REV-The noncritical trips are bypassed during DBAs and provide an alarm on an abnormal engine condition. This alarm provides the operator with sufficient time to react appropriately. The DG availability to mitigate the DBA is more critical than protecting the engine against minor problems that are not immediately detrimental to emergency operation of the DG.
The Frequency is modified by a Note which allows the SR 3.0.2 interval extension (1.25 times the specified interval) to be applied to the interval for this SR, that is, this SR may be performed at an interval up to 30 months within the guidance of SR 3.0.2 for interval extensions. This is an exception to the limitations stated in SR 3.0.2 for SRs with a 24 month Frequency. The 24 month Frequency is based on engineering judgment, taking into consideration unit conditions required to perform the Surveillance, and is intended to be consistent with expected he1 cycle lengths. Operating experience has shown that these components usually pass the SR when performed at the 24 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
Demonstrate once per 24 months that the DGs can start and run continuously at full load capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of which is at a load equivalent to 103 - 110%
100 - 1 10%)for Unit 2 2) of the continuous duty rating and the remainder of the time at a load equivalent to the continuous duty rating of the DG. The DG starts for this Surveillance can be performed either from standby or hot conditions. The provisions for prelubricating and warmup, discussed in SR 3.8.1.2, and for gradual loading, discussed in SR 3.8.1.3, are applicable to this SR.
Prairie Island Unit 1 - Revision 2Q.4 Units 1 and 2 B 3.8.1-20 Unit 2 - Revision 2-04
ENCLOSURE, ATTACHMENT 3 Technical Specification Pages (Retyped) 3.8.1-9 1 page follows
AC Sources-Operating SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SK 3.8.1.9 ............................ NOTES..........................
- 1. Momentary transients outside the load and power factor ranges do not invalidate this test.
- 2. If performed with DG synchronized with offsite power, it shall be performed at a power factor
< 0.85. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.
24 months VerifL each DG operates for > 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
- a. For 2 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded:
Unit 1 > 2832 kW, and
< 3000 kW Unit 2 > 5400 kW, and
< 5940 kW; and
- b. For the remaining hours of the test loaded:
Unit 1 2 2500 kW, and Unit 2 3 4860 kW; and
- c. Achieves steady state voltage > 3740 V and < 4580 V; and frequency 3 58.8 Hz and 5 6 1.2 Hz.
Prairie Island Unit 1 - Amendment No. 44-84-89 Units 1 and 2 3.8.1-9 Unit 2 - Amendment No. 4-49 478