Letter Sequence Other |
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MONTHYEARML0200300022002-01-16016 January 2002
Opportunity for Comment on TIA 2001-10, Design Basis Assumptions for Ability of Prairie Island, Units 2, Emergency Diesel Generators to Meet Single Failure Criteria for External Events
Project stage: Other
ML0226002922002-09-17017 September 2002
Memorandum Regarding Report on the Status of Open TIAs Assigned to NRR
Project stage: Other
ML0236403102002-12-30030 December 2002
Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design-Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events
Project stage: Other
L-PI-03-016, Response to Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events.2003-04-21021 April 2003
Response to Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events.
Project stage: Other
ML0320404122003-09-0404 September 2003
Response to TIA 2001-10, Design Basis Assumptions for Ability of Emergency Diesel Generators to Meet Single Failure Criteria for External Events
Project stage: Other
2002-09-17
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Category:Memoranda
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Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III
ML21055A5972021-03-25025 March 2021
Final Environmental Assessment and Finding of No Significant Impact for the Northern States Power Company'S Initial and Updated Decommissioning Funding Plans Submitted in Accordance with 10 CFR 72.30(B) and (C)
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Summary of the Public Open House to Discuss NRC Activities and the 2018 End-of-Cycle Performance Assessment
ML19136A0272019-05-15015 May 2019
Memorandum to C. Regan Summary of March 28, 2019, Public Meeting with Xcel Energy to Discuss Seismic Consideration for a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at Prairie Island I
ML19071A0372019-03-0707 March 2019
Summary of Meeting with Xcel Energy to Discuss Increasing the Amount of Special Nuclear Material Authorized for Storage at the Prairie Island ISFSI (W/Enclosures 1 and 2)
ML15181A0202015-07-0101 July 2015
July 9, 2015 Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML15107A4932015-04-23023 April 2015
Memo C K Bladey, Notice of Issuance of Exemption, Northern States Power Company, Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation (50-282, 50-306, 72-10)
ML14220A2832014-09-0808 September 2014
Summary of August 5, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, NRC, and Northern States Power Company - Minnesota to Discuss Flooding Analysis Associated with Monticello and Prairie Island Nuclear Gen
ML14205A5242014-07-24024 July 2014
August5, 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML14027A2312014-02-0505 February 2014
Notice of Pre-Application Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2, to Discuss Licensee'S Proposed Changes to the Emergency Diesel Generator Voltage and Frequency Limits
ML13169A2442013-06-17017 June 2013
Memorandum S. Wastler Technical Assistant Request - Review the Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation Request for Exemption from Physical Security Requirements (TAC L24750)
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Rai'S Following Ifib Analysis 2013 Decommissioning Funding Status Report for Prairie Island 1 and 2 and Monticello
ML13101A0292013-04-12012 April 2013
K. Hsueh Memo Site Visit Summary Regarding the Prairie Island ISFSI License Renewal
ML12363A1722012-12-14014 December 2012
CFR 50 Appendix E Evacuation Time Estimate Study
ML12326A9702012-11-21021 November 2012
Summary of October 24, 2012, Meeting with the Northern States Power Company, D/B/A Excel Energy Regarding Security Requirements and Changes Pertaining to Prairie Island TAC L24689 W/ Encl 1 (Attendees) and Encl 2 (Agenda)
ML12318A0572012-11-13013 November 2012
12/6/2012 - Rescheduled Notice of Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2
ML12306A3222012-11-0101 November 2012
Notice of Forthcoming Meeting with Xcel Energy Concerning Prairie Island Nuclear Generating Plant, Units 1 and 2
ML12291A7792012-10-17017 October 2012
S. Wastler Memorandum Technical Assistance Request - Review of Physical Security Plan of Prairie Island Nuclear Generating Plant Independent Spent Fuel Storage Installation (TAC No. L24689)
ML12249A2702012-09-11011 September 2012
Notice of Forthcoming Pre-Application Meeting with Xcel Energy, Inc. Concerning Prairie Island Nuclear Generating Plant
ML12223A4772012-08-0606 August 2012
10/4/2012 Notice of Significant NRC Meeting with Northern States Power Company to Discuss Prairie Island Nuclear Generating Plant, Unit 2
ML1121505252011-08-0404 August 2011
Notice of Forthcoming Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Extended Power Uprate License Amendment Request
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Notice of Forthcoming Meeting with Licensee for Prairie Island Nuclear Generating Plant, Unit 1 to Discuss License Amendment Request to Revise Surveillance Requirement Footnote in Technical Specification 3.8.1, AC Sources - Operating.
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Notice of Closed Pre-Application Meeting NSPM Staff to Discuss Proposed Physical Security Plan Changes That Will Be Submitted for NRC Review and Approval Via License Amendment Request
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Notice of Pre-Application Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 to Discuss Spent Fuel Pool Criticality and Extended Power Uprate
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Summary of Meeting with Northern States Power Company - Minnesota Corporation, Formerly Nuclear Management Company and Transnuclear Regarding License Amendment Request for the TN-40HT Cask Design
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Summary of Meeting with Northern States Power Company to Discuss License Amendment Request Concerning Unit 2 Emergency Diesel Generator Surveillance Test Loads
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Notice of Meeting with Licensee for Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP) to Discuss Their Proposed Alternate Source Term License Amendment
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Review of Revision 29 to the Updated Safety Analysis Report (Tac No. MD5651 and MD5652)
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Memo Transmitting Prairie Island Nuclear Generating Plant: Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02
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2023-07-11
[Table view] |
Text
September 4, 2003 MEMORANDUM TO: Geoffrey E. Grant, Director Division of Reactor Projects Region III FROM: Ledyard B. Marsh, Director /RA/
Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 -
RESPONSE TO TIA 2001 "DESIGN BASIS ASSUMPTIONS FOR ABILITY OF PRAIRIE ISLAND, UNIT 2, EMERGENCY DIESEL GENERATORS TO MEET SINGLE FAILURE CRITERIA FOR EXTERNAL EVENTS" (TAC NO. MB2953)
EXECUTIVE
SUMMARY
By memorandum dated September 7, 2001, you requested technical assistance from the Office of Nuclear Reactor Regulation (NRR) regarding an issue related to design-basis assumptions for the Prairie Island Nuclear Generating Plant (PINGP), Unit 2, emergency diesel generators (EDGs) to meet single failure criteria for external events.
The NRR staff sent letters to the Nuclear Management Company, LLC (the licensee), dated January 16 and December 30, 2002, providing the licensee an opportunity to comment on Task Interface Agreement (TIA) 2001-10. The licensee responded by letters dated March 18, 2002, and April 21, 2003. The NRR staff has reviewed the licensees letters. A meeting was held on April 24, 2003, between the NRR staff and the Office of the General Counsel (OGC) staff to discuss the technical and legal aspects of TIA 2001-01.
The NRR staff concludes that the PINGP Unit 2 emergency alternating current (AC) power system is not required to meet single failure criteria coincident with certain external events (e.g., flood conditions).
BACKGROUND PINGP was designed and constructed prior to the issuance of Appendix A, "General Design Criteria for Nuclear Power Plants," to Title 10 of the Code of Federal Regulations (10 CFR),
Part 50. PINGP was designed to meet the intent of the Atomic Energy Commissions (AECs)
General Design Criteria (GDCs), as originally proposed in July 1967. Construction of the plant was about 50 percent complete and the Final Safety Analysis Report (FSAR) had been filed with the AEC before publication of the AECs revised GDCs in February 1971 and July 1971.
CONTACT: J. Lamb, NRR (301) 415-1446
The AEC did not require the applicant to reanalyze the plant or resubmit the FSAR. However, the AECs technical review did assess the plant against the GDCs in effect at the time, and the AEC was satisfied that the plant design generally conformed to the intent of these criteria.
PINGP was originally licensed with only two EDGs. By letter dated April 13, 1989, the licensee committed to (1) add two additional safeguards EDGs, (2) upgrade the safeguards electrical distribution system, and (3) support compliance with the station blackout (SBO) rule in 10 CFR 50.63.
RISK SIGNIFICANCE Relating to risk significance, you stated that [t]his issue has no effect on the SDP [significant determination process] for an issue with an emergency diesel generator because unrelated failures of other equipment (such as assumed for single failure criteria) is not assumed in an SDP.
REQUESTED ACTION Your requested action was the following: From a design and licensing basis perspective for system functional capability, is the Unit 2 emergency AC power system required to meet single failure criteria for external events such as a flood even though the rest of the plant may not be required to?
STAFF EVALUATION Original Licensing Basis The Commission, in a Staff Requirement Memorandum (SRM) dated September 18, 1992, stated that the staff will not apply the General Design Criteria (GDC) to plants with construction permits issued prior to May 21, 1971. The licensees construction permits were issued in 1968. Therefore, the GDCs are not requirements for the licensee and are not part of the original licensing basis.
The licensees FSAR states that PINGP was designed and constructed to comply with Northern States Powers (NSPs) understanding of the intent of the AEC General Design Criteria for Nuclear Power Construction Permits, as proposed on July 10, 1967. The FSAR description of the 1967 AEC GDCs, as applied to the plant design, comprises part of the PINGP licensing basis.
PINGPs FSAR Section 1.5, Criterion 2, Performance Standards, states the following:
Those systems and components of reactor facilities which are essential to the prevention of accidents which could affect the public health and safety or to mitigation of their consequences shall be designed, fabricated, and erected to performance standards that will enable the facility to withstand, without loss of the capability to protect the public, the additional forces that might be imposed by natural phenomena such as earthquakes, tornadoes, flooding conditions, winds, ice, and other local site effects. The design bases so established shall reflect: (a) appropriate consideration of the most severe of these natural phenomena that have been recorded for the site and the surrounding area and (b) an appropriate margin for withstanding forces greater than
those recorded to reflect uncertainties about the historical data and their suitability basis for design.
PINGPs FSAR Section 1.5, Criterion 39, Emergency Power for Engineered Safety Features, states the following:
Alternate power systems shall be provided and designed with adequate independency, redundancy, capacity, and testability to permit the functioning required of the engineered safety features. As a minimum, the onsite power system and offsite power system shall each, independently, provide this capacity assuming a failure of a single active component in each power system.
A review of the FSAR description of applicability of the 1967 AEC GDCs to the plant and a review of the specific FSAR sections pertaining to the electrical power system did not reveal that the emergency AC power system is required to meet single failure criteria coincident with external events.
The staffs safety evaluation for PINGP was issued September 28, 1972, supplemented March 21, April 30, and May 31, 1973. As with the FSAR, the safety evaluation treats the single failure criteria separately from criteria related to protection against environmental effects. The staff reviewed the electrical power system with respect to compliance with single failure criteria in Chapter 8 of the safety evaluation. Except for noting the seismic classification of the structures housing the EDGs, external events were not mentioned in this part of the review.
The staff made separate findings regarding protection against environmental effects. The staffs safety evaluation did not indicate that the emergency AC power system is required to meet single failure criteria coincident with external events.
In summary, neither the GDCs, the FSAR, or the staffs September 28, 1972, safety evaluation, specify that the emergency AC power system is required to meet single failure criteria coincident with an external event.
The Effect of EDG Modifications on the Licensing Basis The licensee modified PINGP to add two new EDGs in the early 1990s. The specific plant modifications included the addition of the D5/D6 EDGs, the construction of a new diesel generator building, and an upgrade to the electrical safeguards. The licensee made various submittals to the NRC staff regarding the modification. In the TIA, you identified the licensees "Design Report for the Station Blackout/Electrical Safeguards Upgrade Project," dated September 23, 1993, and the NRC staffs Prairie Island SBO/ESU Projects Evaluations, dated April 28, 1992, as potential relevant documents related to the effect of the plant modification on the PINGP licensing basis. The staff thoroughly reviewed these two documents. Neither the GDCs, specific Standard Review Plan (SRP) sections, or other guidance pertaining to natural phenomena (with the exception of seismic qualification standards) are identified in the Design Report with respect to the emergency AC power system. Therefore, the design basis with respect to the emergency AC power system does not include external events coincident with a single failure.
With respect to the D5 and D6 EDG building, the design criteria specified in the September 23, 1993, Design Report for the building itself includes all the current GDCs, including GDC-2, and related SRP sections pertaining to GDC-2.
With respect to the upgrade of the electrical safeguards and distribution systems, the licensees Design Report states that for new plant components and systems, the Class 1E system design will comply with SRP 8.1, "Electrical Power - Introduction" (general requirements), and SRP 8.3.1, "AC Power Systems (On-Site)," among other criteria.
In summary, the licensees modification to its plant to add two new EDGs did not change the design basis as set forth in the PINGP FSAR for either the existing EDGs or the new EDGs with respect to external events. The modification did have the effect of changing the licensing basis with respect to the new diesel generator building and the new plant components designated Class 1E located in the new building with respect to external events. None of these changes, however, had the effect of requiring that the emergency AC system meet single failure criteria coincident with an external event.
STAFF CONCLUSION The staff concludes that the PINGP, Unit 2 emergency AC power system is not required to meet single failure criteria coincident with certain external events, such as flood conditions.
Docket No. 50-306 cc: A. Blough, Region I L. Plisco, Region II A. Howell, Region IV
ML032040412 *See previous concurrence OFFICE PDIII-1/PM PDIII-1/LA EEIB/BC OGC PDIII-1/SC PDIII/D DLPM/D NAME JLamb RBouling JCalvo* CMarco* DHood for TMendiola LMarsh LRaghavan for WRuland DATE 09/03/03 09/03/03 08/04/03 08/08/03 09/03/03 09/04/03 09/04/03
