Text

Issuance of Amendments Technical Specification Changes to Revise Emergency Diesel Generator Test Loads in Surveillance Requirement (SR) 3.8.1.9
	ML101481082
Person / Time
Site:	Prairie Island
Issue date:	06/21/2010
From:	Thomas Wengert; Plant Licensing Branch III
To:	Schimmel M; Northern States Power Co
	Wengert, Thomas J, NRR/DORL, 415-4037
References
	TAC ME0086, TAC ME0087
	Download: ML101481082 (17)
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Mr. Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - ISSUANCE OF ArviENDIVlEl'lTS RE: TECHNICAL SPECIFICATIOI'l CHANGES TO REVISE EMERGENCY DIESEL GENERATOR TEST LOADS IN SURVEILLANCE REQUIREMENT (SR) 3.8.1.9 (TAC NOS. ME0086 AND ME008?)

Dear Mr. Schimmel:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 196 to Facility Operating License No. DPR-42 and Amendment No.185 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 4, 2008, as supplemented by letters dated August 10, 2009, and March 30, 2010.

The amendments increase the 24-month test load for the Unit 1 emergency diesel generators (EDGs) and decrease the 24-month test load for the Unit 2 EDGs in TS SR 3.8.1.9. The request in the November 4, 2008, application to revise the monthly test loads in SR 3.8.1.3 was subsequently withdrawn by the licensee in its March 30, 2010, supplemental letter.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosures:

1. Amendment I'lo. 196 to DPR-42

2. Amendment No. 185 to DPR-60

3. Safety Evaluation cc w/encls: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 196 License No. DPR-42

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated November 4,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:

-2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 196 ,are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: June 21, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 185 License No. DPR-60

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated November 4,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:

-2 Technical Specifications The Technical Specifications contained in Appendix At as revised through Amendment NO.18S ,are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: June 21, 2010

ATTACHMENT TO LICENSE AMENDMENT NOS. 196 AND J 85 FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-50 DOCKET NOS. 50-282 AND 50-305 Replace the following pages of the Facility Operating License No. DPR-42 and DPR-50 with the attached revised pages. The changed areas are identified by a marginal line.

REMOVE INSERT DPR-42, License Page 3 DPR-42, License Page 3 DPR-50, License Page 3 DPR-50, License Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revise page is identified by amendment number and contains a marginal line indicating the area of change.

REMOVE INSERT 3.8.1-9 3.8.1-9

-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 196, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 1, submitted by letters dated October 18, 2006, and January 10, 2007.

Unit 1 Amendment No. 196

-3 (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purposes of volume reduction and decontamination.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 185, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 1, submitted by letters dated October 18, 2006, and January 10, 2007.

Unit 2 Amendment No. 185

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 ----------------------------NOTES-------------------------

I. 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 practicabIe.

24 months Verify each DG operates for > 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For 2: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded:

Unit I 2: 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::: 4860 kW; and

c. Achieves steady state voltage y 3740 V and::: 4580 V; and frequency j 58.8 Hz and < 61.2 Hz.

Prairie Island Unit 1 - Amendment No. m -l-89 1961 Units I and 2 3.8.1-9 Unit 2 - Amendment No. +49 -l-+& 185

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 196 TO FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO. 185 TO FACILITY OPERATING LICENSE NO. DPR-60 NORTHERN STATES POWER COMPANY - MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306

1.0 INTRODUCTION

By application to the U.S. Nuclear Regulatory Commission (NRC) dated November 4, 2008 (Agencywide Documents Access Management System (ADAMS) Accession No. ML083110125),

as supplemented by letters dated August 10,2009 (ADAMS Accession No. ML092230152), and March 30, 2010 (ADAMS Accession No. ML100900088), the Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, requested changes to the technical specifications (TSs) and facility operating licenses for the Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2. The proposed changes would modify TS Surveillance Requirements (SR) related to Emergency Diesel Generator (EDG) Test Loads in SR 3.8.1.3 and SR 3.8.1.9.

On a 24-month frequency, SR 3.8.1.9 requires each EDG to be operated for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , of which at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months are performed within 110 percent of EDG nominal rating and the remainder at a lower load within 90-100 percent of EDG nominal rating. The proposed changes to SR 3.8.1.9 will increase the PINGP Unit 1 EDGs D1 and D2 test load to 2500 kilowatts (kW) each for the 90 percent to100 percent portion of the test and reduce the allowable loading for the two-hour portion of the test on the PINGP Unit 2 EDGs D5 and D6 to a loading between 5400 kW and 5940 kW. The proposed changes to SR 3.8.1.3 (b) and SR 3.8.1.9 (b) to reduce the TS required loading on the Unit 2 EDGs D5 and D6 to 4000 kW were withdrawn by the licensee in its letter dated March 30, 2010.

The supplemental information contained clarifying information, did not change the NRC staff's initial proposed no significant hazards consideration determination, and did not expand the scope of the original Federal Register notice.

2.0 REGULATORY EVALUATION

The following NRC requirements are applicable to the NRC staff's review of the licensee's amendment request:

Enclosure

-2 Title 10 of the Code of Federal Regulations (10 CFR), Part 50 includes the NRC's requirement that TS shall be included by applicants for a license authorizing operation of a production or utilization facility. Section 50.36 (c) of 10 CFR requires that TS include items in five specific categories related to station operation. These categories are: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; and (5) administrative controls. The proposed change to TS 3.8.1 concerns the third category, SRs.

Section 1.5, "General Design Criteria," of the PINGP Updated Safety Analysis Report (USAR),

Revision 30, states that PINGP was designed and constructed to comply with the licensee's understanding of the intent of Atomic Energy Commission (AEC) General Design Criteria (GDC) for Nuclear Power Plant Construction Permits, as proposed on July 10, 1967.

GDC 17, "Electric Power Systems," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, requires, in part, that an onsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The onsite electric power supplies and the onsite electric distribution system shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure. In addition, this criterion requires provisions to minimize the probability of losing electric power from any of the remaining supplies as a result of the loss of power from the unit, the transmission network, or the onsite electric power supplies.

GDC 18, "Inspection and Testing of Electric Power Systems," requires that electric power systems important to safety be designed to permit appropriate periodic inspection and testing to demonstrate operability and functional performance.

AEC GDC 24, "Emergency Power for Protection Systems," states that, in the event of loss of all offsite power, sufficient alternate sources of power shall be provided to permit the required functioning of the protection systems. The facility is supplied with normal, reserve and emergency power to provide for the required functioning of protection systems. In the event of a reactor and turbine trip, emergency power is supplied by two diesel generators per unit, as described in Section 8 of the PINGP USAR. Anyone diesel generator is capable of supplying the emergency power requirements for that unit.

AEC GDC 39, "Emergency Power for Engineered Safety Features (ESF)," states that alternate power systems shall be provided and designed with adequate independency, redundancy, capacity, and testability to permit the functioning required of the ESF. As a minimum, the onsite power system and the offsite power system shall each, independently, provide this capacity assuming a failure of a single active component in each power system. At PINGP, reliability of electric power supply is ensured through two independent connections to the system grid, and a redundant source of emergency power from four diesel generators installed in the facility. Power to the ESF is assured even with the failure of a single active component in each system.

NRC Regulatory Guide (RG) 1.9, "Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants," Revision 4, dated March 2007, describes a method acceptable to the

!\IRC staff for complying with the Commission's regulations with regard to design and testing of diesel generators.

-3 AEC Safety Guide 9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"

dated March 1971, (subsequently superseded by NRC RG 1.9) was applicable when PINGP Unit 1 received its operating license in 1974. This Guide describes an acceptable basis for the selection of diesel generator sets of sufficient capacity and margin to implement GDC 17.

RG 1.108, "Periodic Testing of Diesel Units Used As On-site Electric Power Systems at Nuclear Power Plants", Revision 1, August 1977, describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to periodic testing of diesel electric power units to ensure that the diesel electric power systems will meet their availability requirements. This RG has been withdrawn and the recommendations have been incorporated into RG 1.9, Revision 3 and subsequent revisions.

3.0 TECHNICAL EVALUATION

3.1 Description of the PINGP Electrical Power System The PINGP USAR, Section 8.1, states that, to satisfy AEC GDC 24 and 39, independent alternate power systems are provided with adequate capacity and testability to supply the required ESF and protection systems. Two EDG sets dedicated to each unit are connected to the safeguards buses to supply shutdown power in the event of loss of all other alternating current (AC) auxiliary power. The EDG arrangement provides adequate capacity to supply the ESF for the design-basis accident (DBA) in one unit, assuming the failure of a single component in the system. In the event of a Loss-of-Coolant Accident (LOCA) coincident with a Loss of Offsite Power (LOOP) event, emergency power is available from two EDGs dedicated to each unit.

The original plant design and construction included two Fairbanks-Morse opposed piston EDGs for the two-unit site. These two EDGs, D1 and D2, are now dedicated to Unit 1 to provide onsite standby power sources for 4 kilovolt (kV) safeguards buses 15 and 16. These EDGs are each rated at 2750 kW continuous (for 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months ), 0.8 power factor (PF), 900 revolutions per minute (rpm), 4160 Volt (V), 3-phase, 60 Hertz (Hz). The 1000-hour rating of each EDG is 3000 kW.

The 30-minute rating of each unit is 3250 kW. The PINGP USAR, Section 8.4, states that the Unit 'I EDGs were sized per AEC Safety Guide 9, Paragraph C-2, which requires the predicted load seen by an EDG not to exceed the smaller of either the 2000-hour rating or 90 percent of the 30-minute rating.

In 1992, two Societe Alsacienne de Constructions Mecaniques de Mulhouse (SACM) EDGs, D5 and D6, were installed at PINGP Unit 2 to provide onsite standby power sources for 4 kV safeguards buses 25 and 26. Each SACM EDG is comprised of two tandem-drive units or generator sets. The two Unit 2 EDGs are 4 kV, three phase, 5400 kW continuous (8760 hour0.101 days 2.433 hours 0.0145 weeks 0.00333 months basis), 0.8 PF, 1200 rpm, 4160 V, 3-phase, 60 Hz machines.

EDG loading calculations were provided by the licensee (Ref. 6 and 7) in response to an NRC request for additional information pertaining to license amendment request (LAR) dated October 29,2007 (Ref. 5). Calculation ENG-EE-021 shows that the maximum predicted short time (0 - 5 minutes) sequenced load on Unit 1 EDG D2 is 2538.57 kW. The calculated load on EDG D2 for one hour is approximately 2436 kW. The licensee subsequently performed an evaluation of EDG loading assuming that intermittent loads are considered at 100 percent of

- 4 their rating. As a result of this evaluation, the licensee concluded that maximum sequenced load (0 - 5 minutes) on EOG 02 is 2636.99 kW and the maximum predicted short time (0 - 5 minutes) sequenced load during a LOOP/LOCA event on the Unit 2 EOG 05 is 3864.53 kW. These values are higher than the highest anticipated loads of 2510 kW and 3813 kW for Unit 1 and Unit 2, respectively cited in the current LAR (Ref. 1). The NRC staff's evaluation is based on the higher postulated loadings.

3.2 Evaluation of Proposed Changes

Current TS SR 3.8.1.3 requires that every 31 days:

Verify each OG is synchronized and loaded ~nd operates for ~ 60 minutes at a load:

a. Unit 1; ~ 2500 kW; and

b. Unit 2; ~ 5100 kW and s 5300 kW.

The proposed changes to TS 3.8.1.3 (b) were subsequently withdrawn by the licensee (Ref. 4) and, therefore, SR 3.8.1.3 remains unchanged.

SR 3.8.1.9 currently requires that every 24 months:

Verify each OG operates for ~ 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For ~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded:

Unit 1 ~ 2832 kW, and s 3000 kW and Unit 2 ~ 5562 kW, and s 5940 kW; and

b. For the remaining hours of the test loaded:

Unit 1 ~ 2475 kW, and Unit 2 ~ 4860 kW The proposed SR 3.8.1.9 would require that every 24 months:

Verify each OG operates for ~ 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For ~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded:

Unit 1 ~ 2832 kW and s 3000 kW, and Unit 2 ~ 5400 kW and s 5940 kW; and

b. For the remaining hours of the test loaded:

Unit 1 ~ 2500 kW, and Unit 2 ~ 4860 kW

-5 EDGs D1 and D2 are each rated at 2750 kW continuous (8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months ). Currently, SR 3.8.1.9 (b) requires testing of D1 and D2 at a loadinq z 2475 kW for approximately 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months . Per this LAR, the licensee has proposed increasing the loading for this test to 2500 kW. The summary of engineering calculations provided by the licensee (Ref. 5 and 6) indicates that the maximum postulated loading of EDGs D1 and D2 is less than 2500 kW for extended operation during worst case accident conditions. Based on the results of these calculations, the NRC staff finds that the proposed change to SR 3.8.1.9 (b) to test the EDGs D1 and D2 at 2500 kW for approximately 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months during the endurance run is acceptable as it envelopes the postulated loading and is in compliance with the recommendations of RG 1.9 (Revision 4).

The summary of engineering calculations provided by the licensee (Ref. 5 and 6) indicates that the maximum predicted short time (0 - 5 minutes) sequenced load during a LOOP/LOCA event on Unit 1 EDG D2 is 2636.99 kW (Ref. 6 and 7). The current requirements of SR 3.8.1.9 (a) to test the Unit 1 EDGs at ;:: 2832 kW and :5 3000 kW adequately demonstrate the capability of the EDGs D1 and D2 to support the maximum postulated short-term loading.

EDGs D5 and D6 are each rated at 5400 kW continuous (8760 hour0.101 days 2.433 hours 0.0145 weeks 0.00333 months ). Currently, SR 3.8.1.3 (b) requires monthly testing of D5 and D6 at loadirtqs z 5100 kW and :5 5300 kW. The proposal to revise the D5 and D6 test load frorn z 5100 kW to ;:: 4000 kW was withdrawn by the licensee in its letter dated March 30, 2010 (Ref. 4). Therefore, this requirement remains unchanged as a result of this LAR.

Currently, SR 3.8.1.9 (a) requires D5 and D6 to be tested at z 5562 kW and :5 5940 kW for two or more hours. Per this LAR, the licensee proposed testing at loads z 5400 kW and S 5940 kW for two or more hours. As defined in RG 1.9, Rev. 4, the EDGs used as the onsite electric power system should be able to (1) start and accelerate a number of large motor loads in rapid succession, while maintaining voltage and frequency within acceptable limits, (2) provide power promptly to ESFs if a LOOP and a DBA occur during the same time period, and (3) supply power continuously to the equipment needed to maintain the plant in a safe condition, if an extended LOOP occurs. The endurance and load margin test demonstrates the capability of the EDG at continuous rating and worst-case PF. The preferred duration of an endurance run is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Of this period, 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months should be at a load equal to 105-110 percent of the EDG's continuous rating, and 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months at a load equal to 90-100 percent of the EDG's continuous rating. The test process should verify that frequency and voltage requirements are maintained. The endurance run should envelope the load profile anticipated during the worst case DBA loading including any manually added loads. RG 1.9, Rev. 4 allows testing of EDGs at 90-100 percent of nominal rating based on the assumption that there is a design margin of 5-10 percent in the original sizing of the EDGs.

Per this LAR, the licensee proposed testing EDGs D5 and D6 at 100-110 percent of the nominal rating for the two hours (SR 3.8.1.9 (a)) instead of 105 -110 percent recommended by RG 1.9 (Rev. 4). The intent of this SR is to demonstrate the capability of the EDG to support short-term overload conditions that may occur at the onset or during an event due to motor inrush currents, pumps operating at run out conditions for short durations or unexpected system alignment not considered during the design, resulting in a short-term overload condition of the EDG. In the LAR, the licensee stated that the maximum auto connected load is below 4000 kW. Allowing for short-term overload conditions, the maximum overload condition on D5 and D6 EDGs is expected to be less than the proposed lower limit of testing at 5400 kW. Therefore, the

-6 proposed change to SR 3.8.1.9 (a) to test EDGs 05 and 06 at 100 - 110 percent of the nominal kW rating for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months is acceptable.

The NRC staff has reviewed the licensee's proposed TS changes for PINGP Units 1 and 2 EDGs. Based on the above evaluation, the staff concludes the proposed revisions to the PINGP TSs provide reasonable assurance of the continued availability of the required power to shut down the reactor and to maintain the reactor in a safe condition after an anticipated operational occurrence or a postulated DBA. The staff also concludes that the proposed TS changes are in accordance with 10 CFR 50.36 and the requirements of AEC GDCs 24 and 39 and meet the intent of RG 1.9 (Rev. 4) as related to testing. Therefore, the NRC staff finds the proposed changes to SR 3.8.1.9 to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIROI\lIVlENTAL CONSIDERATION The amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (74 FR 4774). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

1. License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test, dated November 4,2008 (ADAMS Accession Number ML083110125).

2. Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Revise Emergency Diesel Generator Test Loads in SR 3.1.8.3 and SR 3.8.1.9, dated June 26, 2009 (ADAMS Accession Number ML091540227).

-7

3. Supplement No.1 to License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in SR 3.8.1.3 and SR 3.8.1.9, dated August 10, 2009 (ADAMS Accession Number ML092230152).

4. Supplement NO.2 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, dated March 30, 2010 (ADAMS Accession Number ML100900088).

5. License Amendment Request (LAR) to add a Power Factor to the Emergency Diesel Generators' (EDG) 24-hour Load Test (Surveillance Requirement 3.8.1.9) dated October 29, 2007 (ADAMS Accession Number ML073020289).

6. Supplement No.1 to License Amendment Request (LAR) to Add a Power Factor to the Emergency Diesel Generators' (EDG) 24-hour Load Test (Surveillance Requirement 3.8.1.9) dated April 24, 2008 (ADAMS Accession Number ML081150606).

7. Supplement NO.2 to License Amendment Request (LAR) to Add a Power Factor to the Emergency Diesel Generators' (EDG) 24-hour Load Test (Surveillance Requirement 3.8.1.9) dated June 13, 2008 (ADAMS Accession Number ML081650451).

Principal Contributor: G. Matharu, t\lRR Date: June 21, 2010

Mr. Mark A. Schimmel June 21, 2010 Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS RE: TECHNICAL SPECIFICATION CHANGES TO REVISE EMERGENCY DIESEL GENERATOR TEST LOADS IN SURVEILLANCE REQUIREMENT (SR) 3.8.1.9 (TAC NOS. ME0086 AND ME0087)

Dear Mr. Schimmel:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 196 to Facility Operating License No. DPR-42 and Amendment No. 185 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 4, 2008, as supplemented by letters dated August 10, 2009, and March 30, 2010.

The amendments increase the 24-month test load for the Unit 1 emergency diesel generators (EDGs) and decrease the 24-month test load for the Unit 2 EDGs in TS SR 3.8.1.9. The request in the November 4, 2008, application to revise the monthly test loads in SR 3.8.1.3 was subsequently withdrawn by the licensee in its March 30, 2010, supplemental letter.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA!

Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosures:

1. Amendment No. 196 to DPR-42

2. Amendment No. 185 to DPR-60

3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:

PUBLIC LPL3-1 r/f RidsOgcRp Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-1 Resource RidsAcrsAcnw_MailCTR RidsNrrDeEeeb Resource RidsAcrsAcnw_MailCTR Resource GMatharu, NRR RidsNrrDorlLpl3-1 Resource RidsNrrPMPrairielsland Resource RidsNrrDirsltsb Resource RidsNrrDciCptb Resource RidsNrrLABTully Resource RidsRgn3MailCenter Resource ADAMS Accession Number' ML101481082 *via memo dated 5/7/2010 OFFICE NRR/LPL3-11 NRR/LPL3-11 NRRlDEI NRR/DCII NRR/DIRSI OGCINLO NRRlLPL3-11 PM LA EEEB/BC CPTB/BC ITSB/BC WIComments BC NAME TWengert BTuily GWilson* AMcMurtray RElliottlCSS MSmith RPascarel1i for DATE 06/03/10 06/03/10 05/07/10 06/11/10 06/15/10 06/18/10 06/21/10 OFFICIAL RECORD COPY

v t e Letter Sequence Approval
TAC:ME0086, (Approved, Closed) TAC:ME0087, (Approved, Closed)
Initiation Request, Request Acceptance... Supplement Administration Meeting, Meeting, Meeting, Meeting Questions 26 June 2009 Answers Results Approval Other: ML083390695, ML101790452
MONTHYEAR2009-07-08 [Table View]

ML101481082

Text

Dear Mr. Schimmel:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

6.0 CONCLUSION

7.0 REFERENCES

Dear Mr. Schimmel:

Enclosures:

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