View source for L-MT-16-014, License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2

{{Adams
| number = ML16099A097
| issue date = 04/04/2016
| title = License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2
| author name = Gardner P
| author affiliation = Northern States Power Co, Xcel Energy
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000263
| license number = DPR-022
| contact person = 
| case reference number = L-MT-16-014
| document type = Letter type:L, License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 67
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:(l Xcel Energy"                                           Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 April4, 2016                                                                      L-MT-16-014 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM"), requests an amendment to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP). The proposed change revises Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the required 125 VDC subsystems battery charger output current and to remove the second method specified to perform the surveillance. contains a description and summary safety assessment of the proposed TS change as well as the technical bases for the changes. The enclosure also provides the No Significant Hazards Consideration evaluation in accordance with 10 CFR 50.92, "Issuance of Amendment," and the Environmental Assessment. These provide the bases for the conclusion that the license amendment request involves no significant hazards consideration and meets the eligibility criterion for a categorical exclusion as set forth in 10 CFR 51.22, "Criteria for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," paragraph (c)(9). to Enclosure 1 contains the marked-up TS page. Attachment 2 to  provides the marked-up TS Bases pages for information. Enclosure 2 provides a copy of MNGP Calculation 91-006, Revision 4, "125 VDC Battery Charger Sizing."
The MNGP Plant Operations Review Committee has reviewed this application. In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), NSPM is notifying the State of Minnesota by transmitting a copy of this application, with enclosures, to the designated State Official.

Document Control Desk L-MT-16-014 Page 2 of2 NSPM requests NRC approval of the proposed license amendment request (LAR) by April4, 2017. Once approved, the amendment will be implemented within 120 days.
Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments.
If you have any questions or require additional information, please contact Mr. Richard Loeffler at (763) 295-1247.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April '-/, 2016.
    *~~-L-,
Peter A. Gardner Site Vice President- Monticello Nuclear Generating Plant Northern States Power Company - Minnesota

==Enclosures:==

Enclosure 1:        LAR: Revise 125 VDC Battery Charger SR 3.8.4.2 Attachment 1:    Marked-up Technical Specification Page Attachment 2:    Draft Marked-up Technical Specification Bases Pages Enclosure 2:        MNGP Calculation 91-006, Revision 4, "125 VDC Battery Charger Sizing" cc:    Administrator, Region Ill, US NRC Project Manager, Monticello Nuclear Generating Plant, US NRC Resident Inspector, Monticello Nuclear Generating Plant, US NRC State of Minnesota

L-MT-16-014 LICENSE AMENDMENT REQUEST: REVISE 125 VDC BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 Table of Contents ENCLOSURE 1 1.0   

==SUMMARY==
DESCRIPTION .................................................................................. 1

==2.0    BACKGROUND==
INFORMATION ..........................................................................1 3.0   DETAILED DESCRIPTION ...................................................................................2

==4.0   TECHNICAL EVALUATION==
 .................................................................................3 4.1   250 VDC and 125 VDC Electrical Power Systems Description ........................ 3 4.2   Revise the Required 125 VDC System Battery Charger Amperage ................ 5 4.3    Basis for Removal of the Second Testing Option Under SR 3.8.4.2 ............... 7 4.4   Design Basis Accident Considerations ............................................................8

==5.0   REGULATORY EVALUATION==
 .............................................................................9 5.1   Applicable Regulatory Requirements ...............................................................9 5.2   Precedent ...........................................................................................................12 5.3    No Significant Hazards Determination ............................................................ 13

==6.0   ENVIRONMENTAL CONSIDERATION==
 .............................................................. 15

==7.0   REFERENCES==
 ....................................................................................................16 ATTACHMENT 1 ATTACHMENT 2 ENCLOSURE 2 Page 1 of 1

L-MT-16-014 Page 1 of 16 LICENSE AMENDMENT REQUEST: REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 1.0     

==SUMMARY==
DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM"), requests to revise the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP). There are two proposed changes to Surveillance Requirement (SR) 3.8.4.2 in Specification 3.8.4, "DC Sources - Operating".
The first proposed change is to increase the required 125 Volt (V) Direct Current (DC) battery charger output current specified as the first option under SR 3.8.4.2 to resolve a non-conservative TS condition. The second proposed change is to remove from SR 3.8.4.2 an alternative option for meeting the surveillance requirement. This alternative requires verifying each battery charger can recharge the battery to the fully charged state within the required time period, 24 hours for the 250 VDC and 8 hours for the 125 VDC subsystems, respectively, while supplying the largest combined continuous steady state loads, after a battery discharge to the bounding design basis event (DBE) discharge state. The second option under SR 3.8.4.2 was added during the MNGP Improved Technical Specifications (ITS) conversion process in 2006 (Reference 1) but has not been utilized, and it has been determined that it will not be utilized in the future.
There is no specific schedule or timing constraints related to approval of this license amendment request. However, U. S. Nuclear Regulatory Commission (NRC) approval and issuance of a license amendment revising the MNGP TS is requested as soon as reasonable to resolve the non-conservative TS condition.

==2.0     BACKGROUND==
INFORMATION The value of the required output current specified for the 125 VDC battery chargers in SR 3.8.4.2 within the MNGP TS has been identified as being non-conservative. The guidance of NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety," is being applied until this condition has been resolved with approval of this proposed license amendment request.
Corrective actions have been taken to administratively control via procedure changes the required current value during the interim period between the identification of this condition and resolution to ensure conservative operation.

L-MT-16-014 Page 2 of 16 3.0      DETAILED DESCRIPTION The first option under SR 3.8.4.2 currently requires verifying that each required 125 VDC subsystem battery charger supplies greater than or equal to 50 amps. <1l It is proposed to increase the required current output for each required 125 VDC subsystem battery charger to greater than or equal to 75 amps.
The second option under SR 3.8.4.2 requires the following:
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 8 hours for 125 VDC subsystems while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
It is proposed to remove the second option under SR 3.8.4.2 from the MNGP TS. This method has not been utilized in the past, and it has been determined that this method will not be employed at the MNGP in the future to satisfy the surveillance requirement.
Following incorporation of the proposed changes, revised SR 3.8.4.2 would then read (changes are double underlined and deletions are struck through):
SURVEILLANCE                                   FREQUENCY SR 3.8.4.2            Verify each required battery charger supplies the      24 months following:
                         *   ~  150 amps for 250 VDC Div 1
                         *   ~  110 amps for 250 VDC Div 2
                         *   ~  75 amps for 125 VDC subsystems, at greater than or equal to the minimum established float voltage for ~ 4 hours.
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 24 hours for 125 VDC
: 1. Specification 3.8.5, "DC Sources- Shutdown", SR 3.8.5.1 requires SR 3.8.4.2 to be met for the division of DC sources required to be OPERABLE during shutdown conditions.
SR 3.8.5.1 is unaffected by the proposed changes.

L-MT-16-014 Page 3 of 16 SURVEILLANCE                                FREQUENCY subsystems vvhile supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
The TS mark-ups indicating the proposed changes are provided in Attachment 1 to this enclosure. The associated proposed TS Bases changes are provided as mark-ups in  to this enclosure, for information. TS Bases changes are issued in accordance with MNGP Specification 5.5.9, "Technical Specification (TS) Bases Control Program," following approval of the associated license amendment request.

==4.0     TECHNICAL EVALUATION==

MNGP is a boiling water reactor (BWR) of the General Electric BWR/3 design, with a Mark I containment. The plant is located within the city limits of Monticello, Minnesota, on the south bank of the Mississippi River. The electrical power system at the MNGP consists of various Alternating Current (AC) and DC systems. The essential plant DC battery system consists of two 125 VDC and two 250 VDC batteries and subsystems which provide for controls and instrumentation which are vital to reactor and overall plant safety and to power certain functional requirements for reactor shutdown. During normal operation, the DC loads are powered from the battery chargers with the batteries floating on the system. In case of loss of normal power to a battery charger, the DC loads are automatically powered from the station batteries.
4.1     250 VDC and 125 VDC Electrical Power Systems Description The following paragraphs provide a summary discussion of the systems, components, and parameters affected by the proposed changes. The discussion is provided for information but does not describe the changes being proposed.
Two independent divisions of 250 VDC and 125 VDC batteries are provided.
The 250 VDC "power" batteries serve the larger loads such as DC motor driven pumps, valves, etc. The 125 VDC "control" batteries provide the control power for the in-plant 13.8 kVAC breakers, 4160 VAC breakers, 480 VAC Load Center breakers, auxiliary control power for the 1R and 2R Transformers, and various control relays, annunciators, etc. The 125 VDC System also provides power for some emergency lighting.
The Division 1 and Division 2 250 VDC electrical power subsystems provide power to their associated uninterruptible AC power supply (UPS). The Division 1 electrical power subsystem also provides power to support the Reactor Core Isolation Cooling (RCIC) System motor operated valves, and other non-critical

L-MT-16-014 Page 4 of 16 loads. The Division 2 electrical power subsystem supplies power for the High Pressure Coolant Injection (HPCI) System motor operated valves, the HPCI auxiliary oil pumps, and the Control Room Ventilation System control circuits.
Each 250 VDC electrical power subsystem consists of two in series 125 VDC batteries, two normally inservice 125 VDC chargers, a spare 125 VDC charger, and all of the control equipment and interconnecting cabling to the associated distribution panel. Each battery is exclusively associated with a single division.
Each set of battery chargers is also exclusively associated with a 250 VDC electrical power subsystem and cannot be interconnected with the other 250 VDC electrical power subsystem. The inservice and spare chargers are supplied from the associated AC load group.
The Division 1 and Division 2 125 VDC electrical power subsystems provide control power to the associated 4.16 kVAC essential bus and each of the two 480 VAC essential Load Centers, in addition to other non-essential loads. Each 125 VDC electrical power subsystem consists of a one battery (No. 11 for Division 1 and No. 12 for Division 2), one battery charger (D1 0 for Division 1 and D20 for Division 2), and the corresponding control equipment and interconnecting cabling up to the associated distribution panels. Each 125 VDC subsystem battery is composed of 58 C&D Type KCR-13 cells. The inservice battery chargers are supplied from the associated AC load group. The design includes a common spare charger (D40)(2) that can supply either 125 VDC electrical power subsystem.
Each DC battery subsystem is separately housed in a ventilated room. The common standby 125 VDC battery charger is located in a room separate from the other 125 VDC battery chargers electrical power subsystems. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels, except the common standby 125 VDC battery charger may be shared between the Division 1 and Division 2 125 VDC electrical power subsystems, as described previously.
Each division (subsystem) of the DC electrical power system is required to be operable to ensure availability of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (AOO) or a postulated design basis accident (DBA). Loss of any DC electrical power subsystem does not prevent the minimum safety function from being performed.
: 2. The spare 125 VDC battery charger is supplied from the Division 2 AC load group and can only be used to meet the LCO for that division. If it is supplying the Division 1 subsystem, that subsystem is inoperable.

L-MT-16-014 Page 5 of 16 Each essential station battery has adequate storage capacity to meet the duty cycle(s) discussed in Sections 8.5.1.1 and 8.5.2.1 of the MNGP Updated Safety Analysis Report. The essential station batteries are designed with additional capacity above that required by the design duty cycle to allow for temperature variations and aging. The essential batteries for the DC electrical power subsystems are sized to produce capacity greater than required for a DBA and monitored to ensure capacity remains greater than 90 percent during the operating cycle.
4.2   Revise the Required 125 VDC System Battery Charger Amperage SR 3.8.4.2 (first option) currently requires verifying that each 125 VDC battery charger supplies greater than or equal to 50 amps at greater than or equal to the minimum established float voltage to each 125 VDC subsystem for greater than or equal to 4 hours. NSPM proposes to increase the required amperage from each 125 VDC subsystem battery charger from the present value to a value of greater than or equal to 75 amps in SR 3.8.4.2.(3) Increasing the required amperage for each 125 VDC subsystem battery charger corrects a non-conservative TS condition in SR 3.8.4.2.
A simplified methodology for evaluating battery charger sizing is provided within the Institute of Electrical and Electronics Engineers (IEEE) standard, IEEE 946-1985, "IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations" (Reference 2). MNGP Calculation 91-006, Revision 4, "125 VDC Battery Charger Sizing," provided as Enclosure 2, discusses the methodology and assumptions involved in determining a revised amperage value for the first option under SR 3.8.4.2 of greater than or equal to 75 amps for each 125 VDC subsystem. The125 VDC System battery charger sizing was evaluated by calculating the re-charge times(4) considering the coincident 125 VDC System loads also supplied by the charger, utilizing the IEEE 946-1985 methodology.
MNGP Updated Safety Analysis Report Section 8.5.2.1 states:
Each 125 VDC [battery] charger is capable of carrying the normal 125 VDC load and at the same time supplying additional charging current to keep the batteries in a fully charged condition.
IEEE 946-1985 recommends that a battery charger have an output current capability greater than the continuous loads plus the largest combination of non-continuous loads that would be likely to occur simultaneously during normal
: 3. No change is proposed to the required amperage for each of the 250 VDC subsystem battery chargers under the first option of SR 3.8.4.2.
: 4. Note, that for the MNGP there are no explicit licensing basis criteria in place for the recharge time after the design basis discharge.

L-MT-16-014 Page 6 of 16 plant operation. This criterion is met if the battery charger output current exceeds the normal continuous system loads by an amount adequate to bound the non-continuous load combinations likely during normal plant operation.
The respective load profiles used to determine the degree of battery discharge were taken from the sizing worksheets of the battery sizing calculations. The 125 VDC System is required to operate without the battery chargers supplying system loads during two DBEs, i.e., during a DBA, a Loss of Coolant Accident (LOCA) with a Loss of Off-site Power (LOOP) and a Station Blackout (SBO).
The load profiles modelled are a bounding composite combination of loads that would be needed to mitigate a LOOP I LOCA and the loads necessary to operate equipment necessary to mitigate a 4-hour SBO event.
The IEEE standard recommends that the battery charger output current capacity exceed the combination of continuous system loads plus the largest combination of non-continuous loads that would be likely to occur simultaneously during normal operation. The highest actual operating 125 VDC subsystem operating loads were 23 amps (Division 1) and 24 amps (Division 2) determined from a review of several months of system operating logs. After including allowances for uncertainty and margin, the normal continuous 125 VDC subsystem loads have been determined to be less than 30 amps for either subsystem.(s) The 125 VDC battery chargers provide an output current capability of 75 amps (minimum) resulting in more than 45 amps available to serve simultaneous non-continuous loads.
The proposed revised amperage value for the first option under SR 3.8.4.2, of greater than or equal to 75 amps assures each 125 VDC battery charger supplies sufficient current output to meet the respective 125 VDC subsystem loads, while providing sufficient charging capacity to restore the battery in a reasonable timeframe for a full rated discharge with the normal plant 125 VDC subsystem loads, and for a LOOP-LOCA I 4-hour SBO event.
No change is necessary to the frequency of the surveillance (SR 3.8.4.2) as the surveillance will continue to be performed at the current frequency of 24 months.
: 5. The determination of the respective a125 VDC subsystem loading range incorporates tolerances for reading uncertainty and margin.

L-MT-16-014 Page 7 of 16 4.3   Basis for Removal of the Second Testing Option Under SR 3.8.4.2 It is proposed to remove the second testing option under SR 3.8.4.2 from the MNGP TS. Technical Specification Task Force (TSTF) traveler TSTF-360, "DC Electrical Rewrite" (Reference 3), was incorporated into the MNGP TS as part of the Monticello ITS conversion. One of the changes included within the TSTF traveler was a new provision under SR 3.8.4.2 providing an alternative to the criteria that specified to meet this surveillance requirement for battery charger testing. TSTF-360 provides the following description as the basis for this alternative:
NUREG STS [Standard Technical Specification] SR 3.8.4.6 (being revised to SR 3.8.4.2) requires specific parameters for battery charger performance testing. This test is intended to confirm the charger design capacity.
Alternate acceptance criteria [emphasis added] are proposed that would allow an actual in service demonstration that the charger can recharge the battery to the fully charged state within [24] hours while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state. This meets the intent of the existing test and allows for normal in-place demonstration of the charger capability thereby minimizing the time when the charger would be disconnected from the DC bus.
The second option under SR 3.8.4.2 states:
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 8 hours for 125 VDC subsystems while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
The second option was added during the Monticello ITS conversion because it was included as part of the standard wording within the applicable NUREG for the BWR/4 design, i.e., NUREG-1433 (which was applied for the Monticello conversion), and it was thought that inclusion of this alternative would provide additional flexibility that might prove useful for testing of the 250 VDC subsystems and 125 VDC subsystems in the future. However, this method has not been utilized to satisfy this surveillance requirement (SR 3.8.4.2) since its incorporation into the MNGP TS for either the 250 VDC System or the 125 VDC System. It has been determined that this second option will not be employed at the MNGP to satisfy this surveillance requirement for either the 250 VDC System or the 125 VDC System.
The second option requires that each battery charger be capable of recharging the battery after a service test coincident with supplying the largest coincident demands of the various continuous steady state loads (irrespective

L-MT-16-014 Page 8 of 16 of the status of the plant during which these demands occur). This level of loading is not normally available following the battery service test and would need to be supplemented with additional loads.
The requirements to satisfy the second option under SR 3.8.4.2 complicate testing at the MNGP and require initial conditions that are not typically present during a refueling outage. As previously indicated, this option has not been employed at the MNGP to satisfy SR 3.8.4.2 and is not planned to be used in the future. NSPM does not typically perform service tests for the essential batteries, but instead performs modified performance tests on a refuel cycle frequency as described in "Supplemental Safety Evaluation Report - Monticello Nuclear Generating Plant Station Blackout Rule", dated August 5, 1992 (Reference 4).
The MNGP is therefore not generally in the initial conditions necessary to perform the testing as presently described in the MNGP TS Bases.
Furthermore, the second option is considered less desirable to be performed at the MNGP due to the added complexity of controlling the additional load needed to simulate the largest coincident demands of the various continuous steady state loads during the recharge period. Removing the second option also eliminates the difficulty associated with selecting a conservative recharge time to specify in the TS surveillance requirement considering that the MNGP essential batteries may vary from greater than 100 to 90 percent of rated capacity, that recharge time is affected by temperature as well as charger output voltage, and that the largest coincident steady state loads may change somewhat with future plant modifications. Directly loading and monitoring the battery charger output current as specified under the first option of SR 3.8.4.2 is considered to provide a clearer and more definitive demonstration of the battery charger capacity and capability.
Therefore, since the first (original) testing option under SR 3.8.4.2 is being retained and the second option provides an alternate means of meeting the surveillance requirement, independent of the first option, removal of the second
* option for testing the 250 VDC System and the 125 VDC System under SR 3.8.4.2 is acceptable. Testing of the 250 VDC and the 125 VDC Systems will continue to be performed under the "first" testing option under SR 3.8.4.2.
4.4   Design Basis Accident Considerations The initial conditions of the DBA and transient analyses in Updated Safety Analysis Report Chapter 14, assume that the Engineered Safety Feature (ESF) systems are operable. The DC electrical power system provides normal and emergency DC electrical power for the emergency diesel generators (EDGs),
emergency auxiliaries, and control and switching during all modes of operation.
The operability of the DC electrical subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design

L-MT-16-014 Page 9 of 16 basis of the unit. This includes maintaining DC sources operable during accident conditions in the event of:
: a. An assumed loss of all offsite AC power or all onsite AC power; and
: b. A worst case single failure.
The DC electrical power subsystems are also required to be operable to ensure the availability of the required power to shut down the reactor and maintain it in a safe condition after an AOO, in addition to a postulated DBA. Loss of any DC electrical power subsystem does not prevent the minimum safety function from being performed.
The revised 125 VDC battery charger required output current will continue to ensure that the Updated Safety Analysis Report described battery charger design basis is met and that essential batteries can be maintained fully charged to provide adequate power to support the Emergency Core Cooling System function. The limit also assures adequate charger capacity at the conclusion of the essential battery duty cycle following a DBA to support continuous steady state DC system loads. Hence, this proposed TS change to increase the required amperage of the 125 VDC battery chargers from 50 to 75 amps under the first option of SR 3.8.4.2 will assure that each 125 VDC battery charger supplies sufficient current output to meet the respective 125 VDC subsystem loads.
Removal of the second (alternate) testing option under SR 3.8.4.2, only removes some unnecessary flexibility in testing methodology from the MNGP TS. The retention of the first testing option under SR 3.8.4.2 maintains the original methodology for performing and meeting SR 3.8.4.2. Therefore, both of the proposed changes to SR 3.8.4.2 are safe and are acceptable.

==5.0   REGULATORY EVALUATION==

5.1   Applicable Regulatory Requirements 10 CFR 50.36, 'Technical specifications," provides the regulatory requirements for the content required in the TS. 10 CFR 50.36(c)(3) requires the establishment of surveillance requirements "relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The proposed TS changes revise Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2, to increase the required 125 VDC subsystems battery charger amperage, and to also remove a second option under SR 3.8.4.2 to perform battery charger testing.

L-MT-16-014 Page 10 of 16 The MNGP was designed largely before the publishing of the 70 General Design Criteria for Nuclear Power Plant Construction Permits proposed by the Atomic Energy Commission (AEC) for public comment in July 1967, and constructed prior to the 1971 publication of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50. As such, the MNGP was not licensed to the Appendix A, General Design Criteria (GDC).
The MNGP Updated Safety Analysis Report, Section 1.2, lists the principal design criteria (PDCs) for the design, construction and operation of the plant.
USAR Appendix E provides a plant comparative evaluation to the 70 proposed AEC design criteria. It was concluded that the plant conforms to the intent of the GDCs. The applicable GDCs and PDCs are discussed below.
* PDC 1.2.6 - Plant Electrical Power Sufficient normal and standby auxiliary sources of electrical power are provided to attain prompt shutdown and continued maintenance of the plant in a safe condition under all credible circumstances. The capacity of the power sources is adequate to accomplish all required engineered safeguards functions under all postulated design basis accident conditions.
Of the 70 Draft AEC General Design Criteria (AEC-GDC) the following are applicable:
* AEC-GDC Criterion 24 - Emergency Power for Protection Systems (Category 8)
In the event of the loss of all off-site power, sufficient alternate sources of power shall be provided to permit the required functioning of the protection systems.
* AEC-GDC Criterion 39 - Emergency Power for Engineered Safety Features Category A)
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 on-site power system and the off-site power system shall each, independently, provide this capacity assuming a failure of a single active component in each power system.

L-MT-16-014 Page 11 of 16
* AEC-GDC Criterion 41 - Engineered Safety Features Performance Capability (Category A)
Engineered safety features such as emergency core cooling and containment heat removal systems shall provide sufficient performance capability to accommodate partial loss of installed capacity and still fulfill the required safety function. As a minimum, each engineered safety feature shall provide this required safety function assuming a failure of a single active component.
While not part of the MNGP Licensing Basis, the applicable 10 CFR 50, Appendix A, GDC are:
* GDC 17 - Electric power systems An onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents.
The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure.
Electric power from the transmission network to the onsite electric distribution system shall be supplied by two physically independent circuits (not necessarily on separate rights of way) designed and located so as to minimize to the extent practical the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. A switch yard common to both circuits is acceptable. Each of these circuits shall be designed to be available in sufficient time following a loss of all onsite alternating current power supplies and the other offsite electric power circuit, to assure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. One of these circuits shall be designed to be available within a few seconds following a loss-of-coolant accident to assure that core cooling, containment integrity, and other vital safety functions are maintained.
Provisions shall be included to minimize the probability of losing electric power from any of the remaining supplies as a result of, or coincident with,

L-MT-16-014 Page 12 of 16 the loss of power generated by the nuclear power unit, the loss of power from the transmission network, or the loss of power from the onsite electric power supplies.
* GDC 18 - Inspection and testing of electric power systems Electric power systems important to safety shall be designed to permit appropriate periodic inspection and testing of important areas and features, such as wiring, insulation, connections, and switchboards, to assess the continuity of the systems and the condition of their components. The systems shall be designed with a capability to test periodically (1) the operability and functional performance of the components of the systems, such as on site power sources, relays, switches, and buses, and (2) the operability of the systems as a whole and, under conditions as close to design as practical, the full operation sequence that brings the systems into operation, including operation of applicable portions of the protection system, and the transfer of power among the nuclear power unit, the offsite power system, and the onsite power system.
NSPM has evaluated the proposed changes against the applicable regulatory requirements and acceptance criteria. The technical analysis in Section 4.0 concludes that the revised 125V battery charger output current is reasonable and that it is acceptable to remove the second option for meeting SR 3.8.4.2 since it is not necessary and is not going to be performed. Based on this, there is reasonable assurance that the health and safety of the public, following approval of this change, is unaffected.
5.2   Precedent In 1996, the two unit Salem Nuclear Generating Station received two license amendments to revise the respective units TSs to lower the 125 Volt Battery Charger surveillance amperage from at least 200 amps to at least 170 amps so as not to require the replacement of input cables to the battery chargers for charger replacements (Reference 5). IEEE Standard IEEE 946-1992 was utilized to size the replacement battery chargers.
In 1997, Millstone Nuclear Power Station, Unit No.3, received a somewhat similar license amendment to increase the required test voltage for the 125 Volt Battery Chargers (Reference 6).

L-MT-16-014 Page 13 of 16 5.3   No Significant Hazards Determination In accordance with the requirements of 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the Northern States Power Company- Minnesota (NSPM), doing business as Xcel Energy, Inc., requests an amendment to revise Monticello Nuclear Generating Plant (MNGP) Technical Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the 125 VDC subsystems battery charger amperage and to remove the second surveillance option which requires monitoring battery recharge time while controlling additional load to simulate the largest combined demands of the various continuous steady state loads.
NSPM's evaluation against each of the criteria in 10 CFR 50.92, "Issuance of amendment," follows:
: 1.      Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed TS changes revise the battery charger surveillance requirements in SR 3.8.4.2. The DC electrical power system, including associated battery chargers, is not an initiator of any accident sequence analyzed in the Updated Safety Analysis Report (USAR). Rather, the DC electrical power system supports operation of equipment used to mitigate accidents. Operation in accordance with the proposed TS continues to ensure that the DC electrical power system is capable of performing its specified safety functions as described in the USAR. Therefore, the mitigating functions supported by the DC electrical power system will continue to provide the protection assumed by the analysis.
Accidents are initiated by the malfunction of plant equipment, or the catastrophic failure of plant structures, systems, or components (SSCs).
Performance of battery testing is not a precursor to any accident previously evaluated, nor does it change the manner in which the batteries and battery chargers are operated. The proposed testing requirements will not contribute to the failure of the batteries nor any plant SSC. NSPM has determined that the proposed TS changes provide an equivalent level of assurance that the batteries and battery chargers are capable of performing their intended safety functions. Thus, the proposed changes do not affect the probability of an accident previously evaluated.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

L-MT-16-014 Page 14 of 16
: 2.       Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The DC electrical power system, including the associated battery chargers, is not an initiator of any accident sequence analyzed in the USAR. The proposed TS changes do not involve operation of the DC electrical power system in a manner or configuration different from those previously evaluated. Performance of battery testing is not a precursor to any accident previously evaluated. NSPM has determined that the proposed TS changes provide an equivalent level of assurance that the batteries and battery chargers are capable of performing their intended safety functions. Therefore, the mitigating functions supported by the DC electrical power system will continue to provide the protection assumed in the safety analyses.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
: 3.       Does the proposed change involve a significant reduction in a margin of safety?
Response: No The margin of safety is established through the equipment design, the operating parameters, and the setpoints at which automatic actions are initiated. The equipment margins will be maintained in accordance with the plant-specific design bases as a result of the proposed changes. The proposed changes do not adversely affect operation of plant equipment. The proposed TS changes do not result in a change to the setpoints at which protective actions are initiated. Sufficient DC capacity to support operation of mitigation equipment continues to be ensured. The equipment fed by the DC electrical sources will continue to provide adequate power to safety-related loads in accordance with safety analysis assumptions.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, the NSPM has determined that operation of the facility in accordance with the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92, "Issuance of amendment," paragraph (c), in that it does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of

L-MT-16-014 Page 15 of 16 a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

==6.0     ENVIRONMENTAL CONSIDERATION==

10 CFR 51.22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perform an environmental assessment. NSPM has determined that the proposed amendment meets the criteria for a categorical exclusion from an environmental review as set forth in 10 CFR 51.22, specifically 10 CFR 51.22(c)(9). First, the proposed amendment changes a requirement with respect to installation or use of a facility or component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation," or involves a change to an inspection or surveillance requirement. Second, the proposed amendment requires no environmental assessment since operation of the facility in accordance with the proposed amendment does not (i) involve a significant hazards consideration, or (ii) authorize a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) result in a significant increase in individual or cumulative occupational radiation exposure. Therefore, the NSPM concludes pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

L-MT-16-014 Page 16 of 16

==7.0   REFERENCES==
: 1. Letter from T. Beltz (NRC) to J. Conway (NMC), "Monticello Nuclear Generating Plant (MNGP) - Issuance of Amendment for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues (TAG Nos. MC7505, MC7597 through MC7611, and MC8887," dated June 5, 2006
: 2. IEEE Std. 946-1985, "IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations"
: 3. Technical Specification Task Force (TSTF) traveler TSTF-360-A, Revision 1, "DC Electrical Rewrite", dated December 18, 2000.
: 4. Supplemental Safety Evaluation - Monticello Nuclear Generating Plant Station Blackout Rule (10 CFR 50.63), dated August 5, 1992
: 5. Letter from L. Olshan (NRC) to L. Eliason (PSEG), "Salem Nuclear Generating Station, Unit Nos. 1 and 2 (TAG Nos. M94634 and M94635)," dated June 27, 1996. Issuance of Amendment No. 183 for Unit 1 and Amendment No. 164 for Unit 2, respectively.
: 6. Letter from J. Andersen (NRC) to N. Carns (Northeast Nuclear Energy Company), "Issuance of Amendment (TAG No. M98724)," for the Millstone Nuclear Power Station, Unit No. 3," dated September 5, 1997 (Amendment No. 149)

ENCLOSURE 1 ATTACHMENT 1 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 MARKED-UP TECHNICAL SPECIFICATION PAGE
( 1 page follows)

DC Sources- Operating 3.8.4 ACTIONS (continued)
CONDITION                           REQUIRED ACTION             COMPLETION TIME C. Required Action and            C.1        Be in MODE 3.               12 hours associated Completion Time not met.                 AND C.2        Be in MODE 4.               36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE                                    FREQUENCY SR 3.8.4.1        Verify battery terminal voltage is greater than or        7 days equal to the minimum established float voltage.
SR 3.8.4.2        Verify each required battery charger supplies the         24 months following:
                    *   ;;::: 150 amps for 250 VDC Div 1
                    *   ;;::: 110 amps for 250 VDC Div 2
                    *   ;;::: 75 amps for 125 VDC subsystems, at greater than or equal to the minimum established float voltage for ;;::: 4 hours.
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 8 hours for 125 VDC subsystems *.vhile supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
Monticello                                       3.8.4-2               Amendment No. -149, 153

ENCLOSURE 1 ATTACHMENT 2 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 DRAFT MARKED-UP TECHNICAL SPECIFICATION BASES PAGES (FOR INFORMATION)
(4 pages follow)

DC Sources - Operating B 3.8.4 BASES BACKGROUND (continued)
During normal operation, the DC loads are powered from the battery chargers with the batteries floating on the system. In case of loss of normal power to the battery charger, the DC loads are automatically powered from the station batteries.
The DC power distribution system is described in more detail in Bases for LCO 3.8.7, "Distribution System- Operating," and LCO 3.8.8, "Distribution System- Shutdown."
Each DC battery subsystem is separately housed in a ventilated room.
The common standby 125 VDC battery charger is located in a room separate from the other 125 VDC battery chargers electrical power subsystems. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem.
There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels, except the common standby 125 VDC battery charger may be shared between the Division 1 and Division 2 125 VDC electrical power subsystems.
Each Division 1 and Division 2 250 VDC battery has adequate storage capacity to meet the duty cycle(s) discussed in USAR, Section 8.5.1.1 (Ref 4). Each Division 1 and Division 2 125 VDC battery has adequate storage capacity to meet the duty cycle(s) discussed in USAR, Section 8.5.2.1 (Ref. 5). The battery is designed with additional capacity above that required by the design duty cycle to allow for temperature variations and other factors.
The batteries for DC electrical power subsystems are sized to produce capacity greater than required for a design basis accident and monitored to ensure battery capacity will remain > 90% during the operating cycle.
No Changes.         The minimum design voltage limit is 105/210 V.
The page is         The battery cells are of flooded lead acid construction with a nominal included for        specific gravity of 1.215. The open circuit voltage is the voltage information,        maintained when there is no charging or discharging. Once fully charged, so that the         the battery cell will maintain 98% capacity for 30 days without further context of the      charging per manufacturer's instructions. Optimal long term performance change on the       however, is obtained by maintaining a float voltage 2.20 to 2.25 Vpc. This next page is        provides adequate over-potential, which limits the formation of lead clear.              sulfate and self discharge.
Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation, while at the same time maintaining its battery Monticello                         B 3.8.4-2                                Revision No.

DC Sources - Operating B 3.8.4 BASES BACKGROUND (continued) bank fully charged. Each station service battery charger has sufficient e*cess capacity to restore the battery from the design minimum charge to The battery chargers ~ its fully charged state V.'ithin 24 hours 'Nhile supplying normal steady state are sized to charge    teaa&.-
the batteries while supplying the normal   The battery charger is normally in the float-charge mode. Float-charge is continuous DC loads    the condition in which the charger is supplying the connected loads and (Refs. 4 and 5).       the battery cells are receiving adequate current to optimally charge the battery. This assures the internal losses of a battery are overcome and the battery is maintained in a fully charged state.
When desired, the charger can be placed in the equalize mode. The equalize mode is at a higher voltage than the float mode and charging current is correspondingly higher. The battery charger is operated in the equalize mode after a battery discharge or for routine maintenance.
Following a battery discharge, the battery recharge characteristic accepts current at the current limit of the battery charger (if the discharge was significant, e.g., following a battery service test) until the battery terminal voltage approaches the charger voltage setpoint. Charging current then reduces exponentially during the remainder of the recharge cycle. Lead-calcium batteries have recharge efficiencies of greater than 95%, so once at least 105% of the ampere-hours discharged have been returned, the battery capacity would be restored to the same condition as it was prior to the discharge. This can be monitored by direct observation of the exponentially decaying charging current or by evaluating the amp-hours discharged from the battery and amp-hours returned to the battery.
APPLICABLE         The initial conditions of Design Basis Accident (DBA) and transient SAFETY             analyses in USAR, Chapter 14 (Ref. 6), assume that Engineered Safety ANALYSES           Feature (ESF) systems are OPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the emergency diesel generators (EDGs), emergency auxiliaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis of the unit. This includes maintaining DC sources OPERABLE during accident conditions in the event of:
: a. An assumed loss of all offsite AC power or all onsite AC power; and
: b. A worst'case single failure.
The DC Sources- Operating satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
Monticello                              B 3.8.4-3                                  Revision No.

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE REQUIREMENTS (continued) battery servioe test and 'Nill need to be supplemented with additional loads. The duration for this test may be longer than the oharger sizing oriteria sinoe the battery reoharge is affeoted by float voltage, temperature, and the exponential deoay in oharging ourrent. The battery is reoharged '.vhen the measured charging ourrent is < 2 amps for 250 VDC batteries and < 1 amp for 125 VDC batteries.
The Frequency is acceptable, given the unit conditions required to perform the test and the other administrative controls existing to ensure adequate charger performance during these 24 month intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.
SR 3.8.4.3 A battery service test is a special test of the battery's capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length corresponds to the design duty cycle requirements as specified in Reference 4 for the 250 VDC electrical power system and Reference 5 for the 125 VDC electrical power system.
The Frequency of 24 months is acceptable, given plant conditions required to perform the test and the other requirements existing to ensure adequate battery performance during the 24 months intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.
This SR is modified by two Notes. Note 1 allows the performance of a modified performance discharge test in lieu of a service test.
The reason for Note 2 is that performing the Surveillance would remove a required DC electrical power subsystem from service, perturb the electrical distribution system, and challenge safety systems. This restriction from normally performing the Surveillance in MODE 1 or 2 is further amplified to allow portions of the Surveillance to be performed for the purpose of reestablishing OPERABILITY (e.g., post work testing following corrective maintenance, corrective modification, deficient or incomplete surveillance testing, and other unanticipated OPERABILITY concerns) provided an assessment determines plant safety is maintained or enhanced. This assessment shall, as a minimum, consider the potential outcomes and transients associated with a failed partial Surveillance, a successful partial Surveillance, and a perturbation of the offsite or onsite system when they are tied together or operated Monticello                          B 3.8.4-8                                 Revision No.

ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 CALCULATION 91-006, REVISION 4 125 VDC BATTERY CHARGER SIZING (40 pages follow)

QF0549 (FP-E-CAL-01), Rev. 7                                                         Page 1 of4
(! XceiEnergy*                     Calculation Signature Sheet Document Information NSPM Calculation (Doc) No: 91-006                                              I Revision:   4

==Title:==
125 VDC Battery Charger Sizing Facility: ~~~]"MT D   PI                                                  I Unit: ~  1 02 Safety Class:       ~SR       OAugQ        D Non SR Special Codes:    D Safeguards D Proprietary                               ..
Type: Calc        Sub-Type:
I NOTE:          I Print and sign name in signature blocks, as required.
Major Revisions                                        I   D       N/A EC Number: 24146                                     D Vendor Calc Vendor Name or Code:                                 Vendor Doc No:
Description of Revision: See Purpose section of calculation.
The following calculation and attachments have been reviewed and deemed
                                                                                                      ~
acceptable as a legible QA recor~                                                              I Prepared by: (sign)   ~        f           I (print) Rhon Sanderson          Date: 1D - ).8 - Is-Reviewed by:(sign) d~ ~            :--.,
* I  (print)  Jnkc. 5-l-rc.~Se.r    Date: /o /2 8/2<-*1 :s Type of Review: gDesign Verification       D Tech Review D Suitability Review Method Used (For qv Only):~ Review D Alternate Calc D Test Approved by: (sign)~~ Pr.jff /(print) &#xa3;P vJArzL                              Date: to. j:;..~!:Qt?
tt Minor Revisions                                        I   ~       N/A EC No:                                               D Vendor Calc:
Minor Rev. No:
Description of Change:
Pages Affected:
The following calculation and attachments have been reviewed and deemed D
acceptable as a legible QA record                                                              I Prepared by: (sign)                         I  (print)                       Date:
Reviewed by: (sign)                   /
I (print)                       Date:
Type of Review:    D   D~sign Verification D Tech Review D Suitability Review Method Used (For DV Only): D Review D Alternate Calc 0 Test Approved by: (sign)                          /"(print)                       Date:
Record Retention: Retain this form with the associated calculation for the life of the plant.

QF0549 (FP-E-CAL-01), Rev. 7                                                                                               Pa(le 2 of 4 (l Xcel Energy*                                             Calculation Signature Sheet This reference table is used for data entry into the PassPort Controlled Documents Module reference tables (C012 Panel). It may also be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed by using the "TAB" key and filling in the appropriate information in each column.
Reference Documents              (PassPort co12 Panel from C020)
 #   Co~trolled*                                Document Name Document             Doc         Ref Type**
Doc?+ Type                                                                                    Number              Rev      INPUT OUTPUT 1   y        CALC      Div. 1125 Volt Battery Calculation                                   02-179                       3         X 2   y        CALC      Div. II 125 Volt Battery Calculation                                 02-192                       3         X 3                      IEEE Recommended Practice for Sizing Large Lead Storage-N        --------  Batteries for Generating Stations and SubStations IEEE 485-1983             -------      X 4   y        PROC      Operations Manual, Lighting, Description of Equipment                 B.09.14-02                  1         X 5                      C&D Technologies Publication 12-316, KCR-13 Lead-Calcium N        -----     Standby Batteries 12-316                   -----        X 6   y        PROC      Operations Manual, 125 VDC System, Description of Equipment           B.09.10-02                  9         X 7   N        ----. -   Operator Rounds record, Turbine Building East (2010) 2014-2015       ---------------           ----         X 8                      IEEE Recommended Practice for the Design of Safety-Related DC N        -------   Auxiliary Power Systems for Nuclear Power Generating Stations IEEE 946-1985             ----         X 9   y        PROC      D1 0 Battery Charger Preventive Maintenance                          4066-PM                      3         X 10  y        PROC      D20 Battery Charger Preventive Maintenance                           4075-PM                      3         X 11  y        PROC      D40 Battery Charger Preventive Maintenance                 I 4078-PM                      5         X 12  N        - ..----- Replace Div. 1125 VDC Battery Charger D10                             EC720                    ------       X 13  N        ------    Replace Div. 11125 VDC Battery Charger D20                            EC 12877                 ------       X 14  N        -----     Replace 125 VDC Battery Swing Charger D40                             EC 13284                 ------       X 15  N        ------    ITS 125 VDC charger SR 3.8.4.2-0ptoln 2 unachievable                 AR#01131103               ------
16  N        -------   TS SR 3:8.4.2 Non-Conservative for the 125 VDC Chargers              AR # 01456839             -----
17 Record Retention: Retain this form with the associated calculation for the life of the plant.

QF0549 (FP-E-CAL-01), Rev. 7                                                                                                           Page 3 of4 (t Xcel Energy-                                                      Calculation Signature Sheet
* Controlled Doc marked with an "X' means the reference can be entered on the C012 panel in black. Unmarked lines will be yellow. If marked with an "X", also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.
 ** Mark with an 'X" if the calculation provides inputs and/or outputs or both. If not, leave blank. (Corresponds to PassPort "Ref Type" GOdes: Inputs I Both =
     "ICALC", Outputs= "OCALC", Other I Unknown= blank)
Other PassPort Data Associated System (PassPort C011, first three columns)                     OR         Equipment References (PassPort C025, all five columns):
Facility               Unit                       System                      Equipment Type             Equipment Number MT                     1                          125                         CHGR                       010 MT                     1                          125                         CHGR                       020 MT                     1                          125                         CHGR                       040 Superseded Calculations (PassPort C019):
I Faolllty I Calo Dooumenl Numb" .1 Tille Description Codes- Optional (PassPort C018):
Code                        Description (optional)                             Code                              Description (optional)
Notes (Nts)- Optional (PassPortX293 from C020):
Topic Notes                   I Tex,t
[gl Calc Introduction         I [gl Copy directly from the calculation Intra Paragraph or D See write-up below D    (Specify)                I Record Retention: Retain this form with the associated calculation for the life of the plant.

QF0549 (FP-E-CAL-01) Rev. 7                                                                                   Paae 4 of4 (l Xcel Energy-                                       Calculation Signature .Sheet Monticello Specific Information
[g) YES  ON/A       Topic Code(s) (See MT Form 3805):             SBO DYES     jg!N/A     Structural Code(s) (See MT Form 3805):_ __
Does the Calculation:
DYES 0 No           Require Fire Protection Review? (Using MT Form 3765, "Fire Protection Program Checklisr, determine if a Fire Protection Review is required.) If YES, document the engineering review. in the EC. If NO, then attach completed MT Form 3765 to the associated EC.
DYES [g) No         Affect piping or supports? (If Yes, Attach MT Fonn 3544.)
DYES [g) No         Affect 1ST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation.)
Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0527 (FP-E-MOD-07) Rev. 4                                                                              Page 1 of 1
 ~ Xcel Energy~                                                    Design Review Checklist EC Number or Document Number I Title I Revision Number:             91-006. 125 VDC Battery Charger Sizing, Rev. 4 Verifier's Name:       Jake Strasser Discipline:      Electrical Design DESIGN REVIEWCONSIDERATIONS:                                                                     Yes    No     NIA
: 1.       Were the inputs correctly selected and incorporated into design?                         IZI   D*     D
: 2.       Are assumptions necessary to perform the design activity adequately described and        IZI   D      D reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?            .
: 3.       Are the appropriate quality and quality assurance requirements specified?                D     D      IXl
: 4.       Are the applicable codes, standards, and regulatory requirements including issue
* and addends properly identified and are their requirements for design met?
IXl   D      D
: 5.       Have applicable construction and operating experience been considered?                         D      IXl
: 6.       Have the design interface requirements been satisfied?                                         D      D
: 7.       Was an appropriate design method used?                                                         D      D
: 8.       Is the output reasonable compared to inputs?                                                   D      D
: 9.       Are the specified parts, equipment and processes suitable for the required application?
D      IXl
: 10.    *Are the specified materials compatible with each other and the design environmental       D conditions to which the material will be exposed?
: 11.      Have adequate maintenance fea~ures and requirements been specified?                      D
: 12.      Are accessibility and other design provisions adequate for performance of needed         D maintenance and repair?                                *       . .          *
: 13.      Has adequate accessibility been provided to perform the in-service inspection            D expected to be required during the plant life?
: 14.      Has the design properly considered radiation exposure to the public and plant personnel?
D     D      IXl
: 15.      Are the acceptance criteria incorporated in the desi9n documents sufficient to allow
        . verification that.design requirements have been satisfactorily accomplished?
o -o
: 16.      Have adequate pre~operational, subseguent periodic test and inspection                   D requirements been*appropriately specified, including acceptance criteria?
: 17.      Are adequate handling, storage, cleaning, and shipping requirements specified?           D
: 18.      Are adequate identification requirements specified?                                      D
: 19. Are requirements. for record preparation, review, approval, and retention adequately      D specified?                                      .                     .
: 20. Have Design and Operational Margins been considered and documented?                             D      D COMMENTS:           0   None                1Z1 Attached (Use Form QF-0528)                  D In ECTopic Notes Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-0528 (FP-E-MOD-07) Rev. 1 (l     Xcel Energy**                                     Design Review Comment Form Sheet _1_ of _1_-
DOCUMENT NUMBER/ TITLE:                      91_-006, 125 VDC Battery Charger Sizing REVISION:          4        DATE:     10/28/2015 ITEM            REVIEWER'S COMMENTS                             PREPARER'S                 REVIEWER'S
    #                                                             RESOLUTION                 DISPOSITION
: 1.       The calculation references IEEE Std 946-           Included a discussion      Accepted.
1985 for guidance and methodology. The             regarding the 1985 version standard has since been revised (presently         versus the 2004 version.
IEEE Std 946-2004) and given that MNGP has no licensing commitments to the 1985 version, the latest revision should be referenced or the differences dispositioned within the calculation.
: 2.       The recharge time computation for "full-rated"     No response required.      Accepted.
discharge is noted to be very conservative in that the 8-hr rate to 1. 75 vpc is used. From a cell sizing and performance test standpoint "rated" capacity for the MNGP application is generally taken to be the 4-hr rate to 1.81 vpc.
: 3.       Reference 10.22 (ML111110396) is noted to        Reference 10.22 changed    Accepted.
be an interim paper discussing the NRC's           to NUREG/CR-7148.
then ongoing research on float current as an indicator of state-of-charge. The final testing report is documented as NUREG/CR-7148.
The information as presented in the final report has no impact on the data as referenced within the calculation.
: 4.       The composite bi:lttery duty cycle currents for    Values adjusted and        Accepted.
periods 11 and 9 of Div I and Div II,              reference to CAP added.
respectively, need to be adjusted per CAP AR 01474466.
Reviewer: ?J~        . ,_,/~ -           Date: JohRhwr PreQ_arer:
                                                     ,                    ~           /_
I Page 1 of 1

CA-91-006, Rev. 4 TABLE OF CONTENTS Item        Description                                     Pages QF-0549     Calculation Signature Sheet                        4 QF-0527     Design Review Checklist                            1 QF-0528     Design Review Comment Form                         1 TOC         Table of Contents                                  1 Calculation Body (including attachments)                      33 Total    40 Page 1 of 1

MONTICELLO NUCLEAR GENERATING PLANT                                            CA-91-006 TITLE:                                                                         Revision 4 125 VDC Battery Charger Sizing Page 1 of 33
: 1.      PURPOSE The purpose of this calculation is to analyze the sizing of the 125V battery chargers.
The specific battery chargers analyzed are:
D10- Div. 1125 VDC Battery Charger- supplies #11 Battery D20- Div. II 125 VDC Battery Charger- supplies #12 Battery 040 - Swing 125 VDC Battery Charger- can supply either #11 or #12 Battery Revision 3 addressed the increased DC output current capability of the 125 VDC chargers installed perECs 13284,12877, and 720 (References 10.12, 10.13, 10.14).
Revision 4 addresses changes to steady-state loads for post SBO re-charge per new revisions of the station 125 VDC battery calculations (References 10.1, 10.2).
* 2.       METHODOLOGY Ops Manual B.09.10-02 (Ref. 10.6) describes the 125 VDC System equipment. Each battery
(#11 for Division I and #12 for Division II) is composed of 58 C&D Type KCR-13 cells. The 125 VDC system battery chargers D1 0, D20, and D40 are output current-limited at nominal value of 80 amps. The minimum current limit value of 75 amps will be applied in this calculation.
 - During battery recharging, each charger must also supply its divisional 125 VDC system loads.
A simplified methodology for evaluating charger sizing is given in IEEE 946-1985 (Ref. 10.8).
The equation given in this standard will be applied to determine the approximate re-charge times expected for each 125 VDC battery. Note that the IEEE 946 standard has been updated (see following excerpt from IEEE 946-2004). For purposes of this calculation the original1985 version of IEEE 946 specifically for nuclear generating stations will be the primary reference for the methodology and acceptance criteria employed in evaluating charger sizing. Where the 2004 version provides more technical detail or prescribes a more conservative method of evaluation the 2004 version of IEEE 946 will be adhered to.

MONTICELLO NUCLEAR GENERATING PLANT                                                                             CA-91-006 TITLE:                                                                                                          Revision 4 125 VDC Battery Charger Sizing Page 2 of33 Excerpt of IEEE 946-2004:
The original issue- of IEEE Std. 946 was published in 19&5 with fue- title ffiEE Rec-ommended Pl-adice for the Des~gn. of S:afety-R.elated DC Auxili.;uy Power Systems for Nuclear Power Gene-ating Statioru. The 1992 l'e\ision changed ilie title to apply to all generating !>bti.oll!l, while including specific: guidance and a detailed
        'biblitJ_gnphy of nuclear deri.gn refell!llC'J! atand.anls. This revision makes ;a general update. to reflect the most xe<:ent indusb:y practices as. wen as substanfi;U additions to annexes. In addition, as the design of nuclear plmt sy!items has become v.*ell docwnented by other IEEE standards, the- direct emphasis nn unique aspecb of nuelear plant desi_gn has 'b!!en furlhex diminished, with a full lilitlng of the .nuclear <lesign standards included in Anne~ A. Some 'uude<U* di5c=sion and illusinti>.'ec :fi~s* balie been retained as they offe:r a cnns.tructil.re compans<ln to non-nuclear designs without ha1.-:ing to res111f to -additional standards.
Charger sizing will be evaluated by calculating re-charge times considering coincident 125 VDC system loads also supplied by the charger, using the IEEE 946 methodology. This is the same method described in the EPRI Power Plant Electrical Reference Series Volume 9, DC Distribution System (Reference 10.18). Acceptance criteria will be from the 1985 version of IEEE-946. The 2004 version will be referenced as appropriate.
: 3. ACCEPTANCE CRITERIA Per USAR Section 08.05 (Reference 10.17): "Each 125 VDC charger is capable of carrying the normal125 VDC load and at the same time supplying additional charging current to keep the batteries in a fully charged condition." This criterion is met if the charger output current exceeds the normal system loads such that charging current can be supplied to the battery.
For the purposes of determining required output current capability of the 125 VDC chargers, the methodology and criteria of IEEE 946 (References 10.8 and 10.9) will be used, with acceptance criteria from IEEE 946-1985. IEEE 946-1985 recommends a re-charge time of 8 to 12 hours. This IEEE 946-1985 criteria is met if the calculated re-charge time (after a full-rated discharge ofthe battery) is between 8 and 12 hours, considering normal125 VDC system loads.
* IEEE 946-1985 also recommends that the charger have output current capability greater than the continuous loads.plus the largest combination of non-continuous loads that would be likely to occur simultaneously during normal plant operation. This IEEE 946-1985 criteria is met if the charger output current exceeds nornial continuous* system loads by an amount adequate to bound non-continuous load combinations likely during normal plant operation. Note that meeting the IEEE 946 criteria ensures the USAR criterion is met.
This calculation will also evaluate re-charge time following a Station Blackout discharge of each battery. The Monticello licensing basis discharge corresponds to the Station Blackout event ahd the equivalent discharge load profile is taken from the battery sizing calculations (References 10.1 and 10.2). This is the discharge that the battery would undergo if subjected to a service test with a load profile matching that modelled in the battery calculations which

MONTICELLO NUCLEAR GENERATING PLANT                                                CA-91-006 TITLE:                                                                             Revision 4 125 VDC Battery Charger Sizing Page 3 of 33 model a composite profile for the 4-hour LOCA I Station Blackout event The re-charge time will be calculated using the IEEE 946 equation (same equation for both the 1985 and 2004 versions of IEEE 946) with system load considered to be the largest continuous load combination present at the end of the modelled station blackout event. There are currently no explicit licensing basis criteria in place for the recharge time after the design basis discharge.
The load profile used to determine the degree of battery discharge will be taken from the sizing worksheets of the battery sizing calculations. These sizing worksheets tabulate loads vs. time and evaluate battery positive-plates-required in accordance with IEEE Std.485-1983 (Reference 10.3). The profiles modelled are a composite combination of loads that would be needed to mitigate a LOCA event coincident with a loss of offsite power and the loaqs necessary to operate equipment necessary to mitigate a 4-hour Station Blackout event.
: 4.      INPUTS 4.1     The charger output-current limit setting is 78-82 amps, per PM procedures (References 10.9, 10.1 0, 10.11 ). A charger minimum current output of 75 amps will be used for this calculation.
4.2      The battery discharge during an SBO event is modelled in the following calculations:
For Div. I (#11 Battery)- CA-02-179 (Reference 10.1)
For Div. II (#12 Battery)- CA-02-192 (Reference 10.2)
The load data from these calculations is consolidated in the spreadsheet of Attachment
: 02. This spreadsheet tabulates the effective amp-hours discharged for both the Div. I and Div. II SBO events. The load values were adjusted in select time periods in accordance with the issue identified in CAP AR # 01474466 (Reference 10.24). The corrected values are as given in ECs 25634 and 25511 (References 10.25 and 10.26).
Note that the bounding loads considering 1 minute minimum time interval taken from the battery sizing worksheets are used. The results of the calculations in the spreadsheet are as follows:
                     . Div. I (#11 Battery) total amp-hours discharged= 263.01 Div. II (#12 Battery) total amp-hours discharged= 240.49

MONTICELLO NUCLEAR GENERATING PLANT                                           CA-91-006 TITLE:                                                                        Revision 4 125 VDC Battery Charger Sizing Page 4 of 33 4.3   The rated battery discharge capacity will be taken to be the full KCR-13 cell capacity for a discharge to 1. 75 volts I cell as given in Attachment 01.
Full rated discharge amps hours = 495 maximum This is conservative as it is a larger value than the 8-hour value recommended by IEEE 946-1985. Also in Attachment 1 are the ratings as given in the battery sizing calculations (excerpt taken from 02-192). Note that the ratings are slightly different.
The 495 amp-hour value representing ultimate capacity will be used to determine the maximum re-charge time. The 8 hour value from the C&D ratings table of 61 x 8 = 488 will be used to calculate minimum re-charge time.
Full rated discharge amps hours = 488 minimum 4.4   The steady-state system loads after an SBO discharge will be taken from the node current analysis in the battery sizing calculations. The DC system loads at analyzed time steps were inspected to select the load for each battery that represents the largest combination of steady-state loads that could be present at the end of the SBO event..
For the Div. I system, Time Step 52 of the Div. I calculation (Reference 10.1) represents that maximum steady state load on the Div. I 125 VDC system at the end of an SBO event. For the Div. II system, the maximum steady state load considered is taken from Time Step 53 of the Div. II calculation (Reference 10.2). The effective system loads are dependent on the corresponding system voltages. These voltages will be taken as the battery node voltage from the calculations fodhe applicable time steps.
Div. I (#11 Battery) current at Time Step 52 = 61.54 Amps Div. I (#11 Battery) voltage at Time Step 52 = 109.204 VDC Div. II (#12 Battery) current at Time Step 53= 57.95 Amps Div. II (#12 Battery) voltage at Time Step 53= 110.130 VDC For the Div. I system, the current due to the emergency lighting load will be subtracted, as the emergency lights will switch off once AC power is restored to the holding coil for the DC contactor feeding Panel L40 (Reference 10.4) at the end of the SBO event.
Div. I Emergency Lighting current at Time Step 52= 13.94 amps Therefore:
Div. I post-SBO 125 VDC system load= 61.54-13.94 = 47.6 amps (at a battery terminal voltage of 109.204 VDC)

MONTICELLO NUCLEAR GENERATING PLANT                                             CA-91-006 TITLE:                                                                          Revision 4 125 VDC Battery Charger Sizing Page 5 of 33 Div. II post-SBO 125 VDC system load= 57.95 amps (at a battery terminal voltage of 110.130
                                                         .    . VDC) 4.5    For full-rated battery discharge, the system loads present during re-charge would be the same as the 125 VDC system loads under normal plant conditions. Per Operation's Logs (Reference 10. 7), these normal loads are very consistent. Two
* separate months of data were reviewed and the highest load value selected for each Division (Attachment 03):
Div. I normal system load = 23 amps Div. II normal system load= 24 amps The loading recorded in the logs was very consistent. The panel ammeter has an accuracy of 1% of the 150 amps full scale range or +I- 1.5 amps (Reference 10.20). The current shunt has an accuracy of +I- 0.33% or 0.495 amps (References 10.20, 10.21 and Attachment 5). The ammeter scale has 2 amp graduations for a readability error of +/- 1 amp. Combining these errors statistically using a square-root-sum-of-squares method:
Total ammeter uncertainty= (1.5A2 + 0.495A2 + 1A2)A1f2 = 1.87 amps.
Therefore an uncertainty of+/- 2 amps will be considered to apply to the log readings.
For conservatism, the upper limit and lower limits on normal load will be adjusted by
       + or- 3 amps, giving normal load limits as follows:
Div. I minimum normal system load = 23 3 = 18 amps
                                                     =           =
Div. I maximum normal system load 23 + 2 + 3 28 amps Div. II minimum normal system load =24 3 = 19 amps Div. II maximum normal system load = 24 + 2 + 3 = 29 amps
: 5. ASSUMPTIONS 5.1   None

MONTICELLO NUCLEAR GENERATING PLANT                                              CA-91-006 TITLE:                                                                           Revision 4 125 VDC Battery Charger Sizing Page 6 of 33
: 6.      ANALYSIS From IEEE 946-1985 (Reference 10.8), the battery charger sizing should be evaluated using the following formula:
A= l.lxAHR +L T
A       = Charger Rating L       = Station Load AHR . =Battery Discharge in Ampere Hours T       = Hours to Recharge 1.1     = Compensation for battery losses No correction factors for altitude or temperature are needed for the chargers in use at Monticello as temperatures are less than 50 deg; C and altitude is less than 3300 feet.
When solved for time (T), equation 2.1 becomes:
T == l.lxAHR A-L Division I Calculation (01 0 or 040 re-charging #11 .Battery)
For a Station Blackout. design basis discharge event (DIV 1):
During re-charge following a station blackout event, the continuous load given in Input 4.4 will increase as voltage increases during re-charge. The load will be considered constant resistance for conservatism and adjusted for the maximum charger float.
voltage of 130.5 volts, as defined in procedure 4510-PM (Reference 10.19).
The 2004 version of IEEE-946 notes that the actual percent charge restored to a battery when using the given sizing equation is dependent on applied voltage. To ensure a 95% restored charge consistent with the standard, a charger voltage output in the equalizing range may be necessary. Per procedure 4510-PM, the maximum equalizing voltage for the 125 VDC chargers is 135.8 VDC, or 2.342 volts I cell. Note however, that during the current limited portion of the re-charge cycle (bulk phase) battery voltage rises over time to the charger setting. As an example of this charging response for. lead acid batteries reference the following excerpts from C&D Batteries and NRC (References 10.22 and 10.23). At the onset of charging, battery voltage
* would be well below normal float voltage.* The average current available for re-charging the battery would then be*reduced as voltage rises, due to the corresponding increase in current to the system loads. The voltage rise can be conservatively

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MONTICELLO NUCLEAR GENERATING PLANT                                           CA-91-006 TITLE:                                                                        Revision 4 125 VDC Battery Charger Sizing Page 8 of 33 Adjusting system loads as discussed* and applying the sizing equation gives:
L = 47.6 amps x 130.5 VDC /109.204 VDC = 56.9 amps             Input 4.4 A= 75 amps                          Input 4.1 AHR= 263.01 amp-hours               Input 4.2 T = (1.1 x 263.01) I (75- 56.9)
T = 16.0 Hours (Div. L re-charge after design basis Station Blackout event)
For a full-rated battery discharge (DIV 1):
The system load considered for calculating time for a recharge of the battery after a discharge of its rated capacity is taken from Operator logs of the battery charger output current during normal plant conditions.
L = 23 amps +/- 5 amps       Input 4.5 A= 75 amps minimum                         Input 4.1 A= 82 amps maximum                         Input 4.1

MONTICELLO NUCLEAR GENERATING PLANT                                                CA-91-006 TITLE:                                                                             Revision 4 125 VDC Battery Charger Sizing Page 9 of 33
                    =
AHR 495 amp-hours maximum                   Input 4.3 AHR = 488 amp-hourminimum                   Input 4.3 Tmin  = (1.1 x 488) I (82- 18) = 8.3*hours Tmax   = (1.1 x 495) I (75 - 28) =11.6 hours T =8.3 Hours to     11.6 Hours (Div. I. re-charge after full rated battery discharge)
Division II Calculation (020 or 040 re-charging #12 Battery)
For a Station Blackout, design basis discharge event (Div II):
During re-charge following a station blackout event, the continuous load given in Input 4.4 will increase as voltage increases during re-charge. The -load given for the Div. II 125 VDC system can be conservatively considered constant-resistance and adjusted for a maximum charger float voltage of 130.5 volts, as defined in procedure 451 0-PM           *
(Reference 10.19). See the discussion for the Division I station blackoutcharging calculation for justification of the use of 130.5 volts for determination of system loads, even if the actual recharge is performed with the charger at a maximum equalize setting of 135.8 VDC.
L  =57.95 amps x 130.5 VDC 1110.130 VDC =68.7 amps                lnput4.4 This is a large load and bounds the Div. I considered maximum recharge load by a wide margin. As a significant portion of the loading is due to constant power and constant current loads, a DCSDM software run of the Time Step 53 loads was executed with a battery node voltage of 130.5 VDC. *The output report of this run is given in Attachment *
: 4. The calculated load value of 60.25 amps from Attachment 4 will be used.
L  =60.25 amps                       Attachment 4 A= 75 amps                           lnput4.1 AHR = 240.49 amp-hours               Input 4.2 T =(1.1 x 240.49) I (75- 60.25)
T = 18.0 Hours (Div. II. re-charge after design basis Station Blackout event)

MONTICELLO NUCLEAR GENERATING PLANT                                            CA-91-006 TITLE:                                                                         Revision 4
* 125 VDC Battery Charger Sizing Page 10 of 33 For a full-rated battery discharge (DIV II):
The system load considered for calculating time for a recharge of the battery after a discharge of its rated capacity is taken from Operator logs of the battery charger output current during normal plant conditions.
L =24amps       +1- 5 amps     lnput4.5 A =75 amps minimum                        Input 4.1 A= 82 amps maximum                        Input 4.1 AHR = 495 amp-hours maximum               Input 4.3 AHR = 488 amp-hour minimum                Input 4.3 Tmin  =(1.1 x488) I (82 -19)
Tmax = (1.1 x 495) I (75- 29)
T =8.5 Hours to 11.9 Hours (Div. II, re-charge after full rated battery discharge)

==7.0  CONCLUSION==
S IEEE 946-1985 (Reference 10.8) recommends sizing battery chargers for an 8 to 12 hour re-charge time, considering a battery discharged to its full rating and normal DC system loading. The corresponding re-charge times calculated were:
Re-charge after full rated discharge with normal plant loads Div. I, 8.3 to 11.6 hours Div. II, 8.5 to 11.9 hours These calculated times are within the IEEE 946-1985 recommended time range of 8 to 12 hours. The 125 VDC system loading range assumed incorporates tolerance for reading uncertainty and margin. Therefore the charger current limit settings are well-matched to the battery size considering system loads and in accordance with the standard.
IEEE 946 recommends that charger output current capacity exceed the combination of continuous system loads plus the largest combination of non-continuous loads that would be 'likely to occur simultaneously during normal operation. With continuous loads less than 30 amps and charger output current capability of 75 amps (minimum), more*

MONTICELLO NUCLEAR GENERATING PLANT                                             CA-91-006 TITLE:                                                                           Revision 4 125 VDC Battery Charger Sizing Page 11 of 33 than 45 amps is available for simultaneous non-continuous loads. During normal plant operation, additional non-continuous simultaneous loads are very uri likely to exceed 45 amps.
Recharge times were conservatively calculated for a design bas.is battery re-charge considering the continuous loads that would be present post-event:
Recharge after a Station Blackout, design basis discharge event:
Div. I, 16.0 hours Div. II, 18.0 hours The calculated times demonstrate that the each charger's sizing is adequate to supply the maximum combination of continuous loads present after a Station Blackout event and re-charge its battery in a reasonable time (to 95% capacity). The 125 VDC system loads assumed during recharge after the design basis event were conservatively adjusted to correspond to maximum float voltage for the entire recharge time period.
Note that AR #011311 03 documented an issue with the 2nd method of determining acceptance for Tech Specs surveillance requirement SR 3.8.4.2, i.e. that the battery chargers can accomplish a re-charge in <= 8 hours after a design basis discharge event (SBO). AR # 01456839 formally documented this issue as a non-conservative Tech
* Specs surveillance requirement and establishe*d administrative limit for the 1st method of meeting SR 3.8.4.2. The administrative limit 125 VDC system battery charger output current was established as >= 75 amps.
* The basis for the second method of SR 3.8.4.2 involves achieving re-charge of a battery after a service test with the maximum continuous load applied to the system that could be present regardless of plant conditions. The service test would essentially correspond to the design basis load profile modelled in the battery calculations for a station blackout event. The maximum continuous loads would be as determined in this calculation based on a review of the continuous loads applied at the end of this event.
Thus, this calculation demonstrates that re-charge would occur in this case in reasonable time. However, this method of surveillance of the battery chargers would not be used at Monticello as battery testing is performed via a modified performance test, which of necessity discharges the battery to a greater degree than a service test.
The most precise way to ensure the battery charger is capable of performing its design functions is to test it per the 1st method, thus ensuring it can supply adequate current at float voltage for a 4 hour time period.
Final resolution of the Tech Spec issue described in ARs 01131103 and 01456839 requires a permanent change to the 1st method of meeting SR 3.8.4.2. The criteria should be changed to>= 75 amps for 4 hours (as is presently administratively

MONTICELLO NUCL!;AR GENERATING PLANT                                            CA-91-006 TITLE:                                                                          Revision4 125 VDC Battery Charger Sizing Page 12 of 33 controlled): It is recommended that 2nd method of meeting the surveillance be removed, as this test method is not used at Monticello. This calculation shows that a charger current of 75 amps is adequate to re-charge the 125 VDC batteries within a reasonable time after a design basis event and considering continuous post-event loads.
8.0   FUTURE NEEDS AR # 01456839 tracks completion of a License Amendment Request for Technical Specifications SR 3.8.4.2. The first option should be changed to >= 75 amps, as is currently administratively controlled. The second option should be removed from Tech Specs as this test option would not be of practical use at Monticello. This calculation determines that a charger test to >= 75 amps for 4 hours demonstrates the ability to re-charge batteries after the limiting Station Blackout event in reasonable time, considering the largest combination of 125 VDC system steady state loads.
9.0   ATTACHMENTS Attachment 01- Excerpt of C&D Technologies, Publication 12-316, KCR-13 Lead-Calcium Standby Batteries Attachment 02- Spreadsheet showing total discharge amp-hours for Div. I and Div. II 125 VDC batteries based on SBO battery calc load profiles Attachment 03- Excerpt of 2010 Ops Log for 010, 020 charger output current, Sept. 2010, Jan. and June 2011 Attachment 04- DCSDM software sizing report showing calculation 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.

==10.0 REFERENCES==

10.1  Calculation CA-02-179, Div. 1125 Volt Battery Calculation, Rev. 3 10.2  Calculation CA-02-192, Div. 11125 Volt Battery Calculation, Rev. 3 1"0.3 IEEE Std. 485-1983, 'IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations'

MONTICELLO NUCLEAR GENERATING PLANT                                        CA-91-006 TITLE:                                                                     Revision 4 125 VDC Battery Charger Sizing Page 13 of33 10.4  B.09.14-02, Operations Manual, Lighting, Description of Equipment, Rev. 1 10.5  C&D Technologies, Publication 12-316, KCR~13 Lead-Calcium Standby Batteries (see Attachment 01 for excerpt) 10.6  B.09.1 0-02, Operations Manual, 125 VDC System, Description of Equipment, Rev. 9 10.7  Operator rounds records, Turbine Building East (2010), excerpts from December, 2014 and July, 2015 included as Attachment 03.
10.8. IEEE Std. 946-1985, 'IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations' 10.9  IEEE Std. 946-2004, 'IEEE Recommended Practice for the Design of DC Auxiliary Pow~r Systems for Generating. Stations' 10.10 4066-PM, D1 0 Battery Charger Preventive Maintenance, Rev. 3 10.11 4075-PM, D20 Battery Charger Preventive Maintenance, Rev. 3 10.12 4078-PM, D40 Battery Charger Preventive Maintenance, Rev. 5 10.13 EC 720, Replace DIV. 1125 VDC Battery Charger D10 10.14 EC 12877, Replace Div. 11125 VDC Battery Charger D20 10.15 EC 13284, Replace 125 VDC Battery Swing Charger 040 10.15 AR # 01131103, ITS 125VDC charger SR 3.8.4.2-0ption 2 unachievable 10.16 AR # 01456839, TS SR 3.8.4.2 Non Conservative for the 125 VDC Chargers 10.17 USAR-08.05, Plant Electrical Systems, Rev. 30 10.18 EPRI Power Plant Electrical Reference Series, Volume 9, EC Distribution System, Copyright 1987 10.19 451 0-PM, Maintenance of On-Site Batteries and Battery Chargers at Monticello Nuclear Plant, rev. 35 10.20 NX-9173-19, C & D Battery Chargers (D10,020,D40) NLI Model: ARR130K100F-MOD, rev. 1

MONTICELLO NUCLEAR GENERATING PLANT                                     CA-91-006 TITLE:                                                                  Revision 4 125 VDC Battery Charger Sizing Page 14 of 33
* 10.21 Rammeter website page showing.F150A50 current shunt accuracy (Attachment 5) 10.22 NUREG/CR-7148, Confirmatory Battery Testing: The Use of Float Current Monitoring
* to Determine Battery State-of-Charge, p*ublished November 2012 10.23 C&D Technologies Technical Bulletin 41-2128, Charging Valve Regulated Lead Acid Batteries
* 10.24 CAP AR # 01474466, DCSDM Software Issue, initiated 04-14-15 10.25 EC 25634, Monticello 125V #11 Battery Modified Performance Test Profile 10.26 EC 25511, Monticello 125V #12 Battery Modified Performance Test Profile

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                           CA-91-006 TITLE:                                                                                                                                                        Revision 4 125 VDC Battery Charger Sizing Page 15 of33 1 - KCR-13 Battery Ratings: Excerpt of C&D Technologies,                                                                                                page 1 of 2 Publication 12-316, KCR-13 Lead-Calcium Standby Batteries:
Excerpt of 02-192, MNGP 125 Volt Div. II Battery Calculation CDTECHNOLOGfE~~~~~~~- ----~ __
Powet SGluTilnfr-'.::                       ~
* Excerpt of C&D Technologies Doc. 12-316,2007 RATINGS TABLE: AMPERES
                                                                             'Nominal Rat?" 0 77'F (2G'C) in 1.21!> N<!mlnai_SG (lntludas cimnaclor voH.oga drop}*.
Amp&nltO NomlnaiAH Final Volta       Models              Rating
* lihr                4hr            3hr         1.5hr             1 hr           30m!n    15m!n        1mln KCRIKAR-5              200                   25 ..            41 .           50          77              .M                1211     165         243 KCRIKAR-7              250                   31              li3             65          101              126             173       221         300 KCRIKAR-0              330                   41               71             9T          135            ,:169             231       294         412 KCRIKAR-11              410                   52              88              109 '.      166        '     206             294       364         608 1.75        KCRlKAR-13              495                   61              106             tat ~-      204              254             351       450         655 KCRIKAR-16              577                   72.             124             162***.. 237              297             411       6112        707 KCR!i<AR-17             660              .. '92 .             142             174:        272             '340             470       604         871 KCRIKAR-19              742                   92              159             195.        aoa             *378             .520      664         949 KCRIKAR--21             925                   100             176             216.        332             -413             567       728         1028 KCRIKAR-6              194                   24               41             41l :        74               Ill             122      154         213 KCRIKAR-7              239                '30                51              62           95             .117             169       198         264 KCRIKAR-9              :119                . 40.              6ll            93 .        126       . "156 .-              211       264         353 KCWKAR-11               401            ._. .- 60 <       .
ll4             wi*.        155          *. 191 ~            260       327         435 1.76        KCRIKAR-13              479                   SQ.             102             124         191              236             320       404         560 KGR/i<AR-15             659          *.* *70                  119             145         222            . 275             ll75      4Tr         682 KCRIKAR-17              637                   00              136             166'-       254           : 315         . 429       542         746 KCRJKAR-111             719                   90              152         0 196         293           . a!io -* .        474       596         912 KCRIKAR-21              1102             .*-too               169           .-205.        310              382 .           518       653         891 KCRIKAR-6              190                 . 24   ....       @               49           71               96              114      140         *193 KCRJKAR-7              231                   29              .(9       . '511             as     I         109             143      175         22t KCRIKAR-9              ll10                  3~               65             7B          117     I         14&deg;4 ; .. 0 191      293         204 KCRIKAR-11              300                   4~ .             90        '. 97 *.         146              tfr .**         235       289         364
                                                                                                            .                . 219                    .*. 357; 1.81        KCRIKAR-13              464                   511              !!7        . 118.          178                              200                   467 I(CR/KAR-15             541                  *68              114      **..- 139'*        207              254 .<          agg       422         569 KCRIKAR-11              619                   77              1110          *H>7          237              ,291'           9118      479         621 KCRIKAR-10              699                  '97              146             176         264              :123             420      627**        677 KCRIKAR-21              779                   97              161           '194.         289          ,' 353              460       577          736
     *oaa baood en di!<ila~ga tllroody lrom a 72-hoor noat oonlfllon periEEE-450 prooedu1eo.

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                   CA-91-006 TITLE:                                                                                                                                Revision 4 125 VDC Battery Charger Sizing Page 16 of 33 1 - KCR-13 Battery Ratings: Excerpt of C&D Technolog*ies,                                                                    page 2 of 2 Publication 12-316, KCR-13 Lead-Calcium Standby Batteries:
Excerpt of02-192, MNGP 125 Volt Div. II Battery Calculation
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                                                                                                                                 CA-91-006 TITLE:                                                                                                                                                                                                                                                                              Revision 4 125 VDC Battery Charger Sizing Page 17 of 33 2- Spreadsheets showing total discharge amp-hours for                                                                                                                                                                                                                          page 1 of 2 Div. I and Div. 11125 VDC batteries based on SBO battery Calc. load profiles (from calc. sizing worksheets)
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                                                                                               CA-91-006 TITLE:                                                                                                                                                                                                                                            Revision 4 125 VDC Battery Charger Sizing Page 18 of 33 2- Spreadsheets showing total discharge amp-hours for                                                                                                                                                                                       page 2 of2 Div. I and Div, II 125 VDC batteries based on SBO battery Calc. load profiles (from calc. sizing worksheets) l~y._IL~tte.r~~~-q ~l~~h-~.t~.:-
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MONTICELLO NUCLEAR GENERATING PLANT                                    CA-91-006 TITLE:                                                                 Revision 4 125. VDC Battery Charger Sizing Page 19 of 33 3- Excerpt of 2010 Ops Log for 010, 020 charger output       page 1 of 8 current, Dec. 2014 and July, 2015 021)                         Max: !ill till its:~
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MONTICELLO NUCLEAR GENERATING PLANT                                                                               CA-91-006 TITLE:                                                                                                            Revision 4 125 VDC Battery Charger Sizing Page 20 of33 3 - Excerpt of 201 0 Ops Log for D 10, 020 charger output                                               page 2 of 8 current, Dec. 2014 and July, 2015 12/(l:l/2014 11)00                                 ~.Rtl
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                   CA-91-006 TITLE:                                                                                                                Revision 4 125 VDC Battery Charg.er Sizing Page 21 of33 3- Excerpt of 2010 Ops Log for 010, D20 charger output                                                     page 3 of 8 current, Dec. 2014 and July, .2015 Tliti;Jil'oll flplldlll;j Em (2010)                                                          gwr-o2.o;1 Oi*fW AQU~
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MONTICELLO NUCLEAR GENERA TJNG PLANT                                                           CA-91-006 TITLE:                                                                                         Revision 4 125 VDC Battery Charger Sizing Page 22 of 33 3 - Excerpt of 2010 Ops Log for D 10, 020 charger output                             page 4 of 8 current, Dec. 2014 and July, 2015 USVOC CJWIGEJHOR: #U .IIATnJlY C!JRRE!fT                           .~1'1\11 =~ M';l$
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MONTICELLO NUCLEAR GENERATING PLANT                                                         CA-91-006 TITLE:                                                                                      Revision 4 125 VDC Battery Charger Sizing Page 23 of 33 3- Excerpt of 2010 Ops Log for 010, 020 charger output                            page 5 of 8 current, Dec. 2014 and July, 2015 D-~ VOlTAGl-JU)AJ lfUIIATnRV 02!1                                                         !II>.TTERI!!iS 07/(11)201!> 21Xll        tll              ~.~
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MONTICELLO NUCLEAR GENERATING PLANT                                                                       CA-91-006 TITLE:                                                                                                    Revision 4 125 VDC Battery Charger Sizing Page 24 of 33 3- Excerpt of 2010 Ops Log for 010, 020 charger output                                           page 6  of 8 current, Dec. 201.4 and July, 2015 *
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                CA-91-006 TITLE:                                                                                                             Revision 4 125 VDC Battery Charger Sizing Page 25 of 33 3- Excerpt of 2010 Ops Log for 010, 020 charger output                                                   .page 7 of 8 current, Dec. 2014 and July, 2015 D-11JVOLTA~-1LOAT .-11 Blo.TTfR&#xa5; 01(14{2!)15: 21100        ll1                           ~. ~
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MONTICELLO NUCLEAR GENERATING PLANT                                                         CA-91-006 TITLE:                                                                                      Revision 4 125 VDC Battery Charger Sizing Page 26 of33 3 - Excerpt of 201 0 Ops Log for D 10, 020 charger output                        page 8 of 8 current, Dec. 2014 and July, 2015 125'/CiC CIIAAGfll POR Mti llAMllV CURIII:IfT                            lbm;li =:2<; .in~
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MONTICELLO NUCLEAR GENERATING PLANT                                                          CA-91-006 TITLE:                                                                                       Revision 4 125 VDC Battery Charger Sizing Page 27 of33 4- DCSDM software sizing report showing calculation                               page 1 of 6 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
Attachment F Node Voltages By:      - - - - - - - - - - - - - - - - - D a l e : _ _ _ _ _ __
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Xcel Energy 1Monllceno -12liVdo      DCSDM Version 3.0     Attaclunent FD2DBA Page FD2DBA 1 of Cole No. 02.192 Reil. 3                                                              FD2DBA3

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                     CA-91-006
                                                                                                                                                        *.*               Revision 4*
TITLE:
125 VDC Battery Charger Sizing Page28 of 33 4- DCSDM software sizing report showing calculation                                                                                                           page 2 of6 02-:192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
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(l Xcel Energy"                                           Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 April4, 2016                                                                      L-MT-16-014 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM"), requests an amendment to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP). The proposed change revises Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the required 125 VDC subsystems battery charger output current and to remove the second method specified to perform the surveillance. contains a description and summary safety assessment of the proposed TS change as well as the technical bases for the changes. The enclosure also provides the No Significant Hazards Consideration evaluation in accordance with 10 CFR 50.92, "Issuance of Amendment," and the Environmental Assessment. These provide the bases for the conclusion that the license amendment request involves no significant hazards consideration and meets the eligibility criterion for a categorical exclusion as set forth in 10 CFR 51.22, "Criteria for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," paragraph (c)(9). to Enclosure 1 contains the marked-up TS page. Attachment 2 to  provides the marked-up TS Bases pages for information. Enclosure 2 provides a copy of MNGP Calculation 91-006, Revision 4, "125 VDC Battery Charger Sizing."
The MNGP Plant Operations Review Committee has reviewed this application. In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), NSPM is notifying the State of Minnesota by transmitting a copy of this application, with enclosures, to the designated State Official.

Document Control Desk L-MT-16-014 Page 2 of2 NSPM requests NRC approval of the proposed license amendment request (LAR) by April4, 2017. Once approved, the amendment will be implemented within 120 days.
Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments.
If you have any questions or require additional information, please contact Mr. Richard Loeffler at (763) 295-1247.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April '-/, 2016.
    *~~-L-,
Peter A. Gardner Site Vice President- Monticello Nuclear Generating Plant Northern States Power Company - Minnesota

==Enclosures:==

Enclosure 1:        LAR: Revise 125 VDC Battery Charger SR 3.8.4.2 Attachment 1:    Marked-up Technical Specification Page Attachment 2:    Draft Marked-up Technical Specification Bases Pages Enclosure 2:        MNGP Calculation 91-006, Revision 4, "125 VDC Battery Charger Sizing" cc:    Administrator, Region Ill, US NRC Project Manager, Monticello Nuclear Generating Plant, US NRC Resident Inspector, Monticello Nuclear Generating Plant, US NRC State of Minnesota

L-MT-16-014 LICENSE AMENDMENT REQUEST: REVISE 125 VDC BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 Table of Contents ENCLOSURE 1 1.0   

==SUMMARY==
DESCRIPTION .................................................................................. 1

==2.0    BACKGROUND==
INFORMATION ..........................................................................1 3.0   DETAILED DESCRIPTION ...................................................................................2

==4.0   TECHNICAL EVALUATION==
 .................................................................................3 4.1   250 VDC and 125 VDC Electrical Power Systems Description ........................ 3 4.2   Revise the Required 125 VDC System Battery Charger Amperage ................ 5 4.3    Basis for Removal of the Second Testing Option Under SR 3.8.4.2 ............... 7 4.4   Design Basis Accident Considerations ............................................................8

==5.0   REGULATORY EVALUATION==
 .............................................................................9 5.1   Applicable Regulatory Requirements ...............................................................9 5.2   Precedent ...........................................................................................................12 5.3    No Significant Hazards Determination ............................................................ 13

==6.0   ENVIRONMENTAL CONSIDERATION==
 .............................................................. 15

==7.0   REFERENCES==
 ....................................................................................................16 ATTACHMENT 1 ATTACHMENT 2 ENCLOSURE 2 Page 1 of 1

L-MT-16-014 Page 1 of 16 LICENSE AMENDMENT REQUEST: REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 1.0     

==SUMMARY==
DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy (hereafter "NSPM"), requests to revise the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP). There are two proposed changes to Surveillance Requirement (SR) 3.8.4.2 in Specification 3.8.4, "DC Sources - Operating".
The first proposed change is to increase the required 125 Volt (V) Direct Current (DC) battery charger output current specified as the first option under SR 3.8.4.2 to resolve a non-conservative TS condition. The second proposed change is to remove from SR 3.8.4.2 an alternative option for meeting the surveillance requirement. This alternative requires verifying each battery charger can recharge the battery to the fully charged state within the required time period, 24 hours for the 250 VDC and 8 hours for the 125 VDC subsystems, respectively, while supplying the largest combined continuous steady state loads, after a battery discharge to the bounding design basis event (DBE) discharge state. The second option under SR 3.8.4.2 was added during the MNGP Improved Technical Specifications (ITS) conversion process in 2006 (Reference 1) but has not been utilized, and it has been determined that it will not be utilized in the future.
There is no specific schedule or timing constraints related to approval of this license amendment request. However, U. S. Nuclear Regulatory Commission (NRC) approval and issuance of a license amendment revising the MNGP TS is requested as soon as reasonable to resolve the non-conservative TS condition.

==2.0     BACKGROUND==
INFORMATION The value of the required output current specified for the 125 VDC battery chargers in SR 3.8.4.2 within the MNGP TS has been identified as being non-conservative. The guidance of NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety," is being applied until this condition has been resolved with approval of this proposed license amendment request.
Corrective actions have been taken to administratively control via procedure changes the required current value during the interim period between the identification of this condition and resolution to ensure conservative operation.

L-MT-16-014 Page 2 of 16 3.0      DETAILED DESCRIPTION The first option under SR 3.8.4.2 currently requires verifying that each required 125 VDC subsystem battery charger supplies greater than or equal to 50 amps. <1l It is proposed to increase the required current output for each required 125 VDC subsystem battery charger to greater than or equal to 75 amps.
The second option under SR 3.8.4.2 requires the following:
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 8 hours for 125 VDC subsystems while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
It is proposed to remove the second option under SR 3.8.4.2 from the MNGP TS. This method has not been utilized in the past, and it has been determined that this method will not be employed at the MNGP in the future to satisfy the surveillance requirement.
Following incorporation of the proposed changes, revised SR 3.8.4.2 would then read (changes are double underlined and deletions are struck through):
SURVEILLANCE                                   FREQUENCY SR 3.8.4.2            Verify each required battery charger supplies the      24 months following:
                         *   ~  150 amps for 250 VDC Div 1
                         *   ~  110 amps for 250 VDC Div 2
                         *   ~  75 amps for 125 VDC subsystems, at greater than or equal to the minimum established float voltage for ~ 4 hours.
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 24 hours for 125 VDC
: 1. Specification 3.8.5, "DC Sources- Shutdown", SR 3.8.5.1 requires SR 3.8.4.2 to be met for the division of DC sources required to be OPERABLE during shutdown conditions.
SR 3.8.5.1 is unaffected by the proposed changes.

L-MT-16-014 Page 3 of 16 SURVEILLANCE                                FREQUENCY subsystems vvhile supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
The TS mark-ups indicating the proposed changes are provided in Attachment 1 to this enclosure. The associated proposed TS Bases changes are provided as mark-ups in  to this enclosure, for information. TS Bases changes are issued in accordance with MNGP Specification 5.5.9, "Technical Specification (TS) Bases Control Program," following approval of the associated license amendment request.

==4.0     TECHNICAL EVALUATION==

MNGP is a boiling water reactor (BWR) of the General Electric BWR/3 design, with a Mark I containment. The plant is located within the city limits of Monticello, Minnesota, on the south bank of the Mississippi River. The electrical power system at the MNGP consists of various Alternating Current (AC) and DC systems. The essential plant DC battery system consists of two 125 VDC and two 250 VDC batteries and subsystems which provide for controls and instrumentation which are vital to reactor and overall plant safety and to power certain functional requirements for reactor shutdown. During normal operation, the DC loads are powered from the battery chargers with the batteries floating on the system. In case of loss of normal power to a battery charger, the DC loads are automatically powered from the station batteries.
4.1     250 VDC and 125 VDC Electrical Power Systems Description The following paragraphs provide a summary discussion of the systems, components, and parameters affected by the proposed changes. The discussion is provided for information but does not describe the changes being proposed.
Two independent divisions of 250 VDC and 125 VDC batteries are provided.
The 250 VDC "power" batteries serve the larger loads such as DC motor driven pumps, valves, etc. The 125 VDC "control" batteries provide the control power for the in-plant 13.8 kVAC breakers, 4160 VAC breakers, 480 VAC Load Center breakers, auxiliary control power for the 1R and 2R Transformers, and various control relays, annunciators, etc. The 125 VDC System also provides power for some emergency lighting.
The Division 1 and Division 2 250 VDC electrical power subsystems provide power to their associated uninterruptible AC power supply (UPS). The Division 1 electrical power subsystem also provides power to support the Reactor Core Isolation Cooling (RCIC) System motor operated valves, and other non-critical

L-MT-16-014 Page 4 of 16 loads. The Division 2 electrical power subsystem supplies power for the High Pressure Coolant Injection (HPCI) System motor operated valves, the HPCI auxiliary oil pumps, and the Control Room Ventilation System control circuits.
Each 250 VDC electrical power subsystem consists of two in series 125 VDC batteries, two normally inservice 125 VDC chargers, a spare 125 VDC charger, and all of the control equipment and interconnecting cabling to the associated distribution panel. Each battery is exclusively associated with a single division.
Each set of battery chargers is also exclusively associated with a 250 VDC electrical power subsystem and cannot be interconnected with the other 250 VDC electrical power subsystem. The inservice and spare chargers are supplied from the associated AC load group.
The Division 1 and Division 2 125 VDC electrical power subsystems provide control power to the associated 4.16 kVAC essential bus and each of the two 480 VAC essential Load Centers, in addition to other non-essential loads. Each 125 VDC electrical power subsystem consists of a one battery (No. 11 for Division 1 and No. 12 for Division 2), one battery charger (D1 0 for Division 1 and D20 for Division 2), and the corresponding control equipment and interconnecting cabling up to the associated distribution panels. Each 125 VDC subsystem battery is composed of 58 C&D Type KCR-13 cells. The inservice battery chargers are supplied from the associated AC load group. The design includes a common spare charger (D40)(2) that can supply either 125 VDC electrical power subsystem.
Each DC battery subsystem is separately housed in a ventilated room. The common standby 125 VDC battery charger is located in a room separate from the other 125 VDC battery chargers electrical power subsystems. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels, except the common standby 125 VDC battery charger may be shared between the Division 1 and Division 2 125 VDC electrical power subsystems, as described previously.
Each division (subsystem) of the DC electrical power system is required to be operable to ensure availability of the required power to shut down the reactor and maintain it in a safe condition after an anticipated operational occurrence (AOO) or a postulated design basis accident (DBA). Loss of any DC electrical power subsystem does not prevent the minimum safety function from being performed.
: 2. The spare 125 VDC battery charger is supplied from the Division 2 AC load group and can only be used to meet the LCO for that division. If it is supplying the Division 1 subsystem, that subsystem is inoperable.

L-MT-16-014 Page 5 of 16 Each essential station battery has adequate storage capacity to meet the duty cycle(s) discussed in Sections 8.5.1.1 and 8.5.2.1 of the MNGP Updated Safety Analysis Report. The essential station batteries are designed with additional capacity above that required by the design duty cycle to allow for temperature variations and aging. The essential batteries for the DC electrical power subsystems are sized to produce capacity greater than required for a DBA and monitored to ensure capacity remains greater than 90 percent during the operating cycle.
4.2   Revise the Required 125 VDC System Battery Charger Amperage SR 3.8.4.2 (first option) currently requires verifying that each 125 VDC battery charger supplies greater than or equal to 50 amps at greater than or equal to the minimum established float voltage to each 125 VDC subsystem for greater than or equal to 4 hours. NSPM proposes to increase the required amperage from each 125 VDC subsystem battery charger from the present value to a value of greater than or equal to 75 amps in SR 3.8.4.2.(3) Increasing the required amperage for each 125 VDC subsystem battery charger corrects a non-conservative TS condition in SR 3.8.4.2.
A simplified methodology for evaluating battery charger sizing is provided within the Institute of Electrical and Electronics Engineers (IEEE) standard, IEEE 946-1985, "IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations" (Reference 2). MNGP Calculation 91-006, Revision 4, "125 VDC Battery Charger Sizing," provided as Enclosure 2, discusses the methodology and assumptions involved in determining a revised amperage value for the first option under SR 3.8.4.2 of greater than or equal to 75 amps for each 125 VDC subsystem. The125 VDC System battery charger sizing was evaluated by calculating the re-charge times(4) considering the coincident 125 VDC System loads also supplied by the charger, utilizing the IEEE 946-1985 methodology.
MNGP Updated Safety Analysis Report Section 8.5.2.1 states:
Each 125 VDC [battery] charger is capable of carrying the normal 125 VDC load and at the same time supplying additional charging current to keep the batteries in a fully charged condition.
IEEE 946-1985 recommends that a battery charger have an output current capability greater than the continuous loads plus the largest combination of non-continuous loads that would be likely to occur simultaneously during normal
: 3. No change is proposed to the required amperage for each of the 250 VDC subsystem battery chargers under the first option of SR 3.8.4.2.
: 4. Note, that for the MNGP there are no explicit licensing basis criteria in place for the recharge time after the design basis discharge.

L-MT-16-014 Page 6 of 16 plant operation. This criterion is met if the battery charger output current exceeds the normal continuous system loads by an amount adequate to bound the non-continuous load combinations likely during normal plant operation.
The respective load profiles used to determine the degree of battery discharge were taken from the sizing worksheets of the battery sizing calculations. The 125 VDC System is required to operate without the battery chargers supplying system loads during two DBEs, i.e., during a DBA, a Loss of Coolant Accident (LOCA) with a Loss of Off-site Power (LOOP) and a Station Blackout (SBO).
The load profiles modelled are a bounding composite combination of loads that would be needed to mitigate a LOOP I LOCA and the loads necessary to operate equipment necessary to mitigate a 4-hour SBO event.
The IEEE standard recommends that the battery charger output current capacity exceed the combination of continuous system loads plus the largest combination of non-continuous loads that would be likely to occur simultaneously during normal operation. The highest actual operating 125 VDC subsystem operating loads were 23 amps (Division 1) and 24 amps (Division 2) determined from a review of several months of system operating logs. After including allowances for uncertainty and margin, the normal continuous 125 VDC subsystem loads have been determined to be less than 30 amps for either subsystem.(s) The 125 VDC battery chargers provide an output current capability of 75 amps (minimum) resulting in more than 45 amps available to serve simultaneous non-continuous loads.
The proposed revised amperage value for the first option under SR 3.8.4.2, of greater than or equal to 75 amps assures each 125 VDC battery charger supplies sufficient current output to meet the respective 125 VDC subsystem loads, while providing sufficient charging capacity to restore the battery in a reasonable timeframe for a full rated discharge with the normal plant 125 VDC subsystem loads, and for a LOOP-LOCA I 4-hour SBO event.
No change is necessary to the frequency of the surveillance (SR 3.8.4.2) as the surveillance will continue to be performed at the current frequency of 24 months.
: 5. The determination of the respective a125 VDC subsystem loading range incorporates tolerances for reading uncertainty and margin.

L-MT-16-014 Page 7 of 16 4.3   Basis for Removal of the Second Testing Option Under SR 3.8.4.2 It is proposed to remove the second testing option under SR 3.8.4.2 from the MNGP TS. Technical Specification Task Force (TSTF) traveler TSTF-360, "DC Electrical Rewrite" (Reference 3), was incorporated into the MNGP TS as part of the Monticello ITS conversion. One of the changes included within the TSTF traveler was a new provision under SR 3.8.4.2 providing an alternative to the criteria that specified to meet this surveillance requirement for battery charger testing. TSTF-360 provides the following description as the basis for this alternative:
NUREG STS [Standard Technical Specification] SR 3.8.4.6 (being revised to SR 3.8.4.2) requires specific parameters for battery charger performance testing. This test is intended to confirm the charger design capacity.
Alternate acceptance criteria [emphasis added] are proposed that would allow an actual in service demonstration that the charger can recharge the battery to the fully charged state within [24] hours while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state. This meets the intent of the existing test and allows for normal in-place demonstration of the charger capability thereby minimizing the time when the charger would be disconnected from the DC bus.
The second option under SR 3.8.4.2 states:
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 8 hours for 125 VDC subsystems while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
The second option was added during the Monticello ITS conversion because it was included as part of the standard wording within the applicable NUREG for the BWR/4 design, i.e., NUREG-1433 (which was applied for the Monticello conversion), and it was thought that inclusion of this alternative would provide additional flexibility that might prove useful for testing of the 250 VDC subsystems and 125 VDC subsystems in the future. However, this method has not been utilized to satisfy this surveillance requirement (SR 3.8.4.2) since its incorporation into the MNGP TS for either the 250 VDC System or the 125 VDC System. It has been determined that this second option will not be employed at the MNGP to satisfy this surveillance requirement for either the 250 VDC System or the 125 VDC System.
The second option requires that each battery charger be capable of recharging the battery after a service test coincident with supplying the largest coincident demands of the various continuous steady state loads (irrespective

L-MT-16-014 Page 8 of 16 of the status of the plant during which these demands occur). This level of loading is not normally available following the battery service test and would need to be supplemented with additional loads.
The requirements to satisfy the second option under SR 3.8.4.2 complicate testing at the MNGP and require initial conditions that are not typically present during a refueling outage. As previously indicated, this option has not been employed at the MNGP to satisfy SR 3.8.4.2 and is not planned to be used in the future. NSPM does not typically perform service tests for the essential batteries, but instead performs modified performance tests on a refuel cycle frequency as described in "Supplemental Safety Evaluation Report - Monticello Nuclear Generating Plant Station Blackout Rule", dated August 5, 1992 (Reference 4).
The MNGP is therefore not generally in the initial conditions necessary to perform the testing as presently described in the MNGP TS Bases.
Furthermore, the second option is considered less desirable to be performed at the MNGP due to the added complexity of controlling the additional load needed to simulate the largest coincident demands of the various continuous steady state loads during the recharge period. Removing the second option also eliminates the difficulty associated with selecting a conservative recharge time to specify in the TS surveillance requirement considering that the MNGP essential batteries may vary from greater than 100 to 90 percent of rated capacity, that recharge time is affected by temperature as well as charger output voltage, and that the largest coincident steady state loads may change somewhat with future plant modifications. Directly loading and monitoring the battery charger output current as specified under the first option of SR 3.8.4.2 is considered to provide a clearer and more definitive demonstration of the battery charger capacity and capability.
Therefore, since the first (original) testing option under SR 3.8.4.2 is being retained and the second option provides an alternate means of meeting the surveillance requirement, independent of the first option, removal of the second
* option for testing the 250 VDC System and the 125 VDC System under SR 3.8.4.2 is acceptable. Testing of the 250 VDC and the 125 VDC Systems will continue to be performed under the "first" testing option under SR 3.8.4.2.
4.4   Design Basis Accident Considerations The initial conditions of the DBA and transient analyses in Updated Safety Analysis Report Chapter 14, assume that the Engineered Safety Feature (ESF) systems are operable. The DC electrical power system provides normal and emergency DC electrical power for the emergency diesel generators (EDGs),
emergency auxiliaries, and control and switching during all modes of operation.
The operability of the DC electrical subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design

L-MT-16-014 Page 9 of 16 basis of the unit. This includes maintaining DC sources operable during accident conditions in the event of:
: a. An assumed loss of all offsite AC power or all onsite AC power; and
: b. A worst case single failure.
The DC electrical power subsystems are also required to be operable to ensure the availability of the required power to shut down the reactor and maintain it in a safe condition after an AOO, in addition to a postulated DBA. Loss of any DC electrical power subsystem does not prevent the minimum safety function from being performed.
The revised 125 VDC battery charger required output current will continue to ensure that the Updated Safety Analysis Report described battery charger design basis is met and that essential batteries can be maintained fully charged to provide adequate power to support the Emergency Core Cooling System function. The limit also assures adequate charger capacity at the conclusion of the essential battery duty cycle following a DBA to support continuous steady state DC system loads. Hence, this proposed TS change to increase the required amperage of the 125 VDC battery chargers from 50 to 75 amps under the first option of SR 3.8.4.2 will assure that each 125 VDC battery charger supplies sufficient current output to meet the respective 125 VDC subsystem loads.
Removal of the second (alternate) testing option under SR 3.8.4.2, only removes some unnecessary flexibility in testing methodology from the MNGP TS. The retention of the first testing option under SR 3.8.4.2 maintains the original methodology for performing and meeting SR 3.8.4.2. Therefore, both of the proposed changes to SR 3.8.4.2 are safe and are acceptable.

==5.0   REGULATORY EVALUATION==

5.1   Applicable Regulatory Requirements 10 CFR 50.36, 'Technical specifications," provides the regulatory requirements for the content required in the TS. 10 CFR 50.36(c)(3) requires the establishment of surveillance requirements "relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The proposed TS changes revise Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2, to increase the required 125 VDC subsystems battery charger amperage, and to also remove a second option under SR 3.8.4.2 to perform battery charger testing.

L-MT-16-014 Page 10 of 16 The MNGP was designed largely before the publishing of the 70 General Design Criteria for Nuclear Power Plant Construction Permits proposed by the Atomic Energy Commission (AEC) for public comment in July 1967, and constructed prior to the 1971 publication of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50. As such, the MNGP was not licensed to the Appendix A, General Design Criteria (GDC).
The MNGP Updated Safety Analysis Report, Section 1.2, lists the principal design criteria (PDCs) for the design, construction and operation of the plant.
USAR Appendix E provides a plant comparative evaluation to the 70 proposed AEC design criteria. It was concluded that the plant conforms to the intent of the GDCs. The applicable GDCs and PDCs are discussed below.
* PDC 1.2.6 - Plant Electrical Power Sufficient normal and standby auxiliary sources of electrical power are provided to attain prompt shutdown and continued maintenance of the plant in a safe condition under all credible circumstances. The capacity of the power sources is adequate to accomplish all required engineered safeguards functions under all postulated design basis accident conditions.
Of the 70 Draft AEC General Design Criteria (AEC-GDC) the following are applicable:
* AEC-GDC Criterion 24 - Emergency Power for Protection Systems (Category 8)
In the event of the loss of all off-site power, sufficient alternate sources of power shall be provided to permit the required functioning of the protection systems.
* AEC-GDC Criterion 39 - Emergency Power for Engineered Safety Features Category A)
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 on-site power system and the off-site power system shall each, independently, provide this capacity assuming a failure of a single active component in each power system.

L-MT-16-014 Page 11 of 16
* AEC-GDC Criterion 41 - Engineered Safety Features Performance Capability (Category A)
Engineered safety features such as emergency core cooling and containment heat removal systems shall provide sufficient performance capability to accommodate partial loss of installed capacity and still fulfill the required safety function. As a minimum, each engineered safety feature shall provide this required safety function assuming a failure of a single active component.
While not part of the MNGP Licensing Basis, the applicable 10 CFR 50, Appendix A, GDC are:
* GDC 17 - Electric power systems An onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents.
The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure.
Electric power from the transmission network to the onsite electric distribution system shall be supplied by two physically independent circuits (not necessarily on separate rights of way) designed and located so as to minimize to the extent practical the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. A switch yard common to both circuits is acceptable. Each of these circuits shall be designed to be available in sufficient time following a loss of all onsite alternating current power supplies and the other offsite electric power circuit, to assure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. One of these circuits shall be designed to be available within a few seconds following a loss-of-coolant accident to assure that core cooling, containment integrity, and other vital safety functions are maintained.
Provisions shall be included to minimize the probability of losing electric power from any of the remaining supplies as a result of, or coincident with,

L-MT-16-014 Page 12 of 16 the loss of power generated by the nuclear power unit, the loss of power from the transmission network, or the loss of power from the onsite electric power supplies.
* GDC 18 - Inspection and testing of electric power systems Electric power systems important to safety shall be designed to permit appropriate periodic inspection and testing of important areas and features, such as wiring, insulation, connections, and switchboards, to assess the continuity of the systems and the condition of their components. The systems shall be designed with a capability to test periodically (1) the operability and functional performance of the components of the systems, such as on site power sources, relays, switches, and buses, and (2) the operability of the systems as a whole and, under conditions as close to design as practical, the full operation sequence that brings the systems into operation, including operation of applicable portions of the protection system, and the transfer of power among the nuclear power unit, the offsite power system, and the onsite power system.
NSPM has evaluated the proposed changes against the applicable regulatory requirements and acceptance criteria. The technical analysis in Section 4.0 concludes that the revised 125V battery charger output current is reasonable and that it is acceptable to remove the second option for meeting SR 3.8.4.2 since it is not necessary and is not going to be performed. Based on this, there is reasonable assurance that the health and safety of the public, following approval of this change, is unaffected.
5.2   Precedent In 1996, the two unit Salem Nuclear Generating Station received two license amendments to revise the respective units TSs to lower the 125 Volt Battery Charger surveillance amperage from at least 200 amps to at least 170 amps so as not to require the replacement of input cables to the battery chargers for charger replacements (Reference 5). IEEE Standard IEEE 946-1992 was utilized to size the replacement battery chargers.
In 1997, Millstone Nuclear Power Station, Unit No.3, received a somewhat similar license amendment to increase the required test voltage for the 125 Volt Battery Chargers (Reference 6).

L-MT-16-014 Page 13 of 16 5.3   No Significant Hazards Determination In accordance with the requirements of 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," the Northern States Power Company- Minnesota (NSPM), doing business as Xcel Energy, Inc., requests an amendment to revise Monticello Nuclear Generating Plant (MNGP) Technical Specification 3.8.4, "DC Sources- Operating", Surveillance Requirement (SR) 3.8.4.2 to increase the 125 VDC subsystems battery charger amperage and to remove the second surveillance option which requires monitoring battery recharge time while controlling additional load to simulate the largest combined demands of the various continuous steady state loads.
NSPM's evaluation against each of the criteria in 10 CFR 50.92, "Issuance of amendment," follows:
: 1.      Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed TS changes revise the battery charger surveillance requirements in SR 3.8.4.2. The DC electrical power system, including associated battery chargers, is not an initiator of any accident sequence analyzed in the Updated Safety Analysis Report (USAR). Rather, the DC electrical power system supports operation of equipment used to mitigate accidents. Operation in accordance with the proposed TS continues to ensure that the DC electrical power system is capable of performing its specified safety functions as described in the USAR. Therefore, the mitigating functions supported by the DC electrical power system will continue to provide the protection assumed by the analysis.
Accidents are initiated by the malfunction of plant equipment, or the catastrophic failure of plant structures, systems, or components (SSCs).
Performance of battery testing is not a precursor to any accident previously evaluated, nor does it change the manner in which the batteries and battery chargers are operated. The proposed testing requirements will not contribute to the failure of the batteries nor any plant SSC. NSPM has determined that the proposed TS changes provide an equivalent level of assurance that the batteries and battery chargers are capable of performing their intended safety functions. Thus, the proposed changes do not affect the probability of an accident previously evaluated.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

L-MT-16-014 Page 14 of 16
: 2.       Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The DC electrical power system, including the associated battery chargers, is not an initiator of any accident sequence analyzed in the USAR. The proposed TS changes do not involve operation of the DC electrical power system in a manner or configuration different from those previously evaluated. Performance of battery testing is not a precursor to any accident previously evaluated. NSPM has determined that the proposed TS changes provide an equivalent level of assurance that the batteries and battery chargers are capable of performing their intended safety functions. Therefore, the mitigating functions supported by the DC electrical power system will continue to provide the protection assumed in the safety analyses.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
: 3.       Does the proposed change involve a significant reduction in a margin of safety?
Response: No The margin of safety is established through the equipment design, the operating parameters, and the setpoints at which automatic actions are initiated. The equipment margins will be maintained in accordance with the plant-specific design bases as a result of the proposed changes. The proposed changes do not adversely affect operation of plant equipment. The proposed TS changes do not result in a change to the setpoints at which protective actions are initiated. Sufficient DC capacity to support operation of mitigation equipment continues to be ensured. The equipment fed by the DC electrical sources will continue to provide adequate power to safety-related loads in accordance with safety analysis assumptions.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, the NSPM has determined that operation of the facility in accordance with the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92, "Issuance of amendment," paragraph (c), in that it does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of

L-MT-16-014 Page 15 of 16 a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

==6.0     ENVIRONMENTAL CONSIDERATION==

10 CFR 51.22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perform an environmental assessment. NSPM has determined that the proposed amendment meets the criteria for a categorical exclusion from an environmental review as set forth in 10 CFR 51.22, specifically 10 CFR 51.22(c)(9). First, the proposed amendment changes a requirement with respect to installation or use of a facility or component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation," or involves a change to an inspection or surveillance requirement. Second, the proposed amendment requires no environmental assessment since operation of the facility in accordance with the proposed amendment does not (i) involve a significant hazards consideration, or (ii) authorize a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) result in a significant increase in individual or cumulative occupational radiation exposure. Therefore, the NSPM concludes pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

L-MT-16-014 Page 16 of 16

==7.0   REFERENCES==
: 1. Letter from T. Beltz (NRC) to J. Conway (NMC), "Monticello Nuclear Generating Plant (MNGP) - Issuance of Amendment for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues (TAG Nos. MC7505, MC7597 through MC7611, and MC8887," dated June 5, 2006
: 2. IEEE Std. 946-1985, "IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations"
: 3. Technical Specification Task Force (TSTF) traveler TSTF-360-A, Revision 1, "DC Electrical Rewrite", dated December 18, 2000.
: 4. Supplemental Safety Evaluation - Monticello Nuclear Generating Plant Station Blackout Rule (10 CFR 50.63), dated August 5, 1992
: 5. Letter from L. Olshan (NRC) to L. Eliason (PSEG), "Salem Nuclear Generating Station, Unit Nos. 1 and 2 (TAG Nos. M94634 and M94635)," dated June 27, 1996. Issuance of Amendment No. 183 for Unit 1 and Amendment No. 164 for Unit 2, respectively.
: 6. Letter from J. Andersen (NRC) to N. Carns (Northeast Nuclear Energy Company), "Issuance of Amendment (TAG No. M98724)," for the Millstone Nuclear Power Station, Unit No. 3," dated September 5, 1997 (Amendment No. 149)

ENCLOSURE 1 ATTACHMENT 1 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 MARKED-UP TECHNICAL SPECIFICATION PAGE
( 1 page follows)

DC Sources- Operating 3.8.4 ACTIONS (continued)
CONDITION                           REQUIRED ACTION             COMPLETION TIME C. Required Action and            C.1        Be in MODE 3.               12 hours associated Completion Time not met.                 AND C.2        Be in MODE 4.               36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE                                    FREQUENCY SR 3.8.4.1        Verify battery terminal voltage is greater than or        7 days equal to the minimum established float voltage.
SR 3.8.4.2        Verify each required battery charger supplies the         24 months following:
                    *   ;;::: 150 amps for 250 VDC Div 1
                    *   ;;::: 110 amps for 250 VDC Div 2
                    *   ;;::: 75 amps for 125 VDC subsystems, at greater than or equal to the minimum established float voltage for ;;::: 4 hours.
Verify each required battery charger can recharge the battery to the fully charged state within 24 hours for 250 VDC subsystems and 8 hours for 125 VDC subsystems *.vhile supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.
Monticello                                       3.8.4-2               Amendment No. -149, 153

ENCLOSURE 1 ATTACHMENT 2 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 DRAFT MARKED-UP TECHNICAL SPECIFICATION BASES PAGES (FOR INFORMATION)
(4 pages follow)

DC Sources - Operating B 3.8.4 BASES BACKGROUND (continued)
During normal operation, the DC loads are powered from the battery chargers with the batteries floating on the system. In case of loss of normal power to the battery charger, the DC loads are automatically powered from the station batteries.
The DC power distribution system is described in more detail in Bases for LCO 3.8.7, "Distribution System- Operating," and LCO 3.8.8, "Distribution System- Shutdown."
Each DC battery subsystem is separately housed in a ventilated room.
The common standby 125 VDC battery charger is located in a room separate from the other 125 VDC battery chargers electrical power subsystems. Each subsystem is located in an area separated physically and electrically from the other subsystems to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem.
There is no sharing between redundant Class 1E subsystems such as batteries, battery chargers, or distribution panels, except the common standby 125 VDC battery charger may be shared between the Division 1 and Division 2 125 VDC electrical power subsystems.
Each Division 1 and Division 2 250 VDC battery has adequate storage capacity to meet the duty cycle(s) discussed in USAR, Section 8.5.1.1 (Ref 4). Each Division 1 and Division 2 125 VDC battery has adequate storage capacity to meet the duty cycle(s) discussed in USAR, Section 8.5.2.1 (Ref. 5). The battery is designed with additional capacity above that required by the design duty cycle to allow for temperature variations and other factors.
The batteries for DC electrical power subsystems are sized to produce capacity greater than required for a design basis accident and monitored to ensure battery capacity will remain > 90% during the operating cycle.
No Changes.         The minimum design voltage limit is 105/210 V.
The page is         The battery cells are of flooded lead acid construction with a nominal included for        specific gravity of 1.215. The open circuit voltage is the voltage information,        maintained when there is no charging or discharging. Once fully charged, so that the         the battery cell will maintain 98% capacity for 30 days without further context of the      charging per manufacturer's instructions. Optimal long term performance change on the       however, is obtained by maintaining a float voltage 2.20 to 2.25 Vpc. This next page is        provides adequate over-potential, which limits the formation of lead clear.              sulfate and self discharge.
Each battery charger of DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation, while at the same time maintaining its battery Monticello                         B 3.8.4-2                                Revision No.

DC Sources - Operating B 3.8.4 BASES BACKGROUND (continued) bank fully charged. Each station service battery charger has sufficient e*cess capacity to restore the battery from the design minimum charge to The battery chargers ~ its fully charged state V.'ithin 24 hours 'Nhile supplying normal steady state are sized to charge    teaa&.-
the batteries while supplying the normal   The battery charger is normally in the float-charge mode. Float-charge is continuous DC loads    the condition in which the charger is supplying the connected loads and (Refs. 4 and 5).       the battery cells are receiving adequate current to optimally charge the battery. This assures the internal losses of a battery are overcome and the battery is maintained in a fully charged state.
When desired, the charger can be placed in the equalize mode. The equalize mode is at a higher voltage than the float mode and charging current is correspondingly higher. The battery charger is operated in the equalize mode after a battery discharge or for routine maintenance.
Following a battery discharge, the battery recharge characteristic accepts current at the current limit of the battery charger (if the discharge was significant, e.g., following a battery service test) until the battery terminal voltage approaches the charger voltage setpoint. Charging current then reduces exponentially during the remainder of the recharge cycle. Lead-calcium batteries have recharge efficiencies of greater than 95%, so once at least 105% of the ampere-hours discharged have been returned, the battery capacity would be restored to the same condition as it was prior to the discharge. This can be monitored by direct observation of the exponentially decaying charging current or by evaluating the amp-hours discharged from the battery and amp-hours returned to the battery.
APPLICABLE         The initial conditions of Design Basis Accident (DBA) and transient SAFETY             analyses in USAR, Chapter 14 (Ref. 6), assume that Engineered Safety ANALYSES           Feature (ESF) systems are OPERABLE. The DC electrical power system provides normal and emergency DC electrical power for the emergency diesel generators (EDGs), emergency auxiliaries, and control and switching during all MODES of operation. The OPERABILITY of the DC subsystems is consistent with the initial assumptions of the accident analyses and is based upon meeting the design basis of the unit. This includes maintaining DC sources OPERABLE during accident conditions in the event of:
: a. An assumed loss of all offsite AC power or all onsite AC power; and
: b. A worst'case single failure.
The DC Sources- Operating satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
Monticello                              B 3.8.4-3                                  Revision No.

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE REQUIREMENTS (continued) battery servioe test and 'Nill need to be supplemented with additional loads. The duration for this test may be longer than the oharger sizing oriteria sinoe the battery reoharge is affeoted by float voltage, temperature, and the exponential deoay in oharging ourrent. The battery is reoharged '.vhen the measured charging ourrent is < 2 amps for 250 VDC batteries and < 1 amp for 125 VDC batteries.
The Frequency is acceptable, given the unit conditions required to perform the test and the other administrative controls existing to ensure adequate charger performance during these 24 month intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.
SR 3.8.4.3 A battery service test is a special test of the battery's capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discharge rate and test length corresponds to the design duty cycle requirements as specified in Reference 4 for the 250 VDC electrical power system and Reference 5 for the 125 VDC electrical power system.
The Frequency of 24 months is acceptable, given plant conditions required to perform the test and the other requirements existing to ensure adequate battery performance during the 24 months intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.
This SR is modified by two Notes. Note 1 allows the performance of a modified performance discharge test in lieu of a service test.
The reason for Note 2 is that performing the Surveillance would remove a required DC electrical power subsystem from service, perturb the electrical distribution system, and challenge safety systems. This restriction from normally performing the Surveillance in MODE 1 or 2 is further amplified to allow portions of the Surveillance to be performed for the purpose of reestablishing OPERABILITY (e.g., post work testing following corrective maintenance, corrective modification, deficient or incomplete surveillance testing, and other unanticipated OPERABILITY concerns) provided an assessment determines plant safety is maintained or enhanced. This assessment shall, as a minimum, consider the potential outcomes and transients associated with a failed partial Surveillance, a successful partial Surveillance, and a perturbation of the offsite or onsite system when they are tied together or operated Monticello                          B 3.8.4-8                                 Revision No.

ENCLOSURE 2 MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST REVISE BATTERY CHARGER SURVEILLANCE REQUIREMENT 3.8.4.2 CALCULATION 91-006, REVISION 4 125 VDC BATTERY CHARGER SIZING (40 pages follow)

QF0549 (FP-E-CAL-01), Rev. 7                                                         Page 1 of4
(! XceiEnergy*                     Calculation Signature Sheet Document Information NSPM Calculation (Doc) No: 91-006                                              I Revision:   4

==Title:==
125 VDC Battery Charger Sizing Facility: ~~~]"MT D   PI                                                  I Unit: ~  1 02 Safety Class:       ~SR       OAugQ        D Non SR Special Codes:    D Safeguards D Proprietary                               ..
Type: Calc        Sub-Type:
I NOTE:          I Print and sign name in signature blocks, as required.
Major Revisions                                        I   D       N/A EC Number: 24146                                     D Vendor Calc Vendor Name or Code:                                 Vendor Doc No:
Description of Revision: See Purpose section of calculation.
The following calculation and attachments have been reviewed and deemed
                                                                                                      ~
acceptable as a legible QA recor~                                                              I Prepared by: (sign)   ~        f           I (print) Rhon Sanderson          Date: 1D - ).8 - Is-Reviewed by:(sign) d~ ~            :--.,
* I  (print)  Jnkc. 5-l-rc.~Se.r    Date: /o /2 8/2<-*1 :s Type of Review: gDesign Verification       D Tech Review D Suitability Review Method Used (For qv Only):~ Review D Alternate Calc D Test Approved by: (sign)~~ Pr.jff /(print) &#xa3;P vJArzL                              Date: to. j:;..~!:Qt?
tt Minor Revisions                                        I   ~       N/A EC No:                                               D Vendor Calc:
Minor Rev. No:
Description of Change:
Pages Affected:
The following calculation and attachments have been reviewed and deemed D
acceptable as a legible QA record                                                              I Prepared by: (sign)                         I  (print)                       Date:
Reviewed by: (sign)                   /
I (print)                       Date:
Type of Review:    D   D~sign Verification D Tech Review D Suitability Review Method Used (For DV Only): D Review D Alternate Calc 0 Test Approved by: (sign)                          /"(print)                       Date:
Record Retention: Retain this form with the associated calculation for the life of the plant.

QF0549 (FP-E-CAL-01), Rev. 7                                                                                               Pa(le 2 of 4 (l Xcel Energy*                                             Calculation Signature Sheet This reference table is used for data entry into the PassPort Controlled Documents Module reference tables (C012 Panel). It may also be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed by using the "TAB" key and filling in the appropriate information in each column.
Reference Documents              (PassPort co12 Panel from C020)
 #   Co~trolled*                                Document Name Document             Doc         Ref Type**
Doc?+ Type                                                                                    Number              Rev      INPUT OUTPUT 1   y        CALC      Div. 1125 Volt Battery Calculation                                   02-179                       3         X 2   y        CALC      Div. II 125 Volt Battery Calculation                                 02-192                       3         X 3                      IEEE Recommended Practice for Sizing Large Lead Storage-N        --------  Batteries for Generating Stations and SubStations IEEE 485-1983             -------      X 4   y        PROC      Operations Manual, Lighting, Description of Equipment                 B.09.14-02                  1         X 5                      C&D Technologies Publication 12-316, KCR-13 Lead-Calcium N        -----     Standby Batteries 12-316                   -----        X 6   y        PROC      Operations Manual, 125 VDC System, Description of Equipment           B.09.10-02                  9         X 7   N        ----. -   Operator Rounds record, Turbine Building East (2010) 2014-2015       ---------------           ----         X 8                      IEEE Recommended Practice for the Design of Safety-Related DC N        -------   Auxiliary Power Systems for Nuclear Power Generating Stations IEEE 946-1985             ----         X 9   y        PROC      D1 0 Battery Charger Preventive Maintenance                          4066-PM                      3         X 10  y        PROC      D20 Battery Charger Preventive Maintenance                           4075-PM                      3         X 11  y        PROC      D40 Battery Charger Preventive Maintenance                 I 4078-PM                      5         X 12  N        - ..----- Replace Div. 1125 VDC Battery Charger D10                             EC720                    ------       X 13  N        ------    Replace Div. 11125 VDC Battery Charger D20                            EC 12877                 ------       X 14  N        -----     Replace 125 VDC Battery Swing Charger D40                             EC 13284                 ------       X 15  N        ------    ITS 125 VDC charger SR 3.8.4.2-0ptoln 2 unachievable                 AR#01131103               ------
16  N        -------   TS SR 3:8.4.2 Non-Conservative for the 125 VDC Chargers              AR # 01456839             -----
17 Record Retention: Retain this form with the associated calculation for the life of the plant.

QF0549 (FP-E-CAL-01), Rev. 7                                                                                                           Page 3 of4 (t Xcel Energy-                                                      Calculation Signature Sheet
* Controlled Doc marked with an "X' means the reference can be entered on the C012 panel in black. Unmarked lines will be yellow. If marked with an "X", also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.
 ** Mark with an 'X" if the calculation provides inputs and/or outputs or both. If not, leave blank. (Corresponds to PassPort "Ref Type" GOdes: Inputs I Both =
     "ICALC", Outputs= "OCALC", Other I Unknown= blank)
Other PassPort Data Associated System (PassPort C011, first three columns)                     OR         Equipment References (PassPort C025, all five columns):
Facility               Unit                       System                      Equipment Type             Equipment Number MT                     1                          125                         CHGR                       010 MT                     1                          125                         CHGR                       020 MT                     1                          125                         CHGR                       040 Superseded Calculations (PassPort C019):
I Faolllty I Calo Dooumenl Numb" .1 Tille Description Codes- Optional (PassPort C018):
Code                        Description (optional)                             Code                              Description (optional)
Notes (Nts)- Optional (PassPortX293 from C020):
Topic Notes                   I Tex,t
[gl Calc Introduction         I [gl Copy directly from the calculation Intra Paragraph or D See write-up below D    (Specify)                I Record Retention: Retain this form with the associated calculation for the life of the plant.

QF0549 (FP-E-CAL-01) Rev. 7                                                                                   Paae 4 of4 (l Xcel Energy-                                       Calculation Signature .Sheet Monticello Specific Information
[g) YES  ON/A       Topic Code(s) (See MT Form 3805):             SBO DYES     jg!N/A     Structural Code(s) (See MT Form 3805):_ __
Does the Calculation:
DYES 0 No           Require Fire Protection Review? (Using MT Form 3765, "Fire Protection Program Checklisr, determine if a Fire Protection Review is required.) If YES, document the engineering review. in the EC. If NO, then attach completed MT Form 3765 to the associated EC.
DYES [g) No         Affect piping or supports? (If Yes, Attach MT Fonn 3544.)
DYES [g) No         Affect 1ST Program Valve or Pump Reference Values, and/or Acceptance Criteria? (If Yes, inform IST Coordinator and provide copy of calculation.)
Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0527 (FP-E-MOD-07) Rev. 4                                                                              Page 1 of 1
 ~ Xcel Energy~                                                    Design Review Checklist EC Number or Document Number I Title I Revision Number:             91-006. 125 VDC Battery Charger Sizing, Rev. 4 Verifier's Name:       Jake Strasser Discipline:      Electrical Design DESIGN REVIEWCONSIDERATIONS:                                                                     Yes    No     NIA
: 1.       Were the inputs correctly selected and incorporated into design?                         IZI   D*     D
: 2.       Are assumptions necessary to perform the design activity adequately described and        IZI   D      D reasonable? Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?            .
: 3.       Are the appropriate quality and quality assurance requirements specified?                D     D      IXl
: 4.       Are the applicable codes, standards, and regulatory requirements including issue
* and addends properly identified and are their requirements for design met?
IXl   D      D
: 5.       Have applicable construction and operating experience been considered?                         D      IXl
: 6.       Have the design interface requirements been satisfied?                                         D      D
: 7.       Was an appropriate design method used?                                                         D      D
: 8.       Is the output reasonable compared to inputs?                                                   D      D
: 9.       Are the specified parts, equipment and processes suitable for the required application?
D      IXl
: 10.    *Are the specified materials compatible with each other and the design environmental       D conditions to which the material will be exposed?
: 11.      Have adequate maintenance fea~ures and requirements been specified?                      D
: 12.      Are accessibility and other design provisions adequate for performance of needed         D maintenance and repair?                                *       . .          *
: 13.      Has adequate accessibility been provided to perform the in-service inspection            D expected to be required during the plant life?
: 14.      Has the design properly considered radiation exposure to the public and plant personnel?
D     D      IXl
: 15.      Are the acceptance criteria incorporated in the desi9n documents sufficient to allow
        . verification that.design requirements have been satisfactorily accomplished?
o -o
: 16.      Have adequate pre~operational, subseguent periodic test and inspection                   D requirements been*appropriately specified, including acceptance criteria?
: 17.      Are adequate handling, storage, cleaning, and shipping requirements specified?           D
: 18.      Are adequate identification requirements specified?                                      D
: 19. Are requirements. for record preparation, review, approval, and retention adequately      D specified?                                      .                     .
: 20. Have Design and Operational Margins been considered and documented?                             D      D COMMENTS:           0   None                1Z1 Attached (Use Form QF-0528)                  D In ECTopic Notes Form retained in accordance with record retention schedule identified in FP-G-RM-01.

QF-0528 (FP-E-MOD-07) Rev. 1 (l     Xcel Energy**                                     Design Review Comment Form Sheet _1_ of _1_-
DOCUMENT NUMBER/ TITLE:                      91_-006, 125 VDC Battery Charger Sizing REVISION:          4        DATE:     10/28/2015 ITEM            REVIEWER'S COMMENTS                             PREPARER'S                 REVIEWER'S
    #                                                             RESOLUTION                 DISPOSITION
: 1.       The calculation references IEEE Std 946-           Included a discussion      Accepted.
1985 for guidance and methodology. The             regarding the 1985 version standard has since been revised (presently         versus the 2004 version.
IEEE Std 946-2004) and given that MNGP has no licensing commitments to the 1985 version, the latest revision should be referenced or the differences dispositioned within the calculation.
: 2.       The recharge time computation for "full-rated"     No response required.      Accepted.
discharge is noted to be very conservative in that the 8-hr rate to 1. 75 vpc is used. From a cell sizing and performance test standpoint "rated" capacity for the MNGP application is generally taken to be the 4-hr rate to 1.81 vpc.
: 3.       Reference 10.22 (ML111110396) is noted to        Reference 10.22 changed    Accepted.
be an interim paper discussing the NRC's           to NUREG/CR-7148.
then ongoing research on float current as an indicator of state-of-charge. The final testing report is documented as NUREG/CR-7148.
The information as presented in the final report has no impact on the data as referenced within the calculation.
: 4.       The composite bi:lttery duty cycle currents for    Values adjusted and        Accepted.
periods 11 and 9 of Div I and Div II,              reference to CAP added.
respectively, need to be adjusted per CAP AR 01474466.
Reviewer: ?J~        . ,_,/~ -           Date: JohRhwr PreQ_arer:
                                                     ,                    ~           /_
I Page 1 of 1

CA-91-006, Rev. 4 TABLE OF CONTENTS Item        Description                                     Pages QF-0549     Calculation Signature Sheet                        4 QF-0527     Design Review Checklist                            1 QF-0528     Design Review Comment Form                         1 TOC         Table of Contents                                  1 Calculation Body (including attachments)                      33 Total    40 Page 1 of 1

MONTICELLO NUCLEAR GENERATING PLANT                                            CA-91-006 TITLE:                                                                         Revision 4 125 VDC Battery Charger Sizing Page 1 of 33
: 1.      PURPOSE The purpose of this calculation is to analyze the sizing of the 125V battery chargers.
The specific battery chargers analyzed are:
D10- Div. 1125 VDC Battery Charger- supplies #11 Battery D20- Div. II 125 VDC Battery Charger- supplies #12 Battery 040 - Swing 125 VDC Battery Charger- can supply either #11 or #12 Battery Revision 3 addressed the increased DC output current capability of the 125 VDC chargers installed perECs 13284,12877, and 720 (References 10.12, 10.13, 10.14).
Revision 4 addresses changes to steady-state loads for post SBO re-charge per new revisions of the station 125 VDC battery calculations (References 10.1, 10.2).
* 2.       METHODOLOGY Ops Manual B.09.10-02 (Ref. 10.6) describes the 125 VDC System equipment. Each battery
(#11 for Division I and #12 for Division II) is composed of 58 C&D Type KCR-13 cells. The 125 VDC system battery chargers D1 0, D20, and D40 are output current-limited at nominal value of 80 amps. The minimum current limit value of 75 amps will be applied in this calculation.
 - During battery recharging, each charger must also supply its divisional 125 VDC system loads.
A simplified methodology for evaluating charger sizing is given in IEEE 946-1985 (Ref. 10.8).
The equation given in this standard will be applied to determine the approximate re-charge times expected for each 125 VDC battery. Note that the IEEE 946 standard has been updated (see following excerpt from IEEE 946-2004). For purposes of this calculation the original1985 version of IEEE 946 specifically for nuclear generating stations will be the primary reference for the methodology and acceptance criteria employed in evaluating charger sizing. Where the 2004 version provides more technical detail or prescribes a more conservative method of evaluation the 2004 version of IEEE 946 will be adhered to.

MONTICELLO NUCLEAR GENERATING PLANT                                                                             CA-91-006 TITLE:                                                                                                          Revision 4 125 VDC Battery Charger Sizing Page 2 of33 Excerpt of IEEE 946-2004:
The original issue- of IEEE Std. 946 was published in 19&5 with fue- title ffiEE Rec-ommended Pl-adice for the Des~gn. of S:afety-R.elated DC Auxili.;uy Power Systems for Nuclear Power Gene-ating Statioru. The 1992 l'e\ision changed ilie title to apply to all generating !>bti.oll!l, while including specific: guidance and a detailed
        'biblitJ_gnphy of nuclear deri.gn refell!llC'J! atand.anls. This revision makes ;a general update. to reflect the most xe<:ent indusb:y practices as. wen as substanfi;U additions to annexes. In addition, as the design of nuclear plmt sy!items has become v.*ell docwnented by other IEEE standards, the- direct emphasis nn unique aspecb of nuelear plant desi_gn has 'b!!en furlhex diminished, with a full lilitlng of the .nuclear <lesign standards included in Anne~ A. Some 'uude<U* di5c=sion and illusinti>.'ec :fi~s* balie been retained as they offe:r a cnns.tructil.re compans<ln to non-nuclear designs without ha1.-:ing to res111f to -additional standards.
Charger sizing will be evaluated by calculating re-charge times considering coincident 125 VDC system loads also supplied by the charger, using the IEEE 946 methodology. This is the same method described in the EPRI Power Plant Electrical Reference Series Volume 9, DC Distribution System (Reference 10.18). Acceptance criteria will be from the 1985 version of IEEE-946. The 2004 version will be referenced as appropriate.
: 3. ACCEPTANCE CRITERIA Per USAR Section 08.05 (Reference 10.17): "Each 125 VDC charger is capable of carrying the normal125 VDC load and at the same time supplying additional charging current to keep the batteries in a fully charged condition." This criterion is met if the charger output current exceeds the normal system loads such that charging current can be supplied to the battery.
For the purposes of determining required output current capability of the 125 VDC chargers, the methodology and criteria of IEEE 946 (References 10.8 and 10.9) will be used, with acceptance criteria from IEEE 946-1985. IEEE 946-1985 recommends a re-charge time of 8 to 12 hours. This IEEE 946-1985 criteria is met if the calculated re-charge time (after a full-rated discharge ofthe battery) is between 8 and 12 hours, considering normal125 VDC system loads.
* IEEE 946-1985 also recommends that the charger have output current capability greater than the continuous loads.plus the largest combination of non-continuous loads that would be likely to occur simultaneously during normal plant operation. This IEEE 946-1985 criteria is met if the charger output current exceeds nornial continuous* system loads by an amount adequate to bound non-continuous load combinations likely during normal plant operation. Note that meeting the IEEE 946 criteria ensures the USAR criterion is met.
This calculation will also evaluate re-charge time following a Station Blackout discharge of each battery. The Monticello licensing basis discharge corresponds to the Station Blackout event ahd the equivalent discharge load profile is taken from the battery sizing calculations (References 10.1 and 10.2). This is the discharge that the battery would undergo if subjected to a service test with a load profile matching that modelled in the battery calculations which

MONTICELLO NUCLEAR GENERATING PLANT                                                CA-91-006 TITLE:                                                                             Revision 4 125 VDC Battery Charger Sizing Page 3 of 33 model a composite profile for the 4-hour LOCA I Station Blackout event The re-charge time will be calculated using the IEEE 946 equation (same equation for both the 1985 and 2004 versions of IEEE 946) with system load considered to be the largest continuous load combination present at the end of the modelled station blackout event. There are currently no explicit licensing basis criteria in place for the recharge time after the design basis discharge.
The load profile used to determine the degree of battery discharge will be taken from the sizing worksheets of the battery sizing calculations. These sizing worksheets tabulate loads vs. time and evaluate battery positive-plates-required in accordance with IEEE Std.485-1983 (Reference 10.3). The profiles modelled are a composite combination of loads that would be needed to mitigate a LOCA event coincident with a loss of offsite power and the loaqs necessary to operate equipment necessary to mitigate a 4-hour Station Blackout event.
: 4.      INPUTS 4.1     The charger output-current limit setting is 78-82 amps, per PM procedures (References 10.9, 10.1 0, 10.11 ). A charger minimum current output of 75 amps will be used for this calculation.
4.2      The battery discharge during an SBO event is modelled in the following calculations:
For Div. I (#11 Battery)- CA-02-179 (Reference 10.1)
For Div. II (#12 Battery)- CA-02-192 (Reference 10.2)
The load data from these calculations is consolidated in the spreadsheet of Attachment
: 02. This spreadsheet tabulates the effective amp-hours discharged for both the Div. I and Div. II SBO events. The load values were adjusted in select time periods in accordance with the issue identified in CAP AR # 01474466 (Reference 10.24). The corrected values are as given in ECs 25634 and 25511 (References 10.25 and 10.26).
Note that the bounding loads considering 1 minute minimum time interval taken from the battery sizing worksheets are used. The results of the calculations in the spreadsheet are as follows:
                     . Div. I (#11 Battery) total amp-hours discharged= 263.01 Div. II (#12 Battery) total amp-hours discharged= 240.49

MONTICELLO NUCLEAR GENERATING PLANT                                           CA-91-006 TITLE:                                                                        Revision 4 125 VDC Battery Charger Sizing Page 4 of 33 4.3   The rated battery discharge capacity will be taken to be the full KCR-13 cell capacity for a discharge to 1. 75 volts I cell as given in Attachment 01.
Full rated discharge amps hours = 495 maximum This is conservative as it is a larger value than the 8-hour value recommended by IEEE 946-1985. Also in Attachment 1 are the ratings as given in the battery sizing calculations (excerpt taken from 02-192). Note that the ratings are slightly different.
The 495 amp-hour value representing ultimate capacity will be used to determine the maximum re-charge time. The 8 hour value from the C&D ratings table of 61 x 8 = 488 will be used to calculate minimum re-charge time.
Full rated discharge amps hours = 488 minimum 4.4   The steady-state system loads after an SBO discharge will be taken from the node current analysis in the battery sizing calculations. The DC system loads at analyzed time steps were inspected to select the load for each battery that represents the largest combination of steady-state loads that could be present at the end of the SBO event..
For the Div. I system, Time Step 52 of the Div. I calculation (Reference 10.1) represents that maximum steady state load on the Div. I 125 VDC system at the end of an SBO event. For the Div. II system, the maximum steady state load considered is taken from Time Step 53 of the Div. II calculation (Reference 10.2). The effective system loads are dependent on the corresponding system voltages. These voltages will be taken as the battery node voltage from the calculations fodhe applicable time steps.
Div. I (#11 Battery) current at Time Step 52 = 61.54 Amps Div. I (#11 Battery) voltage at Time Step 52 = 109.204 VDC Div. II (#12 Battery) current at Time Step 53= 57.95 Amps Div. II (#12 Battery) voltage at Time Step 53= 110.130 VDC For the Div. I system, the current due to the emergency lighting load will be subtracted, as the emergency lights will switch off once AC power is restored to the holding coil for the DC contactor feeding Panel L40 (Reference 10.4) at the end of the SBO event.
Div. I Emergency Lighting current at Time Step 52= 13.94 amps Therefore:
Div. I post-SBO 125 VDC system load= 61.54-13.94 = 47.6 amps (at a battery terminal voltage of 109.204 VDC)

MONTICELLO NUCLEAR GENERATING PLANT                                             CA-91-006 TITLE:                                                                          Revision 4 125 VDC Battery Charger Sizing Page 5 of 33 Div. II post-SBO 125 VDC system load= 57.95 amps (at a battery terminal voltage of 110.130
                                                         .    . VDC) 4.5    For full-rated battery discharge, the system loads present during re-charge would be the same as the 125 VDC system loads under normal plant conditions. Per Operation's Logs (Reference 10. 7), these normal loads are very consistent. Two
* separate months of data were reviewed and the highest load value selected for each Division (Attachment 03):
Div. I normal system load = 23 amps Div. II normal system load= 24 amps The loading recorded in the logs was very consistent. The panel ammeter has an accuracy of 1% of the 150 amps full scale range or +I- 1.5 amps (Reference 10.20). The current shunt has an accuracy of +I- 0.33% or 0.495 amps (References 10.20, 10.21 and Attachment 5). The ammeter scale has 2 amp graduations for a readability error of +/- 1 amp. Combining these errors statistically using a square-root-sum-of-squares method:
Total ammeter uncertainty= (1.5A2 + 0.495A2 + 1A2)A1f2 = 1.87 amps.
Therefore an uncertainty of+/- 2 amps will be considered to apply to the log readings.
For conservatism, the upper limit and lower limits on normal load will be adjusted by
       + or- 3 amps, giving normal load limits as follows:
Div. I minimum normal system load = 23 3 = 18 amps
                                                     =           =
Div. I maximum normal system load 23 + 2 + 3 28 amps Div. II minimum normal system load =24 3 = 19 amps Div. II maximum normal system load = 24 + 2 + 3 = 29 amps
: 5. ASSUMPTIONS 5.1   None

MONTICELLO NUCLEAR GENERATING PLANT                                              CA-91-006 TITLE:                                                                           Revision 4 125 VDC Battery Charger Sizing Page 6 of 33
: 6.      ANALYSIS From IEEE 946-1985 (Reference 10.8), the battery charger sizing should be evaluated using the following formula:
A= l.lxAHR +L T
A       = Charger Rating L       = Station Load AHR . =Battery Discharge in Ampere Hours T       = Hours to Recharge 1.1     = Compensation for battery losses No correction factors for altitude or temperature are needed for the chargers in use at Monticello as temperatures are less than 50 deg; C and altitude is less than 3300 feet.
When solved for time (T), equation 2.1 becomes:
T == l.lxAHR A-L Division I Calculation (01 0 or 040 re-charging #11 .Battery)
For a Station Blackout. design basis discharge event (DIV 1):
During re-charge following a station blackout event, the continuous load given in Input 4.4 will increase as voltage increases during re-charge. The load will be considered constant resistance for conservatism and adjusted for the maximum charger float.
voltage of 130.5 volts, as defined in procedure 4510-PM (Reference 10.19).
The 2004 version of IEEE-946 notes that the actual percent charge restored to a battery when using the given sizing equation is dependent on applied voltage. To ensure a 95% restored charge consistent with the standard, a charger voltage output in the equalizing range may be necessary. Per procedure 4510-PM, the maximum equalizing voltage for the 125 VDC chargers is 135.8 VDC, or 2.342 volts I cell. Note however, that during the current limited portion of the re-charge cycle (bulk phase) battery voltage rises over time to the charger setting. As an example of this charging response for. lead acid batteries reference the following excerpts from C&D Batteries and NRC (References 10.22 and 10.23). At the onset of charging, battery voltage
* would be well below normal float voltage.* The average current available for re-charging the battery would then be*reduced as voltage rises, due to the corresponding increase in current to the system loads. The voltage rise can be conservatively

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MONTICELLO NUCLEAR GENERATING PLANT                                           CA-91-006 TITLE:                                                                        Revision 4 125 VDC Battery Charger Sizing Page 8 of 33 Adjusting system loads as discussed* and applying the sizing equation gives:
L = 47.6 amps x 130.5 VDC /109.204 VDC = 56.9 amps             Input 4.4 A= 75 amps                          Input 4.1 AHR= 263.01 amp-hours               Input 4.2 T = (1.1 x 263.01) I (75- 56.9)
T = 16.0 Hours (Div. L re-charge after design basis Station Blackout event)
For a full-rated battery discharge (DIV 1):
The system load considered for calculating time for a recharge of the battery after a discharge of its rated capacity is taken from Operator logs of the battery charger output current during normal plant conditions.
L = 23 amps +/- 5 amps       Input 4.5 A= 75 amps minimum                         Input 4.1 A= 82 amps maximum                         Input 4.1

MONTICELLO NUCLEAR GENERATING PLANT                                                CA-91-006 TITLE:                                                                             Revision 4 125 VDC Battery Charger Sizing Page 9 of 33
                    =
AHR 495 amp-hours maximum                   Input 4.3 AHR = 488 amp-hourminimum                   Input 4.3 Tmin  = (1.1 x 488) I (82- 18) = 8.3*hours Tmax   = (1.1 x 495) I (75 - 28) =11.6 hours T =8.3 Hours to     11.6 Hours (Div. I. re-charge after full rated battery discharge)
Division II Calculation (020 or 040 re-charging #12 Battery)
For a Station Blackout, design basis discharge event (Div II):
During re-charge following a station blackout event, the continuous load given in Input 4.4 will increase as voltage increases during re-charge. The -load given for the Div. II 125 VDC system can be conservatively considered constant-resistance and adjusted for a maximum charger float voltage of 130.5 volts, as defined in procedure 451 0-PM           *
(Reference 10.19). See the discussion for the Division I station blackoutcharging calculation for justification of the use of 130.5 volts for determination of system loads, even if the actual recharge is performed with the charger at a maximum equalize setting of 135.8 VDC.
L  =57.95 amps x 130.5 VDC 1110.130 VDC =68.7 amps                lnput4.4 This is a large load and bounds the Div. I considered maximum recharge load by a wide margin. As a significant portion of the loading is due to constant power and constant current loads, a DCSDM software run of the Time Step 53 loads was executed with a battery node voltage of 130.5 VDC. *The output report of this run is given in Attachment *
: 4. The calculated load value of 60.25 amps from Attachment 4 will be used.
L  =60.25 amps                       Attachment 4 A= 75 amps                           lnput4.1 AHR = 240.49 amp-hours               Input 4.2 T =(1.1 x 240.49) I (75- 60.25)
T = 18.0 Hours (Div. II. re-charge after design basis Station Blackout event)

MONTICELLO NUCLEAR GENERATING PLANT                                            CA-91-006 TITLE:                                                                         Revision 4
* 125 VDC Battery Charger Sizing Page 10 of 33 For a full-rated battery discharge (DIV II):
The system load considered for calculating time for a recharge of the battery after a discharge of its rated capacity is taken from Operator logs of the battery charger output current during normal plant conditions.
L =24amps       +1- 5 amps     lnput4.5 A =75 amps minimum                        Input 4.1 A= 82 amps maximum                        Input 4.1 AHR = 495 amp-hours maximum               Input 4.3 AHR = 488 amp-hour minimum                Input 4.3 Tmin  =(1.1 x488) I (82 -19)
Tmax = (1.1 x 495) I (75- 29)
T =8.5 Hours to 11.9 Hours (Div. II, re-charge after full rated battery discharge)

==7.0  CONCLUSION==
S IEEE 946-1985 (Reference 10.8) recommends sizing battery chargers for an 8 to 12 hour re-charge time, considering a battery discharged to its full rating and normal DC system loading. The corresponding re-charge times calculated were:
Re-charge after full rated discharge with normal plant loads Div. I, 8.3 to 11.6 hours Div. II, 8.5 to 11.9 hours These calculated times are within the IEEE 946-1985 recommended time range of 8 to 12 hours. The 125 VDC system loading range assumed incorporates tolerance for reading uncertainty and margin. Therefore the charger current limit settings are well-matched to the battery size considering system loads and in accordance with the standard.
IEEE 946 recommends that charger output current capacity exceed the combination of continuous system loads plus the largest combination of non-continuous loads that would be 'likely to occur simultaneously during normal operation. With continuous loads less than 30 amps and charger output current capability of 75 amps (minimum), more*

MONTICELLO NUCLEAR GENERATING PLANT                                             CA-91-006 TITLE:                                                                           Revision 4 125 VDC Battery Charger Sizing Page 11 of 33 than 45 amps is available for simultaneous non-continuous loads. During normal plant operation, additional non-continuous simultaneous loads are very uri likely to exceed 45 amps.
Recharge times were conservatively calculated for a design bas.is battery re-charge considering the continuous loads that would be present post-event:
Recharge after a Station Blackout, design basis discharge event:
Div. I, 16.0 hours Div. II, 18.0 hours The calculated times demonstrate that the each charger's sizing is adequate to supply the maximum combination of continuous loads present after a Station Blackout event and re-charge its battery in a reasonable time (to 95% capacity). The 125 VDC system loads assumed during recharge after the design basis event were conservatively adjusted to correspond to maximum float voltage for the entire recharge time period.
Note that AR #011311 03 documented an issue with the 2nd method of determining acceptance for Tech Specs surveillance requirement SR 3.8.4.2, i.e. that the battery chargers can accomplish a re-charge in <= 8 hours after a design basis discharge event (SBO). AR # 01456839 formally documented this issue as a non-conservative Tech
* Specs surveillance requirement and establishe*d administrative limit for the 1st method of meeting SR 3.8.4.2. The administrative limit 125 VDC system battery charger output current was established as >= 75 amps.
* The basis for the second method of SR 3.8.4.2 involves achieving re-charge of a battery after a service test with the maximum continuous load applied to the system that could be present regardless of plant conditions. The service test would essentially correspond to the design basis load profile modelled in the battery calculations for a station blackout event. The maximum continuous loads would be as determined in this calculation based on a review of the continuous loads applied at the end of this event.
Thus, this calculation demonstrates that re-charge would occur in this case in reasonable time. However, this method of surveillance of the battery chargers would not be used at Monticello as battery testing is performed via a modified performance test, which of necessity discharges the battery to a greater degree than a service test.
The most precise way to ensure the battery charger is capable of performing its design functions is to test it per the 1st method, thus ensuring it can supply adequate current at float voltage for a 4 hour time period.
Final resolution of the Tech Spec issue described in ARs 01131103 and 01456839 requires a permanent change to the 1st method of meeting SR 3.8.4.2. The criteria should be changed to>= 75 amps for 4 hours (as is presently administratively

MONTICELLO NUCL!;AR GENERATING PLANT                                            CA-91-006 TITLE:                                                                          Revision4 125 VDC Battery Charger Sizing Page 12 of 33 controlled): It is recommended that 2nd method of meeting the surveillance be removed, as this test method is not used at Monticello. This calculation shows that a charger current of 75 amps is adequate to re-charge the 125 VDC batteries within a reasonable time after a design basis event and considering continuous post-event loads.
8.0   FUTURE NEEDS AR # 01456839 tracks completion of a License Amendment Request for Technical Specifications SR 3.8.4.2. The first option should be changed to >= 75 amps, as is currently administratively controlled. The second option should be removed from Tech Specs as this test option would not be of practical use at Monticello. This calculation determines that a charger test to >= 75 amps for 4 hours demonstrates the ability to re-charge batteries after the limiting Station Blackout event in reasonable time, considering the largest combination of 125 VDC system steady state loads.
9.0   ATTACHMENTS Attachment 01- Excerpt of C&D Technologies, Publication 12-316, KCR-13 Lead-Calcium Standby Batteries Attachment 02- Spreadsheet showing total discharge amp-hours for Div. I and Div. II 125 VDC batteries based on SBO battery calc load profiles Attachment 03- Excerpt of 2010 Ops Log for 010, 020 charger output current, Sept. 2010, Jan. and June 2011 Attachment 04- DCSDM software sizing report showing calculation 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.

==10.0 REFERENCES==

10.1  Calculation CA-02-179, Div. 1125 Volt Battery Calculation, Rev. 3 10.2  Calculation CA-02-192, Div. 11125 Volt Battery Calculation, Rev. 3 1"0.3 IEEE Std. 485-1983, 'IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations'

MONTICELLO NUCLEAR GENERATING PLANT                                        CA-91-006 TITLE:                                                                     Revision 4 125 VDC Battery Charger Sizing Page 13 of33 10.4  B.09.14-02, Operations Manual, Lighting, Description of Equipment, Rev. 1 10.5  C&D Technologies, Publication 12-316, KCR~13 Lead-Calcium Standby Batteries (see Attachment 01 for excerpt) 10.6  B.09.1 0-02, Operations Manual, 125 VDC System, Description of Equipment, Rev. 9 10.7  Operator rounds records, Turbine Building East (2010), excerpts from December, 2014 and July, 2015 included as Attachment 03.
10.8. IEEE Std. 946-1985, 'IEEE Recommended Practice for the Design of Safety-Related DC Auxiliary Power Systems for Nuclear Power Generating Stations' 10.9  IEEE Std. 946-2004, 'IEEE Recommended Practice for the Design of DC Auxiliary Pow~r Systems for Generating. Stations' 10.10 4066-PM, D1 0 Battery Charger Preventive Maintenance, Rev. 3 10.11 4075-PM, D20 Battery Charger Preventive Maintenance, Rev. 3 10.12 4078-PM, D40 Battery Charger Preventive Maintenance, Rev. 5 10.13 EC 720, Replace DIV. 1125 VDC Battery Charger D10 10.14 EC 12877, Replace Div. 11125 VDC Battery Charger D20 10.15 EC 13284, Replace 125 VDC Battery Swing Charger 040 10.15 AR # 01131103, ITS 125VDC charger SR 3.8.4.2-0ption 2 unachievable 10.16 AR # 01456839, TS SR 3.8.4.2 Non Conservative for the 125 VDC Chargers 10.17 USAR-08.05, Plant Electrical Systems, Rev. 30 10.18 EPRI Power Plant Electrical Reference Series, Volume 9, EC Distribution System, Copyright 1987 10.19 451 0-PM, Maintenance of On-Site Batteries and Battery Chargers at Monticello Nuclear Plant, rev. 35 10.20 NX-9173-19, C & D Battery Chargers (D10,020,D40) NLI Model: ARR130K100F-MOD, rev. 1

MONTICELLO NUCLEAR GENERATING PLANT                                     CA-91-006 TITLE:                                                                  Revision 4 125 VDC Battery Charger Sizing Page 14 of 33
* 10.21 Rammeter website page showing.F150A50 current shunt accuracy (Attachment 5) 10.22 NUREG/CR-7148, Confirmatory Battery Testing: The Use of Float Current Monitoring
* to Determine Battery State-of-Charge, p*ublished November 2012 10.23 C&D Technologies Technical Bulletin 41-2128, Charging Valve Regulated Lead Acid Batteries
* 10.24 CAP AR # 01474466, DCSDM Software Issue, initiated 04-14-15 10.25 EC 25634, Monticello 125V #11 Battery Modified Performance Test Profile 10.26 EC 25511, Monticello 125V #12 Battery Modified Performance Test Profile

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                           CA-91-006 TITLE:                                                                                                                                                        Revision 4 125 VDC Battery Charger Sizing Page 15 of33 1 - KCR-13 Battery Ratings: Excerpt of C&D Technologies,                                                                                                page 1 of 2 Publication 12-316, KCR-13 Lead-Calcium Standby Batteries:
Excerpt of 02-192, MNGP 125 Volt Div. II Battery Calculation CDTECHNOLOGfE~~~~~~~- ----~ __
Powet SGluTilnfr-'.::                       ~
* Excerpt of C&D Technologies Doc. 12-316,2007 RATINGS TABLE: AMPERES
                                                                             'Nominal Rat?" 0 77'F (2G'C) in 1.21!> N<!mlnai_SG (lntludas cimnaclor voH.oga drop}*.
Amp&nltO NomlnaiAH Final Volta       Models              Rating
* lihr                4hr            3hr         1.5hr             1 hr           30m!n    15m!n        1mln KCRIKAR-5              200                   25 ..            41 .           50          77              .M                1211     165         243 KCRIKAR-7              250                   31              li3             65          101              126             173       221         300 KCRIKAR-0              330                   41               71             9T          135            ,:169             231       294         412 KCRIKAR-11              410                   52              88              109 '.      166        '     206             294       364         608 1.75        KCRlKAR-13              495                   61              106             tat ~-      204              254             351       450         655 KCRIKAR-16              577                   72.             124             162***.. 237              297             411       6112        707 KCR!i<AR-17             660              .. '92 .             142             174:        272             '340             470       604         871 KCRIKAR-19              742                   92              159             195.        aoa             *378             .520      664         949 KCRIKAR--21             925                   100             176             216.        332             -413             567       728         1028 KCRIKAR-6              194                   24               41             41l :        74               Ill             122      154         213 KCRIKAR-7              239                '30                51              62           95             .117             169       198         264 KCRIKAR-9              :119                . 40.              6ll            93 .        126       . "156 .-              211       264         353 KCWKAR-11               401            ._. .- 60 <       .
ll4             wi*.        155          *. 191 ~            260       327         435 1.76        KCRIKAR-13              479                   SQ.             102             124         191              236             320       404         560 KGR/i<AR-15             659          *.* *70                  119             145         222            . 275             ll75      4Tr         682 KCRIKAR-17              637                   00              136             166'-       254           : 315         . 429       542         746 KCRJKAR-111             719                   90              152         0 196         293           . a!io -* .        474       596         912 KCRIKAR-21              1102             .*-too               169           .-205.        310              382 .           518       653         891 KCRIKAR-6              190                 . 24   ....       @               49           71               96              114      140         *193 KCRJKAR-7              231                   29              .(9       . '511             as     I         109             143      175         22t KCRIKAR-9              ll10                  3~               65             7B          117     I         14&deg;4 ; .. 0 191      293         204 KCRIKAR-11              300                   4~ .             90        '. 97 *.         146              tfr .**         235       289         364
                                                                                                            .                . 219                    .*. 357; 1.81        KCRIKAR-13              464                   511              !!7        . 118.          178                              200                   467 I(CR/KAR-15             541                  *68              114      **..- 139'*        207              254 .<          agg       422         569 KCRIKAR-11              619                   77              1110          *H>7          237              ,291'           9118      479         621 KCRIKAR-10              699                  '97              146             176         264              :123             420      627**        677 KCRIKAR-21              779                   97              161           '194.         289          ,' 353              460       577          736
     *oaa baood en di!<ila~ga tllroody lrom a 72-hoor noat oonlfllon periEEE-450 prooedu1eo.

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                   CA-91-006 TITLE:                                                                                                                                Revision 4 125 VDC Battery Charger Sizing Page 16 of 33 1 - KCR-13 Battery Ratings: Excerpt of C&D Technolog*ies,                                                                    page 2 of 2 Publication 12-316, KCR-13 Lead-Calcium Standby Batteries:
Excerpt of02-192, MNGP 125 Volt Div. II Battery Calculation
                                                                           'C&D 'F.I!C:El:N()LOGI&#xa3;S, Jl'ic..
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   * ~~~J .. ?OE,II ~no 2f5~ 12(}_;?~0I:.J 173~ l4:5J 116.0 &4.!l 6~J 53~() +J.ll 38:9 3([8 15;5 ~L8115.913:8 lU
   . KC:R:p 4Ii.7 :J"6g.4:J2~.!dll4:2~6s~6 :no:9 i9:L i6!Lo nt2 11~:1 10.1 59.7 5ts *n:o ~~f~ ri9.o 22.s18.~ 155 k&#xa2;&-Ii* 5o&.Q fl?ll.o~g5.H6f;~ JL5284:P!7.: 206_,413~.:!1101~ _87.9. }j'4.o ~.II .~U.:l!1J~?!dl:2.s.4[rt.~I?.~
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   . KCR.-15 7!.17.-i' 693.4 S!IS.15!l.7 81,8 41Ll 342;1!           l9MJ9,1)J 152311lj) 1{1.4.~ !10.1 71.'1 593 f)O.~ 3!).2 3.1,9 27,0 Kqt~l7 . R11);~ * ~71.1 1575,~ ti(l3,6154S:S 'fliP 39_2J      :B&#xa3;1,~ J:tll.~ 11~~ ]4~:~ 119.~ l(ll.~ :st!l 61, im!f#;7~6.> 3{1.8 K:CR.~I!.l !14a:7      &-u:t   740'.7 6il4.it6iisj 5t~G 4i5.C "iii~? 154:ii 1951 15ll:ll il4.' ii6.~ 9-23 76~5 6{3 so.6W.Ll H:9 KCR."21 1,0283 91L1 812:ll n7.6 1562:151573 474;              Ui.5119.6 215.1115.~ 14Stll2!l.( lOH ltS,S 73J 51i.BfM.4 3!l.l
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                                                                                                                                 CA-91-006 TITLE:                                                                                                                                                                                                                                                                              Revision 4 125 VDC Battery Charger Sizing Page 17 of 33 2- Spreadsheets showing total discharge amp-hours for                                                                                                                                                                                                                          page 1 of 2 Div. I and Div. 11125 VDC batteries based on SBO battery Calc. load profiles (from calc. sizing worksheets)
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                                                                                               CA-91-006 TITLE:                                                                                                                                                                                                                                            Revision 4 125 VDC Battery Charger Sizing Page 18 of 33 2- Spreadsheets showing total discharge amp-hours for                                                                                                                                                                                       page 2 of2 Div. I and Div, II 125 VDC batteries based on SBO battery Calc. load profiles (from calc. sizing worksheets) l~y._IL~tte.r~~~-q ~l~~h-~.t~.:-
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                   CA-91-006 TITLE:                                                                                                                Revision 4 125 VDC Battery Charg.er Sizing Page 21 of33 3- Excerpt of 2010 Ops Log for 010, D20 charger output                                                     page 3 of 8 current, Dec. 2014 and July, .2015 Tliti;Jil'oll flplldlll;j Em (2010)                                                          gwr-o2.o;1 Oi*fW AQU~
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MONTICELLO NUCLEAR GENERATING PLANT                                                                       CA-91-006 TITLE:                                                                                                    Revision 4 125 VDC Battery Charger Sizing Page 24 of 33 3- Excerpt of 2010 Ops Log for 010, 020 charger output                                           page 6  of 8 current, Dec. 201.4 and July, 2015 *
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                CA-91-006 TITLE:                                                                                                             Revision 4 125 VDC Battery Charger Sizing Page 25 of 33 3- Excerpt of 2010 Ops Log for 010, 020 charger output                                                   .page 7 of 8 current, Dec. 2014 and July, 2015 D-11JVOLTA~-1LOAT .-11 Blo.TTfR&#xa5; 01(14{2!)15: 21100        ll1                           ~. ~
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MONTICELLO NUCLEAR GENERATING PLANT                                                          CA-91-006 TITLE:                                                                                       Revision 4 125 VDC Battery Charger Sizing Page 27 of33 4- DCSDM software sizing report showing calculation                               page 1 of 6 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
Attachment F Node Voltages By:      - - - - - - - - - - - - - - - - - D a l e : _ _ _ _ _ __
Check:                                                 Datg: _ _ _ _ _ __
Xcel Energy 1Monllceno -12liVdo      DCSDM Version 3.0     Attaclunent FD2DBA Page FD2DBA 1 of Cole No. 02.192 Reil. 3                                                              FD2DBA3

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                     CA-91-006
                                                                                                                                                        *.*               Revision 4*
TITLE:
125 VDC Battery Charger Sizing Page28 of 33 4- DCSDM software sizing report showing calculation                                                                                                           page 2 of6 02-:192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
Node Voltages Genero~on Dot~>:          08'2512015 03:46pm Batlery:            D2 Scenario:           D2DBA Scenario            o:!Banery CoolposileScenaJio Oosr:ripllon:
I I..... I.::;. I I I I I Iv=. I I 2
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                                                                                      >:10.10
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tlU tW 311     1              fUil!IIEIIfJICI<OOIRO X<:OI e. ..gy /IIOMIIMIIa -11SV<k>                                                              OOSDY Version 3.0                                Al11ohmentFD2DBA Pogo FD2DHA20I FD2DBA3 Calc No. 02-197.11BY. 3

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                         CA-91-006 TITLE:                                                                                                                                                                      Revision 4 125 VDC Battery Charger Sizing Page29 of33 4- DCSDM software sizing report showing calculation                                                                                                               page 3 of 6 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
Node Voltages Generation Date: 08/25'20 15 03:46pm Ballery:         D2 Scenario:        D2DBA Scenario         02 Battery Composite Scenalio

==
Description:==

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                          ~,l.ltf.}OCU.lOrlS                         13:!.7'     lt1'.13, Xcel Energy I Monticello -12SVdo                                                          DCSDM Varslon 3.0                                       Allaohmont F020BA Page FDlDBA 3 of FDlDBA 3 Cole No.02-192Rov. 3

MONTICELLO NUCLEAR GENERATING PLANT                                                . CA-91-006 TITLE:                                                                               Revision 4 125 VDC Battery Charger Sizing Pa9e 30 of33 4- DCSDM software sizing report showing calculation                      page 4 of 6 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
Attachment G Node Currents By:       _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date: _ _ _ _ _ _ __
Check:                                                 Date:-~------
Xcel Energy I MonUcello- 125Vdc      DCSDM version 3.0  Attachmem GD2DBA Page GD2DBA 1 of calo No. 02-192 Rev. 3                                                        GD2DBA3

MONTICELLO NUCLEAR GENERATING PLANT                                                                                                                                   CA-91-006 TITLE:                                                                                                                                                                Revision 4 125 VDC Battery Charger Sizing Page 31 of 33 Attachment 04- DCSDM software sizing report showing calculation                                                                                                        page 5 of6
* 02-192 Time Step 53 loads at a battery node voltage of 130.5 VDC.
Node Currents Gonem~on         Date: CJ8121f/20f5 03:46pm Battery:          02 Beonatlo:         D2DBA Scenario          02 SaHel}' COIIlj)O~Io SoerruiG De5Crlp!lon:
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MONTICELLO NUCLEAR GENERATING PLANT                                                                                                       CA-91-006 TITLE:                                                                                                                                    Revision 4 125 VDC Battery Charger Sizing Page 32 of33 4- DCSDM software sizing report showing calculation                                                                             page 6 of6 02-192 Time Step 53 loads,at a battery node voltage of 130.5 VDC.
Node currents GeneraUon Date; 08/2!!12015 03;48 pm Ballery:       D2 Se<narlo:      D208A Sctnarlo       D2 Balle!y CUnpJsile Sa! MOO Desorlptlon:
          -                                                                    I I I I I I I Ir::=:.a I I
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                                                                                                                                            ~.       =~
(ADC)               (ADCJ  V.DCJ           "DC)         lADC) (lDC)                           111101    CAOO) ll   p&ID               rNiASIE~tE\.~          C..Ol     ,,~q 33
           ~             ~A!fi\1/K.t.\TORS
:;04A~Io\10fiS U!l
                                                  <OO Bl Xcol Enn<gy !llD!llloollo *1251/ck:                              DCSDU Version 3.0                            Alladlment GD201!J\ l'a!JD GDWII/Ia ol GD20DA 3 Cole 'No. 0).19llloY.1

MONTICELLO NUCLEAR GENERATING PLANT                         CA-91-006 TITLE:                                                      Revision 4 125 VDC Battery Charger Sizing Page 33 of33 5- Ram meter web page showing 0.33% accuracy for page 1 of 1 current shunt model F150A50.}}