ML20352A349
| ML20352A349 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/08/2021 |
| From: | Robert Kuntz Plant Licensing Branch III |
| To: | Conboy T Northern States Power Company, Minnesota |
| Kuntz R, NRR/DORL/LPL3, 415-3733 | |
| References | |
| EPID L-2020-LLA-0209, TSTF-582, TSTF-583-T | |
| Download: ML20352A349 (25) | |
Text
January 8, 2021 Mr. Thomas A. Conboy Site Vice President Northern States Power Company - Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENT NO. 205 RE: TECHNICAL SPECIFICATIONS TASK FORCE TRAVELERS TSTF-582, RPV WIC ENHANCEMENTS, AND TSTF-583-T, TSTF-582 DIESEL GENERATOR VARIATION (EPID L-2020-LLA-0209)
Dear Mr. Conboy:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 205 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant. The amendment consists of changes to the technical specifications in response to your application dated September 22, 2020.
The amendment revises the technical specifications related to reactor pressure vessel (RPV) water inventory control (WIC) based on Technical Specifications Task Force (TSTF) Travelers TSTF-582, Revision 0, RPV WIC Enhancements, and TSTF-583-T, Revision 0, TSTF-582 Diesel Generator Variation.
A copy of the Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Robert F. Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosures:
- 1. Amendment No. 205 to DPR-22
- 2. Safety Evaluation
- 3. Notices and Environmental Findings cc: Listserv
NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 205 Renewed License No. DPR-22
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (NSPM), dated September 22, 2020, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-22 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: January 8, 2021 Joel S.
Wiebe Digitally signed by Joel S. Wiebe Date: 2021.01.08 11:02:55 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 205 MONTICELLO NUCLEAR GENERATING PLANT RENEWED FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Renewed Facility Operating License No. DPR-22 Replace the following page of Renewed Facility Operating License No. DPR-22 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT Page 3 Page 3 Technical Specifications Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 1.1-2 1.1-2 1.1-3 1.1-3 3.3.5.3-1 3.3.5.3-1 3.3.5.3-2 3.3.5.3-2 3.3.5.3-3 3.3.5.3-3 3.3.8.1-1 3.3.8.1-1 3.5.2-2 3.5.2-2 3.5.2-3 3.5.2-3 3.5.2-4 3.5.2-4 3.6.1.3-5 3.6.1.3-5 3.8.2-3 3.8.2-3 Amendment No. 205
- 2.
Pursuant to the Act and 10 CFR Part 70, NSPM to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensees filings dated August 16, 1974 (those portions dealing with handling of reactor fuel);
- 3.
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
- 4.
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and
- 5.
Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess, but not separate, such byproduct and special nuclear material as may be produced by operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission, now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
- 1.
Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 2004 megawatts (thermal).
- 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.
- 3.
Physical Protection NSPM shall implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search
Definitions 1.1 Monticello 1.1-2 Amendment No. 205 1.1 Definitions CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
- a.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
- b.
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR)-11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR-12, "External Exposure to Radionuclides in Air, Water and Soil,"
September 1993.
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
a)
The water inventory above the TAF is divided by the limiting drain rate; b)
The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode
Definitions 1.1 Monticello 1.1-3 Amendment No. 205 1.1 Definitions DRAIN TIME (continued) failure, for all penetration flow paths below the TAF except:
- 1.
Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are closed and administratively controlled in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
- 2.
Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
- 3.
Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.
c)
The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d)
No additional draining events occur; and e)
Realistic cross-sectional areas and drain rates are used.
A bounding DRAIN TIME may be used in lieu of a calculated value.
INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f)
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-1 Amendment No. 205 3.3 INSTRUMENTATION 3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.3 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.5.3-1.
ACTIONS
NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
A.1 Initiate action to place channel in trip.
OR A.2.1 Declare associated penetration flow path(s) incapable of automatic isolation.
AND A.2.2 Initiate action to calculate DRAIN TIME.
Immediately Immediately Immediately
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-2 Amendment No. 205 SURVEILLANCE REQUIREMENTS
NOTE--------------------------------------------------------------
These SRs apply to each Function in Table 3.3.5.3-1.
SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-3 Amendment No. 205 Table 3.3.5.3-1 (page 1 of 1)
RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION ALLOWABLE VALUE
- 1. Shutdown Cooling System Isolation
- a.
Reactor Vessel Water Level - Low (b) 2 in one trip system 7 inches
- 2. Reactor Water Cleanup (RWCU) System Isolation
- a.
Reactor Vessel Water Level - Low Low (b) 2 in one trip system
-48 inches (a) (Deleted)
(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
LOP Instrumentation 3.3.8.1 Monticello 3.3.8.1-1 Amendment No. 205 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3 ACTIONS
NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
A.1 Place channel in trip.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. Required Action and associated Completion Time not met.
B.1 Declare associated EDG inoperable.
Immediately
RPV Water Inventory Control 3.5.2 Monticello 3.5.2-2 Amendment No. 205 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
AND C.3 Verify one standby gas treatment (SGT) subsystem is capable of being placed in operation in less than the DRAIN TIME.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours D. DRAIN TIME < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.1
NOTE ---------------
Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
AND D.2 Initiate action to restore secondary containment boundary.
AND Immediately Immediately
RPV Water Inventory Control 3.5.2 Monticello 3.5.2-3 Amendment No. 205 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.
AND D.4 Initiate action to verify one SGT subsystem is capable of being placed in operation.
Immediately Immediately E. Required Action and associated Completion Time of Condition C or D not met.
OR DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
E.1 Initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for the required ECCS injection/spray subsystem, the:
- a. Suppression pool water level is -3 ft; or
- b. Condensate storage tank(s) water level is 7 ft for one tank operation and 4 ft for two tank operation.
In accordance with the Surveillance Frequency Control Program
RPV Water Inventory Control 3.5.2 Monticello 3.5.2-4 Amendment No. 205 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.3 (Not Used)
NOTES-----------------------------
- 1. Operation may be through the test return line.
- 2. Credit may be taken for normal system operation to satisfy this SR.
Operate the required ECCS injection/spray subsystem for 10 minutes.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.5
NOTE------------------------------
Vessel injection/spray may be excluded.
Verify the required ECCS injection/spray subsystem can be manually operated.
In accordance with the Surveillance Frequency Control Program SR 3.5.2.6 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
In accordance with the Surveillance Frequency Control Program
PCIVs 3.6.1.3 Monticello 3.6.1.3-5 Amendment No. 205 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow paths with one or more 18 inch primary containment purge and vent valves not within purge and vent valve leakage limits.
D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND D.2
NOTES------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is isolated.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Once per 31 days for isolation devices outside containment E. One or more MSIVs with leakage rate not within limits.
E.1 Restore leakage rate to within limits.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, or D not met.
F.1 Be in MODE 3.
AND F.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-3 Amendment No. 205 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTE-----------------------------
The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.7, SR 3.8.1.9, and SR 3.8.1.11.
The following SRs are applicable for AC sources required to be OPERABLE:
SR 3.8.1.1 SR 3.8.1.5 SR 3.8.1.2 SR 3.8.1.7 SR 3.8.1.3 SR 3.8.1.9 SR 3.8.1.4 SR 3.8.1.11 In accordance with applicable SRs
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 205 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 Application (i.e., initial and supplements)
Safety Evaluation Date September 22, 2020 (ADAMS Accession No. ML20267A139)
January 8, 2021 Principal Contributors to Safety Evaluation Tarico Sweat
1.0 PROPOSED CHANGE
Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (NSPM, the licensee), requested changes to the technical specifications (TSs) for Monticello Nuclear Generating Plant (Monticello) by license amendment request (LAR) dated September 22, 2020 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20267A139). In its application, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the LAR under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the TSs related to reactor pressure vessel (RPV) water inventory control (WIC) based on Technical Specifications Task Force (TSTF) Travelers TSTF-582, Revision 0, RPV WIC Enhancements (TSTF-582)
(ADAMS Accession No. ML19240A260) and TSTF-583-T, Revision 0, TSTF-582 Diesel Generator Variation (TSTF-583-T) (ADAMS Accession No. ML20248H330) and the associated NRC staff safety evaluation (SE) of TSTF-582 (ADAMS Accession No. ML20219A333).
The boiling-water reactor (BWR) RPV design includes multiple penetrations located below the top of active fuel (TAF). These penetrations provide entry for control rods, recirculation flow, reactor water cleanup (RWCU), and shutdown cooling. Since these penetrations are below the TAF, this creates a potential to drain the reactor vessel water inventory and lose effective core cooling. The loss of water inventory and effective core cooling can potentially lead to fuel cladding failure and radioactive release. Drain Time is the time it would take for the water inventory in and above the RPV to drain to the TAF.
1.1 Proposed TS Changes to Adopt TSTF-582 In accordance with NRC staff-approved TSTF-582, the licensee proposed changes that would revise the Monticello TSs related to RPV WIC to incorporate operating experience and to
correct errors and omissions that the licensee incorporated into the TSs when adopting TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (ADAMS Accession No. ML16074A448). Specifically, the licensee proposed the following changes to adopt TSTF-582:
The Drain Time definition in TS 1.1 would be revised to move the examples of common mode failure mechanisms to the Bases and to delete seismic events.
In TS 1.1, Drain Time definition, the exception from considering the Drain Time for penetration flow paths isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position would be revised to apply the exception to manual or automatic valves that are closed and administratively controlled in the closed position.
The Actions of TS 3.3.5.3 would be revised to permit placing an inoperable isolation channel in trip as an alternative to declaring the associated penetration flow path incapable of automatic isolation.
TS 3.3.5.3, Required Action B.2 requires calculating Drain Time with a Completion Time of immediately. The Required Action would be renumbered as A.2.2 and revised to state, Initiate action to calculate DRAIN TIME.
In TS 3.5.2, the first use of the acronym SGT would be defined in Required Action C.3 and the acronym SGT would be used in Required Action D.4.
TS 3.5.2 and TS 3.3.5.3 would be revised to eliminate the requirement for a manual emergency core cooling system (ECCS) initiation signal to start the required ECCS injection/spray subsystem, and to instead rely on manual valve alignment and pump start. TS 3.5.2 Surveillance Requirements (SRs) related to manual initiation using the ECCS signal (such as verifying automatic alignment of valves on an initiation signal) would be eliminated. Related to this change, the TS 3.3.5 functions, SRs, and Actions that only support manual initiation using an ECCS signal (including interlocks and minimum flow instruments) would be eliminated.
SR 3.5.2.4, that requires operating the required ECCS injection/spray subsystem for at least 10 minutes, would be modified by the addition of two notes. The first Note would state that operation may be through the test return line. The second Note would permit crediting normal system operation to satisfy the SR.
TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs), and TS 3.8.2, AC
[Alternating Current] Sources - Shutdown, SR 3.8.2.1, would be revised to not require SRs that test the ability of the emergency diesel generator to start in Modes 4 and 5.
TSTF-542 eliminated the automatic ECCS initiation in Modes 4 and 5.
1.2 Additional Proposed TS Changes 1.2.1 Proposed TS Changes to Adopt TSTF-583-T The licensee proposed to make the following changes in accordance with TSTF-583-T:
TS 3.3.8.1, Loss of Power (LOP) Instrumentation, would be revised to delete When the associated emergency diesel generator (EDG) is required to be OPERABLE by LCO
[Limiting Condition for Operation] 3.8.2, AC Sources - Shutdown. from the Applicability.
SR 3.8.2.1 would be revised to add SR 3.8.1.10 and SR 3.8.1.13 to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. The format of SR 3.8.2.1 would also be restructured to list the SRs that are still applicable, instead of listing the SRs that are not applicable.
1.2.2 Editorial Variations The Monticello TSs use different numbering than the Standard Technical Specifications (STS) on which TSTF-582 was based. Specifically, TS 3.3.5.2, Reactor Pressure Vessel (RPV)
Water Inventory Control Instrumentation, in the STS was numbered as TS 3.3.5.3 in the Monticello TSs.
2.0 REGULATORY EVALUATION
The regulation at Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c)(2) requires that TSs include LCOs. Per 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met.
The regulation at 10 CFR 50.36(c)(3) requires that TSs include items in the category of SRs, which are 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 LCOs will be met.
The NRC staffs guidance for the review of TSs is in Chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition (SRP), March 2010 (ADAMS Accession No. ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the Standard Technical Specifications, General Electric BWR/4 Plants, NUREG-1433, Volume 1, Specifications, and Volume 2, Bases, Revision 4.0, April 2012 (ADAMS Accession Nos. ML12104A192 and ML12104A193, respectively), as modified by NRC staff-approved travelers. NUREG-1433 is based on the BWR/4 plant design and is representative of the BWR/3 design.
Traveler TSTF-582 revised the STSs related to RPV WIC to incorporate operating experience and to correct editorial errors in TSTF-542, Revision 2. The NRC staff approved TSTF-542, Revision 2, on December 20, 2016 (ADAMS Package Accession No. ML16343B066). The NRC
staff approved TSTF-582 under the CLIIP in a letter dated August 13, 2020 (ADAMS Accession No. ML20219A333). The TSTF-582 SE states that a licensee may adopt the STS changes approved in TSTF-582, if the licensee has already adopted the STS changes approved in TSTF-542.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-582 The NRC staff compared the licensees proposed TS changes in Section 1.1 of this SE against the changes approved in TSTF-582. In accordance with Chapter 16.0 of the SRP, the NRC staff determined that the STS changes approved in TSTF-582 are applicable to Monticello TSs because Monticello is a BWR/3 design and the NRC staff approved the TSTF-582 changes for BWR/3 designs. The licensee meets the TSTF-582 SE provision for adoption of TSTF-582 since the licensee was approved to adopt Traveler TSTF-542 on October 9, 2018 (ADAMS Accession No. ML18250A075). Therefore, the NRC staff concludes that the licensees proposed changes to the Monticello TSs in Section 1.1 of this SE are acceptable in that they are consistent with TSTF-582 and the terms for use stated in the NRC staff SE of TSTF-582.
The NRC staff finds that proposed changes to the TS 1.1 definition and LCOs 3.3.5.3, 3.5.2, and 3.6.1.3 correctly specify the lowest functional capability or performance levels of equipment required for safe operation of the facility in accordance with 10 CFR 50.36(c)(2)(i). Also, the NRC staff finds that proposed changes to the Actions of LCOs 3.3.5.3, 3.5.2, and 3.6.1.3 are adequate remedial actions to be taken until each LCO can be met to provide protection to the health and safety of the public, thereby satisfying 10 CFR 50.36(c)(2)(i).
The NRC staff finds that the proposed revisions to the SRs in TS 3.3.5.3, 3.5.2, and 3.8.2 continue to provide 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 LCOs will be met in accordance with 10 CFR 50.36(c)(3).
Thus, the proposed changes continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and 10 CFR 50.36(c)(3) as discussed in Section 3.0 of the NRC staff SE of TSTF-582.
3.2 Additional Proposed TS Changes 3.2.1 Proposed TS Changes to Adopt TSTF-583-T Refer to Section 1.2.1 of this SE for a description of the proposed changes.
3.2.1.1 TS 3.3.8.1, Applicability The licensee stated that Monticello TS 3.8.2 does not require automatic start and loading of an EDG within 10 seconds on an ECCS initiation signal or a loss of offsite power signal. Currently, TS 3.3.8.1 is applicable in Modes 1, 2, and 3, and when the associated EDG is required to be operable by TS 3.8.2. The NRC staff confirmed that TS 3.8.2 no longer requires automatic start and loading of an EDG on an LOP signal. The NRC staff finds it acceptable to revise the Applicability of LCO 3.3.8.1 by deleting When the associated emergency diesel generator (EDG) is required to be OPERABLE by LCO 3.8.2, AC Sources - Shutdown, because the LOP instrumentation that generates the LOP signal does not need to be operable when the EDG is required to be operable by TS 3.8.2. Therefore, the NRC staff concludes that the LCO
applicability changes will continue to provide for the lowest functional capability or performance levels of equipment required for safe operation of the facility and, thus, meet the LCO requirements of 10 CFR 50.36(c)(2).
3.2.1.2 SR 3.8.2.1 LCO 3.8.2 requires one offsite circuit and one EDG capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8 to be operable in shutdown conditions. The existing Monticello SR 3.8.2.1 lists the TS 3.8.1 SRs that are applicable in shutdown conditions with some exceptions.
TS SR 3.8.1.10 requires that the EDG starts and achieves required voltage and frequency within 10 seconds and required steady state voltage and frequency ranges. The 10-second start requirement associated with the EDG automatic start supports the assumptions in the design basis loss-of-coolant accident analysis. The NRC staff confirmed that 10-second timing is not required during a manual EDG start to respond to a draining event, which has a minimum Drain Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. In addition, SR 3.8.1.2, which requires the EDG to start from standby conditions and achieve the required steady state voltage and frequency ranges, is applicable under SR 3.8.2. The NRC staff finds that the SR 3.8.1.10 testing for the EDGs capability to achieve required steady state voltage and frequency ranges will be performed in SR 3.8.1.2 since SR 3.8.1.2 provides the test for this EDG capability. Therefore, the NRC staff finds it acceptable to add SR 3.8.1.10 to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1.
TS SR 3.8.1.13 states, Verify interval between each sequenced load block is greater than or equal to the minimum design load interval. This SR verifies the load sequence time interval tolerance between each sequenced load block when loads are sequentially connected to the engineered safety features (ESF) bus by an automatic sequencer while the EDG is tied to the ESF bus. TS 3.5.2 requires manual starting of the equipment for water injection to respond to a draining event so that the EDG will be manually loaded during a draining event. No other postulated events require automatic loading of the EDG during shutdown conditions. The NRC staff confirmed that with respect to SR 3.8.13, the load sequencer is used for the automatic loading of the EDG and is not used during a manual loading of the EDG. Therefore, the NRC staff finds it acceptable to add SR 3.8.1.13 to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1.
The NRC staff finds that the proposed changes to revise SR 3.8.2.1 are acceptable because the remaining applicable SRs will continue to demonstrate the operability of the required AC power sources and, as such, ensure the availability of the AC power required to operate the plant in a safe manner and mitigate postulated events during shutdown conditions. Therefore, the NRC staff finds the proposed changes to SR 3.8.2.1 acceptable because the changes continue to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the associated LCO will continue to be met in accordance with 10 CFR 50.36(c)(3).
3.2.2 Editorial The licensee noted that the Monticello TSs have different numbering than the STS for the RPV WIC related TSs. The NRC staff finds that the different TS numbering changes are acceptable because they are editorial clarifications and do not substantively change TS requirements.
Finally, the NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are, therefore, acceptable.
4.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 205 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 Application (i.e., initial and supplements)
Safety Evaluation Date September 22, 2020 (ADAMS Accession No. ML20267A139)
January 8, 2021
1.0 INTRODUCTION
Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested changes to the technical specifications (TSs) for Monticello Nuclear Generating Plant by license amendment request dated September 22, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20267A139). The proposed changes would revise the TSs related to reactor pressure vessel (RPV) water inventory control (WIC) based on Technical Specifications Task Force (TSTF) Travelers TSTF-582, Revision 0, RPV WIC Enhancements, (ADAMS Accession No. ML19240A260) and TSTF-583-T, Revision 0, TSTF-582 Diesel Generator Variation, (ADAMS Accession No. ML20248H330) and the associated NRC staff safety evaluation of TSTF-582 (ADAMS Accession No. ML20219A333).
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Minnesota State official was notified of the proposed issuance of the amendment on December 16, 2020. The State official had no comments.
3.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (85 FR 69655; November 3, 2020). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
ML20352A349 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NAME RKuntz SRohrer (JBurkhardt for)
VCusumano DATE 12/16/2020 12/18/2020 12/15/2020 OFFICE OGC NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME JWachutka NSalgado (JWiebe for)
RKuntz DATE 01/06/2021 01/08/2021 01/08/2021