Text

Issuance of Amendment No. 165 Emergency Core Cooling System Accumulator Technical Specification Changes
	ML20070Q071
Person / Time
Site:	Seabrook
Issue date:	03/27/2020
From:	Justin Poole; Plant Licensing Branch 1
To:	Moul D; Florida Power & Light Energy Seabrook
	Poole J
References
	EPID L-2019-LLA-0117
	Download: ML20070Q071 (15)
	v • d • e

March 27, 2020 Mr. Don Moul Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company NextEra Energy Seabrook, LLC Mail Stop: NT3/JW 15430 Endeavor Drive Jupiter, FL 33478

SUBJECT:

SEABROOK STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT NO. 165 RE: EMERGENCY CORE COOLING SYSTEM ACCUMULATOR TECHNICAL SPECIFICATION CHANGES (EPID L-2019-LLA-0117)

Dear Mr. Moul:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 165 to Renewed Facility Operating License No. NPF-86 for the Seabrook Station, Unit No. 1. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated June 4, 2019.

The amendment modifies the TSs associated with the emergency core cooling system accumulators. Specifically, the amendment modifies the TS actions for an inoperable accumulator, relocates the actions for inoperable accumulator instrumentation, and deletes an unnecessary surveillance requirement. The amendment also deletes a duplicate surveillance requirement associated with the accumulator isolation valves.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

Justin C. Poole, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosures:

1. Amendment No. 165 to NPF-86

2. Safety Evaluation cc: Listserv

NEXTERA ENERGY SEABROOK, LLC, ET AL.*

DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 165 Renewed License No. NPF-86

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

A. The application for amendment filed by NextEra Energy Seabrook, LLC, et al.

(the licensee), dated June 4, 2019, 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.

NextEra Energy Seabrook, LLC, is authorized to act as agent for the: Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, and Taunton Municipal Lighting Plant and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

Enclosure 1

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. NPF-86 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 165, are incorporated into the Renewed Facility Operating License No. NPF-86. NextEra Energy Seabrook, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 27, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 165 SEABROOK STATION, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following page of Renewed Facility Operating License No. NPF-86 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 3 3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Insert 3/4 5-1 3/4 5-1 3/4 5-2 3/4 5-2 3/4 5-5 3/4 5-5

(3) NextEra Energy Seabrook, LLC, pursuant to the Act and 10 CFR Part 70, 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 operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) NextEra Energy Seabrook, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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; (5) NextEra Energy Seabrook, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, 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 (6) NextEra Energy Seabrook, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.

(7) DELETED C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth 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 NextEra Energy Seabrook, LLC, is authorized to operate the facility at reactor core power levels not in excess of 3648 megawatts thermal (100% of rated power).

(2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 165, are incorporated into the Renewed Facility Operating License No. NPF-86. NextEra Energy Seabrook, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS HOT STANDBY, STARTUP, AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.5.1.1 Each Reactor Coolant System (RCS) accumulator shall be OPERABLE with:

a. The isolation valve open and power removed,

b. A contained borated water volume of between 6121 and 6596 gallons,

c. A boron concentration of between the limits specified in the COLR, and

d. A nitrogen cover-pressure of between 585 and 664 psig.

APPLICABILITY: MODES 1, 2, and 3*

ACTION:

a. With one accumulator inoperable, except due to boron concentration not within limits, restore the inoperable accumulator to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one accumulator inoperable due to boron concentration not within limits, restore boron concentration to within limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1.1 Each accumulator shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by:

1) Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and

Pressurizer pressure above 1000 psig.

SEABROOK - UNIT 1 3/4 5-1 Amendment No. 30, 42, 96, 141, 165

EMERGENCY CORE COOLING SYSTEMS ACCUMULATORS HOT STANDBY, STARTUP, AND POWER OPERATION SURVEILLANCE REQUIREMENTS 4.5.1.1 (Continued)

2) Verifying that each accumulator isolation valve is open.

b. By verifying the boron concentration of the accumulator solution under the following conditions:

1) In accordance with the Surveillance Frequency Control Program,

2) Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 1% of tank volume. This surveillance is not required when the volume increase makeup source is the RWST and the RWST has not been diluted since verifying that the RWST boron concentration is equal to or greater than the accumulator boron concentration limit.

c. In accordance with the Surveillance Frequency Control Program when the RCS pressure is above 1000 psig by verifying that power to the isolation valve operator is disconnected.

SEABROOK - UNIT 1 3/4 5-2 Amendment No. 30, 141, 165

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg GREATER THAN OR EQUAL TO 350ºF SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position SI-V-114 SI Pump to Cold-Leg Isolation Open RH-V-14 RHR Pump to Cold-Leg Isolation Open RH-V-26 RHR Pump to Cold-Leg Isolation Open RH-V-32 RHR to Hot-Leg Isolation Closed RH-V-70 RHR to Hot-Leg Isolation Closed SI-V-77 SI to Hot-Leg Isolation Closed SI-V-102 SI to Hot-Leg Isolation Closed

b. In accordance with the Surveillance Frequency Control Program by:

1) Verifying ECCS locations susceptible to gas accumulation are sufficiently filled with water, and

2) Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.**

c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:

1) For all accessible areas of the containment prior to establishing primary CONTAINMENT INTEGRITY, and

2) At least once daily of the areas affected within containment by containment entry and during the final entry when primary CONTAINMENT INTEGRITY is established.

- Not required to be met for system vent flow paths opened under administrative control.

SEABROOK - UNIT 1 3/4 5-5 Amendment No. 30, 58, 61, 141, 144, 165

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 165 TO FACILITY OPERATING LICENSE NO. NPF-86 NEXTERA ENERGY SEABROOK, LLC SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443

1.0 INTRODUCTION

By letter dated June 4, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19157A057), NextEra Energy Seabrook, LLC (the licensee) submitted License Amendment Request No. 19-01, requesting changes to the Technical Specifications (TSs) for Seabrook Station, Unit No. 1 (Seabrook).

The amendment would modify the TSs associated with the emergency core cooling system (ECCS) accumulators. Specifically, the amendment would modify the TS actions for an inoperable accumulator, relocate the actions for inoperable accumulator instrumentation, and delete an unnecessary surveillance requirement (SR). The amendment would also delete a duplicate SR associated with the accumulator isolation valves.

2.0 REGULATORY EVALUATION

2.1 Applicable Regulatory Requirements and Guidance The regulatory requirements and guidance documents that the U.S. Nuclear Regulatory Commission (NRC or the Commission) staff considered in its review of the proposed amendment included the following:

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The NRCs regulatory requirements related to the content of the TSs are contained in Section 50.36, Technical specifications, of Title 10 of the Code of Federal Regulations (10 CFR), which requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design; and (5) administrative controls. However, the regulation does not specify the particular requirements to be included in TSs. LCOs specify minimum requirements for ensuring safe operation of the unit. The TSs state conditions that typically describe the ways in which the requirements of the LCO can Enclosure 2

fail to be met and provide remedial actions when the conditions are not met. Specified with each stated condition are the required action(s) and associated completion time(s) for performing the required actions. SRs are requirements related to test, calibration, or inspection that are performed to assure that the LCOs will be met.

The regulations in 10 CFR 50.46 mandates acceptable criteria for ECCSs for light-water nuclear power reactors.

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, dated March 2010 (ADAMS Accession No. ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared standard technical specifications (STS) for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with the applicable referenced STS (i.e., the current STS), as modified by NRC-approved travelers. In addition, the guidance states that comparing the change to previous STS can help clarify the TSs intent.

WCAP-15049, Risk-Informed Evaluation of an Extension to Accumulator Completion Times, evaluated the risk associated with extending the accumulator completion time from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when an accumulator is declared inoperable for reasons other than its boron concentration being out of specification. The NRC staff approved WCAP-15049 in February 1999.

TSTF-370, Increase Accumulator Completion Time from 1 Hour to 24 Hours (WCAP-15049). The NRC staff, following the consolidated line item improvement process (CLIIP), issued a notice of opportunity for comment on the model safety evaluation and a model no significant hazards consideration determination dated July 15, 2002; 67 FR 46542), and subsequently issued a notice of availability of the models for referencing in license amendment requests using the CLIIP (March 12, 2003; 68 FR 11880).

2.2 System Description Accumulators are pressurized vessels filled with borated water that function to supply water to the reactor vessel during a loss-of-coolant accident (LOCA). They are a passive safety system that activate once the reactor vessel pressure drops below the accumulator pressure, piping water into the reactor coolant system (RCS) cold leg through an accumulator line. This line is separated from the RCS by a motor-operated isolation valve and two check valves in series.

Three of the four accumulators must be functioning to ensure adequate coverage of the core during a LOCA.

2.3 Description of TS Changes 2.3.1 Proposed Changes to TS 3.5.1.1 The additions are in bold and deletions are stricken.

ACTION:

a. With one accumulator inoperable, except due to boron concentration not within limits as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within 24 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one accumulator inoperable due to boron concentration not within limits the isolation valve being dosed, restore boron concentration to within limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months either immediately open the isolation valve or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With one pressure or water level channel inoperable per accumulator, return the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d. With two pressure channels or two water level channels inoperable per accumulator, immediately declare the affected accumulator(s) inoperable.

SURVEILLANCE REQUIREMENTS 4.5.1.1.1 Each accumulator shall be demonstrated OPERABLE:

d. In accordance with the Surveillance Frequency Control Program by verifying that each accumulator isolation valve opens automatically under each of the following conditions:

1) When an actual or simulated RCS pressure signal exceeds the P-11 (Pressurizer Pressure Block of Safety Injection)

Setpoint, and

2) Upon receipt of a Safety Injection test signal.

2.3.2 Proposed Changes to TS 3/4.5.2 The deletions are stricken.

4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position SI-V-3 Accumulator Isolation Open*

SI-V-17 Accumulator Isolation Open*

SI-V-32 Accumulator Isolation Open*

SI-V-47 Accumulator Isolation Open*

SI-V-114 SI Pump to Cold-Leg Isolation Open RH-V-14 RHR Pump to Cold-Leg Isolation Open RH-V-26 RHR Pump to Cold-Leg Isolation Open RH-V-32 RHR to Hot-Leg Isolation Closed RH-V-70 RHR to Hot-Leg Isolation Closed SI-V-77 SI to Hot-Leg Isolation Closed SI-V-102 SI to Hot-Leg Isolation Closed

Pressurizer pressure above 1000 psig.

3.0 TECHNICAL EVALUATION

3.1 Background

Seabrook requests to update its TS 3/4.5.1, Accumulators, to be consistent with the STS, and specifically, TS 3.5.1, Accumulators, described in NUREG-1431, Standard Technical Specifications - Westinghouse Plants, and TSTF-370. In addition to this change, the licensee requests to remove TS actions for inoperable accumulator pressure and level instrumentation, remove the SR that verifies certain accumulator discharge isolation valves are capable of automatically opening, and remove a redundant SR regarding verifying accumulator valve position.

3.2 Changes to TS 3.5.1.1 ECCS accumulators can be inoperable for numerous reasons, including those conditions that are addressed by SRs, including borated water volume, boron concentration, nitrogen cover pressure, and a closed isolation valve. NUREG-1431 TS 3.5.1 addresses accumulator inoperability for two conditions: (1) boron concentration not within limits, and (2) inoperability for reasons other than boron concentration not within limits. The STS completion time for restoring accumulator operability with boron concentration outside limits is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . One accumulator below the minimum boron concentration limit, however, will have no effect on available ECCS water and an insignificant effect on core subcriticality during re-flood. Boiling of ECCS water in the core during re-flood concentrates boron in the saturated liquid that remains in the core.

Therefore, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is a reasonable period to return boron concentration to within limits. With an accumulator inoperable for reasons other than boron concentration not within limits the STS provides 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore accumulator operability as permitted in TSTF-370 which was justified in WCAP-15049-A.

WCAP-15049-A describes the risks of changing the accumulator completion time from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when an accumulator is determined inoperable due to reasons other than improper boron concentration. WCAP-15049-A was approved by the NRC in February 1999 in order to reduce the burden on the operators. It was determined that the 1-hour competition time would be insufficient in most cases for a licensee to respond appropriately to an inoperable accumulator. As stated in WCAP-15049-A, this change has no deterministic safety significance, and therefore, is acceptable.

Seabrook TS 3.5.1.1 currently addresses accumulator inoperability by two conditions: (1) due to a closed isolation valve and (2) for reasons other than a closed isolation valve, with completion times of immediately and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , respectively. TS 3.5.1.1 is revised to be consistent with NUREG-1431 and TSTF-370. Seabrook TS 3.5.1.1 currently does not contain an action that specifically addresses the condition that accumulator boron is not within limits, although it does have a surveillance on boron concentration. In this case, when boron concentration is not within limits, entry into the condition for reasons other than a closed isolation valve would be required. However, since Action a is revised to address all causes of accumulator inoperability excluding boron concentration, Action b is modified to address the condition that accumulator boron concentration is not within limits. In the revised case, if inoperability is due to a closed isolation valve, then entry into the condition for reasons other than boron concentration not within limits would be required.

In addition to revising the actions for accumulator inoperability, including extending the completion time for an inoperable accumulator, the change removes the TS actions (Actions c and d) for inoperable accumulator pressure and level instrumentation because the instrumentation does not meet the criteria for mandatory inclusion in the TSs. Generic Letter 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation, recommends relocating the accumulator pressure and level instrumentation SRs from the STS as summarized below:

The NRC staff and industry effort to develop new STS recognized that accumulator instrumentation operability is not directly related to the capability of the accumulators to perform their safety function. Therefore, surveillance requirements for this instrumentation are being relocated from the new STS, and the only surveillance that is being retained is that required to confirm that the parameters defining accumulator operability are within their specified limits.

Based on the above, the NRC staff finds that removing Actions c and d from the Seabrook TS is acceptable.

In the STS, if two accumulators are inoperable, there is an explicit Condition D in TS 3.5.1 that requires entry into LCO 3.0.3 to shut down the unit. Seabrook TS 3.5.1.1 does not have an explicit condition for LCO 3.0.3 entry. However, since there is no condition addressing two inoperable accumulators, the default action is to enter LCO 3.0., which is equivalent to the STS.

Another change in the application is to remove SR 4.5.1.1.d. This SR verifies that each accumulator isolation valve automatically opens when RCS pressure exceeds the P-11 (permissive for pressurizer pressure block of safety injection) setpoint and upon receipt of a safety injection (SI) signal. Since the isolation valves are open with power removed during plant operation and required periodic surveillances verify that power to the valve motor operators is removed, the valves are open, and no position alarms are present, the possibility of inadvertent closure of the isolation valves is eliminated. Because the valves are energized for only brief intervals to change valve position during startup or shutdown, the automatic actuation features to assure the valves will open when required serve no useful function. Thus, the NRC staff finds that periodic testing per SR 4.5.1.1.d is not required, and deletion of the SR is acceptable.

3.3 Changes to TS 3.5.2 NextEra Energy Seabrook, LLC requests to revise SR 4.5.2.a to remove valves SI-V-3, SI-V-17, SI-V-32, and SI-V-47 from the table, as these valves correspond to accumulator isolation valves

whose status is already accounted for in SR 4.5.1.1.a.2 and SR 4.5.1.1.c. SR 4.5.2.a duplicates the requirements of SR 4.5.1.1.a.2, which verifies that each accumulator isolation valve is open, and SR 4.5.1.1.c, which verifies that power to the accumulator isolation valves operators is removed when RCS pressure is above 1,000 pounds per square inch gauge (psig). The NRC staff agrees that having these valves in SR 4.5.2.a duplicates the requirements of SR 4.5.1.1.a.2 and SR 4.5.1.1.c, and therefore, the staff finds the removal of the specified valves from SR 4.5.2.a to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the State of New Hampshire and Commonwealth of Massachusetts officials were notified of the proposed issuance of the amendment on March 13, 2020. The officials had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.

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 published in the Federal Register on August 29, 2019 (84 FR 45545). 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.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) 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.

Principal Contributors: D. Woodyatt B. Tjader Date: March 27, 2020

ML20070Q071 *by e-mail OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DSS/SNSB/BC(A)* NRR/DSS/STSB/BC*

NAME JPoole LRonewicz JBorromeo VCusumano DATE 03/16/2020 03/13/2020 01/13/2020 10/25/2019 OFFICE OGC - NLO* NRR/DORL/LPL1/BC* NRR/DORL/LPL1/PM*

NAME DRoth JDanna JPoole DATE 03/16/2020 03/17/2020 03/27/2020

v t e Letter Sequence Approval
EPID:L-2019-LLA-0117, (Approved, Closed)
Initiation Acceptance Administration Questions Answers Results Approval Other:
MONTHYEAR2019-07-15 [Table View]

ML20070Q071