ML19186A205

Issuance of Amendment No. 217 Remote Shutdown System

ML19186A205
Person / Time
Site:	Hope Creek
Issue date:	08/06/2019
From:	James Kim Plant Licensing Branch 1
To:	Carr E Public Service Enterprise Group
Kim J, NRR/DORL, 301-415-4125
References
EPID L-2018-LLA-0295
Download: ML19186A205 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C. 20555-0001 August 6, 2019 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT NO. 217 RE: REMOTE SHUTDOWN SYSTEM (EPID L-2018-LLA-0295)

Dear Mr. Carr:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 217 to Renewed Facility Operating License No. NPF-57 for the Hope Creek Generating Station (Hope Creek) in response to your application dated October 30, 2018.

The amendment revises Technical Specification 3.3.7.4, "Remote Shutdown System Instrumentation and Controls," to make the Hope Creek Generating Station requirements consistent with Standard Technical Specification 3.3.3.2, "Remote Shutdown System" in NUREG-1433, Volume 1, Revision 4. The change increases the allowed outage time for inoperable remote shutdown system components to a time that is more consistent with their safety significance. Also, the amendment deletes Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1, and relocates them to the Technical Requirements Manual where they will be directly controlled by Hope Creek.

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

Sincerely, James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosures:

1. Amendment No. 217 to Renewed License No. NPF-57

2. Safety Evaluation cc: Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 Renewed License No. NPF-57

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

A. The application for amendment filed by PSEG Nuclear LLC dated October 30, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment Gan be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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 Facility Operating License No. NPF-57 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 217, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

• The license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jame 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: August 6, 2019

ATTACHMENT TO LICENSE AMENDMENT NO. 217 HOPE CREEK GENERATING STATION RENEWED FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following page of the Renewed Facility Operating License with the revised page.

The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove 3

Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert viii viii ix ix 3/4 3-74 3/4 3-74 3/4 3-75 3/4 3-75 through 3/4 3-83 3/4 3-76 (deletion page) 3/4 3-77 3/4 3-78 3/4 3-79 3/4 3-80 3/4 3-81 3/4 3-82 3/4 3-83

reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) PSEG Nuclear 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) PSEG Nuclear 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) PSEG Nuclear 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. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation.

(7) PSEG Nuclear LLC, pursuant to the Act and 10 CFR Part 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's 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 PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3902 megawatts thermal ( 100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 217, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-57 Amendment No. 217

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Table 3.3.5-1 Reactor Core Isolation Cooling System Actuation Instrumentation . . . . . . . . . . . . . . . . . . . . 3/4 3-52 Table 3.3.5-2 Reactor Core Isolation Cooling System Actuation Instrumentation Setpoints .......... 3/4 3-54 Table 4.3.5.1-1 Reactor Core Isolation Cooling System Actuation Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-55 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-56 Table 3.3.6-1 Control Rod Block Instrumentation ............ 3/4 3-57 Table 3.3.6-2 Control Rod Block Instrumentation Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 3-59 Table 4.3.6-1 Control Rod Block Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . . . 3/4 3-60 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-62 Table 3.3.7.1-1 Radiation Monitoring Instrumentation ....... 3/4 3-63 Table 4.3.7.1-1 Radiation Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . . . 3/4 3-66 Remote Shutdown System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 3-7 4 HOPE CREEK viii Amendment No. 217

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Accident Monitoring Instrumentation . . . . . 3/4 3-84 Table 3.3.7.5-1 Accident Monitoring Instrumentation . . . . . 3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements 3/4 3-87 Source Range Monitors . . 3/4 3-88 3/4.3.8 DELETED . . . . . . . . . . 3/4 3-103 3/4.3.9 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-105 Table 3.3.9-1 Feedwater/Main Turbine Trip System Actuation Instrumentation . . . . . 3/4 3-106 HOPE CREEK ix Amendment No. 217

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.4 The remote shutdown system functions shall be OPERABLE.

APPLICABILITY OPERATIONAL CONDITIONS 1 and 2.

---

NOTE--------------------------------------------------------

Sepa rate ACTION entry is allowed for each Function ACTION:

a. With one or more of the required functions inoperable, restore the inoperable function(s) to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.7.4.1 Each normally energized required instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at the frequency specified in the Surveillance Frequency Control Program.

4.3.7.4.2 Each required control circuit and transfer switch shall be demonstrated OPERABLE by verifying its capability to perform its intended function in accordance with the Surveillance Frequency Control Program.

4.3.7.4.3 Each required instrumentation channel° shall be demonstrated OPERABLE by performance of a CHANNEL CALIBRATION at the frequency specified in the Surveillance Frequency Control Program.

Safety Relief Valve Position, Standby Diesel Generator Breaker Indication, and Switchgear Room Cooler Status Indication are excluded from CHANNEL CALIBRATION.

HOPE CREEK 3/4 3-74 Amendment No. 217

Pages 3/4 3-75 through 3/4 3-83 intentionally deleted HOPE CREEK 3/4 3-75 through 3/4 3-83 Amendment No. 217

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 217 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-57 PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354

1.0 INTRODUCTION

By letter dated October 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18304A191), PSEG Nuclear LLC (the licensee) requested U.S. Nuclear Regulatory Commission (NRC or the Commission) approval for a license amendment request (LAR) to revise the Hope Creek Generating Station (Hope Creek)

Technical Specifications (TSs). The LAR proposes to revise TS 3.3.7.4, "Remote Shutdown System Instrumentation and Controls," to make the Hope Creek requirements consistent with Standard Technical Specification (STS) 3.3.3.2, "Remote Shutdown System." The change would increase the allowed outage time for inoperable remote shutdown system components from 7 days to 30 days. Also, the amendment would delete Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1, and relocate them to the Technical Requirements Manual (TRM) where they would be directly controlled by Hope Creek.

2.0 REGULATORY EVALUATION

2.1 Description of the Remote Shutdown System The remote shutdown system (RSS) provides the means for achieving and maintaining safe shutdown conditions from outside the main control room in the unlikely event that the main control room becomes uninhabitable. The primary control station for the RSS is the remote shutdown panel. In the event of a failure at the remote shutdown panel, sufficient redundant safety grade instrumentation and controls are available remotely from both the main control room and the remote shutdown panel to ensure that safe shutdown of the reactor can be achieved in accordance with the requirements of Title 10 of the Code of Federal Regulations (1 O CFR), Part 50, Appendix A, "General Design Criteria [GDC] for Nuclear Power Plants,"

Criterion 19 (GDC 19).

2.2.1 Description of Proposed Changes

1. Revise TS 3.3. 7.4 Limiting Condition for Operation (LCO) to state that the Remote Shutdown System functions shall be OPERABLE. Delete references to Enclosure 2

Tables 3.3. 7.4-1 and 3.3.7.4-2 listing the specific instruments and controls for the remote shutdown system. The proposed change will relocate information in these tables to licensee-controlled documents.

2. Revise TS 3.3.7.4 ACTION a. to delete the reference to monitoring instrumentation channels as shown in the associated Table 3.3.7.4-1. The action will be simplified to state the entry condition for the action as "one or more of the required functions inoperable." Add a note to permit separate condition entry for each function.

3. Revise TS 3.3.7.4 ACTION a. to change the required action time from 7 days to 30 days.

4. Delete TS 3.3. 7.4 ACTION b.

5. Delete Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1, and relocate the remote shutdown system equipment information to the TRM.

6. Revise Surveillance Requirement (SR) 4.3. 7.4.1 to:

a) delete reference to Table 4.3.7.4-1, which is being deleted; b) relocate channel calibration to a new SR 4.3.7.4.3; c) require the channel check only for normally energized remote shutdown system instrumentation; and e) replace "the" with "a."

7. Revise SR 4.3.7.4.2 replacing "At least one of each of the above remote shutdown switch(es) and control circuits" with "each required control circuit and transfer switch."

8. Add new section SR 4.3.7.4.3, stating the following: "Each required instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CALIBRATION at the frequency specified in the Surveillance Frequency Control Program."

9. Add a note to SR 4.3.7.4.3 that the safety relief valve position, standby diesel generator breaker indication, and switchgear room cooler status indication are excluded from channel calibration;

10. Revise TS Index pages viii and ix to reflect the TS Section 3.3.7.4 title and deletion of the tables.

2.3 Regulatory Requirements Section 50.36 of 10 CFR, "Technical specifications," identifies the requirements for the TS categories for operating power plants. Of the six requirements, the following two are applicable to this review:

• 10 CFR 50.36(c)(2) states, in part:

Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.

When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.

• 10 CFR 50.36(c)(3) states:

Surveillance requirements 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 limiting conditions for operation will be met.

Appendix A to 10 CFR Part 50, GDC 19, "Control room," states, in part:

Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.

2.4 Regulatory Guidance NUREG-1433, Volume 1, Revision 4, "Standard Technical Specifications, General Electric BWR/4 Plants" (ADAMS Accession No. ML12104A192).

3.0 TECHNICAL EVALUATION

3.1 Revision to TS 3.3.7.4 LCO for the Remote Shutdown System GDC 19 requires that the licensee provide remote shutdown capability. The remote shutdown system functions are described in the Updated Final Safety Analysis Report.

The licensee has requested a revision to TS 3.3. 7.4 LCO to state that the remote shutdown system functions shall be operable. The revision would delete references to instrumentation as shown in the associated Tables 3.3.7.4-1 and 3.3.7.4-2. In Section 3.3.7.4 of the current TSs, Tables 3.3. 7.4-1, 3.3. 7.4-2, and 4.3. 7.4-1 list the specific instruments and controls for the remote shutdown system. The proposed change would relocate these requirements to licensee-controlled documents.

The definition of operable in NUREG-1433 states that a system shall be operable or have operability "when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system to perform its specified safety function(s) are also capable of performing their related support function." This definition provides adequate guidance for determining what instrumentation and controls are necessary for a particular remote shutdown function. The ability to transfer control of a function from the main control room to the auxiliary shutdown panel is a required support function by the TS definition of operable. Therefore, listing specific instrumentation and controls is unnecessary

and may lead to needless expenditure of licensee and NRC resources, processing license amendments to revise the remote shutdown system details in TS Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1. These details are not necessary to describe the actual regulatory requirements.

Moreover, SR 4.3. 7.4.2 still requires the local panel transfer function to be tested, which is sufficient to assure that the system will be operable. Relocation of the list of variables to the TRM is acceptable because the TRM is consistent with the design basis as described in the Updated Final Safety Analysis Report. Therefore, it can be relocated to the TRM without a significant safety impact. Changes to the TRM are evaluated in accordance with 10 CFR 50.59 requirements.

In addition, precedent for the relocation has been established with Technical Specifications Task Force (TSTF} Traveler TSTF-266, "Eliminate the Remote Shutdown System Table of Instrumentation and Controls," and Revision 2 of NUREG-1433, which incorporated TSTF-266 into the Improved STS. Moreover, relocation of the subject list of variables to the TRM is acceptable because its inclusion in the TSs does not fall within the criteria for mandatory inclusion in the TSs in 10 CFR 50.36(c)(2)(ii). The NRC staff finds that sufficient regulatory controls exist under the regulations to maintain the effect of the provisions in the TRM. Based on the above evaluation, the NRC staff finds that the proposed change is acceptable.

3.2 Revision to TS 3.3.7.4 Action The licensee has proposed a revision to TS 3.3. 7.4 ACTION a. to delete the reference to monitoring instrumentation channels as shown in the associated Table 3.3.7.4-1. The action will be simplified to state the entry condition for the action as:

With one or more of the required functions inoperable, restore the inoperable function to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />." A note would be added to permit "Separate ACTION entry is allowed for each Function.

The proposed deletion of the references to monitoring instrumentation is acceptable for the reasons discussed in Section 3.1 above. Adding a note of "Separate ACTION entry is allowed for each Function," to the current TS would permit separate entry into the required action, should more than one function be inoperable. Without the proposed note, the new wording could be interpreted as not allowing separate entry for each function; thus, entry into the required actions for an inoperable channel of a second function would result in a plant shutdown per LCO 3.0.3. The proposed note is consistent with NUREG-1433. The NRC staff finds that these changes will ensure that the inoperable equipment is restored to an operable status and conversely provide reasonable assurance that the licensee will comply with the regulations.

3.3 TS 3.3. 7.4 Action Time Change The licensee proposed to revise TS 3.3. 7.4 ACTION a. to change the required action time from 7 days to 30 days.

The proposed change in action time from 7 days to 30 days is based on operating experience and the low probability of an event occurring that would require the control room to be evacuated. In addition, precedent for extending the allowed outage time to 30 days has been established with TSTF-266 and Revision 2 of NUREG-1433, which incorporated TSTF-266 into the Improved STS. The NRC staff finds that this proposed change is acceptable.

3.4 Deletion of TS 3.3.7.4 Action The licensee proposed to delete TS 3.3.7.4 ACTION b., which states:

With the number of OPERABLE remote shutdown system controls less than required in Table 3.3.7.4-2, restore the inoperable control(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Table 3.3.7.4-2 is being deleted, as discussed in Section 3.1 above, and relocated to a licensee-controlled document; reference to it is no longer applicable. TS 3.3.7.4 ACTION a.

was revised to add the wording "one or more required functions," which now encompasses the required actions of TS 3.3. 7.4 ACTION b. ACTION a. will continue to meet the requirements for an inoperable remote shutdown system control; therefore, TS 3.3. 7.4 ACTION b. is no longer needed. The NRC staff finds that this proposed change is acceptable.

3.5 Deletion of Tables 3.3.7.4-1, 3.3.7.4-2, and 4.3.7.4-1 The licensee has proposed to delete Tables 3.3. 7.4-1, 3.3. 7.4-2, and 4.3. 7.4-1 and relocate the remote shutdown system equipment information to the TRM. The NRC staff reviewed the proposed changes and found them acceptable for the reasons discussed in Section 3.1 above.

3.6 Revisions to SR 4.3. 7.4.1 and add SR 4.3. 7.4.3 The NRC staff's evaluation of the licensee-proposed changes to SR 4.3.7.4.1 and the addition of SR 4.3.7.4.3 is as follows:

a) The licensee proposed to remove reference to Table 4.3. 7.4-1, which was proposed to be deleted. The NRC staff finds this change acceptable for reasons discussed in Section 3.1 above.

b) The licensee proposed to relocate channel calibration to a new SR 4.3.7.4.3.

Currently, the SR to perform a channel calibration is located in SR 4.3.7.4.1.

The licensee stated in the LAR that splitting out the channel calibration into a new SR (4.3.7.4.3) and rewording the SR makes it consistent with the Improved STS. The NRC staff reviewed the change and determined that relocating the channel calibration to SR 4.3. 7.4.3 continues to meet the requirements of 10 CFR 50.36(c)(3) for channel calibration of instrument channels because the proposed SR effectively maintains the existing TS requirement for a channel calibration. Therefore, the change is acceptable.

c) The licensee proposed to add the statement "normally energized" to SR 4.3.7.4.1. This change would require the channel check only for normally energized remote shutdown system instrumentation. The licensee stated in the LAR that performing a channel check of normally deenergized instrumentation is not practical or feasible during power operation. This change is consistent with Improved STS SR 3.3.3.2.1. The NRC staff finds the proposed change to the TS acceptable.

d) Add a note to SR 4.3. 7.4.3 that the safety relief valve position, standby diesel generator breaker indication, and switchgear room cooler status indication are

excluded from channel calibration. The note makes the remote shutdown system consistent with the requirements already established for safety relief valve position, standby diesel generator breaker indication, and switchgear room cooler status indication in current TS Table 4.3. 7.4-1. The NRC staff finds the proposed change to the TS acceptable.

e) Replace "the" with "a" in SR 4.3.7.4.1. This is an administrative change to ensure that, with the revisions mentioned above, the SR remains grammatically correct. Therefore, the proposed change is acceptable.

3.7 Revisions to SR 4.3.7.4.2 The licensee proposed to revise SR 4.3. 7.4.2 by replacing "At least one of each of the above remote shutdown switch(es) and control circuits" with "each required control circuit and transfer switch." The licensee stated that these changes make the SR wording consistent with Improved STS SR 3.3.3.2 and reflect the removal of TS Table 3.3. 7.4-2. The NRC staff reviewed the changes and determined that the proposed revision to SR 4.3. 7.4.2 is functionally equivalent to the existing SR and demonstrated that the required control circuit and control switch be operable. Therefore, the NRC staff finds this change acceptable.

3.8 Revisions to TS Index Pages The licensee proposed to revise TS Index pages viii and ix to reflect the TS Section 3.3.7.4 title and the deletion of the tables. This change is being made for consistency, does not affect any requirements associated with the remote shutdown system, and is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment on June 7, 2019. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes requirements with respect to installation or use of a facility component 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 (83 FR 64897). 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 Commission's 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 Contributor: T. Sweat Date: August 6, 2019

SUBJECT:

HOPE CREEK GENERATING STATION - ISSUANCE OF AMENDMENT NO. 217 RE: REMOTE SHUTDOWN SYSTEM (EPID L-2018-LLA-0295)

DATED AUGUST 6, 2019 DISTRIBUTION:

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NAME JKim KEntz LRonewicz PSnyder DATE 07/19/2019 07/16/2019 07/19/2019 07/01/2019 OFFICE OGC- NLO** NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME JScro Joanna JKim DATE 07/30/2019 08/02/2019 08/06/2019 OFFICIAL RECORD COPY