ML17121A510

Issuance of Amendment License Amendment Request for Editorial and Administrative Changes to Technical Specifications

ML17121A510
Person / Time
Site:	Palisades
Issue date:	06/08/2017
From:	Jennivine Rankin Plant Licensing Branch III
To:	Entergy Nuclear Operations
Rankin J, NRR/DORL/LPL3, 415-1530
References
CAC MF8796
Download: ML17121A510 (13)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 8, 2017 Vice President, Operations Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530

SUBJECT:

PALISADES NUCLEAR PLANT - ISSUANCE OF AMENDMENT RE: LICENSE AMENDMENT REQUEST FOR EDITORIAL AND ADMINISTRATIVE CHANGES TO TECHNICAL SPECIFICATIONS (CAC NO. MF8796)

Dear Sir or Madam:

The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the enclosed Amendment No. 263 to Renewed Facility Operating License No. DPR-20 for the Palisades Nuclear Plant (PNP). The amendment approves changes to the PNP license and technical specifications (TS) in response to your application dated November 9, 2016.

Specifically, the amendment revises TS 5.5.10, "Ventilation Filter Testing Program," to correct and modify the description of the control room ventilation and fuel handling area ventilation systems. In addition, the amendment corrects an editorial omission in TS Limiting Condition for Operation 3.0.9.

A copy of our related safety evaluation is provided in Enclosure 2. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

(

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X*v~O----~

J 1

Jennivine K. Rankin, Project Manager Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255

Enclosures:

1. Amendment No. 263 to DPR-20

2. Safety Evaluation cc w/encls: Distribution via Listserv

Amendment ML17121A510 *via memo OFFICE N RR/DORL/LPL3-1 /PM NRR/DORL/LPL3-1 /LA NRR/DSS/SBPB/BC NRR/DSS/STSB/BC (A)

NAME JRankin SRohrer RDennig

• JWhitman DATE 05/02/17 05/01/17 04/04/17 05/16/17 OFFICE OGG NRR/DORL/LPL3-1 /BC NRR/DORL/LPL3-1/PM NAME RNorwood DWrona JRankin DATE 05/25/17 06/08/17 06/08/17 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-255 PALISADES NUCLEAR PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 263 License No. DPR-20

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

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee),

dated November 9, 2016, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-20 is hereby amended to read as follows:

The Technical Specifications contained in Appendix A, as revised through Amendment No. 263, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Qd~on2hie;--

Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: June 8 , 2O1 7

ATTACHMENT TO LICENSE AMENDMENT NO. 263 RENEWED FACILITY OPERATING LICENSE NO. DPR-20 PALISADES NUCLEAR PLANT DOCKET NO. 50-255 Replace the following page of the Renewed Facility Operating License No. DPR-20 with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT Page 3 Page 3 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contains marginal lines indicating the area of change.

REMOVE INSERT Page 3.0-3 Page 3.0-3 Page 5.0-15 Page 5.0-15 Page 5.0-16 Page 5.0-16

(1) Pursuant to Section 104b of the Act, as amended, and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," (a) ENP to possess and use, and (b) ENO to possess, use and operate, the facility as a utilization facility at the designated location in Van Buren County, Michigan, in accordance with the procedures and limitation set forth in this license; (2) ENO, pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess, and use source and special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3) ENO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use byproduct, source, and special nuclear material as sealed sources for reactor startup, reactor instrumentation, radiation monitoring equipment calibration, and fission detectors in amounts as required; (4) ENO, 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 for sample analysis or instrument calibration, or associated with radioactive apparatus or components; and (5) ENO, 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 operations of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act; 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) ENO is authorized to operate the facility at steady-state reactor core power levels not in excess of 2565.4 Megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) The Technical Specifications contained in Appendix A, as revised through Amendment No. 263, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the license amendment request dated December 12, 2012, as supplemented by letters dated February 21, 2013, September 30, 2013, October 24, 2013, December 2, 2013, April 2, 2014, May 7, 2014, June 17, 2014, August Renewed License No. DPR-20 Amendment No. 2e2, 263

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.7 Special Test Exception (STE) LCOs in each applicable LCO section allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with STE LCOs is optional. When an STE LCO is desired to be met but is not met, the ACTIONS of the STE LCO shall be met. When an STE LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:

a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or

b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.

LCO 3.0.9 When one or more required barriers are unable to perform their related support function(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support function(s), and risk is assessed and managed. This specification may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s) for different categories of initiating events.

Palisades Nuclear Plant 3.0-3 Amendment No. ~. 263

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Secondary Water Chemistry Program A program shall be established, implemented and maintained for monitoring of secondary water chemistry to inhibit steam generator tube degradation and shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables, *

b. Identification of the procedures used to measure the values of the critical variables,

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

d. Procedures for the recording and management of data,

e. Procedures defining corrective actions for all off-control point chemistry conditions, and

f. A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective actions.

5.5.10 Ventilation Filter Testing Program A program shall be established to implement the following required testing of Control Room Ventilation (CRV) and Fuel Handling Area Ventilation (FHAV) systems at the frequencies specified in Regulatory Guide 1.52, Revision 2 (RG 1.52), and in accordance with RG 1.52 and ASME N510-1989, at the system flowrates and tolerances specified below*:

a. Demonstrate for each of the ventilation systems that an in place test of the High Efficiency Particulate Air (HEPA) filters shows a penetration and system bypass< 0.05% for the CRV system and< 1.00% for the FHAV system when tested in accordance with RG 1.52 and ASME N510-1989:

Ventilation System Flowrate (CFM)

FHAV (single fan operation) 7300 +/- 20%

FHAV (dual fan operation) 10,000 +/- 20%

CRV 3,200 +10% -5%

Palisades Nuclear Plant 5.0-15 Amendment No. ~. 263

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Ventilation Filter Testing Program (continued)

b. Demonstrate for each of the ventilation systems that an in place test of the charcoal adsorber shows a penetration and system bypass < 0.05% for the CRV system and < 1.00% for the FHAV system when tested in accordance with RG 1.52 and ASME N510-1989.

Ventilation System Flowrate (CFM)

FHAV (dual fan operation) 10,000 +/- 20%

CRV 3200 +10% -5%

c. Demonstrate for each of the ventilation systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in RG 1.52 shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of

30°C and equal to the relative humidity specified as follows

Ventilation System Penetration Relative Humidity FHAV 6.00% 95%

CRV 0.157% 70%

d. For each of the ventilation systems, demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with RG 1.52 and ASME N510-1989:

Ventilation System Delta P (In HzO) Flowrate (CFM)

FHAV (dual fan operation) 6.0 10,000 +/- 20%

CRV 8.0 3200 +10% -5%

e. Demonstrate that the heaters for the CRV system dissipates the following specified value+/- 20% when tested in accordance with ASME N510-1989:

Ventilation System Wattage CRV 15 kW The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Ventilation Filter Testing Program frequencies.

• Should the 720-hour limitation on charcoal adsorber operation occur during a plant operation requiring the use of the charcoal adsorber - such as refueling - testing may be delayed until the completion of the plant operation or up to 1,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of filter operation; whichever occurs first.

Palisades Nuclear Plant 5.0-16 Amendment No. '-* 263

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-20 ENTERGY NUCLEAR OPERATIONS, INC.

PALISADES NUCLEAR PLANT DOCKET NO. 50-255

1.0 INTRODUCTION

By application dated November 9, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16314A027), Entergy Nuclear Operations, Inc. (ENO, the licensee) requested changes to the renewed facility operating license and technical specifications (TSs) for Palisades Nuclear Plant (PNP). Specifically, the amendment revises TS 5.5.10, "Ventilation Filter Testing Program [VFTP]," to: (1) correct the ventilation train and surveillance flowrate parameter for the control room ventilation (CRV) system from control room air handling units to the control room high-efficiency particulate air (HEPA) filter trains in TS 5.5.1 Oa and (2) change the component identification labels for fans in the CRV and the fuel handling ventilation system. In addition, the proposed amendment would correct an editorial omission in TS Limiting Condition for Operation (LCO) 3.0.9.

The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff's original proposed no significant hazards consideration determination was published in the Federal Register on February 14, 2017 (82 FR 10596).

2.0 REGULATORY EVALUATION

The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff reviewed the proposed TS changes against the regulatory requirements and guidance listed below to ensure that there is reasonable assurance that the systems and components affected by the proposed TS changes will perform their safety functions.

The NRC's regulatory requirements related to the content of the TSs are set forth in Title 1O of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications." This regulation requires that the TSs include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.

Enclosure 2

As discussed in 10 CFR 50.36(c)(2), LCOs are the lowest functional capability or performance level of equipment required for safe operation of the facility. When LCOs are not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCOs can be met.

3.0 TECHNICAL EVALUATION

3.1 TS LCO 3.0.9 - Correct Typographical Error The licensee proposes to add a period to the end of the first paragraph in LCO 3.0.9. LCO 3.0.9 was added to the TS by letter dated October 22, 2014 (ADAMS Accession No. ML14283A287) in Amendment No. 252. Amendment No. 252 inadvertently omitted the period at the end of this paragraph.

The NRG staff concludes the addition of a period to the end of the first paragraph in LCO 3.0.9 to be an editorial change and is corrective in nature, and therefore, is acceptable.

3.2 TS 5.5.1 Oa - Flowrate Correction The license amendment request (LAR) and final safety analysis report Sections 9.8.2.1 and 9.8.2.4 state that the CRV contains two independent, redundant trains that recirculate and filter the air within the control room envelope. Each train has a control room air filter unit that is provided for emergency operation. Each filter unit includes upstream HEPA filters, two banks of carbon absorber trays, downstream HEPA filters, and a fan (either V-26A or V-268).

Each CRV train also contains an air handling unit that provides conditioned air to the control room. Each air handling unit has a fan (either V-95 or V-96) operating at a flowrate of 12,500 cubic feet per minute (cfm) each. During normal operations, one air handling unit is in service with the air handling unit associated with the other train in standby.

TS 5.5.10a currently states that a program shall be established to:

a. Demonstrate for each of the ventilation systems that an inplace test of the High Efficiency Particulate Air (HEPA) filters show a penetration and system bypass <0.05% for the CRV and <1.00% for the Fuel Handling Area Ventilation [FHAV] System when tested in accordance with RG [Regulatory Guide] 1.52 and ASME [American Society of Mechanical Engineers] N510-1989:

Ventilation System Flowrate (CFM)

V-8A or V-88 7300 +/- 20%

V-8A and V-88 10,000 +/- 20%

V-95 or V-96 12,500+/-10%

The LAR states that, since the HEPA filters are located in the control room air filter units, TS 5.5.1 Oa should provide the flowrate associated with each of the CRV air filter unit fans (3200 cfm, + 1O percent, -5 percent) rather than the flowrate for each of the CRV air handling unit fans (12,500 cfm, +/- 1O percent). The licensee also states that the incorrect fan and flowrate information was added to the TS by letter dated October 31, 1996 (ADAMS Accession No. ML020840145), in Amendment No. 174. The associated LAR for Amendment No. 174 did not

discuss why the CRV air handling unit fan information was added rather than the CRV air filter unit fan information.

The NRC staff reviewed the proposed change to TS 5.5.1 Oa. TS 5.5.1 Oa should state requirements for testing of the HEPA filters, which are located in the CRV filter train and not the air handling units. The corrections to TS 5.5.1 Oa will continue to maintain the required testing of the CRV systems at the frequencies specified in RG 1.52, Revision 2, and ASME N510-1989.

This correction is considered to be administrative, therefore, the staff finds the change acceptable.

3.3 Additional proposed change to TS 5.5.1 O The licensee proposes to modify TS 5.5.10 by replacing the identification number for the systems' components with the acronym for the noun names of the ventilation systems (e.g.,

fans V-26A and V-268 would be replaced by the acronym "CRV" for the control room ventilation system). These changes would improve clarity and conforms with Section 5.5.11, "Ventilation Filter Testing Program (VFTP), of NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," Revision 4 (ADAMS Accession No. ML12102A165). The licensee also proposes changes to define the CRV and FHAV system acronyms and consistently use the acronyms throughout TS 5.5.10.

The NRC staff reviewed the proposed changes to TS 5.5.1 O and confirmed that replacing the identification number for the systems' components with the acronym for the noun names of the ventilation system still allows proper testing of the system as required by the TS. Each testing requirement in the VFTP lists a specific component to be tested within the system. These components have specific identification numbers located within the system, which will be identified by an acronym listed in TS 5.5.10. The NRC staff also reviewed the changes to define the CRV and FHAV system acronyms and concludes those to be editorial changes. The proposed changes maintain the testing requirements for the VFTP, therefore, the staff finds the changes acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Michigan State official was notified on April 27, 2017, of the proposed issuance of the amendment. The State official 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. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, or 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 (82 FR 10596, February 14, 2017). 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 needs to 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, NRR/DSS Date of issuance: June 8, 2017