ML15063A293

Issuance of Amendments Revision to Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor

ML15063A293
Person / Time
Site:	Salem
Issue date:	03/30/2015
From:	Carleen Parker Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Parker C, NRR/DORL/LPL1-2, 415-1603
References
TAC MF3691, TAC MF3692
Download: ML15063A293 (20)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 30, 2015 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1AND2-ISSUANCE OF AMENDMENTS RE: REVISION TO POWER DISTRIBUTION LIMITS FOR AXIAL FLUX DIFFERENCE AND HEAT FLUX HOT CHANNEL FACTOR (TAC NOS. MF3691 AND MF3692)

Dear Mr. Joyce:

The Commission has issued the enclosed Amendment Nos. 307 and 289 to Renewed Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated March 24, 2014.

The amendments revise Surveillance Requirements (SRs) 4.2.1.3, 4.2.1.4, and 4.2.2.2.f associated with Power Distribution Limits TS 3/4.2.1, "Axial Flux Difference (AFD)," and TS 3/4.2.2, "Heat Flux Hot Channel Factor-Fa(Z)."

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

Docket Nos. 50-272 and 50-311

Enclosures:

1. Amendment No. 307 to Renewed DPR-70

2. Amendment No. 289 to Renewed DPR-75

3. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, I

~~

Carlee;:~ark, i Project~~:-

Plant Licensing ~anch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR. LLC EXELON GENERATION COMPANY. LLC DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERA TING LICENSE Amendment No. 307 Renewed License No. DPR-70

1.

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

A The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees) dated March 24, 2014, 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 Title 10 of the Code of Federal Regulations (10 CFR),

Chapter I;

8.

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 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.

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. DPR-70 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. 307, 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.

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

FOR THE NUCLEAR REGULATORY COMMISSION

~~

Attachment:

Changes to Renewed Facility Operating License and the Technical Specifications Date of Issuance: March 30, 2015 Douglas A. Broaddus, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO. 307 RENEWED FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following page of Renewed Facility Operating License No. DPR-70 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page3 Insert Page3 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 areas of change.

Remove Page 3/4 2-3 Page 3/4 2-7 Insert Page 3/4 2-3 Page 3/4 2-7 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 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 307, 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)

Deleted Per Amendment 22, 11-20-79 (4)

Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this renewed license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this renewed license.

(5)

PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Renewed License No. DPR-70 Amendment No. 307

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.1.3 The target flux difference shall be determined by measurement in accordance with the Surveillance Frequency Control Program. The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 The target flux difference shall be updated in accordance with the Surveillance Frequency Control Program. The provisions of Specification 4.0.4 are not applicable.

SALEM - UNIT 1 314 2-3 Amendment No. 307

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

d.

Remeasuring Fxy according to the following schedule:

1.

When Fxyc is greater than the FxyRTP limit for the appropriate measured core plane but less than the Fxy L relationship, additional core power distribution measurements shall be taken and Fxyc compared to FxtTP and F L.

xy.

a)

Either within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 20% of RA TED THERMAL POWER or greater, the THERMAL POWER at which Fx/ was last determined, or b)

In accordance with the Surveillance Frequency Control Program, whichever occurs first.

2.

When the Fxyc is less than or equal to the Fx/TP limit for the appropriate measured core plane, additional core power distribution measurements shall be taken and Fxyc compared to FxlTP and Fx/ in accordance with the Surveillance Frequency Control Program.

e.

The Fxy limit for Rated Thermal Power (FxlrP) shall be provided for all core planes containing bank "D" control rods and all unrodded core planes in the COLR per specification 6.9.1.9.

f.

The Fxy limits of e, above, are not applicable to the excluded core plane regions as measured in percent of core height from the bottom of the fuel.

g.

Evaluating the effects of Fx( on F0 (Z) to determine if F0 (Z) is within its limit whenever Fx/ exceeds Fxy.

SALEM - UNIT 1 314 2-7 Amendment No. 307

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 289 Renewed License No. DPR-75

1.

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

A.

The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees) dated March 24, 2014, 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 Title 10 of the Code of Federal Regulations (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 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.

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. DPR-75 is hereby amended to read as follows:

The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, 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.

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

FOR THE NUCLEAR REGULATORY COMMISSION 133~

~

Attachment:

Changes to Renewed Facility Operating License and the Technical Specifications Date of Issuance: March 30, 2015 Douglas A. Broaddus, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO. 289 RENEWED FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following page of Renewed Facility Operating License No. DPR-75 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page 3 Insert Page 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 areas of change.

Remove Page 3/4 2-3 Page 3/4 2-7 Insert Page 3/4 2-3 Page 3/4 2-7 (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 or 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.

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 steady state reactor core power levels not in excess of 3459 megawatts (thermal).

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, 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. DPR-75 Amendment No. 289

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.1.3 The target flux difference shall be determined by measurement in accordance with the Surveillance Frequency Control Program. The provisions of Specification 4.0.4 are not applicable.

4.2.1.4 The target flux difference shall be updated in accordance with the Surveillance Frequency Control Program. The provisions of Specification 4.0.4 are not applicable.

SALEM - UNIT 2 3/4 2-3 Amendment No. 289

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS <Continued)

2.

When the Fxyc is less than or equal to the Fx/TP limit for the appropriate measured core plane, additional core power distribution measurements shall be taken and Fxyc compared to FxyRTP and Fx/ in accordance with the Surveillance Frequency Control Program.

e.

The Fxy limit for Rated Thermal Power (Fx/TP) shall be provided for all core planes containing bank "D" control rods and all unrodded core planes in the COLR per specification 6.9.1.9.

f.

The Fxy limits of e., above, are not applicable to the excluded core plane regions as measured in percent of core height from the bottom of the fuel.

g.

Evaluating the effects of Fxl on Fa(Z) to determine if F0 (Z) is within its limit whenever Fx/ exceeds Fxy.

4.2.2.3 When Fa(Z) is measured pursuant to specification 4.10.2.2, an overall measured Fa(Z) shall be obtained from a core power distribution measurement and increased by the applicable manufacturing and measurement uncertainties as specified in the COLR.

SALEM - UNIT 2 3/4 2-7 Amendment No. 289

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 307 AND 289 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PSEG NUCLEAR, LLC EXELON GENERATION COMPANY. LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1AND2 DOCKET NOS. 50-272 AND 50-311

1.0 INTRODUCTION

By letter dated March 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14083A439), PSEG Nuclear, LLC (the licensee) submitted a request for changes to the Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, technical specifications (TSs). The requested changes would revise Surveillance Requirements (SR) 4.2.1.3, 4.2.1.4, and 4.2.2.2.f associated with Power Distribution Limits TS 3/4.2.1, "Axial Flux Difference (AFD)," and TS 3/4.2.2, "Heat Flux Hot Channel Factor-F0 (Z)." The proposed change eliminates or relocates information considered to be: (1) an inaccuracy; or (2) an unnecessary level of detail.

The proposed changes would:

1. Remove inaccurate detail from SR 4.2.1.3 regarding determination of target flux difference;

2. Remove unnecessary level of detail in SR 4.2.1.4 regarding method of determining the target flux difference; and

3. Remove unnecessary level of detail in SR 4.2.2.2.f by relocating the Fxy peaking factor (Fxy) axial exclusion zone to the TS Bases.

2.0 REGULATORY EVALUATION

The Nuclear Regulatory Commission (NRC) staff took into consideration the regulatory requirements and guidance discussed below.

The NRC's regulatory requirements related to the content of the TSs are set forth in Title 10 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) limiting conditions of operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs.

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 LCO can be met.

As discussed in 1 O CFR 50.36(c)(3), SRs 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.

On July 22, 1993, the Commission issued its "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors," which identifies four criteria for defining the scope of technical specifications. The final policy statement explained that "by applying the four criteria contained in the Policy Statement a licensee should capture all of those specific characteristics of its facility and the conditions for its operation that a required to meet the principal operative standard in Section 182a. of the Atomic Energy Act" (58 FR 39132; July 22, 1993). The final policy statement described the safety benefits of the improved Standard Technical Specifications (STS) and encouraged licensees to use the improved STS as the basis for plant-specific TS amendments and for complete conversions to the improved STS. Further, the final policy statement provided guidance for evaluating the required scope of the licensee's improved TS and defined the guidance criteria for determining which of the LCOs and associated surveillances should remain in its improved TS. Using this approach, licensees should keep existing LCO requirements that fall within or satisfy any of the final policy statement criteria in the TS. Those LCO requirements that do not fall within or satisfy any of these criteria may be relocated to licensee-controlled documents. The Commission codified the four criteria in 10 CFR 50.36(c)(2)(ii) (60 FR 36953; July 19, 1995). NUREG-1431, "Standard Technical Specifications Westinghouse Plants," Revision 4, dated April 2012 (ADAMS Accession No. ML 121 OOA228), was developed based on the criteria in the Final Policy Statement.

Proposed changes to the STS are submitted by the industry's TS Task-Force (TSTF) or proposed by the NRC staff, and are called travelers. Once approved, the TSTF Traveler is generally added to future versions of the STS. Also, once approved, a TSTF Traveler may be used and referenced in the preparation of license amendment requests by multiple licensees.

The approved TSTF Traveler provides the model technical and regulatory bases for the license amendment requests.

Salem, Units 1 and 2, were designed using the Atomic Industry Forum general design criteria and the licensee's understanding of the intent of the Atomic Energy Commission's (AECs) proposed General Design Criteria. A comparison of the Salem, Units 1 and 2, plant design was done with 1 O CFR Part 50, Appendix A, GDC for Nuclear Power Plants, dated July 7, 1971. The comparison was documented in the Salem Updated Final Safety Analysis Report (UFSAR)

Section 3.1.3, which states, in part, that "the Salem Plant design conforms with the intent of the "General Design Criteria for Nuclear Power Plants, dated July 7, 1971.... "

Appendix A to 10 CFR Part 50, General Design Criterion (GDC) 10, "Reactor design," requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.

The proposed amendment would relocate details from SR 4.2.1.4 and SR 4.2.2.2.f to the TS bases. The TS bases control program is described in TS Section 6.17, "Technical Specification (TS) Bases Control Program," for Salem, Unit 1, and TS Section 6.16, "Technical Specification (TS) Bases Control Program," for Salem, Unit 2. Specifically the Salem, Units 1 and 2, TS Sections 6.17 and 6.16, respectively, state:

This program provides a mean for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. PSEG may makes changes to the Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the License, or

2. A change in the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c.

Proposed changes to the Bases that require either condition of the Specification 6.17.b [6.16.b for Salem Unit 2] above shall be reviewed and approved by the NRC prior to implementation.

d. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

e. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent the UFSAR.

After the information in SR 4.2.1.4 and SR 4.2.2.2.f is relocated to the TS Bases, any future changes would be controlled by the provisions of the TS Bases Program.

3.0 TECHNICAL EVALUATION

to the letter dated March 24, 2014, proposes changes to three SRs associated with Power Distribution Limits TS 3/4.2.1, "Axial Flux Difference (AFD)," and 3/4.2.2, "Heat Flux Hot Channel Factor -Fa(Z)":

1. SR4.2.1.3

2. SR 4.2.1.4

3. SR 4.2.2.f 3.1 Evaluation of Change to SR 4.2.1.3 PSEG proposes to change specific wording regarding details of the initial target flux difference measurement SR as follows:

The target flux difference of each OPERABLE excore channel shall be determined by measurement in accordance with the Surveillance Frequency Control Program. The provisions of Specification 4.0.4 are not applicable.

The proposed change would remove the words "of each OPERABLE excore channel" from SR 4.2.1.3. PSEG states that this would clarify that the target flux difference is determined for the entire core instead of for each excore channel and bring the Salem, Units 1 and 2, TSs into closer alignment with NUREG-1431.

The NRC staff-approved TSTF-24, "Delete the Details on Updating the Target Flux Difference,"

as incorporated into NUREG-1431, describes the AFD as being determined for the entire core, not each excore channel, and approves the removal of the language "of each OPERABLE excore channel." Specifically, TSTF-24 and NUREG-1431 update the TS bases language for determining target flux difference to state the following:

[m]easurement of the target flux difference is accomplished by taking a flux map where the core is at equilibrium xenon conditions, preferably at high power levels with the control banks nearly withdrawn. This flux map provides the equilibrium xenon axial power distribution from which the target value can be determined.

The target flus difference varies slowly with core burnup.

The NRC staff compared the revised wording for SR 4.2.1.3 to approved TSTF-24, as incorporated into NUREG-1431, and confirmed that the revised wording is consistent.

The NRC staff reviewed the licensee's statement that the SR wording implied calculations for the initial target flux difference would be performed on individual excore channels as opposed to the entire core. The NRC staff does not interpret the wording from the Salem, Units 1 and 2, TSs to indicate that the target flux difference calculations should be performed for each individual excore channel. In fact, the notes from LCO 3.2.3A in NUREG-1431 use similar wording (e.g., "The AFD shall be considered outside the target band when two or more OPERABLE excore channels indicate AFD to be outside the target band"). This related wording is also found in the Salem, Units 1 and 2, TSs under SRs Section 4.2.1.2, which is not impacted by the proposed changes.

While the NRC staff does not agree that the wording for SR 4.2.1.3 is inaccurate, the NRC staff does find that the change is consistent with approved TSTF-24 and NUREG-1431. Therefore, the NRC staff finds this change to be acceptable.

3.2 Evaluation of Change to SR 4.2.1.4 PSEG proposes to remove details related to target flux difference methodology as follows:

The target flux difference shall be updated in accordance with the Surveillance Frequency Control Program by either determining the target flux difference pursuant to 4.2.1.3 above of by linear interpolation between the most recently measured value and 0 percent at the end of the cycle life. The provisions of Specification 4.0.4 are not applicable.

Note: Salem, Unit 2, TS states "0%"

In the letter dated March 24, 2014, PSEG states that the level of detail is unnecessary and that it is also technically inconsistent with the Salem UFSAR and NUREG-1431 TS Bases. The licensee proposes to move and revise the details to the TS Bases section and to have the option to use a predicted end of cycle value to update target flux difference.

The NRC staff-approved TSTF-24, as incorporated into NUREG-1431, deletes information on how the target flux difference is determined from the SR as an unnecessary level of detail. The bases approved by TSTF-24 contain more information, and a more accurate description on how the target flux is to be determined. The NRC staff compared the proposed change to approved TSTF-24, as incorporated into NUREG-1431, and concluded that by relocating and revising the details from SR 4.2.1.4 to the TS Bases, the proposed revised wording would be consistent with TSTF-24 and NUREG-1431.

Additionally, the NRC staff compared the proposed technical change to the Salem UFSAR. The NRC staff confirmed that the UFSAR does allow for reload target values to be based on cycle-specific data, which is also consistent with the Westinghouse Standard TS Bases found in NUREG -1431 and approved TSTF-24.

The NRC staff concludes that the proposed change to SR 4.2.1.4 would be consistent with approved TSTF-24 and NUREG-1431. In addition, the proposed change would bring the details found in the Salem, Units 1 and 2, TS Bases in alignment with the Salem UFSAR. Therefore, the NRC staff finds this change to be acceptable.

3.3 Evaluation of Change to SR 4.2.2.2.f The licensee proposes to relocate the peaking factor axial exclusion zones from the TS to the TS Bases, as follows:

The Fxy limits of e, above, are not applicable in the follo*.ving to the excluded core plane regions as measured in percent of core height from the bottom of the fuel-:-.

1.

Lower core region from 0 to 15% inclusive.

2.

Upper core region from 85 to 100% inclusive.

3.

Grid plane regions at 17.8 :t 2%, 32.1 i: 2%, 46.4 + 2%, 60.6 :t 2% and 74.9 :t 2% inclusive.

4.

Core plane regions within :t2% of core height (i: 2.88 inches) about the bank demand position of the bank "D" control rods.

Note: Salem, Unit 2, TS has minor editorial differences.

The licensee states that this relocation is consistent with NUREG-1431 and that the LCO will continue to be met.

The NRC staff compared the proposed changes with NUREG-1431 and confirmed that the revised TS would be consistent and the LCO would continue to be met. The NRC staff noted that the proposed relocation of the exclusion zones also included some minor editorial changes.

These changes make the wording more similar to NUREG-1431 and do not effectively change the meaning. Therefore, the NRC staff finds this change to be 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 amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change 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 surveillance requirements. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (79 FR 32770). Accordingly, the amendments meet 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 amendments.

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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Christopher Van Wert Date: March 30, 2015

ML15063A293

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DSS/SRXB/BC DSS/SNPB/BC OGC NAME CParker ABaxter CJackson JDean AGhosh w/comments DATE 03/10/2015 03/06/2015 03/19/2015 03/10/2015 03/26/2015