ML16060A401

Issuance of Amendments Relocation of Specific Surveillance Requirement Frequencies

ML16060A401
Person / Time
Site:	Calvert Cliffs
Issue date:	04/11/2016
From:	Richard Guzman Plant Licensing Branch 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Guzman R
References
CAC MF7056, CAC MF7057
Download: ML16060A401 (21)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 11, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

ISSUANCE OF AMENDMENTS RE: RELOCATION OF SPECIFIC SURVEILLANCE REQUIREMENT FREQUENCIES (CAC NOS. MF7056 AND MF7057)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 317 to Renewed Facility Operating License No. DPR-53, and Amendment No. 295 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2, respectively. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 5, 2015 (Agencywide Documents Access and Management System Accession No. ML15310A064).

These amendments revise Surveillance Requirement (SR) frequencies for SRs 3.4.6.4, 3.4. 7.4, 3.4.8.3, 3.5.2.10, 3.6.6.9, 3.9.4.2, and 3.9.5.4. The proposed changes to the SR frequencies are to relocate the frequencies to the Surveillance Frequency Control Program.

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, Richard V. Guzman, Sr. Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. Amendment No. 317 to DPR-53

2. Amendment No. 295 to DPR-69

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC CALVERT CLIFFS NUCLEAR POWER PLANT. LLC CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE DOCKET NO. 50-317 Amendment No. 317 Renewed License No. DPR-53

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

A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated November 5, 2015, 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:

Enclosure 1

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 317, are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days following approval of this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION Travis L. Tate, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: April 11 , 2O1 6

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, LLC CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE DOCKET NO. 50-318 Amendment No. 295 Renewed License No. DPR-69

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

A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated November 5, 2015, 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:

Enclosure 2

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 295, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days following approval of this amendment.

FOR THE NUCLEAR REGULATORY COMMISSION Travis L. Tate, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of lssuance:Apr i l 11 , 2o1 6

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 317 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 295 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised page. The revised page is identified by amendment number and contain a marginal line indicating the areas of change.

Remove Page Insert Page 3 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 contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 3.4.6-3 3.4.6-3 3.4.7-3 3.4.7-3 3.4.8-3 3.4.8-3 3.5.2-4 3.5.2-4 3.6.6-4 3.6.6-4 3.9.4-4 3.9.4-4 3.9.5-5 3.9.5-5

(4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation 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 license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:

(1) Maximum Power Level Exelon Generation is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 317, are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

(a) For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. DPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.

(3) Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 305 are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Additional Conditions.

(4) Secondary Water Chemistry Monitoring Program Exelon Generation shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

Amendment No. 317

(4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation 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 license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now and hereafter applicable; and is subject to the additional conditions specified and incorporated below:

(1) Maximum Power Level Exelon Generation is authorized to operate the facility at reactor steady-state core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 295 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(a) For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.

(3) Less Than Four Pump Operation The licensee shall not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.

(4) Environmental Monitoring Program If harmful effects or evidence of irreversible damage are detected by the biological monitoring program, hydrological monitoring program, and the Amendment No. 295

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RCS or SOC loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.6.2 Verify secondary side water level in In accordance required steam generator(s) is > -50 inches. with the Surveillance Frequency Control Program SR 3.4.6.3 Verify correct breaker alignment and In accordance indicated power available to the required with the loop components that are not in operation. Surveillance Frequency Control Program SR 3.4.6.4 -------------------NOTE-------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4.

Verify required SOC train locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.4.6-3 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one SOC loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify required SG secondary side water In accordance level is > -50 inches. with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and In accordance indicated power available to the required with the SOC loop components that are not in Surveillance operation. Frequency Control Program SR 3.4.7.4 Verify required SOC train locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Survei 11 ance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.4.7-3 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

RCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.8.3 Verify SOC train locations susceptible to In accordance gas accumulation are sufficiently filled with the with water. Surveillance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.4.8-3 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.10 Verify ECCS locations susceptible to gas In accordance accumulation are sufficiently filled with with the water. Surveillance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.5.2-4 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.6 Verify each containment spray pump starts In accordance automatically on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train starts In accordance automatically on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed. Following maintenance that could result in nozzle blockage SR 3.6.6.9 Verify containment spray locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.6.6-4 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

SOC and Coolant Circulation-High Water Level 3.9.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.4.2 Verify required SDC loop locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.9.4-4 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

SOC and Coolant Circulation-Low Water Level 3.9.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.5.4 Verify SOC loop locations susceptible to gas In accordance accumulation are sufficiently filled with with the water. Surveillance Frequency Control Program CALVERT CLIFFS - UNIT 1 3.9.5-5 Amendment No. 317 CALVERT CLIFFS - UNIT 2 Amendment No. 295

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELOCATION OF SPECIFIC SURVEILLANCE REQUIREMENT FREQUENCIES AMENDMENT NO. 317 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 295 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 EXELON GENERATION COMPANY, LLC DOCKET NOS. 50-317 AND 50-318

1.0 INTRODUCTION

By application dated November 5, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 1531 OA064), Exelon Generation Company, LLC (the licensee) requested an amendment to the facility operating licenses for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (CCNPP), to revise the technical specifications (TSs) to relocate surveillance requirement (SR) frequencies to the previously approved surveillance frequency control program (SFCP).

The license amendment request (LAR) proposed changes to TSs 3.4.6, 3.4.7, 3.4.8, 3.5.2, 3.6.6, 3.9.4, and 3.9.5. These TSs are covered in the U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Improved Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2 (TSTF-523) "Generic Letter 2008-01, Managing Gas Accumulation" (ADAMS Accession No. ML13053A075) dated February 21, 2013. The proposed changes would relocate the SR frequency to the previously approved licensee-controlled SFCP. The NRC issued amendments that implemented TSTF-523 into the CCNPP TSs by letter dated July 30, 2015 (ADAMS Accession No. ML15161A380). The NRC issued amendments to relocate specific surveillance frequencies to the licensee-controlled SFCP by letter dated August 17, 2015 (ADAMS Accession No. ML15211A005).

The proposed changes would revise the SR frequencies related to gas accumulation included in TSTF-523 from the current 31-day frequency to a frequency in accordance with the SFCP. The proposed chaoge would relocate these SR frequencies from the TSs to the licensee-controlled SFCP.

Enclosure 3

2.0 REGULATORY EVALUATION

2.1 Regulatory Requirements The regulatory requirements and guidance documents that the NRC staff used in their review of the application are listed below:

• In Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR), the NRC established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; and (5) administrative controls.

2.2 Regulatory Guidance

• NUREG-1432, Revision 4.0, "Standard Technical Specifications, Combustion Engineering Plants," Revision 4.0, April 2012 (ADAMS Accession Nos. ML12102A165 and ML12102A169).

• Technical Specification Task Force (TSTF) Standard Technical Specifications (STS)

Change Traveler TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative 5b" (ADAMS Accession No. ML090850642). The Federal Register notice published on July 6, 2009 (74 FR 31996),

announced the availability of TSTF-425, Revision 3.

• Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS)

Change Traveler TSTF-523, Revision 2 "Generic Letter 2008-01, Managing Gas Accumulation," model safety evaluation (SE) dated December 23, 2013. The Federal Register noticed published on January 15, 2014 (79 FR 2700) announced the availability of TSTF-523, Revision 2.

3.0 TECHNICAL EVALUATION

3.1 Background By letter dated July 30, 2015, the NRC issued license amendments that revised the CCNPP TSs by implementing TSTF-523. These amendments added new SRs related to gas accumulation for the shutdown cooling system, the emergency core cooling system, and the containment spray system to the CCNPP TSs. In accordance with the model SE for TSTF-523, the new SR frequencies were set at a 31-day interval.

By letter dated August 17, 2015, the NRC issued license amendments that revised the CCNPP TSs by implementing TSTF-425. These amendments revised the CCNPP TSs to require that changes to specific SR frequencies be made in accordance with NEI 04-10, Revision 1. These amendments incorporated NRG-approved TSTF-425 into the license. In addition, these

amendments added the SFCP to Section 5.0, "Administrative Controls," Subsection 5.5, "Programs and Manuals."

3.2 Licensee's Proposed Changes In its LAR dated November 5, 2015, the licensee proposed moving the following SR frequencies to the licensee-controlled SFCP:

SR Current SR Frequency Proposed SR Frequency 3.4.6.4 31 days In accordance with the SFCP 3.4.7.4 31 days In accordance with the SFCP 3.4.8.3 31 days In accordance with the SFCP 3.5.2.10 31 days In accordance with the SFCP 3.6.6.9 31 days In accordance with the SFCP 3.9.4.2 31 days In accordance with the SFCP 3.9.5.4 31 days In accordance with the SFCP At the time the TSTF-523 amendment was issued, the licensee did not have an approved SFCP. Therefore, a 31-day SR frequency was established for the SRs listed in the table above.

Since then, the NRC issued the amendment incorporating TSTF-425 into the license, thereby allowing the licensee to establish an SFCP in accordance with NEI 04-10, Revision 1.

3.3 NRC Staff Evaluation As noted in the discussion above, the licensee previously received license amendments that incorporated the SRs listed in TSTF-523 and the SFCP from TSTF-425 into the CCNPP facility operating licenses. Both of these license amendments were previously reviewed and approved by the NRC staff. The previous staff reviews for the amendments established that addition of the SRs in TSTF-523 met the regulatory requirements of 10 CFR 50.36 because the changes provided assurance that the necessary quality of systems and components will be maintained and that the limiting conditions for operation will be met, and therefore, were acceptable to the staff. In addition, the previous staff reviews found that the licensee's probabilistic risk assessment (PRA) models are of sufficient technical adequacy and that the licensee satisfied the key principles of risk-informed decisionmaking to support the licensee's SFCP. The staff previously determined that the relocation of certain surveillance frequencies to the SFCP allowed the licensee to continue to meet the requirements of 10 CFR 50.36. Based on these previous reviews, the NRC staff does not need to review the technical adequacy of the licensee's PRA or the SRs shown above, as the licensee has not proposed any changes to its PRA or to the other parts of the SRs.

Section 1.0, "Introduction," of the model SE for TSTF-523, states that licensees with an SFCP have the option to set the SR frequencies, " ... in accordance with the Surveillance Frequency Control Program .... " In addition, the licensee has not proposed any optional changes or deviations to either of the previously approved amendments. The licensee did not have an approved SFCP at the time the TSTF-523 amendment was approved for CCNPP. However, with the incorporation of TSTF-425 into the license for CCNPP, which allowed the licensee to

establish an SFCP, the licensee meets the requirements in the model SE for TSTF-523 to set the SR frequencies in accordance with the SFCP. Therefore, the changes to the SR frequencies proposed by the licensee are in accordance with both TSTF-425 and TSTF-523 and are approved.

3.4 Technical Evaluation Conclusions The NRC staff has found that the changes described above are in accordance with both TSTF-425 and TSTF-523; in addition, the changes satisfy the criteria for TSs in 10 CFR 50.36.

Therefore, the NRC staff has concluded that the changes to the SR frequencies for the SRs described above are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Maryland 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 the 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 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 published in the Federal Register on January 5, 2016 (81 FR 261 ). 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.

7.0 REFERENCES

1. Letter from James Barstow to U.S. Nuclear Regulatory Commission, "License Amendment Request to Relocate Surveillance Frequency Requirements," November 5, 2015 (ADAMS Accession No. ML15310A064).

2. "Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-523, Revision 2, 'Generic Letter 2008-01, Managing Gas Accumulation,' Using the Consolidated Line Item Improvement Process," December 23, 2013 (ADAMS Accession No. ML13255A169).

3. Chereskin, Alexander N., USNRC, Letter to Gudger, David T., Exelon Generation Company, LLC, "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; R. E. Ginna Nuclear Power Plant; and Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendments Regarding Implementation of Technical Specifications Task Force Traveler 523, 'Generic Letter 2008-01, Managing Gas Accumulation" (TAC Nos. MF4405, MF4406, MF4407, and MF4409), July 30, 2015 (ADAMS Accession No. ML15161A380).

4. Chereskin, Alexander N., USNRC, Letter to Hanson, Bryan C., Exelon Nuclear, "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Issuance of Amendment Re: Adoption of TSTF-425, Relocate Specific Surveillance Frequencies to a Licensee Controlled Program (TAC Nos. MF4065 and MF4066)," August 17, 2015 (ADAMS Accession No. ML15211A005).

5. Federal Regulation, U.S. Code of Federal Regulations, "Domestic Licensing of Production and Utilization Facilities - Technical Specifications," 10 CFR Part 50, Section 36.

6. U.S. Nuclear Regulatory Commission, "Standard Technical Specifications - Combustion Engineering Plants, Volumes 1 and 2, NUREG-1432, Revision 4, April 2012 (ADAMS Accession Nos. ML12102A165 and ML12102A169).

7. Technical Specification Task Force Improved Standard Technical Specifications Change Travel-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -

RITSTF Initiative Sb, March 18, 2009 (ADAMS Accession No. ML090850642).

Principal Contributor: Alexander N. Chereskin Date: April 11, 2016

ML16060A401 OFFICE DORL/LPLl-1/PM DORL/LPLl-1 /LA DSS/STSB/BC OGC DORL/LPLl-1 /BC DORL/LPLl-1 /PM NAME AChereskin KGoldstein RElliott SF owler TT ate RGuzman (LRonewicz for)

DATE 3/4/16 3/2/16 3/3/16 3/17/16 04/11/16 04/11/16