ML15050A144

Issuance of Amendments Proposed Change to Indian Point 3 Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves (Tac No. MF3754)

ML15050A144
Person / Time
Site:	Indian Point
Issue date:	03/06/2015
From:	Pickett D Plant Licensing Branch 1
To:	Entergy Nuclear Operations
Pickett D
References
TAC MF3754, FOIA/PA-2016-0148
Download: ML15050A144 (13)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 6, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF AMENDMENTS RE: PROPOSED CHANGE TO INDIAN POINT 3 TECHNICAL SPECIFICATIONS REGARDING REACTOR VESSEL PRESSURE/TEMPERATURE LIMIT CURVES (TAC NO. MF3754)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 255 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 1, 2014.

The amendment revises TS Figures 3.4.3-1, "Heatup Limitations for Reactor Coolant System,"

3.4.3-2, "Cooldown Limitations for Reactor Coolant System, and 3.4.3-3, "Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System" to address vacuum fill operations in the TSs. The proposed changes clarify that the figures are applicable for vacuum fill conditions where pressure limits are considered to be met for pressures that are below 0 pounds per square inch gauge (psig) (i.e., up to and including full vacuum conditions). Vacuum fill operations for the reactor coolant system can result in system pressures below 0 psig.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely,

/JJl~a.£ c?~~,,,v Douglas V. Pickett, Senior Project Manag? l Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-286

Enclosures:

1. Amendment No. 255 to DPR-64

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR INDIAN POINT 3, LLC ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Amendment No. 255 License No. DPR-64

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

A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated April 1, 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 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 this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-64 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 255, are hereby incorporated in the license. ENO 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 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

~'.JJ~

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Benjamin G. Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: March 6, 2015

ATTACHMENT TO LICENSE AMENDMENT NO. 255 FACILITY OPERATING LICENSE NO. DPR-64 DOCKET NO. 50-286 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines 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 3.4.3-3 3.4.3-3 3.4.3-4 3.4.3-4 3.4.3-5 3.4.3-5

(4) ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, Arndt. 203 to receive, possess, and use in amounts as required any 11/27/00 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; (5) ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Arndt. 203 possess, but not separate, such byproduct and special 11/27/00 nuclear materials as may be produced by the operation of the facility.

C. This amended 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 ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 3216 megawatts thermal (100% of rated power).

(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 255 are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications.

(3) (DELETED) Arndt. 205 2-27-01 (4) (DELETED) Arndt. 205 2-27-01 D. (DELETED) Amdt.46 2-16-83 E. (DELETED) Amdt.37 5-14-81 F. This amended license is also subject to appropriate conditions by the New York State Department of Environmental Conservation in its letter of May 2, 1975, to Consolidated Edison Company of New York, Inc., granting a Section 401 certification under the Federal Water Pollution Control Act Amendments of 1972.

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• • • ~..._ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 255 TO FACILITY OPERATING LICENSE NO. DPR-64 ENTERGY NUCLEAR INDIAN POINT 3, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

1.0 INTRODUCTION

By letter dated April 1, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14099A333) (Reference 1), Entergy Nuclear Operations, Inc.

(Entergy, the licensee) submitted a request for changes to the Indian Point Nuclear Generating Unit No. 3 (IP3) Technical Specifications (TSs). The proposed amendment would revise TS Figures 3.4.3-1, "Heatup Limitations for Reactor Coolant System," 3.4.3-2, "Cooldown Limitations for Reactor Coolant System," and 3.4.3-3, "Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System" to address vacuum fill operations. The proposed changes clarify that the figures are applicable for vacuum fill conditions where pressure limits are considered to be met for pressures that are below 0 pounds per square inch gauge (psig)

(i.e., up to and including full vacuum conditions). Vacuum fill operations for the reactor coolant system (RCS) can result in system pressures below 0 psig.

2.0 REGULATORY EVALUATION

The following explains the applicability of General Design Criteria (GDC) for IP2 and IP3. The construction permits for IP2 and IP3 were issued by the Atomic Energy Commission (AEC) on October 14, 1966 and August 13, 1969, and the operating licenses were issued on September 28, 1973, and December 12, 1975. The plant GDC are discussed in the Updated Final Safety Analysis Report (UFSAR) Chapter 1.3, "General Design Criteria," (Reference 2) with more details given in the applicable UFSAR sections. The AEC published the final rule that added Title 1O of the Code of Federal Regulations ( 10 CFR) Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," in the Federal Register (36 FR 3255) on February 20, 1971(Reference3), with the rule effective on May 21, 1971. In accordance with an U.S.

Nuclear Regulatory Commission (NRC) staff requirements memorandum from S. J. Chilk to J. M. Taylor, "SECY-92-223 - Resolution of Deviations Identified During the Systematic Evaluation Program," dated September 18. 1992 (ADAMS Accession No. ML003763736)

(Reference 4), the Commission decided not to apply the Appendix A GDC to plants with Enclosure 2

construction permits issued prior to May 21, 1971. Therefore, the GDC which constitute the licensing bases for IP2 and IP3 are those in the UFSARs.

As discussed in the UFSARs, the licensees for IP2 and IP3 have made some changes to the facilities over the life of the units that have committed to some of the GDCs from 10 CFR Part 50, Appendix A The extent to which the Appendix A GDC has been invoked can be found in specific sections of the UFSARs and in other IP2 and IP3 licensing basis documentation, such as license amendments.

10 CFR 50.36, "Technical specifications," includes requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.

The NRC has established requirements in 10 CFR Part 50 to protect the integrity of the reactor coolant pressure boundary in nuclear power plants. The staff evaluates the acceptability of a facility's pressure-temperature (P-T) limits based on the following NRC regulations and guidance: Appendix G, "Fracture Toughness Requirements," to 10 CFR Part 50 (Reference 5);

Appendix H, "Reactor Vessel Material Surveillance Program Requirements," to 10 CFR Part 50 (Reference 6); Regulatory Guide (RG) 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," (Reference 7); Generic Letter (GL) 92-01, Revision 1, "Reactor Vessel Structural Integrity," (Reference 8); and GL 92-01, Revision 1, Supplement 1, "Reactor Vessel Structural Integrity," (Reference 9). Appendix G to 10 CFR Part 50 requires that facility P-T limits for the reactor vessel (RV) be at least as conservative as those obtained by applying the linear elastic fracture mechanics methodology of Appendix G to Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code. Appendix H to 10 CFR Part 50 establishes requirements related to facility RV material surveillance programs. RG 1.99, Revision 2, contains methodologies for determining the increase in transition temperature and the decrease in upper-shelf energy resulting from neutron irradiation.

3.0 TECHNICAL EVALUATION

3.1 Licensee's Evaluation The following changes to TS Figures for the P-T limit curves were proposed in the licensee's April 1, 2014, submittal:

• TS Figure 3.4.3-1, "Heatup Limitations for Reactor Coolant System" is revised to include the phrase, "Curves are applicable for vacuum fill."

• TS Figure 3.4.3-2, "Cooldown Limitations for Reactor Coolant System" is revised to include the phrase, "Curves are applicable for vacuum fill."

• TS Figure 3.4.3-3, "Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System" is revised to include the phrase, "Curves are applicable for vacuum fill."

3.2 Staff Evaluation The licensee's April 1, 2014, submittal proposed changes to TS Figures 3.4.3-1, 3.4.3-2 and 3.4.3-3 for the P-T limit curves for IP3, adding the following note to the figures, "Curves are applicable for vacuum fill." The revisions clarify that pressure limits are considered to be met for pressures that are below 0 psig (i.e., up to and including full vacuum conditions).

IP3 TS Bases 3.4.3, "RCS Pressure and Temperature Limits" provides the additional detail that vacuum fill of the RCS is performed " ... in Mode 5 under sub-atmospheric pressure and isothermal conditions." Certain operating practices, such as vacuum fill operations for the RCS, are common practice in both boiling water reactors and pressurized water reactors and can result in system pressures below 0 psig. Although the RV is not specifically evaluated for negative pressures, the magnitude of the negative pressure is limited to one atmosphere and thus is not expected to result in significant stresses. Therefore, the staff finds the revisions to the IP3 TS addressing pressures below 0 psig to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified 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, 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 (79 FR 64223). 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.

7.0 REFERENCES

1. Ventosa, John A., Site Vice President, Entergy Nuclear Operations, Inc. letter to Document Control Desk, U.S. Nuclear Regulatory Commission, "Proposed Changes

to Indian Point 3 Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves," (NL-14-035), Dockets No. 50-286, April 1, 2014, ADAMS Accession No. ML14099A333.

2. NRG, "Updated Final Safety Analysis Report (UFSAR), - Chapter 1.3, General Design Criteria", [Redacted Version] for Indian Point Nuclear Generating Unit No. 3, June 2011, ADAMS Accession No. ML11236A228.

3. Federal Regulation U.S. Code of Federal Regulations, "Domestic Licensing of Production and Utilization Facilities - General Design Criteria for Nuclear Power Plants," Title 10, of the Code of Federal Regulations (10 CFR) Part 50, Appendix A,"

as published in the Federal Register, February 20, 1971, 36 FR 3255.

4. Chilk, Samuel J. Secretary, Staff Requirements Memo to James M. Taylor, Executive Director of Operations, "SECY-92-223 - Resolution of Deviations Identified During The Systematic Evaluation Program," September 18, 1992, ADAMS Accession No. ML003763736.

5. Federal Regulation U.S. Code of Federal Regulations, "Domestic Licensing of Production and Utilization Facilities - Fracture Toughness Requirements,," Title 10, of the Code of Federal Regulations (10 CFR) Part 50, Appendix G.

6. Federal Regulation U.S. Code of Federal Regulations, "Domestic Licensing of Production and Utilization Facilities - Reactor Vessel Material Surveillance Program Requirements," Title 10, of the Code of Federal Regulations (10 CFR) Part 50, Appendix H.

7. USNRC, Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials," Revision 2, May 1988. *

8. USNRC, Generic Letter (GL) 92-01, Revision 1, (10 CFR 50.54(f)) "Reactor Vessel Structural Integrity."

9. USNRC, Generic Letter (GL) 92-01, Revision 1, Supplement 1, (10 CFR 50.54(f)

"Reactor Vessel Structural Integrity," May 19, 1995.

Principal Contributor: C.Fairbanks Date: March 6, 2015

March 6, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3- ISSUANCE OF AMENDMENTS RE: PROPOSED CHANGE TO INDIAN POINT 3 TECHNICAL SPECIFICATIONS REGARDING REACTOR VESSEL PRESSURE/TEMPERATURE LIMIT CURVES (TAC NO. MF3754)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 255 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 1, 2014.

The amendment revises TS Figures 3.4.3-1, "Heatup Limitations for Reactor Coolant System,"

3.4.3-2, "Cooldown Limitations for Reactor Coolant System," and 3.4.3-3, "Hydrostatic and lnservice Leak Testing Limitations for Reactor Coolant System" to address vacuum fill operations in the TSs. The proposed changes clarify that the figures are applicable for vacuum fill conditions where pressure limits are considered to be met for pressures that are below 0 pounds per square inch gauge (psig) (i.e., up to and including full vacuum conditions). Vacuum fill operations for the reactor coolant system can result in system pressures below 0 psig.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely, IRA/

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-286

Enclosures:

1. Amendment No. 255 to DPR-64

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

PUBLIC LPL 1-1 R/F RidsNrrPMlndianPoint RidsNrrDorl RidsNrrLAKGoldstein RidsNrrDorlLp11-1 RidsNrrDeEvib RidsNrrDorlDpr RidsRgn1 MailCenter RidsNrrDssStsb RidsAcrsAcnw_MailCTR CFairbanks ADAMS ACCESSION NO.: ML15050A144 *by memo dated OFFICE LPL 1-1/PM LPL 1-1/PM LPL 1-1/LA DE/EVIB ST SB/BC OGC LPL 1-1/BC NAME DRender DPickett KGoldstein SRosenberg* RElliott STurk BBeasley DATE 2/19/15 03/06/15 02/20/15 02/13/15 02/23/15 3/3/15 03/06/15 OFFICIAL RECORD COPY