ML15070A124
| ML15070A124 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/30/2015 |
| From: | Balwant Singal Plant Licensing Branch IV |
| To: | Edington R Arizona Public Service Co |
| Singal B | |
| References | |
| TAC MF3143, TAC MF3144, TAC MF3145 | |
| Download: ML15070A124 (29) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Randall K. Edington Executive Vice President Nuclear/
Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 March 30, 2015
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND
. 3 - ISSUANCE OF AMENDMENTS RE: TECHNICAL SPECIFICATION CHANGE REGARDING MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE FOR STARTUP TEST ACTIVITY REDUCTION PROGRAM (TAC NOS. MF3143, MF3144, AND MF3145)
Dear Mr. Edington:
- The U.S. Nuclear Regulatory Co.mmission (NRC, the Commission) has issued the enclosed Amendment No. 195 to Renewed Facility Operating License No. NPF-41, Amendment No. 195 to Renewed Facility Operating License No. NPF-51, and Amendment No. 195 to Renewed Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated November 20, 2013, as supplemented by letters dated November 20, 2013, and January 16 and December 19, 2014.
The amendments modify the moderator temperature coefficient (MTC) TS Surveillance Requirements associated with implementation of Westinghouse Electric Company LLC's topical report WCAP-16011-NP-A, Revision 0, "Startup Test Activity Reduction Program," February 2005. The changes are consistent with NRG-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-486, Revision 2, "Revise MTC Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011)."
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No. 195 to NPF-41
- 2. Amendment No. 195 to NPF-51
- 3. Amendment No. 195 to NPF-74
- 4. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, b~cb.8l~
Balwant K. Singal, Senior Project Manager,
Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY, ET AL.*
DOCKET NO. STN 50-528 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 License No. NPF-41
- 1.
- The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles
. Department of Water and Power, and Southern California Public Power Authority dated November 20, 2013, as supplemented by letters dated November 20, 2013, and January 16 and December 19, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 1 O 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. NPF-41 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. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwis.e stated in specific license conditions.
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance. The licensee shall submit a summary report, including the verification of applicability requirements, following the first application of the Startup Test Activity Reduction (STAR) Program as stated in Attachment 4 of the application dated November 20, 2013, associated with this amendment. If the safety analysis or STAR applicability requirements are not satisfied, the STAR program for the affected fuel cycle will not be used.
Attachment:
Changes to the Renewed Facility Operating License No. NPF-41
- and Technical Specifications Date of Issuance: March 30, 2015 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY. ET AL.
DOCKET NO. STN 50-529 PALO VERDE NUCLEAR GENERATING STATION. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 License No. NPF-51
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated November 20, 2013, as supplemented by letters dated November 20, 2013, and January 16 and December 19, 2014, complies with the standards and
- requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 arnendment 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. NPF-51 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. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions..
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance. The licensee shall submit a summary report, including the verification of applicability requirements, following the first application of the Startup Test Activity Reduction (STAR) Program as stated in Attachment 4 of the application dated November 20, 2013, associated with this amendment. If the safety _
analysis or STAR applicability requirements are not satisfied, the STAR program for the affected fuel cycle will not be used.
Attachment:
Changes to the Renewed Facility Operating License No. NPF-51 and Technical Specifications Date of Issuance: March 30, 2015 FOR THE NUCLEAR REGULATORY COMMISSION
--c!:. ~
? /ff'1...,f.1:J Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY. ET AL.
DOCKET NO. STN 50-530 PALO VERDE NUCLEAR GENERATING STATION. UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 License No. NPF-74
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf*of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated November 20, 2013, as supplemented by letters dated November 20, 2013, and January 16 and December 19, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Ch?pter 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 assuran.ce (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.
- I 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. NPF-74 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revis.ed through Amendment No. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where othe.rwise stated in specific license conditions.
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance. The licensee shall submit a summary report, including the verification of applicability requirements, following the first application of the Startup Test Activity Reduction (STAR) Program as stated in Attachment 4 of the application dated November 20, 2013, associated with this amendment. If the safety analysis or STAR applicability requirements are not satisfied, the STAR program for the affected fuel cycle will not be used.
Attachment:
Changes to the Renewed Facility Operating License No. NPF-74 and Technical Specifications Date of Issuance: March 30, 2015 FOR THE NUCLEAR REGULATORY COMMISSION
~~
f:.,- M-f1<+*fv!:J Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NOS. 195, 195, AND 195 RENEWED FACILITY OPERATING LICENSE NOS. NPF-41, NPF-51, AND NPF-74 DOCKET NOS. STN 50-528, STN 50-529. AND STN 50-530 Replace the following pages of the Renewed Facility Operating Licenses Nos. NPF-41, NPF-51, and NPF-74, and 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.
Renewed Facility Operating License No. NPF-41 REMOVE INSERT 5
5 Renewed Facility Operating License No. NPF-51 REMOVE INSERT 6
6 Renewed Facility Operating License No. NPF-74 REMOVE INSERT 4
4 Technical Specifications REMOVE 3.1.4-1 3.1.4-2 INSERT 3.1.4-1 3.1.4-2 3.1.4-3 (1)
Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power), in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed operating license.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
(3)
Antitrust Conditions This renewed operating license is subject to the antitrust condition$
delineated in Appendix C to this renewed license.
(4)
Operating Staff Experience Requirements Deleted (5)
- Post-Fuel-Loading Initial Test Program (Section 14. SER and SSER 2f Deleted (6)
Environmental Qualification
.Deleted (7)
Fire Protection Program APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:
APS may make changes to the approved fire protection program without prior approval, of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed Facility Operating License No. NPF-41 Amendment No. 195 (1)
Maximum Power Level Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts.
thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection *Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this renewed operating license.
APS shalloperate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
(3)
Antitrust Conditions This renewed operating license is subject to the antitrust conditions delineated in Appendix C to this renewed operating license.
( 4)
Operating Staff Experience Requirements (Section 13.1.2. SSER 9)
- Deleted (5)
Initial Test Program (Section 14, SER and SSER 2)
Deleted (6)
Fire Protection Program APS shall implement and maintain in effed all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:
APS may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(7) lnservice Inspection Program (Sections 5.2.4 and 6.6, SER and SSER 9)
Deleted The parenthetical notation, following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed Facility Operating License No. NPF-51 Amendment No. 195 (4)
Pursuant to the Act and 10 CFR Part 30, 40, and 70, APS to receive, possess, and use in amounts 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 (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, APS to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation 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 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 Arizona Public Service Company (APS) is authorized to operate the facility at reactor core power levels not in excess of 3990 megawatts thermal (100% power), in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated into this renewed operating licens_e.
APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
(3)
Antitrust Conditions This renewed operating license is subject to the antitrust conditions delineated in Appendix C to this renewed operating license.
(4)
Initial Test Program (Section 14. SER and SSER 2)
Deleted (5)
Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 171, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Additional Conditions.
Renewed Facility Operating License No. NPF-74 Amendment No. 195
3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Moderator Temperature Coefficient (MTC)
MTC
. 3.1.4 LCO 3.1.4 The MTC shall be maintained within the limits specified in the COLR. and a maximum positive limit that varies linearly.
from 0.5 E-4 ~k/k/°F at 0% RTP to 0.0 ~k/k/°F at 100% RTP.
APPLICABILITY:
. MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
MTC not within* limits. A.l Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> PALO VERDE UNITS 1.2.3 3.1.4-1 AMENDMENT NO. W 195
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.4.1
- -"\\~-----------------NOTE------------------
I. _,.J This Surveillance is not required to be performed prior to entry into MODE 2.
Verify MTC is within the upper limit specified in*the COLR.
PALO VERDE UNITS 1.2.3 3.1.4-2 FREQUENCY MTC 3.1.4 Prior to entering MODE 1 after each fue 1 1 oadi ng AND
NOTE-----
Only required to be performed when MTC determined prior to entering MODE 1 is verified using adjusted predicted MTC Each fuel cycle within 7 EFPD of reaching 40 EFPD core burnup (continued)
AMENDMENT NO. ++/-+ 195
SURVEILLANCE REQUIREMENTS (continued)
SR 3.1. 4. 2 SURVEILLANCE
NOTES-------------------
- 1.
This Surveillance is not required to be performed prior to entry into MODE 1 or 2.
- 2.
If the MTC is more negative than the limit specified in the COLR when extrapolated to the end of cycle.
SR 3.1.4.2 may be repeated.
Shutdow~
must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower l i mit.
- 3.
The MTC verification at 2/3 of expected core burnup is not required if the results of the measurement at 40 EFPD are within a tolerance of
+/- 0.16*10E-4 Lik/k/°F from the corresponding design values.
Verify MTC is within the lower limit specified in the COLR.
PALO VERDE UNITS 1.2,3 3.1.4-3 MTC 3.1.4 FREQUENCY Each fue 1 eye 1 e within 7 EFPD of reaching 40 EFPD core burnup AND Each fuel cycle within 7 EFPD of reaching 2/3
- of expected core burnup AMENDMENT NO. W 195
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 195, 195, AND 195 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-41. NPF-51, AND NPF-74 ARIZONA PUBLIC SERVICE COMPANY. ET AL.
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530
1.0 INTRODUCTION
By application dated November 20, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13329A036), 1 as supplemented by letters dated November 20, 2013, 2 and January 16 and December 19, 2014 (ADAMS Accession Nos. ML13329A699, ML14027A701, and ML15005A028, respectively), Arizona Public Service Company (APS, the licensee) requested changes to the Technical Specifications (TSs) for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS). Portions of the letter dated November<20, 2013 (P), contain sensitive unclassified non-safeguards information and accordingly have been withheld from public disclosure.
The proposed changes would modify the moderator temperature coefficient (MTC) TS Surveillance Requirement (SR) 3.1.4.1, utilizing the Westinghouse Electric Company LLC (Westinghouse) topical report (TR) WCAP-16011-NP-A, Revision 0, "Startup Test Activity Reduction Program," February 2005 (ADAMS Accession No. ML050660118). The changes are consistent with NRG-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-486, Revision 2, "Revise MTC Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011)" (ADAMS Accession No. ML071300267). The use of WCAP-16011-NP-A is justified by the licensee in the Westinghouse WCAP-17787-NP, Revision 0, "Palo Verde Nuclear Generating Station STAR Program Implementation Report," August 2013 (ADAMS Accession No. ML13329A038),
provided as Attachment 6 to the letter dated November 20, 2013 (NP).
APS also requested a change to the PVNGS TS, which would not require the MTC
- determination in SR 3.1.4.2 if the result of the MTC determination required in TS 3.1.4.1 is within a certain tolerance of the corresponding design value. This change is based on the methods described in Combustion Engineering (CE) Owners Group Report CE NPSD-911-A and Amendment 1-A, "Analysis of Moderator Temperature Coefficients in Support of a Change 1 Designated as November 20, 2013 (NP).
2 Designated as November 20, 2013 (P).
in the Technical Specifications End-of-Cycle Negative MTC Limits," September 2000 (ADAMS Accession No. ML003752592).
The supplemental letters dated January 16 and December 19, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on February 27, 2014 (79 FR 11146).
2.0 REGULATORY EVALUATION
The Commission's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications."
Section 50.36 requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The regulation requires, in part, that the TSs include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. The changes proposed by the licensee are related to the existing SRs.
Startup Physics Testing The regulations in 10 CFR Part 50 do not explicitly prescribe specific post-refueling startup testing. However, the genesis for post-refueling startup testing can be traced to the preoperational testing. The regulation at 10 CFR 50.34, "Contents of applications; technical information," requires the licensee to specify post-refueling startup testing in the Final Safety Analysis Report (FSAR). The regulation at 10 CFR 50.36 specifies SRs 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. The MTC is a parameter controlled in the licensee's TSs, including an LCO that is verified through SRs. As such, the MTC and the applicable LCOs and SRs are subject to regulatory oversight.
.Section 10 CFR 50.36(a)(1) of 10 CFR states, in part, that "[a] summary statement of the bases or reasons for such specifications other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications." The licensee 'may make changes to the TS Bases without prior NRC staff review and approval in accordance with the TS Bases Control Program in TS 5.5.14.
End-of-Cycle MTC Conditional Measurement Elimination The reviewed methodology describes the process to be used to evaluate and apply conditional measurement elimination to TS 3.1.4, "Moderator Temperature Coefficient (MTC)." This TS specifies SRs required by 10 CFR 50.36(c)(3), "Surveillance requirements," to demonstrate that the MTC is within the limits assumed in the licensee's FSAR accident and transient analyses.
Over the course of the cycle, the MTC becomes increasingly negative as a result of fuel burn up and controlled dilution of the boron in the reactor coolant system (RCS). 1.n accordance with SR 3.1.4.1, the licensee must therefore perform a beginning-of-cycle MTC measurement to verify that the upper limit on MTC (the most positive MTC limit) will be met. The licensee must I
also perform an end-of-cycle MTC measurement, in accordance with SR 3.1.4.2, to ver,ify that the lower limit on MTC (the most negative MTC limit) will also be met.
The change proposed by the licensee addresses this end-of-life most negative MTC SR. Under TS 3.1.4, the licensee must perform an MTC measurement before the end of the cycle. The licensee must perform this measurement 7 effective full-power days (EFPD) after reaching two-thirds of expected core burnup.
The limitations on MTC contained in TS 3.1.4 and verified by SR 3.1.4.2 provide assurance that the value of the coefficient remains within the limiting Condition assumed in the FSAR accident and transient analyses. This provides assurance that the reactor will be operated in a safe manner.
3.0 TECHNICAL EVALUATION
3: 1
Background
3.1.1 Discussion of STAR Program WCAP-16011-NP-A describes methods intended to reduce the time required for startup testing and proposes methods to eliminate the control element assembly (CEA) worth and isothermal temperature coefficient (ITC) measurements at hot zero power (HZP). WCAP-16011-NP-A includes a method to substitute the measured value of the MTC at HZP with an alternate MTC value consisting of the predicted (calculated) MTC and measured critical boron concentration (CBC) at HZP. WCAP-16011-NP-A also adds an ITC measurement at intermediate to hot full power (HFP), and applicability requirements for core design, fabrication, refueling,* startup testing, and CEA lifetime viability requirements. WCAP-16011-NP-A methods can only be applied to cores that are well characterized by an existing database.
The STAR Program (WCAP-16011-NP-A) was originally developed as part of a project sponsored by the Westinghouse Owners Group. Implementation of the STAR Program was approved, by NRC letter dated January 14, 2005 (ADAMS Accession No. ML050180327), for the original group of participating CE plants, which did not include PVNGS. NUREG-1432, Volume 1, Revision 4.0, "Standard Technical Specifications - Combustion Engineering Plants,
October 2011 (ADAMS Accession No. ML12102A165), has also been updated to include TS changes that are consistent with STAR implementation. The program has since been applied to a number of CE plants..
The purpose of the WCAP-17787-NP is to justify application of the STAR Program to PVNGS.
The PVNGS plants are of the CE System 80 design. With respect to reactor, core, and fuel design, WCAP-17787-NP establishes that these plants are similar to those CE plants that have already been approved for STAR application.
Attachment A of Appendix Gin WCAP-16011-NP-A includes a list of specific actions and recommended activities to be performed to allow implementation of the STAR Program for non-participating plants. The justification contained within WCAP-17787-NP follows the general guidelines set forth in Attachment A of Appendix G of WCAP-16011-NP-A.
As part of STAR program implementation, the licensee requested a change to SR 3.1.4.1 to allow the HZP ITC to be determined by a calculated value that is augmented by the measured CBC during startup. If this alternate determination of the HZP ITC is performed, the licensee must perform a measurement of the HFP ITC within 7 EFPD of reaching a core burnup of 40 EFPD.
3.1.2 Discussion of Conditional MTC Measurement Elimination The licensee also proposed changes to SR 3.1.4.2 to allow the option to eliminate the MTC measurement at two-thirds of expected core burnup, if the result of the 40 EFPD MTC measurement is within a tolerance limit of the design value. If the measurement were not within the tolerance limit, then performance of the two-thirds cycle surveillance would be required. The CE Owners Group TR CE NPSD-911-A and Amendment 1-A provides justification for the proposed change. Attachment 7 to the licensee's letter dated November 20, 2013 (NP),"Near End of Cycle (EOC) MTC Elimination Informational Benchmark," discusses the PVNGS CASMO/SIMULATE models used by APS in support of this EOC MTC elimination request.
3.2 Description of TS Changes The proposed amendment would modify the MTC SRs 3.1.4.1 and 3.1.4.2 as follows:
SR 3.1.4.1 The current Frequency for SR 3.1.:4.1 states:
Prior to entering MODE 1. after each fuel loading The revised Frequency for SR 3.1.4.1 would state:
Prior to entering MODE 1 after each fuel loading
- - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - ""' -
Only required to be performed when MTC determined prior to entering MODE 1 is verified using adjusted predicted MTC Each fuel cycle within 7 EFPD of reaching 40 EFPD core burnup SR 3.1.4.2 The current Surveillance Notes for SR 3.4.1.2 state:
NOTES--------~-----------------
- 1.
This Surveillance is not required to be performed prior to entry into MODE 1or2.
- 2.
If the MTC is more negative than the COLR limit when extrapolated to the end of cycle, SR 3.1.4.2 may be repeated. Shutdown must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower limit.
'The revised Surveillance Notes for SR 3.4.1.2 state:
- - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1.
This Surveillance is not required to be performed prior to entry into MODE 1or2.
- 2.
If the MTC is more negative than the limit specified in the COLR when extrapolated to the end of cycle, SR 3.1.4.2 may be repeated. Shutdown must occur prior to exceeding the minimum allowable boron concentration at which MTC is projected to exceed the lower limit.
- 3.
The MTC verification at 2/3 of expected core burn up is not required if the res.ults of the measurement at 40 EFPD are within a tolerance of
+/- 0.16*1 OE-4 b.k/k/°F from the corresponding design values.
The current Frequency for SR 3.1.4.2 states:
Each fuel cycle within 7 effective full power days (EFPD) of reaching 40 E,FPD core burnup Each fuel cycle within 7 EFPD of reaching ~ of expected core burnup The revised, Frequency for SR 3.1.4.2 would state:
Each fuel cycle within 7 EFPD of reaching 40 EFPD core burnup Each fuel cycle within 7 EFPD of reaching 2/3 of expected core burnup 3.3
NRC Staff Evaluation
3.3.1 Evaluation of PVNGS STAR Implementation The generic STAR program is defined in the NRG-approved TR WCAP-16011-NP-A. This TR describes changes to pressurized-water reactor reload startup testing to reduce testing operations and testing time while achieving the following objectives: (1) ensure that the core can be operated as designed, and (2) employ normal operating procedures in the startup evolution. In this context, the use of the reactivity computer was not considered by CE to be a "normal" operating procedure.
WCAP-16011-NP-A describes a method to reduce the time required for startup testing. To this end, the TR allows elimination of the CEA worth and ITC measurements at HZP. The TR also allows substitution of the measured value of the MTC at HZP with an alternate MTC value
- consisting of the predicted (calculated) MTC and measured CBC at HZP. An MTC measurement at intermediate to HFP, and applicability requirements for core design, fabrication, refueling, startup testing, and CEA lifetime viability is added as additional requirements.
Because of the applicability requirements and various startup measurement changes, this method can only be applied to cores that are well characterized by an existing database of previous measurements. This database is used to demonstrate that core calculations are accurate, ascertain the effectiveness of the existing startup testing program for comparison to the STAR program effectiveness, and determine if changes to the applicability requirements or measurements need to be included in the STAR program implementation at the plant.
In the NRC safety evaluation (SE) for WCAP-16011~NP-A, dated January 14, 2005 (ADAMS Accession No. ML050180327), the NRC identified three conditions and limitations for the application of the WCAP-16011-NP-A to individual licensees.
- 1.
The STAR program is applicable only to the participating plants as defined in Table 3-1 of the TR.
- 2.
Should any of the STAR test results fall outside of the test criteria, either ascertain that the safety analysis and STAR applicability requirements are satisfied, or discontinue use of the STAR program for that fuel cycle. *
- 3.
The Staff requires each licensee.using STAR to submit a summary report following the first application, either successful or not, of STAR to its.
plant. The report should (a) identify the core design method used, (b) compare the measured and calculated.values and the differences between these values to the corresponding core design method uncertainties and (c) show compliance with the STAR applicability requirements. If the application of STAR is unsuccessful, identify the reasons why the STAR application failed.
3.3.1.1 Condition 1 As mentioned previously, the licensee provided WCAP-17787-NP to justify application of the STAR program to PVNGS. When determining whether or not it is *acceptable to extend the STAR program to any plant not originally considered in WCAP-16011-NP-A, the NRC staff considers two major issues. First, the staff considers changes to be made to the plants startup testing program and whether the changes made impact the effectiveness of original program.
Second, the staff considers whether there are any unique design features that would impact the ST AR applicability..
Section 3 of WCAP-17787-NP addresses first part of this first consideration. The PVNGS startup physics program is evaluated on its own merits, then compared to a "generic program" (developed based on contemporary plant practices in WCAP-16011-NP-A), and the STAR program. Table 3-2 of the WCAP-summarizes the comparison. In moving to the STAR program, PVNGS will eliminate a CEA worth test. PVNGS will also eliminate an HZP CBC test and an inverse boron worth test, both of which are used solely to support the CEA worth test.
The HZP ITC measurement is also removed and replaced with an MTC alternative surveillance, as previously discussed. The original STAR program implemented a CEA drop characteristics test, largely to verify CEA coupling. PVNGS plans to deviate from the original STAR program and not perform this test, as the plant has other means of verifying CEA coupling due to PVNGS's unique design features.,
The other part of the first consideration (the impact of the test changes) and the second consideration (the design features unique to the plant) are discussed in Section 4 of WCAP-17787-NP. Section 3 discussed the purpose of each test and Section 4 assesses the ability of both the generic program and the STAR program to evaluate problems. These assessments are based on a review of problem detection in the industry presented in Appendix A,. "effectiveness ratings" for each test, pre-operational activity, and STAR applicability requirements as determined in Appendix B, and a discussion of the PVNGS unique design features provided in Appendix C.
WCAP-17787-NP, Appendix A, describes a review of plant operating history to determine
- whether or not the conclusions of the original STAR topical report (i.e., that certain startup tests could be eliminated with no impact on detection of problems) remained applicable. The appendix concluded that, since the original STAR topical report was released, prediction of CEA worth and MTC have significantly improved and that the tests eliminated in the STAR program have not been effective at detecting problems. Based on ~ review of the information provided, the NRC staff accepts these conclusions and therefore accepts the continued applicability of the concJusions from the original STAR topical report.
WCAP-17787-NP, Appendix B, provided updates of the effectiveness ratings that were developed in the original STAR topical report. These updates accounted for (1) differences between the generic testing program and the PVNGS testing program, (2) differences between the STAR report and PVNGS pre-operational activities, (3) changes to the STAR applicability requirements for application to PVNGS, and (4) several unique plant design features. Though the majority of the effectiveness ratings remained the same between PVNGS and the original STAR report, one test and one pre-operational activity were found to be less effective in detecting CEA distortion and CEA absorber loss due to unique design features at PVNGS.
However, the information presented by the licensee indicated that these problems remain better detected by other tests and pre-operational activities. The licensee also stated that the effectiveness with which these problems are detected using the STAR program is the same as or better than the original STAR program and the current PVNGS startup program. The NRC staff reviewed the information provided by the licensee and determined (a) that the difference in test effectiveness is a result of one of the PVNGS unique design features and therefore exists within the current PVNGS testing regime and (b) that the eliminated CEA worth and drop characteristics tests are less effective at detecting problems than tests that are retained in the PVNGS STAR program, resulting in no net change in the effectiveness of detecting CEA distortion and absorber loss. Because the differences resulted in no net change in the startup program's ability to detect core problems, the staff determined that this difference in the effectiveness rating of the aforementioned test and pre-operational activity is acceptable.
WCAP-17787-NP, Appendix C, summarized an evaluation of the rest of the CE fleet to identify design features that are unique to PVNGS. This appendix also described how these design features have influenced PVNGS startup testing and pre-operational activities, and what kind of effect they could have on the implementation of the STAR program. Several unique design features were identified and assessed for their impact. Though most were found to have no bearing on the testing, the licensee used one feature to justify the elimination of the CEA drop characteristics test from the PVNGS STAR program, because alternate means were available to confirm CEA-extension shaft coupling. The unique design of PVNGS is such that CEAs are not.
shuffled from one position to another during outages. The NRC staff reviewed the method by
- which the licensee proposed to verify coupling of the CEA to the shaft and determined that it will function as well as the performance of the eliminated CEA drop characteristics test. The other functions of the CEA drop characteristics test were evaluated in Appendix B and determined to be better detected by other tests, as descri~ed in the above paragraph. The staff determined, therefore, that this variance from the original STAR program is acceptable.
WCAP-17787-NP, Appendix C, also discusses several changes and additions to the STAR applicability requirements that are added as a result of the PVNGS unique design features. The NRC staff reviewed these changes and additions and determined that they are necessary to account for PVNGS unique design features and will help to ensure that the startup testing performed remains effective in detecting problems with the core.
The NRC staff reviewed Section 4 of WCAP-17787-NP and the supporting Appendices A, B, and C, and determined that the PVNGS STAR implementation discussed therein will be as effective as the current PVNGS startup program.
3.3.1.2 Cond 0
itions 2 and 3 The regulatory commitments made by the licensee are described in Attachment 4 of the letter dated November 20, 2013 (NP), and are also described in Section 4.0 of this SE. Two of these commitments were intended to satisfy Conditions 2 and 3. The NRC staff reviewed these commitments and determined that the licensee acceptably satisfied the conditions.
Condition 2 is satisfied through the following commitment:
APS will include verification of the approved applicability requirements in appropriate site startup testing procedures. APS will include guidance in the procedures to ensure that the safety analysis and STAR applicability requirements are satisfied when STAR test results fall outside the test criteria. If the safety analysis or STAR applicability requirements are not satisfied, the STAR program for the affected fuel cycle will not be used.
Condition 3 is satisfied through the following commitment:
APS will submit a summary report following the first application of STAR at PVNGS that will:. (a) identify the core design method used, (b) compare the measured and calculated values and the differences between these values to the corresponding core design method uncertainties and (c) show compliance with the STAR applicability requirements. If the application of STAR is unsuccessful, APS will identify the reasons why the STAR application failed.
3.3.1.3 Conclusion on STAR Implementation The NRC staff reviewed the licensee's justification for application of the STAR program to PVNGS, as described in WCAP-17787-NP. The staff determined that the use of the STAR program is acceptable at PVNGS, subject to the variances discussed in WCAP-17787-NP. The licensee provided regulatory commitments described above to satisfy Conditions 2 and 3 of WCAP-16011-NP-A.
3.3.2 Evaluation of 2/3 Cycle MTC Measurement Conditional Elimination TS 3.1.4 provides limitations on the MTC to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. These limitations are administratively controlled within the Core Operating Limits Report (COLR). Accurate knowledge of the MTC at EOC is of prime importance in order to ensure that the most negative MTC will always be conservative with respect to the TS limit. The requirements to measure the MTC at the beginning-of-cycle (BOC) (one at HZP and one at power) and near EOC (i.e.,
two-thirds expected core burnup) provide confirmation that the measured MTC value is within its limits and will remain within its limits throughout each cycle.
This proposed change modifies the MTC TSs to eliminate the two-thirds cycle MTC surveillance, if the result of the first MTC measurement falls within +/- 0.16*1 OE-4 ~k/k/°F of the calculated MTC (design value). However, if the result of the first test is not within that limit, then performance of the two-thirds cycle surveillance will be required.
The licensee's methodology for this conditional EOC MTC measurement elimination is based on CE NPSD-911-A. The NRC SE on CE NPSD-911-A, Amendment 1, dated June.14, 2000 (ADAMS Accession No. ML003723422), stated the approach described in CE NPSD-911-A was acceptable provided the following conditions, as described in Amendment 1, were met:
- 1.
In order to ensure that the moderator temperature coefficient will not exceed the Technical Specification limit with a confidence/tolerance of 95/95 percent, the cycle must be designed, using the CE methodology, such that the best estimate MTC is:
- a. more negative than the BOC Technical Specification limit by the design margin
- b. more positive than the EOC Technical Specification limit by the design margin
- 2.
The design margin is determined to be 1.6 pcm/° F [percent mille/degrees Fahrenheit] at all times in life.
- 3.
The analysis of the revised data base, including the most recent measured and calculated MTCs, has established that if the measured beginning-of-cycle moderator temperature coefficients are within 1.6 pcm/° F of the best estimate prediction, then it can be assumed that the end-of-cycle coefficient will also be within 1.6 pcm/° F of the prediction and its measurement is not required.
- 4.
The measured data reduction must be based on the current CE methodology as described in the report.
- 5.
If the beginning-of-cycle measurements fail the acceptance criteria of
+/-1.6 pcm/° F and the discrepancy cannot be resolved, the end-of cycle surveillance test must be performed.
Conditions *1 and 4 of CE NPSD-911-A require the use of the CE methodology for core design and measured data reduction. APS, however, does not use the CE methodology for these purposes. PVNGS's nuclear design and analysis is performed with the CASMO/SIMULATE code system, the use of which atPVNGS was approved by the NRC by letter dated March 20, 2001 (ADAMS Accession No. ML010860187). To justify application of the CE NPSD-911-P-A methodology without the CE nuclear design methodology, APS provided benchmarks in of the letter dated November 20, 2013 (NP), entitled "Near End of Cycle (EOC)
MTC Elimination Informational Benchmark," where the licensee stated.
Benchmarks that were performed in support of the transition of Palo Verde to CASMO/SIMULATE confirm that the MTC predictive uncertainty for CASMO/SIMULATE is within the acceptance value of 1.6 pcml°F and the variance at BOC and near EOC pool. The Palo Verde Safety Analyses employ a conservative ITC uncertainty of 1.6 pcm/°F.
The licensee provided additional data on these benchmarks in Table 1 of the Attachment 7 to the letter dated November 20, 2013 (NP). The CASMO/SIMULATE data compare well to the DIT/ROCS data provided in the CE NPSD-911-A TR, with a slightly lower standard deviation (and therefore a slightly tighter tolerance limit). The NRC staff therefore considers the use of CASMO/SIMULATE at PVNGS to be compatible with the CE conditional EOC MTC measurement elimination methodology documented in CE NPSD-911-A, with an ITC uncertainty of 1.6 pcm!° F. The staff determined that this aspect of Conditions 1 and 4 is satisfied..
Conditions 1 and 2 of CE NPSD-911-A require the design margin between the best-estimate MTC for the cycle and the TS limits to be 1.6 pcm/° F at all times in core life, and that the uncertainty in predictions of the ITC or MTC must be less than this 1.6 pcm/° F design margin.
The licensee addressed the first Condition in its December 19, 2014, response to an NRC request for additional information. The NRC staff requested that the licensee clarify how APS would ensure that the plant would remain bounded by LCO 3.1.4 most negative MTC limit in operation up to the plant TS limits. APS stated, in part:
APS performs a reload analysis (reload core safety evaluation) e(:ich cycle that includes a conservative calculation of the most negative MTC possible during the planned operating cycle. The analysis includes the biases, uncertainties, and operating allowances required to ensure margin is maintained to the limits of LCO 3.1.4.
The magnitude of this design margin was also addressed by the licensee in Attachment 7 to the letter dated November 20, 2013 (NP). Since the licensee stated that the ITC uncertainty to be used would be 1.6 pcm/° F and that this uncertainty would be included in the calculation of the most negative MTC limit provided in the COLR, the NRC staff determined that the licensee satisfied CE NPSD-911-A Conditions 1 and 2.
Conditions 3 and 5 govern how the CE NPSD-911-Amethodology is to be applied. Condition 3 clarifies that the methodology allows elimination of the EOC MTC measurement if the BOC MTC measurement is within 1.6 pcm/° F of the design value. Condition 5 explicitly requires the licensee to perform the EOC MTC measurement if the BOC MTC measurement is not within 1.6 pcm/° F of the design value. The NRC staff determined that both of these conditions are satisfied by the language provided in the proposed TS changes. The acceptance criterion of "0.16*1 OE-4 tik/k/° F" provided in the TS change is equal to the 1.6 pcm/°F criterion prescribed in the TR methodology, though the units have been adjusted to be consistent with the PVNGS TS. The measurement is eliminated if the acceptance criterion is met, and is required if the acceptance criterion is not met. Hence, the staff determined that CE NPSD-911-A Conditions 3 and 5 are satisfied.
The NRC staff reviewed APS's proposed TS changes related to the application of the CE NPSD-911-A methodology. The staff determined that they were aligned to the conditions and limitations specified in the NRC's SE for the methodology and concludes, therefore, that the proposed TS changes are acceptable.
3.3.3 Results of the NRC Staff Evaluation The licensee submitted WCAP-17787-NP to justify application of the STAR methodology described in WCAP-16011-NP-A (the original STAR report) as well as to support the modifications requested by PVNGS in its letter dated November 20, 2013 (NP). The NRC staff reviewed WCAP-17787-NP against WCAP-16011-NP-A to verify that use of the STAR methodology at PVNGS will produce results at least as effective as the present PVNGS startup program. The NRC staff review, as discussed in Section 3.3.1, concluded that the use of the PVNGS STAR program as described in WCAP-17787-NP and WCAP-16011-NP-A is acceptable at PVNGS. The modification of SR 3.1.4.1 is therefore also acceptable.
Similarly, the licensee requested a change to SR 3.1.4.2, which verifies that the EOC MTC values are within TS operating limits, based on the methodology of CE NPSD-911-A. The NRC staff reviewed the requested TS change against the conditions and limitations set in the SE for CE NPSD-911-A. Since the licensee met the criteria specified in the SE for CE NPSD-911-A, the NRC staff concludes that the modification of SR 3.1.4.2 is acceptable.
The NRC staff concludes that SR 3.1.4.1 and SR 3.1.4.2, as modified, meet the regulatory requirements of 10 CFR 50.36 because they continue to provide assurance that the necessary quality of systems and components will be maintained and that the LCOs will be met.
Therefore, the NRC staff concludes that the proposed changes are acceptable.
The licensee also provided the proposed TS Bases changes corresponding to the proposed TS changes. The proposed TS bases are provided for information only and are not reviewed by the NRC staff.
4.0 REGULATORY COMMITMENTS The licensee made the following regulatory commitments in its letter dated November 20, 2013 (NP), to satisfy the NRC staff conditions specified in WCAP-16011-NP-A for its application to PVNGS. The licensee provided the proposed TS Bases to the NRC staff in the letter dated November 20, 2013 (NP). The other commitments are referenced in the implementation statement on the amendment pages.
Regulatory Commitment Description Due Date/Event APS will establish Technical Specification Bases for Complete and implement with TS 3.1.4 consistent with those shown in the *license approved license amendment amendment.
implementation.
APS will include verification of the applicability Complete and implement with requirements in appropriate site startup testing procedures. approved license amendment APS will include guidance in the procedures to ensure that implementation.
the safety analysis and STAR applicability requirements are satisfied when STAR test results fall outside the test criteria. If the safety analysis or STAR applicability requirements are not satisfied, the STAR program for the affected fuel cycle will not be used.
APS will submit a summary report following the first Within 90-days of completion of application of STAR at PVNGS that will: (a) identify the the first application of STAR at core design method used, (b) compare the measured and PVNGS.
calculated values and the differences between these values to the corresponding core design method uncertainties and (c) show compliance with the STAR applicability requirements. If the application of STAR is unsuccessful, APS will identify the reasons why the STAR application failed.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arizona* State official was notified on March 13, 2015, of the proposed issuance of the amendment. The State official had no comments.
6.0 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. 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 February 27, 2014 (79 FR 11146). 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.
7.0 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 Contributors: R. Anzalone, NRR/DSS/SNPB M. Hamm, NRR/DSS/STSB Date: March 30, 2015
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosures:
- 1. Amendment No. 195 to NPF-41
- 4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-1 r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-1 Resource RidsNrrDssSnpb Resource ADAMS Accession No. ML15070A124 Sincerely; IRA!
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMPaloVerde Resource RidsRgn4MailCenter Resource MHamm, NRR/DSS/STSB RAnzalone, NRR/DSS/SNPB
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