ML15321A472
| ML15321A472 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/23/2015 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | James Shea Tennessee Valley Authority |
| Sayoc E, NRR/DORL/LPLII-2 | |
| References | |
| CAC MF5748, CAC MF5749, CAC MF5750 | |
| Download: ML15321A472 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 December 23, 2015
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - ISSUANCE OF AMENDMENTS REGARDING REVISIONS TO TECHNICAL SPECIFICATION 3.3.6.1, "PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION" (CAC NOS. MF5748, MF5749, AND MF5750)
Dear Mr. Shea:
The Commission has issued the enclosed Amendment Nos. 294, 319, and 277 to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68, for the Browns Ferry Nuclear Plant, Units 1, 2, and 3, respectively. These amendments are in response to your application dated February 17, 2015, as supplemented by letter dated September 25, 2015.
The amendments revise Technical Specification (TS) Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," to correct an inadvertent omission made by Amendment Nos. 251, 290, and 249, for Units 1, 2, and 3, respectively. Specifically, the proposed revision would add the number "3" to the column titled, "Applicable Modes or Other Specified Conditions, for Function 5.g, Standby Liquid Control (SLC) System Initiation. This revision corrects the error discussed above and ensures that the SLC System Mode applicability aligns with all SLC System safety functions, as well as with the Mode applicability of TS 3.1.7, "Standby Liquid Control (SLC) System." The SLC System is required to be operable in Mode 3 because, in addition to reactivity control in Modes 1 and 2, the SLC System is used to maintain suppression pool pH at or above 7 in the event of a loss-of-coolant accident. The SLC System operation and operability remain unchanged as a result of these amendments.
A copy of our related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Docket Nos. 50-259, 50-260, and 50-296
Enclosures:
- 1. Amendment No. 294 to DPR-33
- 2. Amendment No. 319 to DPR-52
- 3. Amendment No. 277 to DPR-68
- 4. Safety Evaluation cc w/enclosures: Distribution via Listserv Sincerely, v~L/h~
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERA TING LICENSE Amendment No. 294 Renewed License No. DPR-33
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 17, 2015, as supplemented by letter dated September 25, 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-33, and is hereby amended as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 2 9 4, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
Attachment:
FOR THE NUCLEAR REGULA TORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance:
December 2 3, 2O1 5
ATTACHMENT TO LICENSE AMENDMENT NO. 294 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Replace page 3 of Renewed Facility Operating License No. DPR-33 with the attached Page 3.
Replace the following page of Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE 3.3-60 INSERT 3.3-60
(3)
(4)
(5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
BFN-UNIT 1 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; 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 294, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, 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 234.
Renewed License No. DPR-33 Amendment No. 294
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 5.
Reactor Water Cleanup (RWCU) System Isolation
- a.
Main Steam Valve Vault 1,2,3 2
F SR 3.3.6.1.2 s 201°F Area Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
- b.
Pipe Trench Area 1,2,3 2
F SR 3.3.6.1.2 s 135"F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
- c.
Pump Room A Area 1,2,3 2
F SR 3.3.6.1.2 s 152"F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
- d.
Pump Room B Area 1,2,3 2
F SR 3.3.6.1.2 s 152°F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
- e.
Heat Exchanger Room 1,2,3 2
F SR 3.3.6.1.2 s 170"F Area (West Wall)
SR 3.3.6.1.5 Temperature - High SR 3.3.6.1.6
- f.
Heat Exchanger Room 1,2,3 2
F SR 3.3.6.1.2 s 143°F Area (East Wall)
SR 3.3.6.1.5 Temperature - High SR 3.3.6.1.6
- g.
SLC System Initiation 1,2,3 1(a)
H SR 3.3.6.1.6 NA
- h.
Reactor Vessel Water 1,2,3 2
F SR 3.3.6.1.1 2'. 528 inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6
- 6.
Shutdown Cooling System Isolation
- a.
Reactor Steam Dome 1,2,3 F
SR 3.3.6.1.2 s 115 psig Pressure - High SR 3.3.6.1.5 SR 3.3.6.1.6
- b.
Reactor Vessel Water 3,4,5 2(b)
SR 3.3.6.1.1 2'. 528 inches Level-Low, Level3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6
- c.
Drywell Pressure - High 1,2,3 2
F SR 3.3.6.1.2 s 2.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6 (a) One SLC System Initiation signal provides logic input to close both RWCU valves.
(b) Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 1 3.3-60 Amendment Nos. ~. ~.
~.~,294
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 319 Renewed License No. DPR-52
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 17, 2015, as supplemented by letter dated September 25, 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-52, and is hereby amended as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 31 9, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
Attachment:
FOR THE NUCLEAR REGULA TORY COMMISSION
~~~***
Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 23, 201 5
ATTACHMENT TO LICENSE AMENDMENT NO. 319 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Replace page 3 of Renewed Facility Operating License No. DPR-52 with attached page 3.
Replace the following page of Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE 3.3-62 INSERT 3.3-62 sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
BFN-UNIT 2 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; 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal.
(2)
Technical Specifications
- 3)
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 319, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 253. For SRs that existed prior to Amendment 253, 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 253.
The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's Renewed License No. DPR-52 Amendment No. 319
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6. 1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1
- 5.
Reactor Water Cleanup (RWCU) System Isolation
- a.
Main Steam Valve Vault 1,2,3 2
F SR 3.3.6. 1.2
~ 188°F Area Temperature - High SR 3.3.6. 1.5 SR 3.3.6. 1.6
- b.
Pipe Trench Area 1,2,3 2
F SR 3.3.6. 1.2
~ 135°F Temperature - High SR 3.3.6. 1.5 SR 3.3.6. 1.6
- c.
Pump Room A Area 1,2,3 2
F SR 3.3.6. 1.2
~ 152°F Temperature - High SR 3.3.6. 1.5 SR 3.3.6. 1.6
- d.
Pump Room B Area 1,2,3 2
F SR 3.3.6. 1.2
~ 152°F Temperature - High SR 3.3.6. 1.5 SR 3.3.6. 1.6
- e.
Heat Exchanger Room 1,2,3 2
F SR 3.3.6. 1.2
~ 143°F Area (West Wall)
SR 3.3.6. 1.5 Temperature -.High SR 3.3.6. 1.6 f,
Heat Exchanger Room 1,2,3 2
F SR 3.3.6. 1.2
~ 170°F Area (East Wall)
SR 3.3.6. 1.5 Temperature - High SR 3.3.6. 1.6
- g.
SLC System Initiation 1,2,3 1(a)
H SR 3.3.6. 1.6 NA
- h.
Reactor Vessel Water 1,2,3 2
F SR 3.3.6. 1. 1 2 528 inches Level - Low, Level 3 SR 3.3.6. 1.2 above vessel SR 3.3.6. 1.5 zero SR 3.3.6. 1.6
- 6.
Shutdown Cooling System Isolation
- a.
Reactor Steam Dome 1,2,3 F
SR 3.3.6. 1.2
~ 115 psig Pressure - High SR 3.3.6. 1.5 SR 3.3.6. 1.6
- b.
Reactor Vessel Water 3,4,5 2(b)
SR 3.3.6. 1. 1 2 528 inches Level - Low, Level 3 SR 3.3.6. 1.2 above vessel SR 3.3.6. 1.5 zero SR 3.3.6. 1.6
- c.
Drywell Pressure - High 1,2,3 2
F SR 3.3.6. 1.2
~ 2.5 psig SR 3.3.6. 1.5 SR 3.3.6. 1.6 (a) One SLC System Initiation signal provides logic input to close both RWCU valves.
(b) Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 2 3.3-62 Amendment No. ~. ~. ~.
21+, 291, 31 9
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT. UNIT 3 AMENDMENT TO RENEWED FACILITY OPERA TING LICENSE Amendment No. 277 Renewed License No. DPR-68
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated February 17, 2015, as supplemented by letter dated September 25, 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-68, and is hereby amended as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 2 7 7, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
Attachment:
FOR THE NUCLEAR REGULATORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 23, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 277 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Replace page 3 of Renewed Facility Operating License No. DPR-68 with attached page 3.
Replace the following page of Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE 3.3-61 INSERT 3.3-61 (3)
Pursuant to the Act and 1 O CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
BFN-UNIT 3 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; 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 The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 277, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 212 to Facility Operating License DPR-68, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment 212, 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 212.
Renewed License No. DPR-68 Amendment No. 277
- 5.
- 6.
(a)
(b)
FUNCTION Reactor Water Cleanup (RWCU) System Isolation
- a.
Main Steam Valve Vault Area Temperature - High
- b.
Pipe Trench Area Temperature - High
- c.
Pump Room A Area Temperature - High
- d.
Pump Room B Area Temperature - High
- e.
Heat Exchanger Room Area (West Wall)
Temperature - High
- f.
Heat Exchanger Room Area (East Wall)
Temperature - High
- g.
SLC System Initiation
- h.
Reactor Vessel Water Level - Low, Level 3 Shutdown Cooling System Isolation
- a.
Reactor Steam Dome Pressure - High
- b.
Reactor Vessel Water Level - Low, Level 3
- c.
Drywell Pressure - High Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C.1 1,2,3 2
F SR 3.3.6.1.2 s 201°F SR 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 2
F SR 3.3.6.1.2 s 135°F SR 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 2
F SR 3.3.6.1.2 s 152°F SR 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 2
F SR 3.3.6.1.2 s 152°F SR 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 2
F SR 3.3.6.1.2 s 143°F SR 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 2
F SR 3.3.6.1.2 s 170°F SR 3.3.6.1.5 SR 3.3.6.1.6 1,2,3 1(a)
H SR 3.3.6.1.6 NA 1,2,3 2
- 528 inches SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6 1,2,3 F
SR 3.3.6.1.2 s 115 psig SR 3.3.6.1.5 SR 3.3.6.1.6 3,4,5 2(b)
<:: 528 inches SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6 1,2,3 2
F SR 3.3.6.1.2 s 2.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6 One SLC System Initiation signal provides logic input to close both RWCU valves.
Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 3 3.3-61 Amendment No. 2-R, 24J, 249,
~.~, 277
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 294 TO RENEWED FACILITY OPERA TING LICENSE NO. DPR-33, AMENDMENT NO. 319 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-52, AND AMENDMENT NO. 277 TO RENEWED FACILITY OPERA TING LICENSE NO. DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1. 2. AND 3 DOCKET NOS. 50-259. 50-260. AND 50-296
1.0 INTRODUCTION
By letter dated February 17, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15050A179), as supplemented by letter dated September 25, 2015 (ADAMS Accession No. ML15268A569), Tennessee Valley Authority (TVA, the licensee),
submitted a license amendment request (LAR) regarding the Browns Ferry Nuclear Plant (BFN),
Units 1, 2, and 3, to modify Technical Specification (TS) 3.3.6.1, "Primary Containment Isolation Instrumentation," to incorporate an additional mode of applicability for the Reactor Water Cleanup (RWCU) System isolation on Standby Liquid Control (SLC) System initiation instrumentation.
The supplemental letter dated September 25, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register.
2.0 REGULATORY EVALUATION
2.1 Description of Proposed Change TS 3.3.6.1, "Primary Containment Isolation Instrumentation, requires that the primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 be operable.
Function 5.g, Reactor Water Cleanup System Isolation - SLC System Initiation, requires the associated instrumentation to be operable in Mode 1, Power Operation, and Mode 2, Startup.
The proposed change would modify these requirements to require the SLC System Initiation instrumentation to also be operable in Mode 3, Hot Shutdown. This change would align the Applicable Modes for the instrumentation with the requirements for the SLC System in TS 3.1.7.
TVA stated that this change corrects an omission from Table 3.3.6.1-1 that originated with the application and issuance of Amendment Nos. 251, 290, and 249 (ADAMS Accession No. ML042730028) for BFN, Units 1, 2, and 3, respectively, regarding full scope implementation of the alternate source term. Amendment Nos. 251, 290, and 249, in part, revised TS 3.1.7 to expand the required Modes in which the SLC System is required to be operable to include Mode 3.
2.2 Regulatory Criteria and Guidance The categories of items required to be in the TSs are provided in Title 1 O of the Code of Federal Regulations (10 CFR) Section 50.36(c). As required by 10 CFR 50.36(c)(2)(i), the TSs will include Limiting Conditions for Operation (LCOs), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. Per 10 CFR 50.36(c)(2)(i), when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.
The U.S. Nuclear Regulatory Commission (NRC) staff's guidance for review of TSs is contained in Chapter 16, "Technical Specifications," of NUREG-0800, Revision 3, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor]
Edition," March 2010 (ADAMS Accession No. ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared Standard Technical Specifications (STSs) for each of the LWR nuclear designs. NUREG-1433, "Standard Technical Specifications
- General Electric Plants (BWR/4)," contains the STSs for General Electric Plants Boiling-Water Reactors (BWR/4).
3.0 TECHNICAL EVALUATION
The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory to a subcritical condition with the reactor in the most reactive xenon free state without taking credit for control rod movement. The system is manually operated from the control room and consists of a storage tank, two positive displacement pumps and two explosive valves in parallel. The SLC System contains at least 4,000 gallons of sodium pentaborate at a concentration between 8.0 and 9.2 percent by weight.
TS 3.1.7 requires the SLC System to be operable in Modes 1, 2, and 3.
The RWCU System consists of pumps, heat exchangers, and filter/demineralizers, and is used to purify a portion of the recirculation flow. The processed fluid may be returned to the reactor vessel, radwaste, or the main condenser. Section 4.9.3 of the Updated Final Safety Analysis Report for BFN states that isolation of the RWCU System is automatically initiated when the SLC System has been actuated, in order to prevent removal of the boron solution by the RWCU System.
The proposed change would require the instrumentation associated with isolation of the RWCU System on SLC initiation to be operable during the same modes in which the SLC System is required to be operable.
The NRC staff reviewed the safety evaluation for Amendment Nos. 251, 290, and 249, which related to full scope implementation of the alternate source term at BFN, Units 1, 2, and 3. In its safety evaluation, the NRC staff discussed the need for maintaining a basic pH in the suppression pool in order to minimize release of radioactive iodine during a design basis loss of coolant accident (LOCA). The pH would be controlled using the basic solution released to the suppression pool from the SLC System. One of the TS changes associated with the alternate source term amendments was to require operability of the SLC System in Mode 3 (Hot Shutdown).
During its review of the LAR dated February 17, 2015, the NRC staff noted a discrepancy between the licensing basis of the SLC System contained in the current revision of the Final Safety Analysis Report for BFN and the submittal dated February 17, 2015, including the proposed TS Bases changes that were included as an attachment. In a request for additional information (RAI) dated August 26, 2015 (ADAMS Accession No. ML15245A003), the NRC staff requested that the licensee clarify the SLC System's function in maintaining the post-LOCA suppression pool pH, and whether the pH was supposed to be maintained below 7 or at or above 7. In its RAI response dated September 25, 2015, the licensee stated that the SLC System's function is to maintain suppression pool pH at or above 7 following an LOCA, and provided revised TS bases pages to correct this error. Since the licensee corrected the LAR and TS bases in order to conform to the current licensing basis of the SLC System, the NRC staff concludes that this RAI is resolved.
The NRC staff determined that it is appropriate to require the RWCU System isolation instrumentation to be operable when the SLC System is required to be operable in order to prevent removal of the sodium pentaborate solution by the RWCU System in the case of an SLC System initiation. This would ensure the sodium pentaborate solution is available for suppression pool buffering following an LOCA involving fuel damage as assumed in the Accident Source Term analysis. Therefore, since the licensee's request ensures that the Modes of applicability of the SLC System align with the Modes of applicability for the RWCU System isolation instrumentation, the NRC staff concludes that this change is acceptable.
The NRC staff reviewed the technical discussion of the proposed changes provided in the LAR dated February 17, 2015, to ensure that the reasoning was logical, complete, and clearly written, as described in Chapter 16 of NUREG-0800. The NRC staff reviewed the proposed changes for continued compliance with the regulations in 10 CFR 50.36, for consistency with conventional terminology, and with the format and usage rules embodied in the STSs. The NRC staff concludes that since the proposed change adds an additional Mode of applicability, corrects an inadvertent error in the Mode of applicability of the RWCU isolation instrumentation, and aligns TS Table 3.3.6.1 Function 5.g Modes of applicability with those in TS 3.1.7, that this change is acceptable. Based on the above, the NRC staff concludes that the change is compatible with the guidance for TSs as provided in NUREG-0800 and NUREG-1433, and that this change is consistent with the requirements of 10 CFR 50.36.
The regulation at 10 CFR 50.36(a)(1) states, in part, that: "A summary statement of the bases or reasons for such specifications... 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, TS 5.5.10.
Accordingly, along with the proposed TS changes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The NRC staff determined that the proposed TS Bases changes, as supplemented, are consistent with the proposed TS changes and provide the purpose for each requirement in the specification consistent with the Commission's Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors dated July 22, 1993 (58 FR 39132).
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Alabama 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. 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 (80 FR 30097; May 26, 2015). 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 the operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Margaret H. Chernoff Date: December 23, 2015
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DATE 11/5/15 12/17/15 12/23/15 12/23/15