ML13014A711
| ML13014A711 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 02/06/2013 |
| From: | Michael Mahoney Plant Licensing Branch III |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| Michael Mahoney, NRR/DORL, 415-3867 | |
| References | |
| TAC ME8881, TAC ME8882, TAC ME8883, TAC ME8884 | |
| Download: ML13014A711 (62) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 February 6, 2013 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: REVISE TECHNICAL SPECIFICATIONS 3.3.1 and 3.3.2 (TAC NOS. ME8881, IVIE8882, ME8883, AND ME8884)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendments No. 171 to Facility Operating License No. NPF-72 and No. 171 to Facility Operating License No. NPF-77 for the, Braidwood Station, Units 1 and 2, respectively, and No. 178 to Facility Operating License No. NPF-37 and No. 178 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated June 6,2012, as supplemented by letter dated November 19, 2012.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Michael Mahoney, Ject Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454 and STN 50-455
Enclosures:
- 1. Amendment NO.171 to NPF-72
- 2. Amendment NO.171 to NPF-77
- 3. Amendment No.178 to NPF-37
- 4. Amendment No.178 to NPF-66
- 5. Safety Evaluation cc w/encls: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 License No. NPF-72
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 6,2012, as supplemented by letter dated November 19, 2012, 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 Facility Operating License No. NPF-72 is hereby amended to read as follows:
-2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 171 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days for Braidwood, Unit 1.
FOR THE NUCLEAR REGULATORY COMMISSION oel S. Wiebe, Acting Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: February 6, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 License No. NPF-77
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 6, 2012, as supplemented by letter dated November 19, 2012, 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 Facility Operating License No. NPF-77 is hereby amended to read as follows:
-2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 171 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date if its issuance and shall be implemented within 90 days for Braidwood, Unit 2.
FOR THE NUCLEAR REGULATORY COMMISSION el S. Wiebe, Acting Chief lant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: February 6, 2013
ATTACHMENT TO LICENSE AMENDMENT NOS. 171 AND 171 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Facility Operating Licenses and Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-72 License NPF-72 Page 3 Page 3 License NPF-77 License NPF-77 Page 3 Page 3 TSs TSs 3.3.1-11 through 21 3.3.1-11 through 21 3.3.2-9 through 17 3.3.2-9 through 17
- 3 (3) Exelon Generation Company, pursuant to the Act and 10 CFR Part 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) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. The 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 The licensee is authorized to operate the facility at reactor core power levels is not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 171, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 171
-3 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) Exelon Generation Company, LLC pursuant to the Act and 10 CFR Parts30, 40 and 70, to receive, possess, and use in amounts are 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) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30,40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. The 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 The licensee is authorized to operate the facility at reactor core power levels is not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.171 , and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 171
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.1.6 ---------- ----NOTE--- --------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is ~ 75% RTP.
Calibrate excore channels to agree with In accordance incore measurements. with the Surveillance Frequency Control Program SR 3.3.1. 7 ----------- NOTES----- ---------
- 1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.
- 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capabil ity.
Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
BRAIDWOOD - UNITS 1 &2 3.3.1 - 11 Amendment No .171/171
RTS Instrumentation 3.3.1 SliRVEI LLANCE REQlI IREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.8 -------------------NOTES------- --------
- 1. This Surveillance shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.
- 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass capability.
Perform COT. -----NOTE---
On 1y requi red when not performed within the Frequency specified in the Surveillance Frequency Control Program Prior to reactor startup AND Four hours after reducing power below P 10 for power and intermediate instrumentation Four hours after reducing power below P-6 for source range instrumentation (continued)
BRAIDWOOD - UNITS 1 &2 3.3.1 - 12 Amendment No.1 71/1 71
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.1.8 (continued) In accordance with the Surveillance Frequency Control Program SR 3.3.1. 9 -------- -------NOTE ------- ------
Verification of setpoint is not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 -------- ----NOTE- --------- ----
This Surveillance shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.11 - --------- ---NOTE-- --------
Neutron detectors are excluded from CHANNEL CAL IBRATI ON.
Perform CHANNEL CALIBRATION. In accordance with the Surveil 1ance Frequency Control Program (continued)
BRA IDWOOD - UN ITS 1 & 2 3.3.1 13 Amendment No. 171/171
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVE I LLANCE FREQUENCY SR 3.3.1.12 ------- - -------NOTE-------- - ------
The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.13 -------------------NOTE-------------------
Verification of setpoint is not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 -------------------NOTE-------------------
Verification of setpoint is not required.
Perform TADOT. -----NOTE-----
Only requi red when not performed within previous 31 days Prior to reactor startup (continued)
BRAIDWOOD - UNITS 1 &2 3.3.1 14 Amendment No. 171/171
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.15 -------------- --NOTE-- ------ ------
Neutron detectors are excluded from response time testing.
Verify RTS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 & 2 3.3.1 - 15 Amendment No.1 71/ 1 71
RTS Instrumentation 3.3.1 Table 3.3.1-r (page 1 of 6)
Reactor Trip System InstrUirentation APPLICABLE MODtS OR OTHER SPEC I FI EO REOUIRED SURVE I LLAJliCE ALLOW,ABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REOU I RE'1ENTS VALUE
- l. Manual Reactor Trip 1,2 2 B SR 3.3.1.13 NA 3('), 4(,1, 5(a} 2 C SR 3.3.1.13 NA
- 2. Power Range Neutron Flux
- a. High 1,2 4 0 SR 3.3.1.1 .s llO.8%
SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15
- b. Low }(Oi ,2 4 SR 3.3.1.1 .s SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15
- 3. Power Range Neutron 1,2 4 E SR Fl ux-High Positive SR Rate
- 4. Intermediate Range pbl. 2<<1 2 F,G SR 3.3.1.1 .s 30.0% RTP Neutron Fl ux SR 3.3.1.8 SR 3.3.1.11
- 5. Source Range Neutron 2(0) 2 H, J SR 3.3.1.1 -;; 1.42 E5 cps Flux SR 3.3.1.8 SR 3.3, L 11 SR 3.3.1.15 3('), 4('), 5(') 2 I,J SR 3.3.1.1 -;; 1.42 E5 cps SR 3.3.
{continued; (a) With Rod Control System capable of rod withdrawal or one or rrore rods not fully inserted.
(b) Below the polO (Power Range Neutron Flux) interlock.
(cl M:!ove the P-6 (Source Range Block Permissive) interlock.
Cd) Below the P-6 (Source Range Block Permissive) interlock.
BRAIDWOOD UNITS 1 & 2 3.3.1 - 16 Amendment No .171/171
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 6)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECI FI ED REQUIRED SU RV ElLLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIO~S REQU I REMENTS VALUE
- 6. Overtemperature ~T 1,2 4 E SR 3.3.1.1 Ret'er to SR 3.3.1.3 Note 1 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15
- 7. OverplYtler ~T 1,2 4 E SR 3.3.1.1 ~efer to SR 3.3.1.7 Note 2 SR 3.3.1.10 SR 3.3.1.15
- 8. Pressuri zer Pressure
- a. Low 1(e) 4 K SR 3.3.1.1 ~ 1875 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15
- b. High 1,2 4 SR 3.3.1.1 $; 2393 psig SR 3.3.1.7 SR 3.3.1.10 SR. 3.3.1.15
- 9. Pressuri zer Water 11,,] 3 K SR 3.3.1.1 Level-High SR 3.3.1.7 SR 3.3.1.10 span
- 10. Reactor Coolant 1Ie) 3 K SR 3.3.1.1 ~ 89.3% of Flow-LIYtI (per loop) SR 3.3.1.7 loop minimum SR 3.3.1.10 measured flo\-I SR 3.3.1.15
- 11. Reactor Coolant PlJ1lP 1(e) 4 R SR 3.3.1.l3 NA (Rep) Breaker Position (per train)
(continued)
(e) Above the P-7 (Low Power Reactor Trios Block) interlock.
BRAIDWOOD - UNITS 1 &2 3.3.1 17 Amendment No .171/171
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 6)
Reactor Tri p System lnstrurrentati on APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE
- 12. Undervoltage 4 K SR " 4920 V RCPs (per train) SR SR
- 13. Underfrequency 4 K SR 3.3.1.9 " 56,08 Hz RCPs (per train) SR 3.3,1.10 SR 3.3,1.15
- 14. Steam Generator (SGl Water Leve1- Lew Low (per SGl
- a. Unit 1 1.2 4 E SR 3.3.1.1 " 16,1% of SR 3.3.1.7 narrew range SR 3,3,1.10 i nstrurrent SR 3,3.1.15 span
- 15. Turbine Trip
- 16. Safety Injecti on (SI) 1,2 2 trains M SR 3.3.1.13 NA Input from Engineered Safety Feature Actuati on System (ESFAS)
(continued)
(e) Above the P-7 (Lew Povler Reactor Trips Block) interlock.
(f) Above the P-8 (Power Range Neutron Flux) interlock.
BRAIDWOOD UNITS 1 & 2 3.3.1 18 AmendmentNo.171/171
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 6)
Reactor Trip System Instrumentation APPLICABLE PIlDES OR OTHER SPECI FlED REQUIRED SURVEI LLt>.NCE ALLOWA3LE FUNCTION CONDITIONS CH.ANNELS CON:lITIONS REQUIREMENTS VALUE
- 17. Reactor Tri p System Interlocks
- b. Pa..er Reactor Block, P*7 (1) P-lO Input 3 P SR 3.3.1.11 NA SR 3.3.1.12 (2) p.l3 Input 2 P SR 3.3.1.10 NA SR 3.3.1.12
- d. Power Ranfe 1,2 3 0 SR 3.3.1.11 ~
Neutron F ux, P-lO SR 3.3.1.12
- e. Turbine Impulse 2 P SR 3.3.1.10 ~ 12.1%
Pressure, P-13 SR 3.3.1.12 turbine power
- 18. 1,2 2 trains N SR 3.3.1.4 NA 3Cll, 4{al, 2 trains C SR 3.3.1.4 NA
- 19. Reactor Trip Breaker 1,2 1 each per RTB Q SR 3.3.1.4 NA Undervo1tage and Shunt Tri p Mechani sms 3('), 4('), 5(') 1 each per RTB C SR 3.3.1.4 ,'iA
- 20. Automatic Trip Logic 1,2 2 trains ..., Sri 3.3.1.5 NA 3('), 4(d), 5(') 2 trains C Sri 3.3.1.5 N.~
(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(d) Bela... the P-6 (Source Range Block Permissive) interlock.
(g) Including any reactor trip bypass breakers that are racked in and closed for bypassing an iUB.
BRAIDWOOD - UNITS 1 &2 3.3.1 - 19 Amendment No .171/171
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 6)
Reactor Trip System Instrumentation Note 1: OvertemRerature ~T The Overtemperature ~T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.04% of ~T span.
Where: ~T is measured Reactor Coolant System (RCS) ~T, of.
~To is the indicated ~T at RTP, of.
sis the Laplace transform operator, sec* l .
T is the measured RCS average temperature, of.
TI is the nominal Tav9 at RTP, s *.
P is the measured pressurizer pressure, psig.
pi is the nominal RCS operating pressure, =
- K1 --
- K2 --
- K3 --
- T1 --
- T2 --
- T3 <~
- T4 --
- T 15 --
- T16 <
fl(~I) = *{* + (qt - qb)} when qt - qb <
- RTP s qt qb S
- {(qt - qb) - *} when qt - qb >
- RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respecti vely, and qt + qb is the tota 1 THERI~AL POWER in percent RTP.
- As specified in the COLR.
BRAIDWOOD - UNITS 1 &2 3.3.1 - 20 Amendment ro. 171/171
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 6)
Reactor Trip System Instrumentation Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 3.60% of AT span.
Where: AT is measured RCS AT, ATo is the indicated AT at RTP, of.
sis the Laplace transform operator, sec!.
T is the measured RCS average temperature, of.
T/ / is the nomi na 1 Tavg at RTP, s *.
~=* Ks =
- for increasing Tavg K,;
- when T > 1"
- for decreasing Tavg
- when T s T" TI --
- T2 --
- T3 -<
- T.6 -<
- T7 -- *
- As specified in the COLR.
BRAIDWOOD - UNITS 1 &2 3.3.1 21 Amendment No. 171/171
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.2.3 -------------------NOTE------- ----------
Verification of relay setpoints not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.4 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.5 Perform MASTER RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 ------- ----------NOTE-------- -------
The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
BYRON - UNITS 1 &2 3.3.2 - 9 Amendment No. 171/171
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.7 -------------------NOTE--------
Verification of relay setpoints not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.8 Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.9 ------------ -NOTE------ --------
Verification of setpoint not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.10 ------------- - NOTE------- - ------
This Surveillance shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)
BYRON - UNITS 1 &2 3.3.2 - 10 Amendment No .171/171
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SURVE ILLANCE FREQUENCY SR 3.3.2. Verify ESFAS RESPONSE TIMES are within In accordance 1imi t. with the Surveil 1ance Frequency Control Program SR 3.3.2.12 Verify ESFAS RESPONSE TIMES are within In accordance 1imit. with the Surveillance Frequency Control Program BYRON - UNITS 1 &2 3.3.2 - 11 Amendment No.1 71/171
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIO~S CHANNELS CONDITIONS REQUIREMENTS
- l. Safety Injection
- a. Manual Initiation 1,2,3,4 2 8 SR 3.3.2.9 NA
- b. 1,2,3,4 2 trains C SR 3.3.2.4 NA SR 3.3.2.5 SR 3.3.2.8
- c. 1,2,3 3 C SR 3.3.2.1 :; 4.6 psig SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12
- d. 1,2,3(') 4 0 SR 3.3.2.1 ~ 1817 psig SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12
- e. 1,2,3(') 3 per steam 0 SR 3.3.2.1 ~ 614 psi gfb) line SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12
- 2. Contaj nrrent Spray
- a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.9 NA
- b. 1,2,3,4 2 trains C SR NA SR SR
- c. 1,2,3 4 E SR 3.3.2.1 :; 21. 2 psi g SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 (co",t lnued)
(a) flOOve the P-ll (Pressurizer Pressure) interlock.
(b) Time constants used in the lead/lag controller are t,;;: 50 seconds and t2 :; 5 seconds.
BYRON - UNITS 1 & 2 3.3.2 - 12 Amendment No.1 71/1 71
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 6)
Engineered Safety Feature Actuation System InstrllTntation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CONDITlONS CHANNELS CONDITlONS REQU I RENENTS VALUE
- 3. Contai ment Iso1at; on
- a. Phase A Isolatioo (1) Mmual 1,2,3,4 2 B SR 3.3.2.9 NA Initiation (2) Autar.atic 1,2,3,4 2 trains C SR 3.3.2.4 NA Actuatioo SR 3.3.2.5 Logic and SR 3.3.2.8 Actuation Rel ays (3) Safety Refer to Function 1 (Safety Injection) for all initiation fUl1ctions and requirments.
Injection
- b. Phase B Isolation (1) Manual 1,2,3,4 2 B SR 3.3.2.9 Initiation (2) AutOOBtic 1,2,3,4 2 trains C SR NA A<."tuati on SR Logic and SR Actuation Relays (3) Contaiment 1,2,3 4 E SR 3.3.2.1 $ 21.2 psig Pressure SR 3.3.2.6 High-3 SR 3.3.2.10 SR 3.3.2.12 (contim.lL:;cI)
BYRON UNITS 1 & 2 3.3.2 13 Amendment No .171/171
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page of 6)
Engineered Safety Feature Actuation Instrll'!entati on APPLICABLE MODES OR OTHER SPECIFI ED REQU!RED SURVE I LLANCE ALLOIJABLE FUNCTION CONDITIONS CHA~NELS CONDITIONS REOUI REMENTS VALUE
- 4. Steam Li ne 1501 ati on
- a. Manual Initiation l,2(c),3 Icl 2 F SR 3.3.2.9 NA
- b. AutCinatic Actuation 1, 21g) ,31g ) 2 trains G SR 3.3.2.4 NA Logic and Actuation SR 3.3.2.5 Relays SR 3.3.2.8
- c. I, 21g) ,3 1g ) 3 D SR ~ 9.4 psig 2 SR SR SR
- d. Steam Line Pressure (ll Low 1,2(g)*31,)(f)lg) 3 steam 0 SR 3.3.2.1 :?! 614 psi gl')
Sf<. 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 (2) Negative 3Id )lg) 3 per steam 0 SR 3.3.2.1 165.3 psi'e)
Rate-High 1ine SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 (contilcuEd)
(a) Above the P-ll (Pressurizer Pressure) interlock.
(b) Time constants used in the lead/lag controller are t: ~ 50 seconds and tz ~ 5 seconds.
(cl Except when all Main Steam Isolation Valves (MSIVs) are closed.
(d) Below the P-ll (Pressurizer Pressure) interlock with Function 4.d.l blocked.
(el Time constant utilized in the rate/lag controller is ~ 50 seconds.
(f) Below the P-ll (Pressurizer Pressure) interlock with Function 4.d.2 not enabled.
(g) Except when all Main Steam Isolation Valves (MSIVs) and MSIV bypass valves are closed.
BYRON UNITS 1 & 2 3.3.2 - 14 Amendment No . 1 71 /1 71
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 6)
Engineered Safety Feature Actuation System lnstrumentati on APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHMJNELS CONDITIONS REQU I RE~ENTS VALUE
- 5. Turbine Trip and Feed'water Iso1ati on
- a. Autanat i c 2 trains G SR 3.3.2.4 NA Actuati on Logi c SR 3.3.2.5 and Actuati on SR 3.3.2.8 Relays b, Steam Generator (SG) Water Level -High High (P-14)
- 1) Unit 1 4 per SG o SR 3.3.2.1 89.9% of SR 3.3.2.4 na r row range SR 3.3.2.5 instrument SR 3.3.2.6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12 Z) Unit 2 4 per SG o SR 3.3.2.1 s 81.5% of SR 3.3.2.4 narrow range SR 3.3.2.5 instrument SR 3.3.2.6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12
- c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(contmued)
(h) Except when all Feedwater Isolation Valves are closed or isolated by a closed manual valve.
BYRON UNITS 1 & 2 3.3.2 - 15 Amendment No.171/171
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 6)
Engineered Safety Feature Actuation System InstrLlfentation APPLICABLE MODES OR OTHER SPECl FI ED REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQU:REMENTS VALUE
- 6. Auxil i ary Feedwater
- a. Automatic Actuation 1,2,3 2 trains G SR 3.3.2.4 NA LOri c and Actuati on SR 3.3.2.5 Re ays SR 3.3.2.8
- b. SG Water Level -Low Low
- 1) Unit 1 1,2,3 4 per SG 0 SR 3.3.2.1 ~ 16. of SR 3.3.2.6 narrow range SR 3.3.2.10 instrLlfent SR 3.3.2.12 span
- 2) Unit 2 1,2,3 4 per SG D SR 3.3.2.1 z 34.8% of SR 3.3.2.6 r.a rrow racge SR 3.3.2.10 instrument SR 3.3.2.12 span
- c. Safety Injecti on Refer to Function 1 (Safety Injection) for all initi ation functions and requi rements.
- d. Loss of Offsite Power 1,2,3 2 H SR 3.3.2.3 ~ 2730 V (Undervoltage on SR 3.3.2.10 Bus 141(241>> SR 3.3.2.11
- e. Undervo1tage 1,2 4 SR 3.3.2.7 z 4920 V Coolant Pump SR 3.3.2.10 train) SR 3.3.2.12
- f. 1,2,3 1 per train J SR z 17.4 psia SR SR 7
I. Switchover to Containrrent Surrp
- a. Actuation 1,2,3,4 2 trains C SR NA Actuation SR SR
- b. Refue1i ng Water 1,2,3,4 4 K SR 3.3.2.1 Storage Tank (RWSTl SR 3.3.2.6 Leve1-Low Low SR 3.3.2.10 span SR 3.3.2.12 Coincident with Refer to Function 1 (Safety Injection) for all initi ali on functions and requi rements.
Safety Injection (contlnlBj)
BYRON - UNITS 1 & 2 3.3.2 - 16 Amendment No .171/171
ESFAS Instrumentation 3.3.2 Table 3.3.2*1 (page 6 of 6)
Engjneered Safety Feature Actuation System Instrumentation APPLl CABLE f'.VDES OR OTHER SPECIFi ED REQUIRED SURVEI LLA\CE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUI RE'1ENTS
- 8. ESFAS Interlocks
- a. Reactor Tri P. P*4 1,2,3 2 per train F SR 3.3.2.9 NA
- b. Pressure. 1.2.3 2 L SR 3.3.2.6 s; 1936 ps~g SR 3.3.2.10
- .. T",,-Lew Lew, P*12 1,2,3 3 L SR SR BYRON - UNITS 1 & 2 3.3.2 - 17 Amendment NO.1 71/1 71
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 EXELON GENERATION COMPANY LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 178 License No. NPF-37
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 6,2012, as supplemented by letter dated November 19, 2012, 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 Facility Operating License No. NPF-37 is hereby amended to read as follows:
-2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 178 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days for Byron, Unit No.1.
FOR THE NUCLEAR REGULATORY COMMISSION
~ticJ;}
~ oel S. Wiebe, Acting Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: February 6, 2013
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 178 License No. NPF-66
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 6,2012, as supplemented by letter dated November 19, 2012, 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 Facility Operating License No. NPF-66 is hereby amended to read as follows:
- 2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 178 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14,1985, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days for Byron, Unit No.2.
FOR THE NUCLEAR REGULATORY COMMISSION
~etw~
~ el S. Wiebe, Acting Chief lant Licensing Branch 111-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: February 6, 2013
ATTACHMENT TO LICENSE AMENDMENT NOS. 178 AND 178 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Facility Operating License and Appendix uA" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-37 License NPF-37 Page 3 Page 3 License NPF-66 License NPF-66 Page 3 Page 3 TSs TSs 3.3.1-11 through 22 3.3.1-11 through 22 3.3.2-9 through 17 3.3.2-9 through 17
- 3 (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 instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulation 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 The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 178 and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Deleted.
(4) Deleted.
(5) Deleted.
(6) The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report, and as approved in the SER dated February 1987 through Supplement No.8, subject to the following provision:
The licensee 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.
Amendment No. 178
-3 (3) 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; (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 instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulation 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 The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No 178, and the Environmental Protection Plan contained in Appendix 8. both of which were attached to License No. NPF-37, dated February 14, 1985. are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Deleted.
(4) Deleted.
(5) Deleted.
Amendment No. 178
RTS Instrumentation 3.3.1 SURVEI LLANCE REQU IREtvlENTS (cont i nued)
SURVEILLANCE FREQUENCY SR 3.3.1.4 -------- -NOTE-----------
This Surveillance must be performed on the RTBB prior to placing the bypass breaker in service.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.6 -------------------NOTE-------------
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is ~ 75% RTP.
Calibrate excore channels to agree with In accordance incore measurements. with the Surveillance Frequency Control Program (cont -j nued)
BYRON UNITS 1 & 2 3.3.1 11 Amendment No : 178/178
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1. 7 ------------ NOTES------- --------
- 1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.
- 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capabil ity.
Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
BYRON - UNITS 1 &2 3.3.1 - 12 Amendment No: 178/178
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVE ILLANCE FREQUENCY SR 3.3.1.8 -------------- NOTES ---------------
- 1. This Surveillance shall include verification that interlocks P-6 and P 10 are in their required state for existing unit conditions.
- 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
Perform COT. - -- NOTE Only requi red when not performed within the Frequency specified in the Surve-j 11 ance Frequency Control Program Prior to reactor startup AND Four hours after reducing power below P-lO for power and intermediate instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND (continued)
BYRON - UNITS 1 & 2 3.3.1 13 Amendment No: 178/178
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.8 (continued) In accordance with the Survelllance Frequency Control Program SR 3.3.1.9 -------------------NOTE--- - -----
Verification of setpoint is not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 -------------------NOTE-This Surveillance shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.11 ------------ NOTE -- -
Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (cont -j nued)
BYRON UNITS 1 &2 3.3.1 14 Amendment No : 1 7 8 / 178
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.1.12 -------- ------NOTE- -------- ------
The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.13 ----- --- ---- -NOTE ----- --- ------
Verification of setpoint is not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 - --------- ----NOTE- --------- - ---
Verification of setpoint is not required.
Perform TADOT. -----NOTE-----
Only required when not performed within previous 31 days Prior to reactor startup (cont-inued)
BYRON UNITS 1 &2 3.3.1 15 Amendment No: 178/178
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.1.15 -------------------NOTE Neutron detectors are excluded from response time testing.
Veri fy RTS RESPONSE TI~IE is wi thi n 1imi ts . In accordance wi th the Surveillance Frequency Control Program BYRON UNITS 1 & 2 3.3.1 - 16 Amendment No : 178/1 7 8
RTS Instrumentation 3.3.1 Table 3.3.1-2 (page 1 of 6)
Reactor Trip System Instrurrentation APPLICABLE f'bDES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWftlU FUNCTION CONDITIONS CHANNELS CONDITIONS REQU I REMENTS VALUE
- 1. Manual Reactor Trip 1,2 2 B SR 3.3.1.13 NA 3(a), 4(a) , 5(a; 2 C SR 3.3.1.13 NA
- 2. Power Range Neut ron Flux
- a. High 1,2 4 0 SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR3.3.1.11 SR 3.3.1.15
- b. Low lib) ,2 4 E SR 1.1 " 27.0%
- 3. Power Range Neutron 1,2 4 E SR 3.3.1.7 RTP Fl ux-High Positive Rate SR 3.3.1.11 "constant tirre
- > 2 sec
- 4. Intermediate Range 1(b), 2(c) 2 F,G SR 3.3.1.1 " 30.0% RTP Neutron Fl ux SR 3.3.1.8 SR 3.3.1.11
- 5. Source Range Neutron 21d) 2 H,I SR 3.3.1. " 1.42 ES cps Flux SR 3.3.1 SR 3.3.1 SR 3.3.1 3('1, 4('). 51,) 2 I,J SR 3.3.1.1 " 1.42 E5 cps SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 (continued)
(a) With Rod Control System capable of rod withdrawal or one or rrore rods not fully inserted.
(b) Below the P-IO (Power Range Neutron Flux) interlock.
(c) ftbove the P-6 (Source Range Block Permissive) interlock.
(d) Below the P-6 (Source Range Block Permissive) interlock.
BYRON UNITS 1 & 2 3.3.1-17 Amendment No: 1 7 8 / 178
RTS Instrumentation 3.3.1 AppLtCABLt MODES OR OTHER SPECl FI ED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQU I REMENTS VALUe:
- 6. OvertEll1pl2rature ilT 1,2 4 E SR 3.3.1.1 Refer to SR3.3.1.3 ~ote 1 SR3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15
- 7. Overpal'ler ilT 1,2 4 E SR 3.3.1.1 Refer to SR 3.3.1.7 Note 2 SR 3.3.1.10 SR 3.3.1.15
- 8. Pressurizer Pressure
- a. Low lie) 4 K SR 2: 1875 psig SR SR SR
- 10. Reactor Coolant l(e) 3 K SR Flow-Low (per loop) SR SR SR
- 11. Reactor Coolant Pump Fe) 4 R SR 3.3.1.13 \A.
(RCP) Breaker Position (per train)
(continued)
(e) Above the P-7 (LOW Power Reactor Trips Block) interbck.
BYRON ~ UNITS 1 &2 3.3.1 18 Amendment No: 178/178
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 6)
Reactor Trip System Instrurrentation APPLICABLE MODES OR OTHER SPECI FI ED REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQU I REMENTS VALUE
- 12. Undervoltage l(e) 4 K SR 3.3.1.9 ;> 4920 V RCPs (per train) SR 3.3.1.10 SR 3.3.1.15
- 13. Underfrequency l(e) 4 K SR 3.3.1.9 ;> 56.08 Hz RCPs (per train) SR3.3.1.10 SR 3.3.1.15
- 14. Steam Generator (SG)
Water Leve1-Low Low (per SG)
- a. Unit 1 1,2 4 E SR 3.3.1.1 ;>16.1%of SR 3.3.1.7 narrow range SR3.3.1.10 i nstrurrent SR 3.3.1.15 span
- b. Unit 2 1,2 4 E SR 3.3.1.1 ;> 34.8% of SR 3.3.1.7 narrow range SR3.3.1.10 i nstrurrent SR 3.3.1.15 span
- 15. Turbine Trip
- 16. Safety Injection (SI) 1,2 2 trains M SR 3.3.1.13 NA I nput from Engi neered Safety Feature Actuati on System (ESFAS)
(continued)
(e) Above the P-J (Low Power Reactor Trips Block) interlock.
(f) /'bove the P-8 (Power Range Neutron Flux) interlock.
BYRON - UNITS 1 &2 3.3.1 - 19 Amendment No: 178/1 7 8
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 6)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEI LlANCE ALLOWilBLE FUNCTION CONDITIONS CHANNELS CCNDITIONS REQU I REMENTS VALUE
- 17. Reactor Tri p System Interlocks
- a. Scurce Range Block 2(dl 2 0 SR :;, 6E-11 arp Permi ssive. P*6 SR
- b. Low Power Reactor Trips Block. P-7 (1) P-lO Input 3 P SR 3.3.l.11 NA SR 3.3.1.12 (2) p.l3 Input 2 P SR NA SR
- e. Turbine lmpul se 2 P SR 10 Pressure. p.l3 SR 12
- 18. Trip 1.2 2 trains N SR 3.3.1.4 NA (RTBs)(g) 3{d) 1 4(a) , 5(a) 2 trains C SR 3.3.1.4 NA
- 19. Reactor Trip Breaker 1.2 1 each per RTB Q SR 3.3.1.4 NA Undervo1tage and Shunt Tri p M::chani sms 3(a) t 4(a), 5<<(1) 1 each per RTB C SR 3.3.1.4 NA
- 20. Automatic Trip Logic 1,2 2 trains M SR3.3.1.5 NA 3(ai, 4(a) 1 5(a) 2 trains C SR3.3.1.5 NA (a) Wi th Rod Control System capable of rod withdrawa 1 or one or more rods not fully inserted.
(d) Below the P-6 (Source Range Block Permissive) interlock.
(g) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.
BYRON UNITS 1 & 2 3.3.1 - 20 Amendment No: 178/178
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 6)
Reactor Trip System Instrumentation Note 1: Overteillperature !IT The Overtemperature !IT Function Allowable Value shall not exceed the follow-ing Trip Setpoint by more than 1.04% of !IT span.
II T (l+Tl s) 1 ~ II To {Kl(-l K2
+ T 4 S) [ T 1 - TI] + K3 (P - P1) - fl (ll I)}
(l+Tzs) S ( l+T 5 S) ( 1+T6 s )
Where: llT is measured Reactor Coolant System (RCS) tlT, of.
!lTo is the indicated !IT at RTP, OF.
sis the Laplace transform operator, sec l.
T is the measured RCS average temperature, OF.
TI is the nomi na 1 Tav9 at RTP, ~ *.
P is the measured pressurizer pressure, psig.
pi is the nominal RCS operating pressure, =
- K1 --
- K2 --
- K3 --
- T1 --
- T2 --
- T3 <-
- T4 --
- Tr = *
~
T6 -<
- fj(llI) = *{* + (qt qb)} when qt - qb <
- RTP $ qt qb ~
- {(qt - qb) - *} when qt - qb >
- RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.
- As specified in the COLR.
BYRON - UNITS 1 &2 3.3.1 - 21 Amendment No: 178/178
RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 6)
Reactor Trip System Instrumentation Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 3.60% of AT span.
Where: AT is measured RCS AT, of.
ATo is the indicated AT at RTP, sis the Lapl ace transform operator, sec 1
- T is the measured RCS average temperature, of.
T/I is the nominal Tavg at RTP, ~ *.
K4 -- * ~ =
- for increasing K,; -
- when T > Til
- for decreasing
- when T ~ Til T1 -
- Tz -
- T.6 -<
- T7 -- *
- As specified in the COLR.
BYRON - UNITS 1 &2 3.3.1 Amendment No: 178/178
ESFAS Instrumentation 3.3.2 SURVEI LLANCE REQU IREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.3 ---------- -------NOTE----------------- -
Verification of relay setpoints not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.4 Perform ACTUATION LOGIC TEST. In accordance with the Su rvei 11 ance Frequency Control Program SR 3.3.2.5 Perform MASTER RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 -- - ------------NOTE-------------------
The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
BRAIDWOOD - UNITS 1 &2 3.3.2 - 9 Amendment No. 178/178
ESFAS Instrumentation 3.3.2 SURVEI LLANCE REQU I RE~IENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.7 -------------------NOTE------------------
Verifi on of relay setpoints not required.
Perform TADOT. In accordance with the Survelllance Frequency Cont ro 1 Prog ram SR 3.3.2.8 Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.9 ------- NOTE-------------------
Verification of setpoint not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.10 --------- -- NOTE-------------------
This Surveillance shall include verification that the time constants are adj the prescribed values.
Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)
BRAIDWOOD - UNITS 1 &2 3.3.2 10 Amendment No:178/178
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.2.11 Verify ESFAS RESPONSE TIMES are within In accordance 1imit. with the Surveillance Frequency Control Program SR 3.3.2.12 Verify ESFAS RESPONSE TIMES are within In accordance 1imit. with the Surveillance Frequency Control Program BRAIDWOOD - UNITS 1 &2 3.3.2 - 11 Amendment No: 178/178
ESFAS Instrumentation 3.3.2 1 of 6)
Engi neered Safety System Instrumentation REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CHANNELS CONDITIONS REQU IREMENTS VALLE
- 1. Safety Injection
- a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.9 NA
- b. Autanati c 1,2,3,4 2 trains C SI<. NA Actuati on Logi c SR and Actuat i on SR Relays
- c. Contai nrrent 1,2,3 3 D SR 3.3.2.1 :;; 4.6 Pressure- Hi gh 1 SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12
- d. Pressuri zer 1,2,3(') 4 D SR 3.3.2.1 ~ 1817 psig Pressure- Low SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12
- e. Steam Line 1,2,3(') 3 steam D SR 3.3.2.1 ~ 614 psi gil))
Pressure-Low ine SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12
- 2. Containrrent Spray
- a. Manual Initiation 1,2,3,4 2 B SR 3.3.2.9 NA
- b. Autanatic 1,2,3,4 2 trains C SR 3.3.2.4 NA Actuati on Logi c SR 3.3.2.5 and Actuati on SR 3.3.2.8 Relays
- c. Containrrent 1,2,3 4 E SR 3.3.2.1 :f 21.2 Pressure High-3 SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 (cont' nued)
(a) KJove the P-l1 (Pressurizer Pressure) interlock.
(bl Ti rre constants used in the 1ead/l ag contro11 er are tl ~ 50 seconds and tz :f 5 seconds.
BRAIDWOOD - UNITS 1 &2 3.3.2 - 12 Amendment No: 178/1 7 8
ESFAS Instrumentation 3.3.2 3.3.2-1 (page 2 of 6)
Engi nee red Safety Actuation System InstrlJl1entation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEI LLANCE FUNCTION CONDITIONS CHA.\NELS CONDITIONS REQUI REMENTS
- 3. Contaiment Isolation
- a. Phase A Isolation (1) 1,2,3,4 2 B SR 3.3.2.9 NA (2) Autamtic 1,2,3,4 2 trains C SR 3.3.2.4 NA Actuation SR 3.3.2.5 Logic and SR 3.3.2.8 Actuation Relays (3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirffiffits.
Injection
- b. Phase B Isolation (1) Manual 1,2,3.4 2 B SR 3.3.2.9 NA Initiation (2) Autamtic 1,2,3,4 2 trains C SR 3.3.2.4 NA Actuation SR 3.3.2.5 Logic and SR 3.3.2.8 Actuation Relays (3) Contail1l1l2l1t 1,2,3 4 E SR 3.3.2.1 <; 21.2 psig Pressure SR 3.3.2.6 High-3 SR 3.3.2.lQ SR 3.3.2.12 (contlrllJEii)
BRAIDWOOD - UNITS 1 & 2 3.3.2 - 13 Amendment No: 178/178
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page of 6)
Engineered Safety Feature Actuation lnstrunentation APPLICABLE MCDES OR OTHER SPECIFIED REQUIRED SURVE ILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQU IREMENTS
- 4. Steam Line Isolation
- a. Manual Initiation 2 F SR 3.3.2.9 NA
- b. Automatic Actuation 1,2(g) ,3(g) 2 trains G SR 3,3.2.4 NA Logi c and Actuati on SR 3.3.2.5 Relays SR 3.3.2.8
- c. ContaiI1Irent 3 D SR ,; 9.4 psig Pressure-Hi gh 2 SR SR SR
- d. Steam Line Pressure (1) Low 1,219),31.)(019) 3 steam D SR 3.3.2.1 SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 (2) Negative 3 per steam D SR 3.3.2.1 ,; 165.3 Rate-High line SR 3.3.2.6 SR 3.3,2.10 SR 3.3.2.12 (conti nui'iD (a) Above the P-ll (Pressurizer Pressure) interlock.
(b) Time constants used in the lead/lag controller are tl ;,: 50 seconds and t2'; 5 seco'lds.
(c) Except when all Main Steam Isolation Valves (MSIVs) are closed.
(d) Below the P-l1 (Pressurizer Pressure) interlock with Function 4.d.l blocked.
(el Time constant utnized in the rate/lag controller is 50 seconds.
(f) BelOW the P-ll (Pressurizer Pressure) interlock with Function 4.d.2 not enabled.
(g) Except when all Main Steam Isolation Valves (MSIVs) and MSIV bypass valves are closed.
BRAIDWOOD UNITS 1 & 2 3.3.2 - 14 Amendment No: 1 7 8/1 7 8
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 6)
Engineered Safety Feature Actuation System InstrUJrentation REQUIRED SURVE ILLANCE FUNCTION CHANNELS CONDITIONS REQUI REMENTS
- 5. Turbine Trip and Feedwater Isolation
- a. Automatic 1 ,2 Ih ),3(h) 2 trains G SR 3.3.2.4 NA
.A.ctuat ion Logi c SR 3.3.2.5 and Actuati on SR 3.3.2.8 Re lays
- b. Steam Generator (SG) Water Leve1-Hi gh Hi gh (P-14l
- 1) Unit 1 1,2(h) ,3(") 4 per SG D SR 3.3.2.1 ::; 89.9% of SR 3.3.2.4 narrow range SR 3.3.2.5 instrument SR 3.3.2.6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12
- 2) Unit 2 1,2(") ,3: h) 4 per SG D SR 3.3.2.1 ::; 81.5% of SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12
- c. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and reqclirements.
(contmuedl (h) Except when all Feedwater Isolation Valves are closed or isolated by a closed manual valve.
BRAIDWOOD - UNITS 1 &2 3.3.2 - 15 Amendment No: 178/178
Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 6)
Engineered Safety Feature Actuati on System InstrLl1entati on APPLICABLE MODES O~
OTHER SPECIFI ED REQUIRED SURVE ILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUr REMENTS VALUE
- a. Actuation 1,2,3 2 trai ns G S", 3.3.2.4 NA Actuation SR 3.3.2.5 SR 3.3.2.8
- b. SG Water Level-Lo,;
Low
- 1) Unit 1 1,2,3 4 per SG D SR 3.3.2.1 ;> 16.1% of SR 3.3.2.6 SR 3.3.2.10 SR 3.3.2.12 span
- 2) Unit 2 1,2,3 4 per SG D SR 3.3.2.1 ;> 34.8% of SR 3.3.2.6 narrow range SR 3.3.2.10 i nstrurrent SR 3.3.2.12 span
- c. Safety Injection Refer to Functjon 1 (Safety Injection) for all initiation functions and requirerrents.
- d. Loss of Offsite Power 1,2,3 2 H SR 3.3.2.3 2730 V (Undervoltage on SR 3.3.2.10 Bus 141(24])) SR 3.3.2.11
- e. Undervoltage 1,2 4 SR 3.3.2.7 ;:: 4920 V Coolant PlJTIP SR 3.3.2.10 train) SR 3.3.2.12
- f. Auxil i ary Feedwater 1,2,3 1 per train u 1
SR 3.3.2.1 ;> 17.4 psia Pump Suction Transfer SR 3.3.2.2 on Suction SR 3.3.2.10 Pressure- Low
- 7. to Contai nrrent
- a. Automat i e Actuation 1,2,3,4 2 trains C SR NA Logic and Actuation SR Rel ays SR
- b. Refueling Water 1,2,3,4 4 K SR 3.3.2.1 ;::44.7% of Storage Tank (R~ST) SR 3.3.2.6 i nstrLl1ent Level-Low Low SR 3.3.2.10 span SR 3.3.2.12 Coi nei dent with Refer to Function 1 (Safety Injection) for all initiation functions and req,;irements.
Safety Injection icont'nue3)
BRAIDWOOD - UNITS 1 &2 3.3.2 - 16 Amendment No: 178/178
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 6)
Engineered Safety Feature Actuation System Instrumentation APPLI CPSLE M'JDES OR OTIiER SPECIFIED REQUIRED SURVi:I LLANCE ALLOWPSLE FUNCTION CONDITIONS CHANNELS CONDITIONS Rf:QUIREMENTS VALJE
- 8. ESFAS Interlocks
- a. Reactor Trip, P-4 1,2,3 2 P2r train F SR 3.3.2.9 NA
- b. Pressurizer Pressure, 1,2,3 2 L SR 3.3.2.6 1936 psig P-l1 SR 3.3.2.10
- c. T",,-La,.; La,.;, P-12 1,2,3 3 L SR 3.3.2.6 ~ 548.O"F SR 3.3.2.10 BRAIDWOOD - UN 1 &2 3.3.2 17 Amendment No: 178/178
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 171 TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 171 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 178 TO FACILITY OPERATING LICENSE NO. NPF-37, AND AMENDMENT NO. 178 TO FACILITY OPERATING LICENSE NO. NPF-66 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457,STN 50-454, AND STN 50-455,
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 6, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12159A304),
supplemented by letter dated November 19, 2012, (ADAMS Accession No. ML123250334),
Exelon Generation Company, LLC (Exelon, the licensee), requested license amendments for Braidwood Station (Braidwood), Units 1 and 2, and Byron Station (Byron), Unit Nos. 1 and 2.
The proposed amendments add a note to surveillance requirements (SRs) 3.3.1.7,3.3.1.8, and 3.3.1.12 in technical specifications (TS) 3.3.1, "Reactor Trip System (RTS) Instrumentation," and SR 3.3.2.2 and SR 3.3.2.6 in TS 3.3.2, "Engineered Safety Features Actuation System (ESFAS)
Instrumentation," at each plant, to exclude the solid state protection system (SSPS) input relays from the Channel Operational Test (COT) SRs for RTS and ESFAS functions with installed SSPS bypass capability.
The November 19, 2012, supplement contained clarifying information and did not change the NRC staff's initial proposed finding of no significant hazards consideration or expand the scope of the original Federal Register notice.
2.0 BACKGROUND
By letters dated March 30, and April 12, 2012 (ADAMS Accession Nos. ML120660494 and ML120950371, respectively), the NRC approved amendments for Exelon to revise Required Action Notes in Braidwood and Byron TS 3.3.1, and TS 3.3.2, ESFAS Instrumentation, to allow certain functions in the RTS and ESFAS SSPS instrumentation to be tested in bypass following installation of the bypass test capability.
-2 As documented in NRC letter dated March 30, 2012, the following functions in the RTS and ESFAS TSs are being modified to have installed bypass capability and permit COT in bypass:
TS Section 3.3.1 (Table 3.3.1-1)
Function 2 Power Range Neutron Flux Function 3, Power Range Neutron Flux - High Positive Rate Function 6 Overtemperature AT Function 7 Overpower AT Function 8 Pressurizer Pressure Function 9 Pressurizer Water Level - High Function 10 Reactor Coolant Flow - Low (per loop)
Function 14 Steam Generator (SG) Water Level - Low Low (per SG)
TS Section 3.3.2 (Table 3.3.2-1)
Function 1.c Safety Injection - Containment Pressure - High 1 Function 1.d Safety Injection - Pressurizer Pressure - Low Function 1.e Safety Injection - Steam Line Pressure - Low Function 4.c Steam Line Isolation - Containment Pressure - High 2 Function 4.d Steam Line Isolation - Steam Line Pressure Function 5.b Turbine Trip and Feedwater Isolation - Steam Generator (SG) Water Level- High High (P-14)
Function 6.b Auxiliary Feedwater - SG Water Level - Low Low Function 7.b Switch over to Containment Sump - Refueling Water Storage Tank (RWST) Level - Low Low
3.0 REGULATORY EVALUATION
The NRC staff reviewed the proposed TS changes against the following regulatory requirements to ensure that there is reasonable assurance that the systems and components affected by the proposed TS changes will perform their safety functions:
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," establishes the fundamental regulatory requirements. Specifically, Appendix A, to 10 CFR Part 50, "General Design Criteria for Nuclear Power Plants,"provides criteria for the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety.
In 10 CFR 50.36, "Technical specifications," the Commission established its regulatory requirements related to the contents of the TS. Specifically, 10 CFR 50.36 states that "each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specifications in accordance with the requirements of this section."
In addition, 10 CFR 50.36(c)(3) states, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
-3 The NRC staff reviewed the proposed TS changes against these requirements to ensure reasonable assurance that the systems affected by the proposed TS changes will perform their required safety functions.
4.0 TECHNICAL EVALUATION
The Braidwood and Byron TS Definition for a COT states:
A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.
At Braidwood and Byron, the SSPS input relays are currently tested during a COT that is performed in accordance with the licensee's Surveillance Frequency Control Program (SFCP)
(e.g., on a frequency of 184 days or 6 months). The proposed change would add a Note to SRs 3.3.1.7,3.3.1.8,3.3.1.12, and 3.3.2.6 stating, "The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability." However, the SSPS input relays will continue to be cycled during channel calibration under SRs 3.3.1.10, 3.3.1.11, and 3.3.2.10.
In December 2011, the licensee discovered that the changes necessary to exclude the SSPS input relays from the COT for the RTS and ESFAS functions with installed bypass test capability had not been included in license amendment request (LAR) dated March 14,2011 (ADAMS Accession No. ML110760088). Cycling of the complete channel with associated SSPS input relays could result in a partial trip of the actuation logic and a shift in the logic that would require only one additional trip Signal to cause a reactor trip or an engineered safety feature actuation, i.e., from a two-out-of-four to one-out-of-three logic or from two-out-of-three to one-out-of-two logic. To prevent this from happening, it is desirable not to go to partial trip testing during normal plant operation.
The proposed change will exclude the SSPS input relays from the COT surveillance for the RTS and ESFAS instrumentation that will be tested in bypass following implementation of the bypass test instrumentation modification. The proposed change is needed to support use of bypass test capability that is being installed to reduce the potential for unnecessary reactor trips or engineered safeguards actuation due to a failure or transient in a redundant channel.
The Braidwood and Byron TS Definition for a Channel Calibration states:
A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALI BRAliON shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions. Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an in-place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated.
SRs 3.3.1.10,3.3.1.11, and 3.3.2.10 require the performance of a Channel Calibration, which
-4 SRs 3.3.1.10,3.3.1.11, and 3.3.2.10 require the performance of a Channel Calibration, which also requires cycling the SSPS input relay. The SSPS input relays will be cycled during the performance of these surveillances, performed in compliance with the SFCP (i.e., on an 18 month frequency). These surveillances will verify operability of the SSPS input relays and provide assurance that there are no failures that would prevent the actuation of a required RTS or ESFAS function.
In response to the NRC staff request for additional information by letter dated November 19, 2012, the licensee provided information on the failure history of the SSPS input relays.
Following the approval of the Braidwood and Byron license amendment nos. 148 and 153 (respectively) on January 29,2008 (ADAMS Accession No. ML080110179), the licensee increased COT frequency from a 92-day to 184-day frequency.
Since 2008, at Braidwood, there have been approximately eight tests performed (184-day frequency) on each input relay for the functions that provide an SSPS input, with no occurrence of a failed relay. A comprehensive review of the usage history dating back to 2000 was conducted for SSPS logiC input relays. Only one SSPS logic input relay failure was found to have occurred on May 2, 2002, during an outage. There are greater than 500 SSPS input relays per unit at Braidwood.
At Byron, since 2008, there have been approximately eight tests performed (184-day frequency) on each input relay for the functions that provide an SSPS input, with no occurrence of a failed relay. A comprehensive review of the usage history dating back to 2000 was conducted for SSPS logic input relays, and Byron had only one SSPS input relay which failed to return to a non-tripped state following the Byron, Unit No.1, spring 2011, refueling outage. There are greater than 500 input relays per unit at Byron. Byron has had no other SSPS input relay failures on Unit No.1 or Unit No.2 either during normal operation or during functional testing.
The licensee requested other United States nuclear plants to provide failure history of SSPS input relays in their plants. Eleven licensees responded to this request. One plant with a 6-month COT reported one failure during the last three cycles and the remaining 10 plants reported three failures (combined) during the last three cycles of 18-month COT.
The NRC staff concludes from the above failure history that SSPS input relays are highly reliable and the exclusion of the SSPS input relays from COT will not have any appreciable effect on the plant safety and hence, will comply with the requirements specified in Section 3.0 of this safety evaluation (SE).
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change the requirements with respect to installation or use of a facility's components 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
-5 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 (77 FR 53927; September 4,2012). 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
In December 2011, the licensee realized that in the previous LAR dated March 14,2011, for installing bypass test capabilities to RTS and ESFAS instrumentation, Exelon did not exclude SSPS input relays from the COT. By the LAR dated June 6, 2012, the licensee proposed to rectify this limitation by adding notes to exclude SSPS input relays from COT for RTS and ESFAS functions with installed bypass test capability.
The NRC staff finds the proposed LAR will improve the plant reliability by preventing the possibility of unnecessary reactor trip or engineered safeguards actuation due to a failure or transient in a redundant channel and will comply with the regulatory requirements specified in Section 3.0 of this SE and hence, acceptable to the NRC staff.
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Mazumdar, NRR Date of issuance: February 6, 2013
Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNITS NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISE TECHNICAL SPECIFICATIONS 3.3.1 and 3.3.2 (TAC NOS. ME8881, ME8882, ME8883, AND ME8884)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendments No. 171 to Facility Operating License No. NPF-72 and No. 171 to Facility Operating License No. NPF-77 for the, Braidwood Station, Units 1 and 2, respectively, and No. 178 to Facility Operating License No. NPF-37 and No. 178 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated June 6, 2012, as supplemented by letter dated November 19, 2012.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454 and STN 50-455
Enclosures:
- 1. Amendment NO.171 to NPF-72
- 2. Amendment NO.171 to NPF-77
- 3. Amendment No.178 to NPF-37
- 4. Amendment No.178 to NPF-66 5, Safety Evaluation cc w/encls: Listserv DISTRIBUTION PUBLIC LPL3-2 R/F RidsNrrDeEicb Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlLpl3-2 Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsNrrDorlDpr Resource RidsNrrPMBraidwood Resource RidsAcrsAcnw_MailCTR Resource Accession Number' Package'ML13014A677 , BWI' ML13011A277 Letter' ML13014A711 *By Memo Dated i
OFFICE DORLlLPL3-2/PM DO RLlLPL3-2/LA DE/EICB/BC OGC NAME MMahoney SRohrer JThorpe* RRader DATE 01/28/13 01/22/13 12/18/12 214/13 OFFICE DORLlLPL3-2/BC DORLlLPL3-2/PM
!NAME JWiebe/Acting MMahoney DATE 2/05/13 2/06/13 OFFICIAL RECORD COPY