RS-19-115, Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
| ML19354B645 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/20/2019 |
| From: | Demetrius Murray Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-19-115 | |
| Download: ML19354B645 (120) | |
Text
{{#Wiki_filter:4300 \.V1nf1elcJ F~ oac! Exelon Ger1eration VVa1-re n v1ile. l L 60555 630 65 7 2000 Office RS-19-115 10 CFR 50 .90 December 20 , 2019 U.S . Nuclear Regulatory Commission ATTN: Document Control Desk Washington , DC 20555-0001 Braidwood Station , Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station , Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Supplement to Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505 , Revision 2, "Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b" References : 1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Comm ission , "Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, 'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b' ," dated December 13, 2018 (ADAMS Accession No . ML18352B063)
- 2) Email from J. Wiebe (U .S. Nuclear Regulatory Commission) to L. A. Simpson (Exelon Generation Company, LLC) , " ... Clarification Call Regarding Certain RAI Response and an Audit Identified Issue," dated November 20 , 2019 In EGC letter dated December 13, 2018 (Reference 1), Exelon Generation Company, LLC (EGC) requested an amendment to the Renewed Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station , Units 1 and 2 (Braidwood) , and Renewed Facility Operating License Nos.
NPF-37 and NPF-66 for Byron Station , Units 1 and 2 (Byron) , respectively. The proposed amendments would modify Techn ical Specifications (TS) requirements to permit the use of risk-informed completion times (RICTs) in accordance with the Technical Specifications Task Force (TSTF) Traveler TSTF-505 , Revision 2, "Provide Risk-Informed Extended Completion Times - RITSTF [Risk-Informed TSTF] Initiative 4b ," (ADAMS Accession No . ML18183A493).
U.S. Nuclear Regulatory Commission December 20, 2019 Page 2 In NRC email dated November 20, 2019 (Reference 2) , the NRC determined that additional information is needed to complete its review. As discussed during the clarification call held with the NRC on November 25, 2019, EGC is providing this supplement with the requested information. In addition, as requested during the audit conducted in June 2019 , Attachments 2 and 3 to this supplement provide an updated mark-up of the Braidwood and Byron TS pages . Attachment 4 provides a revision to Enclosure 1, the list of revised required actions to corresponding PRA functions. Attachments 2, 3, and 4 supersede all TS pages and Enclosure 1 previously provided . EGC has reviewed the information supporting the No Significant Hazards Consideration and the Environmental Consideration that was previously provided to the NRC in Attachment 1 of the Reference 1 letter. The additional information provided in this submittal does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration. This additional information also does not affect the conclusion that there is no need for an environmental assessment to be prepared in support of the proposed amendment. In accordance with 10 CFR 50.91 , "Notice for public comment; State consultation ," paragraph (b) , EGC is providing a copy of this letter and its attachment to the State of Illinois. This letter contains no regulatory commitments. Should you have any questions concerning this submittal , please contact Ms. Lisa Simpson at (630) 657-2815 . I declare under penalty of perjury that the foregoing is true and correct. Executed on the 20th day of December 2019 . Respectful! , Attachments :
- 1) Supplemental Information
- 2) Proposed Technical Specifications Changes for Braidwood Station , Units 1 and 2
- 3) Proposed Technical Specifications Changes for Byron Station , Units 1 and 2
- 4) Enclosure 1, Revision 1, to LAR to Adopt Risk Informed Completion Times TSTF-505 ,
Revision 2 cc: NRC Regional Administrator - Region Ill NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector - Byron Station NRC Project Manager, NRR - Braidwood and Byron Stations Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 1 Supplemental Information By letter dated December 13, 2018 , (Reference 1) Exelon Generation Company , LLC (EGC) requested an amendment to the Renewed Facility Operating License Nos. NPF-72 and NPF-77 for Braidwood Station , Units 1 and 2 (Braidwood), and Renewed Facility Operating License Nos. NPF-37 and NPF-66 for Byron Station , Units 1 and 2 (Byron) , respectively . The proposed amendments would modify Technical Specifications (TS) requirements to permit the use of risk-informed completion times (RICTs) in accordance with the Technical Specifications Task Force (TSTF) Traveler TSTF-505 , Revision 2, "Provide Risk-Informed Extended Completion Times - RITSTF [Risk-Informed TSTF] In itiative 4b ," (ADAMS Accession No. ML18183A493) . By email dated November 20 , 2019 (Reference 2) , the NRC determined that additional information is needed to complete its review. This attachment provides the requested information .
References:
- 1) Letter from D. M. Gullatt (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission , "Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505 ,
Revision 2, 'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b'," dated December 13, 2018 (ADAMS Accession No. ML18352B063)
- 2) Email from J. Wiebe (U.S. Nuclear Regulatory Commission) to L.A. Simpson (Exelon Generation Company , LLC) , " ... Clarification Call Regarding Certain RAI Response and an Audit Identified Issue," dated November 20 , 2019 Clarification items for Byron/Braidwood TSTF-505 application
- 1. Clarify the status of implementation items. If all items are already completed , the license condition will be no longer necessary. The RAI responses discuss only some of the 50 .69 implementation items .
EGC Response: of the Byron/Braidwood TSTF-505 LAR submitted December 13, 2018 (Reference 1) provided a list of PRA implementation items that must be completed prior to implementing the RICT Program at Braidwood and Byron . The following table identifies an update to the list of items provided in Attachment 5 of Reference 1. All the Braidwood and Byron RICT Program PRA implementation items are currently completed ; therefore , the license conditions proposed in Reference 1 are no longer necessary. 1
ATTACHMENT 1 Supplemental Information Updated Attachment 5, Braidwood and Byron RICT Program PRA Implementation Items Source Description Status ADAMS The internal events and fire PRA models will be updated to Complete Accession No. versions that include the updated HVAC modeling prior to ML18165A181 implementing the Risk Informed Completion Time (RICT) Program at Braidwood and Byron . 50.69 RAI 3.a ADAMS Where breaker coordination could not be confirmed for a Complete Accession No . unit, the applicable model is being updated so that load ML18165A181 side cables are designated as causing the loss of the associated power supply. The FPRA models for Byron and 50.69 RAI 3.b Braidwood will be updated to incorporate failures required to account for instances where breaker coordination cannot be confirmed prior to implementing the Risk Informed Completion Time (RICT) Program at Braidwood and Byron. ADAMS Identification of all wall mounted panel configurations with Complete Accession No. four or more switches will be completed and any resulting ML18165A181 changes to the Byron and Braidwood FPRA models to incorporate the impact of these panels will be made prior to 50.69 RAI 3.d implementing the Risk Informed Completion Time (RICT) Program at Braidwood and Byron. ADAMS The Byron and Braidwood FPRA models that will be used Complete Accession No. for Risk Informed Completion Time (RICT) Program ML18165A181 implementation at Braidwood and Byron will include a new sump clogging value consistent with the WCAP-16362-NP 50.69 RAI 3.e guidance. ADAMS The Byron and Braidwood Fire PRAs to be used to support Complete Accession No . the implementation of the Risk Informed Completion Time ML18165A181 (RICT) Program at Braidwood and Byron will retain a 1E-06 joint HEP floor value and justification will be included in the 50 .69 RAI 8.c Fire PRA documentation for specific HEP combinations for which a value of less than 1E-05 is used. ADAMS The additional failure contribution of the Westinghouse Complete Accession No. RCP Shutdown Seal Bypass failure mode will be added to ML18165A181 the Byron and Braidwood Internal Events and Fire PRA models prior to implementing the Risk Informed Completion 50.69 RAI 11 Time (RICT) Program at Braidwood and Byron. 2
ATTACHMENT 1 Supplemental Information
- 2. Byron/Braidwood TSTF-505 deviates from the guidance with regards to the periodicity of the PRA update process and the tracking of cumulative risk (see table below). Justification for these deviations would be necessary (If these were accepted with justification in response to a different application you may be able to point to that acceptance) .
Topic NEI 06-09-A guidance LAR Comments PRA Update "the PRA shall be maintained Enclosure 7 states: Additional 12 Process and updated in accordance months from with approved station PRA updates for plant guidance procedures on a periodic changes are performed basis not to exceed two at least once every 48 refueling cycles ." months. BWD and BYR Stations have 18-month refueling cycles ; however, a frequency of 48 months for PRA updates would be equivalent for plants with a 24-month cycle . Cumulative "The as-occurred cumulative LAR Enclosure 11 states: Additional 30 Risk Tracking risk associated with the use of months from RMTS beyond the front-stop The RICT Program will guidance CT for equipment out of require calculation of service shall be assessed and cumulative risk impact at compared to the guidelines for least once everv small risk changes in 48 months . Braidwood Regulatory Guide 1.174 [4] Station and Byron Station and corrective actions applied (BWD and BYR) have as appropriate. This 18-month refueling cycles ; howeve r, a assessment shall be conducted every refueling frequency of 48 months cycle on a periodicity not to for PRA updates would be equivalent for plants exceed 24 months." with a 24-month cycle. EGC Response: EGC agrees that the statements within Enclosure 7 and Enclosure 11 of the Byron/Braidwood TSTF-505 LAR submitted December 13, 2018 (Reference 1) deviate from the NEI guidance. Specifically:
- PRA Updates for Braidwood and Byron shall be maintained and updated in accordance with approved station procedures on a periodic bases not to exceed two refueling cycles ,
in accordance with the guidance of NEI 06-09-A, Revision 0-A.
- The RICT Program for Braidwood and Byron will require calculation of cumulative risk impact every refueling cycle on a periodicity not to exceed 24 months, in accordance with the guidance of NEI 06-09-A, Revision 0-A.
3
ATTACHMENT 1 Supplemental Information
- 3. At the audit the agreed upon modified wording to the notes below was as follows :
For TS 3.3.5 RA B.1 CT:
--------------------------------------------------------1\J()TE:---------------------------------------------------
Rl CT entry is not permitted for the Loss of Function Condition when the same Function is inoperable on more than one Bus. For TS 3.7.4 RA B.1 CT:
--------------------------------------------------------1\J()TE:---------------------------------------------------
RICT entry is not permitted for the Loss of Function Condition when more than two required SG P()RV lines are inoperable. EGC Response: E:GC has incorporated the proposed l\J()TE: for TS 3.3 .5 into Attachments 2 and 3 for Braidwood TS and Byron TS, respectively. As discussed during the clarification call on l\Jovember 25 , 2019, E:GC has proposed an alternative approach for TS 3.7.4 that eliminates the need for a l\J()TE: for Required Action B.1. An additional Condition eliminates a loss of function condition for TS 3.7.4. Attachments 2 and 3 provide an update mark-up of the Braidwood and Byron TS pages . 4
ATTACHMENT 2 Proposed Technical Specifications Changes for Braidwood Station, Units 1 and 2 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 Updated Mark-up of Technical Specifications Pages for Braidwood Station B/B TS Inserts
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour or any subsequent 8 hour interval from the previous performance (plus the extension allowed by SR 3.0 .2), Condition Bis entered. The Completion Time clock fo r Condition A does not stop after Condition Bis entered, but continues from the time Condition A was initially entered . If Required Action A.l is met after Condition B is entered , Condition B is exited and operati on may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired. EXAMPLE 1.3-8 ACTim~s CONDITION REilllJ RED ACTION COMPLETION TIME A. One A. l Restore subs~stem 7 _d_m subsvstem to OPERABLE inoQerable. status. OR In accordance with the Risk Informed ComQletion Time Program B. Required B. l Be in MODE 3. Q_ hours Action and associated AND ComQletion Time not B_2_ Be in___MOD E_-2,_ 36 hours met. BRAIDWOOD - UNITS 1 &2 1.3 - 13 Amendment 00
Completion Times 1.3 1.3 Completion Ti mes EXAMPLES (continued) When a subsystem is declared inoperable, Condition A is entered. The 7 day Completion Time mav be appli ed as discussed in Example 1.3-2. However. the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Complet i on Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered. The Risk Infom1ed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions. the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e. not the RICT) or 12 hours after the plant configuration change, whichever is less . If the 7 day Completion Time clock of Condition A ha s expired and subsequent changes in plant condition result in exit-ing the ap_p_licability of the Risk Info rmed Completion Time Program without re storing the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Act ions B.l and B.2 starL If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsvstem has not been restored to OPERABLE. status, Condition Bis also entered and the Completion Time clocks for Required Actions B.l and B.2 start. If the inoperable subsvstems are restored to OPERABLE status after Condition B is entered Condit i ons A is exited. and therefore, the Required Actions of Condition B may be terminated. IMMEDI ATE When "Immediatel y" is used as a Completion Time, t he COMPLETION TIME Required Action should be pursued without delay and in a cont roll ed manner. BRAIDWOOD - UNITS 1 &2 1.3 - 14 Amendment .gg
RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE. APPLICABILITY: According to Table 3.3.1-1. ACTIONS -- -----------------------------------NOTE -------- ----------- ------------------ Separate Condition entry is allowed for each Function. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels or Table 3.3.1 -1 for the trains inoperable. channel(s) or train(s). B. One Manual Reactor B.1 Restore channel to 48 hours Trip channel OPERABLE status. inoperable. DR
~ ----
~'~!'.
g ;-2 ge-~i- n N09E -3 ;* 34 *R&t.H"-5 (continued) BRAIDWOOD - UNITS 1 &2 3.3.1 - 1 Amendment 9-8
RTS Instrumentation 3 .3 . 1 ACTIONS (continued) CONDITION REQUIRED ACTION COMP LETION TI ME D. One Power Range -------------NOTE------------ Neutron Flux-High One channel may be bypassed channel inoperable. for up to 12 hours for survei l lance testing and setpoint adjustment . D. l Place channel in 72 hours trip. (continued) BRAIDWOOD - UNITS 1 &2 3 .3.l - 3 Amendment 188
RTS Instrumentation 3.3.l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. One channel -------------NOTE------------ inoperable. One channel may be bypassed for up to 12 hours for surveillance testing. E.l Place channel in 72 hours trip.
<: [RICT INSERT]
Be-+n-MHGE- 3 . (continued) BRAIDWOOD - UNITS 1 &2 3.3.1 - 4 Amendment 188
RTS Instrumentation 3.3.l ACTIONS (continued) CONDITION REQUIRED ACTIO N COMPLETION TIME K. One channel ------------NOTES------------ inoperabl e . 1. For Functions with installed bypass test capability (Functions Sa, 9, 10), one channel may be bypassed for up to 12 hours for surveillance testing.
- 2. For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours for surveil lance testing of other channels.
K. l Place channel in 72 hours trip.
~ -** {~ICT-~\JSE~T J OR v _? R2c:k+ee- T-H E-RMA*L DJll.lC:D +8 *-hours
!INSERT TS 3 3 1J l\..L I U"V'ILI\
~ lCondition L tG < *P-7.
- l. One Turbine Trip ------------NOTE-------------
channel inoperable. The inoperable channel may be bypassed for up to 12 hours for survei llance testing of other channels. 1::.1 Place channel in 72 hours trip.
~ GR
~ ~ICTINSERT
-<E-- _ INSERT TS 3 3.11 Redtlec..a__::i::f-+E-RMAl::--P.m+rn 1-8 R01:+r-s J_ '2 L -'- tB-~ *P--8*;- Condition N ._J (continued) BRAIDWOOD - UNITS 1 &2 3.3.l - 6 Amendment 9
RTS Instrumentation 3.3.l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME £ M. One train inoperable. -------- ----NOTE ------------- One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE. Restore train to 24 hours OPERABLE status.
~ -** - 4~1CT_INSffi!J M.2 Be i-R-f488E-**3; *38 he*LJrs ~L One RTB train -------------NOTE---- --------
(7 inoperable. One train may be bypassed for up to 4 hours for surveillance ~ testing, provided the other train is OPERABLE.
~L 1 Restore train to 24 hours OPERABLE status.
~ OR N;2 Dr.
U C
; n M(l D.C I T !- 1 lV DC
')
0 * £ 8. One or more channels _., 8 .1 inoperable. ~ Verify interlock is in required state for existing unit cond itions. 1 hour o__?.. Uo L (continued) BRAIDWOOD - UNITS 1 &2 3.3.l - 7 Amendment -139*
RTS Instrumentation 3.3.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME
.P. One or more channels ~* Jl. l Verify interlock is 1 hour (1 inoperable. in required state for existing unit
~ conditions. INSERT TS 3.3.1 J *7 Fl8tff-S
<E-- Condition S One trip mechanism 0.1 Restore ~ -Aepi::r-as+e 48 hours inoperable for one trip mechanism to RTB.
[~ OPERABLE status. JNSERT TS *3_ 3 1- ]_ Be i-H *M09-E--3-.- J;J1
~ -lCondition hf\tU<::
U JI 1ruu1 J H. One Reactor Coolant ------------NOTE------------- Pump (RCP) Breaker The inoperable channel may be Position channel (per bypassed for up to 4 hours v_ J train) inoperable. for surveillance testing of other channels. c
-~ H. l Place channel in 6 hours trip.
[\{J GH ___ [INSERT TS 3.3 .1]- HeElB E:-e---T++SQ:fi4A !::-P8~*J SR: 1 he u-F& f g--<;~.P ;m
--E 1~ondition W BRAIDWOOD - UNITS 1 &2 3.3.1 - 8 Amendment 69
RTS Instrumentation 3.3.1 Table 3.3. 1-1 (page 2 of 6) Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE
- 6. Overt emperature ~T 1, 2 4 E SR 3 .3.1.1 Refer 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. Overpower ~T 1, 2 4 SR 3.3. 1.1 Refer to SR3 .3.l.7 Note 2 SR 3 .3.1.10 SR 3.3. 1.15
- 8. Pressurizer Pressure
- a. Lo111 1 .* 4 K SR 3. 3 . 1.1 2 1875 psig SR 3 .3. 1.7 SR 3.3 . 1. 10 SR 3.3.1.15
- b. High 1, 2 4 E SR 3.3 . 1. 1 s 2393 psig SR 3 .3 . 1.7 SR 3 .3. 1.10 SR 3.3 . 1. 15
- 9. Pressurizer Water 11-* 3 K SR 3.3 . 1.1 s 93 .5% of Level-High SR 3.3 . 1.7 instrument SR 3.3. 1.10 span 10 . Reactor Cool ant 1' 3 K SR 3 .3 . 1.1 2 89 .3% of Flow-Low (per loopJ SR 3 .3 . 1.7 loop minimum SR 3.3.1.10 measurec fl ow SR 3.3.1.15 11 . Reactor Coolant Pump (RCPl Brea ke r Position 1' 4 [\7}7 R SR 3.3. 1.13 NA (per t rain)
(continued) (el Above t he P-7 (Lo111 Power Reactor Trips Block) interlock . BRAIDWOOD - UNITS 1 &2 3.3.1 - 17 Amendment -l-f-RTS In st rumentati on 3.3 .1 Table 3.3 .1-1 (page 3 of 6) Reactor Trip System Instrumentation APPLICABLE MJDES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 12 . Undervoltage l ' 4 K SR 3.3.1.9 ?. 4920 v RCPs (per train) SR 3.3.1.10 SR 3.3.1.15 13 . Underfrecuency 1' 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 CSGl Water Level-Low Low (per SGl
- a. Unit 1 1,2 4 SR 3.3.1.1 ?. 16.1% of SR 3.3.1.7 narrow range SR 3.3.1.10 inst rument 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 nar row range SR 3.3.1.10 instrument SR 3.3.1.15 span 15 . Turbine Trip
- a. Emergency Trip Header Pressu re
- 1. 3 [0}--;;. L SR 3 .3.1.10 SR 3.3.1.14
?. 910 psig (per train)
- b. Turbine Throttle Valve Closure 1 4 [!J L SR 3.3 .1.10 SR 3.3.1.14
?. 1% open (per train) 16 . Safety Injection CS!)
Input from Engi neered 1,2 2 trains [Q}--7 M SR 3.3.1.13 NA Safety Feature Actuation System CESFASl (con t inued) CeJ Above the P-7 (Low Power Reactor Trips Block) interlock . (f) Above the P-8 (Power Range Neutron Flux) interlock . BRA IDWOOD - UNITS 1 &2 3.3. 1 - 18 Amendment -+/----7+
RTS Instrumentati on 3.3 .1 Table 3.3. 1- 1 (page 4 of 6) Reactor Tr ip System Instrumentat i on APPL ICABLE VODES OR OTHER SPEC IFIED REQUI RED SURVEI LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 17 . Reactor Trip System Interlocks
- a. Source Range Bl ock 2 ,. 2 SR 3.3 . 1. 11 2 6E-ll amp Permissive , P-6 SR 3 .3 . 1.12
- b. Low Power Reactor Trips Block , P-7 (1) P-10 Input 3 SR 3.3 . 1.11 NA SR 3.3 .1.12 (2) P-13 Input SR 3.3 . 1.10 NA SR 3.3 . 1.12
- c. Power Range 3 SR 3.3 . 1.11 <: 32 . 1% RTP Neutron Flux , P-8 SR 3.3. 1.12
- d. Power Range 1,2 3 SR 3.3.1.11 2 7.9% RTP and Neutron Flux, P- 10 SR 3. 3 . 1. 12 <: 12.1% RTP
- e. Turbine Impulse 2 SR 3 . 3 . 1. 10 <: 12 . 1'%
Pressure , P-13 SR 3.3 . 1. 12 turbine power
- 18. Reactor Trip 1, 2 2 trains El_.::,,.
_! ./ N SR 3.3. 1.4 NA Breakers (RTBs) ' 3 4 . ' 5 *>' 2 t rains c SR 3 .3. 1.4 NA 19 . Reactor Trip Brea ker Undervoltage and Shunt 1,2 1 each per RTB ITJ---7" Q SR 3.3. 1.4 NA Tri p Mechanisms 3' 4 ' , 5*., 1 each per RTB c SR 3.3 . 1.4 ~IA
- 20. Automatic Trip Logic 1, 2 2 trai ns M SR 3.3 . 1. 5 NA 3' 4 ' , 5:1: 2 trai ns c SR 3.3 . 1. 5 NA (al Wi th Rod Contra l System capabl e of rod wi thdrav1a l or one or more rods not fully inserted .
(d) Below the P-6 (Source Range Block Permi ssi ve) interlock . (g) Incl uding any reactor trip bypass breakers that are racked i n and closed for bypassi ng an RTB . BRAIDWOOD - UNITS 1 &2 3.3.l - 19 Amendment -1,Ll-
ESFAS In strumentati on 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCD 3.3.2 The ESFAS instrumentation for eac h Function in Table 3.3.2-1 sha ll be OPERABLE. APPLICABI LI TY: According to Tabl e 3.3.2-1. ACTIONS
--- -- ------ -------- --- -- --------NOTE ----------------- -- ------- ----- -- ----
Separate Condition entry is allowed for each Function. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A. l Enter the Condition Immediately with one or more referenced in required channels or Table 3.3.2 -1 for the trains inoperabl e. cha nnel (s) or train(s). B. One channel B.l Restore channel to 48 hours inoperable. OPERABLE status. GR:
~- - -D3Jf!.~NSERT 8-;-3-;-f ge-+r.MGQE }-;- ~~4-¥:i-et+r-s-AN-9 g"7~ ge--l-A-MGtlf-~ 84--,b, 00-rS*
(continued) BRAIDWOOD - UNITS 1 &2 3.3.2 - 1 Amendment .g.g
ESFAS Instrumentation 3.3 .2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. C.l ------- -NOTE----- ---- One train may be bypassed for up to 4 hours for surveil l ance testing provided the other train is OPERABLE . Restore train to 24 hours OPERABLE status.
~* . {!31CT INSE~~J 38~ *hol:lrs
*68 --h8 tJPS (continued)
BRAIDWOOD - UNITS 1 &2 3.3.2 - 2 Amendment 69
ESFAS In strumentation 3 .3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. One channel D.l --------NOTE--------- inoperable. One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in 72 hours trip.
~----- ---fR ICT~S ER!_]
8-A-s-ct-r-s
;~ 2 B-e -=i- A----MOBE 4-. 84--¥1Slff s (continued)
BRAIDWOOD - UNITS 1 &2 3.3 . 2 - 3 Amendment 8-G
ESFAS Instrumentation 3.3.2 ACTIONS (contin ued) CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment E.1 --------NOTE --- ------ Pressure channel One additional inoperable . channel may be bypassed for up to 12 hours for surveil l ance testing . Place channel in 72 hours bypass.
-fl8 ct PG 84- A-eu-rs-F. One channel or train F.1 Restore channel or 48 hours inoperable . train to OPERABLE status .
§4-~Re-c:-r-s f-.-272- 8-e - i-R-- M8GE ~- 60--ABllPS (cont i nued)
BRAIDWOOD - UNITS 1 &2 3.3.2 - 4 Amendment +@
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME G. One train inoperable . G.1 --------NOTE--------- One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE. Restore train to 24 hours OPERABLE status . ~ - - ---- {F3_J_g_T ~SERI] G-; 2 .~ Be--i+l- M9DS-4 . H. One channel H.1 --------NOTE--------- inoperable. One channel may be bypassed for up to 2 hours for survei llance testing provided the other channel is OPERABLE. Place channel in 1 hour trip.
- j- --h0{:JPS 3--A-e-l:l-P-S-(continued)
BRAIDWOOD - UNITS 1 &2 3.3.2 - 5 Amendment -i-6-9
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME I. One channel I. l --------NOTE--------- inoperable. The inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels. Place channel in 72 hours trip.
~------- -~ICT_~NSER-fJ J. One or more trains J.l Declare associated Immediately inoperable. auxiliary feedwater pump inoperable.
(continued) BRAIDWOOD - UNITS 1 &2 3.3.2 - 6 Amendment -169
ESFAS Instrumentat i on 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME K. One channel K.l --------NOTE---------- inoperable. One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in 72 hours trip.
-{f~ICT INSE~j 1-08 RGU-r (continued)
BRAIDWOOD - UNITS 1 &2 3.3.2 - 7 Amendment -188
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME L. One or more channels L.l Verify interlock is 1 hour inoperable. in required state for existing unit condition. INSERT TS 3 3 2 .]
~Conditions I? M, N, and 0 13 *-h8 lJP.5
- -~* ~<
SURVEILLANCE REQUIREMENTS - ----- -- -------------- -- --------- ----NOTE ------- ---- ------------- ----------- - Refer to Table 3.3.2 -1 to determine which SRs apply for each ESFAS Function. SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. In accordance with the Surveil l ance Frequency Control Program SR 3.3.2.2 Perform COT. In accordance with the Surveillance Frequency Control Program (continued) BRAIDWOOD - UNITS 1 &2 3.3.2 - 8 Amendment +6-9
LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 Two channel s per bus of the loss of voltage Function, two channel s per bus of the degraded voltage Function and two channels per bus of the low degraded vo l tage Function sha ll be OPERABLE. APPLICABILITY : MODES 1, 2, 3, and 4; When associated DG is required to be OPERABLE by LCO 3.8 .2, "AC Sources-Shutdown." ACTIONS
-- --- -- --- ------- ------------NOTE- ------ ---------- - -- ---------- -- --- --
Separate Condit i on entry i s allowed for each Function. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 --------NOTE- -------- with one channel on For l oss of voltage one or more buses Funct i on, the inoperabl e. inoperable channel may be bypassed for up to 2 hours for surveillance testing of t he other channel. Pl ace channel in 1 hour trip. ~------~I' B. One or more Functions B.1 Restore one channel 1 hour with two channel s on for the Function on one or more buses the affected bu~7 **
-~
inoperable. OPERABLE status. /
- --iRICT I
--- (continued)
- - - - - - - -NOTE- - - - - - -
~*
RICT entry is not permitted for the Loss of Function Condition when the same Function is inoperable on more than one bus BRAIDWOOD - UNITS 1 &2 3.3 .5 - 1 Amendment J:.88
Pressurizer PORVs 3.4 .11 3.4 REACTOR COO LANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Reli ef Va l ves (PORVs) LCO 3.4.11 Each PORV and associated block va l ve shal l be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS
---- ------ --- -- ---- ------- ----- NOTE ---- --- -- ------ --- -- ----- ------- --- -
Separate Condition entry is allowed for each PORV and each bl ock va l ve. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A. l Close and maintain 1 hour inoperable and capable power to associated of being manually block va l ve. cycled. B. One PORV inoperabl e B.l Cl ose assoc i ated 1 hour and not capable of block valve. being manually cycled. AND B.2 Remove power from 1 hour associated block valve. AND B.3 Restore PORV to 72 hours OPERABLE status . ~ **-*- --{RICT I NSERT I (continued) BRAIDWOOD - UNITS 1 &2 3.4.11 - 1 Amendment -84
Pressurizer PORVs 3.4.11 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME
- c. One block va l ve C. l Place associated PORV 1 hour inoperable. in manual control.
AND C.2 Restore block valve 72 hours to OPERABLE status. ~-------{RICT I NS~ D. Required Act ion and D.l Be in MODE 3. 6 hours associated Compl etion Time of Condition A, AND B, or C not met. D.2 Be in MODE 4. 12 hours E. Two PORVs inoperable E.l Be in MODE 3. 6 hours and not capable of being manually cycled. AND E.2 Be in MODE 4. 12 hours F. Two block valves F.l Restore one bl ock 2 hours inoperabl e. valve to OPERABLE status. G. Required Act i on and G. l Be in MODE 3. 6 hours associated Completion Time of Condition F AND not met. G.2 Be in MODE 4. 12 hours BRAIDWOOD - UNITS 1 &2 3.4.11 - 2 Amendment -9B
ECCS -Operati ng 3.5.2 3.5 EMERGENCY CORE COOLI NG SYSTEMS (ECCS) 3.5.2 ECCS-Operat ing LCO 3.5.2 Two ECCS trains sha ll be OPERABLE.
--- ----------- --- -------- ---NOTES---------- --- ------------- -
- 1. In MODE 3, both Safety Inj ection (SI) pump f l ow paths and a portion of both Residual Heat Remova l (RHR) pump flow paths may be isol ated by clos i ng the i sol ati on va l ves for up to 2 hours to perform press ure i solati on valve testing per SR 3.4. 14 .1.
- 2. In MODE 3, a portion of both Res idual Heat Remova l (RH R) pump f l ow paths may be i sola ted by cl osing the isol at ion valves for up to 2 hours to perform pressu re isolat ion valve t esti ng per SR 3.4 .14.1, provided an alternate means of cold l eg injection i s avai l abl e for each isolated fl ow path .
APPLICABI LITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTI ON COMPLETION TIME A. One train i nopera ble . A. l Restore trai n to 7 days r---- I OPERABLE status . <--------* -**~RICT L. -----*--- - - B. Two trains inoperabl e. B.l Rest ore one t rain to 72 hours OPERABLE status . AND At least 100%of t he ECCS fl ow equival ent t o a singl e OPERABLE ECCS train ava i labl e. (conti nued) BRAIDWOOD- UNITS 1 &2 3.5.2 - 1 Amendment 9-8
Conta i nment Air Locks 3.6.2 ACT IONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME
- c. One or more C.1 Initiate action to Immediately containment air l ocks evaluate overall inoperable for reasons conta inment leakage other than Condition A rate per LCO 3.6.1.
or B. AND C.2 Verify a door is 1 hour closed in the affected air lock . AND C.3 Restore air lock to 24 hours OPERABLE status . ~-~* . *- ~RICTJ D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours BRAIDWOOD - UNITS 1 &2 3.6.2 - 4 Amendment 9-8
Contai nment Isola ti on Val ves 3.6 .3 3.6 CONTAINMENT SYSTEMS 3.6.3 Conta inment Isol ation Va l ves LCO 3.6.3 Each contai nment i so l at i on va l ve shall be OPERAB LE. APPLI CAB ILITY: MODES 1, 2, 3, and 4. ACTIONS
--------- --------- ----- --- ---- NOTES - ------------- -- --------- ---------- -
- 1. Penetration flow pat h(s) except fo r 48 inch purge va l ve f l ow paths may be un isol ated intermittentl y under admin i strat i ve cont rols.
- 2. Separate Cond i tion entry i s all owed for each penetrati on f l ow path.
- 3. Enter appli cabl e Condit i ons and Requ i red Act i ons for systems made inoperabl e by contai nment i so l ati on va l ves.
- 4. Enter applicable Condi tions and Req uired Actions of LCO 3.6.1, "Conta inment ," when i sol atio n valve leakage res ults in exceed ing t he overal l conta i nment l ea kage ra t e accepta nce cr iteria .
CONDITION REQUIRED ACTION COMPLETION TI ME A. ---- --- - -NOTE--------- A.1 Isol ate t he affected 4 ho urs Onl y appl icable t o penetrat i on f l ow pat h penetrati on flow paths by use of at l east /
-@cTlNSERT.
wit h two conta inment one closed and i so l ati on valves. de -act i vated
---- --------- -- - -- ---- automat i c or remote manua l valve , closed One or more manua l valve , bl i nd penetrati on f l ow pa th s fl ange , or chec k wi t h one conta i nment valve with fl ow iso l at ion va l ve th roug h t he va l ve i noperabl e except for secured.
pu rge va l ve l eakage not withi n limi t . AND (conti nued) BRAIDWOOD - UNITS 1 &2 3.6.3 - 1 Amendment 98
Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMP LETI ON TIME A. (continued) A.2 -- ----- -NOTES------- -
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative l
means. Verify the affected Once per 31 days penetration flow path for isolation i s i so 1ated. devices outside containment AND ~oil.owing ]
- 1solat1on Prior to entering MODE 4 from MOOE 5 if not performed within the previous 92 days for isolation devices inside containment (continued)
BRAIDWOOD - UNITS 1 &2 3.6.3 - 2 Amendment 9B
Containment Isolation Va l ves 3.6.3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. ---- ---- -NOTE--------- C. l Isolate the affected 72 hours Only applicable to penetration f l ow path penetration f l ow paths by use of at l east < f!_INSE R_!J with only one one closed and containment isolation de -activated valve and a closed automatic or remote system. manual valve, closed
-- - -------- --- -- -- ---- manual valve, or bl i nd flange.
One or more penetration flow paths AND with one containment isolation valve C.2 --------NOTES -------- inoperable. 1. Isol ation dev ices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means .
Verify the affected penetrati on flow path Once per 31 daysj is isolated. J following D. One or more D.1 Restore purge valve 24 hours penetration flow paths leakage to within isolation with one or more limits. containment purge valves not wi thin purge va l ve l eakage limits . (contrnued) BRAIDWOOD - UNITS 1 &2 3.6 .3 - 4 Amendment -98
MS I Vs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Va l ves (MSIVs) LCO 3.7.2 Four MSIVs and their associated actuator trains shall be OPERABLE. APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are closed. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV actuator A. l Restore MS IV actuator 7 days train inoperable . train to OPERABLE ~* - --- ~JCII NSERT status . ~- B. Two MSIVs each wit h one actuator train inoperable such that B. l Restore one MSIV actuator trai n to OPERABLE status. 72 hours
~ -*-
L
@:cf!i:iSERT ]
the inoperable actuator trains are in different ESF Divis i ons .
- c. Two MSIVs each with C. l Restore one MS IV 24 hours one actuator tra i n actuator train to inoperabl e and bot h OPERABLE status .
i noperabl e actuator trains are in the same ESF Division. D. Two MS IV actuator D.l Dec l are t he affected Immediately trains i noperabl e on MSIV inoperable . the same MSIV . (cont rn ued) BRAIDWOOD - UNITS 1 &2 3.7.2 - 1 Amendment -IBl
MS IVs 3.7.2 ACT IONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Three or more MSIV E.l Declare each affected Immediately actuator trains MSIV inoperabl e. inoperabl e. OR Required Acti on and associated Compl et i on Time of Condition A, B, or C not met. F. One MSIV inoperable in F.l Restore MSIV to 8 hours MODE 1. OPERABLE status .
-E--- - ~ iRICT_I G. Required Action and G. l Be in MODE 2. 6 hours associated Compl etion Time of Conditi on F not met.
H. ---------NOTE --------- H.l Close MSIV. 8 hours Separate Condition entry i s all owed for AND each MSIV.
------ --- - - - -- -------- H.2 Verify MSIV is Once per 7 days cl osed .
One or more MSIV inoperabl e in MODE 2 or 3. I. Required Action and I. l Be in MODE 3. 6 hours associated Compl etion Time of Condit i on H AND not met. I. 2 Be in MODE 4. 12 hours BRAIDWOOD - UNITS 1 &2 3.7.2 - 2 Amendment -18+
SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs) LCD 3.7.4 Four SG PORV lines sha ll be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQU I RED ACTION COMPLETION TIME A. One SG PORV line A. l Restore SG PORV line 30 days inoperable. to OPERABLE status. ~ - {~_IC!J B. Two OP--fflGPe-- SG PORV B.l Restore -a.:i 1- but one 24 hours lines inoperable. SG PORV line to OPERABLE status. -<E---- ---~ -~RICfl NSERTj Lo 1 - ,~ I [g}~ G. Required Action and C. l Be in MODE 3. 6 hours associated Completion Time not met. AND [g} :-; -C. 2 Be in MODE 4. 12 hours C_ Three or more SG C 1 Restore all but one SG 24 hours PORV lines PORV lines to OPERABLE inoperable_ status _ BRAIDWOOD - UNITS 1 &2 3.7.4 - 1 Amendment 34
AF System 3.7.5 3.7 PLANT SYSTEMS 3.7 .5 Auxiliary Feedwater (AF) System LCO 3.7.5 Two AF trains shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS
NOTE----------- ----- -----------------
LCO 3.0.4.b i s not applicable when enter ing MODE 1. CONDITION REQUIRED ACTION COMPLETION TIME A. One AF train A. l Restore AF train to 72 hours inoperable. OPERABLE status. ~- - ---~~c!_L B. Required Action and B.l Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met. B.2 Be in MODE 4. 12 hours
- c. Two AF trains C.l ---------NOTE--------
inoperable. LCO 3.0.3 and al l ot her LCD Required Actions requiring MODE changes are suspended until one AF train i s restored to OPERABLE status. Initiate action to Immediately restore one AF train to OPERABLE status. BRAIDWOOD - UNITS 1 &2 3.7 .5 - 1 Amendment -}34
CC System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Coo li ng Water CCC) System LCO 3.7.7 The CC System shal l be OPERAB LE. APP LICABI LITY : MODES 1, 2, 3, and 4. ACTIONS
-- ---------- -- ---- ------------NOTE- ------------- ---- ------- - --- ------ --
Enter appl icabl e Cond iti ons and Required Actions of LCO 3.4 .6, "RCS Loops -MODE 4," for Residua l Heat Remova l loops made i noperable by CC. CON DITION REQU I RED ACTION COMP LETION TI ME A. One CC fl ow path A. l Restore CC f l ow path 7 days inoperabl e. to OPERABLE stat us . ~-- --* -- *{~ ICT 1. B. One req uired CC pump B.1 Restore required CC 7 days inopera ble . pump to OPERABLE ~-~- -- {~1cf1 status . C. Required Act i on and C. l Be in MODE 3. 6 hours associ ated Compl et i on Ti me of Condi tion A or AND B not met . C.2 Be i n MODE 5. 36 hou rs BRAIDWOOD - UNITS 1 &2 3.7.7 - 1 Amendment 8
SX System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Essentia l Service Water (SX) System LCO 3.7.8 The fo llowing SX trains shall be OPERABLE:
- a. Two unit-speci fic SX trains; and
- b. One opposite-unit SX train for uni t-specific support.
APPLICAB ILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TI ME A. One unit-specific SX A. l ------ -- NOTES-- ------ train inoperabl e. 1. Enter appli cabl e Conditions and Required Actions of LCO 3 . 8 .1, AC 11 Sources-Operati ng , for 11 Emergency Diesel Generato r made inopera bl e by SX .
- 2. Enter appli cable Conditi ons and Required Actions of LCO 3 .4.6, 11 RCS Loops -
MODE 4 , " for Residua l Heat Removal loops made inoperabl e by sx. Restore uni t -specifi c SX trai n t o OPERABLE status . (continued) BRAIDWOOD - UNITS 1 &2 3.7.8 - 1 Amendment 193
SX System 3.7.8 ACTIONS (continued) COND ITION REQUIRED ACTION COMPLETION TIME B. Oppos ite-un it SX train B.l Restore oppos i te -unit 7 days inoperable. SX train to OPERABLE status. < --iRICT INSERTj C. Required Action and C.l Be in MODE 3. 6 hours associated Completion Time of Condition A or AND B not met. C.2 Be in MODE 5. 36 hours BRAIDWOOD - UNITS 1 &2 3.7.8 - 2 Amendment 1-93
AC Sources -Opera ting 3.8.l 3.8 ELECTRICAL POWER SYSTEMS 3.8.l AC Sources-Operating LCO 3.8.1 The following AC el ectrical sources shal l be OPERABLE:
- a. Two qualifi ed circuits per bus between the offsite transmi ss ion network and the onsite Cl ass l E AC El ectri ca l Power Distribution System ; and
- b. Two Diesel Generators CDGs) capabl e of supplying the ons ite Class lE AC Electri ca l Power Distribution System .
APPLI CAB ILITY : MODES 1, 2, 3, and 4. ACTIONS -- -- ---- -------- -------------- ----NOTE----- -- --- ----- ------------------ LCO 3.0.4 . b i s not appl ica bl e to DGs. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more buses with A.l Perfo rm SR 3.8.1.l 1 hour one requi red quali fi ed fo r t he requi red ci rcui t inoperabl e. OPERABLE qua l i f i ed circui t s . Once per 8 hours thereaft er AND A.2 Restore requi red qualifi ed circuit (s ) to OPERAB LE st atus . (continued ) BRAIDWOOD - UNITS 1 &2 3.8.1 - 1 Amendment .WJ
AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (cont inued) B.5 Restore DG to 14 days OPERABLE status . ~ IRICTI NSERT I
- c. Required Act i on and C. l Restore DG to 72 hours associ ated Compl etion OPERABLE stat us .
Time of Required Action B.1 not met. D. One or more buses wi th D.1 Restore one required 24 hours two required qualified qua l ified circuit per circuits inoperable. bus to OPERABLE -E-----* [~I~! INSERTj status. E. One DG inoperable and ------ ------ NOTE ---------- --- one or more buses with Enter appl icable Conditions one required qua li fied and Required Actions of ci rcuit inoperable. LCD 3.8.9 , "Di stribution Systems-Operating," when OR Condition E is entered with no AC power source to a One DG inoperable and division. one bus with two - - - -------------------------- required qua li fied circuits inoperable. E.1 Restore required 12 hours qua l ified circuit(s) ~* *- {RICT ~ to OPERABLE status. OR E.2 Restore DG to 12 hours OPERABLE status . ~-~I NSERT (cont i nued) BRAIDWOOD - UNITS 1 & 2 3.8. 1- 3 Amendment ZQJ
DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCD 3.8.4 Division 11(21 ) and Division 12(22 ) DC electrical power subsystems shall be OPERABLE and not crossti ed to the opposite unit. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One battery charger A. l Crosstie 2 hours inoperabl e. opposite-unit bus with associated OPERABLE battery charger to t he affected di vision. A. 2 Restore battery 2 ho urs termi nal vol ta ge to greater than or equa l to t he minimum establi shed fl oat voltage . AND A. 3 Veri fy battery fl oat Once per 12 c urre nt ~ 3 amps . hours AND A.4 Restore battery 7 days charger t o OPERAB LE st at us . ~* - ---{!3_~~I--~~_§~~~~_!J (continued) BRAIDWOOD - UNITS 1 &2 3.8.4 - 1 Amendment l -24
DC Sources -Opera ti ng 3.8. 4 ACTI ONS (cont i nued) COND ITION REQUIRED ACTION COMPLETION TIME B. One DC el ect ri ca l B.l Open at l east one 204 hours power divis i on crossti e breaker crosstied to between t he crosstied ~I NSERT I opposite -unit DC divisions. elect rical powe r subsystem t hat has an inoperable battery charger, while opposite uni t is i n MODE 1, 2, 3, or 4.
- c. One DC el ectrical C. l ------- -- NOTE --------
power division Only required when crosstied to opposite unit has an opposite -unit DC inoperable battery. el ectri ca l power - --- --- - - - - -- -- - - - --- subsystem wi t h an i noperabl e source , Verify opposite -uni t Once per whi l e opposite un i t is DC bus l oad 12 hours in MODE 5, 6, or : : : 200 amps. defueled. AND C.2 Open at least one 7 days crosstie brea ker -<E-* jRICTI NSERIJ between the crosstied di vi sions. D. One DC electri cal D. l Restore DC el ectri cal 2 hours power subsystem i noperabl e for reasons power subsystem to OPERAB LE status.
-<E----- .. ---ffiiCT_L other t han Cond i tion A, B, or C.
E. Requi red Acti on and E.l Be in MODE 3. 6 hours Associated Compl eti on Time not met . AND E.2 Be i n MODE 5. 36 hours BRAIDWOOD- UNITS 1 &2 3.8.4 - 2 Amendmen t 193
Inverters-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8 .7 Inverters-Operating LCO 3.8.7 Four instrument bus inverters shall be OPERABLE. APPLICABILITY : MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One instrument bus A. l --------NOTE----- -- -- inverter inoperable. Enter appli cabl e Conditions and Required Actions of LCO 3.8.9, "Distribution Systems-Operating" with any i nstrument bus de-energized. Restore inverter to 7 days OPERABLE status. ~- -{!31C-f}NSERT] B. Required Action and B.l Be in MODE 3. 6 hours associated Completi on Time not met. AND B.2 Be in MODE 5. 36 hours BRAI DWOOD - UNITS 1 &2 3.8.7 - 1 Amendment +2-9
Di stribution Syst ems-Operat i ng 3.8.9 ACTIONS CONDI TI ON REQUIRED ACTION COMPLETION TIME A. One AC electrica l A.1 Restore AC el ectrical 8 hours power distribution power distributi on ~------{RfQT ~ subsystem i noperable . subsystem t o OPERABLE status . B. One AC instrument bus B.1 Restore AC instrument 2 hours electrica l power bus el ectrica l power ----*__ JFZl"c TI distri bution subsystem distribution I inoperabl e. subsystem t o OPERABLE status .
- c. One DC el ectrica l C. l Restore DC el ectrical 2 ho urs power distributi on power di st ri bution ~***-**~-! F<i (: T I 1~- -- ~~ --*- *- * ~~ **
subsystem inoperabl e. subsystem to OPERABLE L - *-*- - .*. status .
- 0. Required Action and 0.1 Be in MOOE 3. 6 ho urs associated Compl eti on Time of Condition A, ANO B, or C not met .
0.2 Be in MOOE 5. 36 hours (continued) BRAIDWOOD - UNITS 1 & 2 3.8.9 - 2 Amendment Q3
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5 .19 Su rveillance Frequency Control Program This program provides controls for Su rveillance Frequencies . The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
- a. The Surveillance Frequency Control Program shall conta in a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
- b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
- c. The Provisions of Surveillance Requirements 3.0.2 and 3.0 .3 are applicable to the Frequencies established in the Surveillance Frequency Control Program .
5.5.20 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following :
- a. The RICT may not exceed 30 days;
- b. A RICT may only be utilized in MODE 1 and 2;
- c. When a RICT is being used, any change to the plant configuration change, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.
- 1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration .
- 2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e ., not the RICT) or 12 hours after the plant configuration change, whichever is less.
- 3. Revising the RICT is not required If the plant configuration change would lower plant risk and would result in a longer RICT.
BMIDWOOD- UNITS 1 & 2 5.5-24 Amendrnent-165
Programs and Manuals 5.5 5.5 Programs and Manuals
- d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
- 1. Numerically accounting for the increased possibility of CCF in the RICT calculation; or
- 2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs .
- e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant, as spec ified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods approved for use with this program , or other methods approved by the NRC for generi c use; and any change in the PRA methods to assess risk that are outside these approval boundaries require prior NRC approval.
BRAIDWOOD - UNITS 1 & 2 5.5-25 Amendment .le§
B/B TS INSERTS RICT INSERT In accordance with the Risk Informed Completion Time Program INSERT TS 3.3.1 Condition L L. Required Action and L.1 Reduce THERMAL POWER 6 hours associated Completion to< P-7. Time of Condition K not met. INSERT TS 3.3.1 Condition N N. Required Action and N.1 Reduce THERMAL POWER 6 hours associated Completion to< P-8. Time of Condition M not met. INSERT TS 3.3.1 Condition S S. Required Action and S.l Be in MODE 2. 6 hours associated Completion Time of Condition R not met. INSERT TS 3.3.1 Condition U U. Required Action and U.l Be in MODE 3. 6 hours associated Completion Time of Condition B, D, E, 0, P, Q, or T not met .
8/8 TS INSERTS INSERT TS 3.3.1 Condition W W. Required Action and W .1 Reduce THERMAL POWER 6 hours associated Completion to< P-7. Time of Condition V not met. INSERT TS 3.3.2 Condition M M. Required Action and M .1 Be in MODE 3. 6 hours associated Completion Time of Conditions B, C, or AND Knot met. M.2 Be in MODE 5. 36 hours INSERT TS 3.3.2 Condition N N. Required Action and N.1 Be in MODE 3. 6 hours associated Completion Time of Conditions D, E, F, AND G, H, or L not met. N.2 Be in MODE 4. 12 hours INSERT TS 3.3.2 Condition 0
- 0. Required Action and 0.1 Be in MODE 3. 6 hours associated Completion Time of Condition I not met.
2
ATTACHMENT 3 Proposed Technical Specifications Changes for Byron Station, Units 1 and 2 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 Updated Mark-up of Technical Specifications Pages for Byron Station B/B TS Inserts
Compl eti on Times
- 1. 3 1.3 Compl eti on Times EXAMPLES (cont i nued)
If after Conditi on A i s entered, Req uired Acti on A.l is not met wi t hin ei t her t he i ni t i al 1 hour or any subseq uent 8 hour i nt erva l from the previo us pe rformance (pl us t he extens i on al l owed by SR 3.0.2) , Cond iti on B i s entered. The Compl et i on Ti me cl oc k for Cond i t i on A does not st op aft er Condi tion B i s ente red, but cont in ues from t he t ime Condition A was i niti all y ent ered. If Req ui red Action A. l i s met after Condi t i on B i s entered , Condi t i on B i s exi ted and ope ration may contin ue in accordance wi t h Condi t i on A, prov i ded t he Compl eti on Time for Req ui red Acti on A.2 has not expired . EXAMPLE 1.3-8 ACTIONS crn~DITION REQUIRED ACTION COMPLETION TIME A. One A. l Restore subs~stem 1 davs s ub s~stem to OPERABLE inoperabl e. status. OR In accordance with the Ri sk Informed Completion Time Program B. Reguired B.l Be in MODE 3. 6 hours Action and associated ANO Completion Time not B.2 Be in MODE 5. 36 hours met. BYRON - UNITS 1 &2 1. 3 - 13 Amendment +/-GB
Completion Times 1.3 1.3 Completion Times EXAMPLES (continued) When a subsystem is declared i noperable, Condition A is entered. The 7 day Compl et i on Time mav be applied as discussed in Example 1.3-2. However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered. The Risk Inforn1ed Completion Time Prog ra m requires recalculation of the RICT to reflect changing plant conditions. For planned changes. the revised RICT must be determined prior to implementation of the change in configurat ion. For emergent conditions , the revised RICT mus t be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours after the pl ant configuration change, whichever is less . If t he 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring t he inoperable subsystem to OPERABLE status, Condit ion B is also entered and t he Completion Time clocks for Required Actions B.1 and B.2 start. If t he RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.l and B.2 start. If the inoperable subsvstems are restored to OPERABLE status after Condition B is entered Conditions A is exited. and therefore . the Required Actions of Condition B may be terminated. IMMEDI ATE When "Immediatel y" is used as a Compl etion Time , the COMPLETION TIME Required Action should be pursued without delay and in a cont rolled manner. BYRON - UNITS 1 &2 1.3 - 14 Amendment +GB
RTS In st rumentation 3.3. l 3.3 INSTRUMENTATION 3.3 .1 Reactor Tri p System (RTS) Instrumentat i on LCO 3.3 .1 The RTS instrumentation for each Functi on in Tabl e 3.3.1 -1 shall be OPERAB LE. APP LICABILITY : According to Tabl e 3.3.1- 1. ACTIONS
------ ------ ------------ -----NOTE------- ----- ---------- ---- ------- ----
Separate Condi tion entry i s all owed for each Function. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Funct i ons A. l Enter t he Cond i t i on Immediately wit h one or more referenced in req ui red chan nel s or Tabl e 3.3.1-1 for t he trains inoperabl e. channel (s) or tra in (s) . B. One Manua l Reactor B.l Restore channel to 48 hours Trip channel OPERAB LE status . inoperabl e. ~-- -- ~IC_!_I GR B-; 8 e -- ~ -n MGtl~ --3-~~ -§4 *f'r8-U-P-S (continued) BYRON- UNITS 1 &2 3.3 .1 - 1 Amendment 0§
RTS Instrumentation 3.3.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TI ME D. One Power Range ------------NOTE------------- Neutron Flux-High One channel may be bypassed channel inoperable. for up to 12 hours for surveillance testing and setpoint adjustment. 0.1 Place channel in 72 hours trip.
- IRIC~~-SE~TJ
-78 hGUP-5 E. One channel ------- ------NOTE- -----------
inoperable. One channel may be bypassed for up to 12 hours for surveillance testing. E.l Place channel in 72 hours trip. E.2 -Be- in- -MG-DE . .f*8 *h-e ~ r-s (continued) BYRON - UNITS 1 &2 3.3.l - 3 Amendment -}86
RTS Instrumentation 3.3.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME J . One Source Range J.l Restore channel to 48 hours Neutron Flux channel OPERABLE status. inoperable. OR J.2.1 Initiate action to 48 hours fu l ly insert all rods. AND J.2.2 Place the Rod Control 49 hours System in a condition incapable of rod withdrawa l . K. One channel --- ---------NOTES---- -- ------ inoperabl e. 1. For Functions with installed bypass test capability (Functions Sa, 9, 10), one channel may be bypassed for up to 12 hours for surveillance testing.
- 2. For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
K.1 Pl ace channel in 72 hours trip .
~--- jRIST INS ERT I J
GR INSERT TS 3.3 -~2- HeEJuee-T-H-E-RMAl::- Pm-J EH 8-+i-e*tH--S- ~--- -t-e-~ ,Q __t-;- Condition L (continued) BYRON - UNITS 1 &2 3.3.1 - 5 Amendment 85
RTS Instrumentation 3.3 .l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME t . One Turbine Trip ------------NOTE------------- (7 channel inoperabl e. The inoperable channel may be bypassed for up to 12 hours ~ for surveillance testing of other channel s.
-l: . 1 Place channel in 72 hours f
(§ GR trip .
~-------~ICT_~SE~!J
-l . 2 -Re8-aee-WrfHMAl::---P8WER 8--fieur-s-to ~ -P-8-;
M. One train inoperable. ------------NOTE------------- One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE . M. l Restore train to 24 hours OPERABLE status .
~ no
~
-<E---- -- -~ICT _!_f'!SER~_]
M-.-2 Be- -in- MOO& 3-;- 30 -fieu rs (continued) BYRON - UNITS 1 &2 3.3 .l - 6 Amendment 7-6
RTS Instrumentation 3.3.l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME N. One RTB train ------------NOTE------------- inoperable. One train may be bypassed for up to 4 hours for surveillance testing, provided the other train is OPERABLE. N .1 Restore train to 24 hour OPERABLE status .
~ no
..'=!..D
~ --
0
-ffilCI IN SERT j
~L l'i* L r; Be -i r=: MGgE --3-;- h8 U-P-S nv . One or more channels - 0.1 Verify interlock is in 1 hour inoperabl e. required state for
~ existing unit conditions .
OR 0-.-2 Be- ~~--n M0-0E :- :; hours (continued) BYRON - UNITS 1 &2 3 .3 .1 - 7 Amendment 6
RTS Instrumentation 3.3 .l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME One or more channels .p_. 1 Verify interlock is 1 hour inoperable. in requi red state for existing unit conditions. INSERT TS 3.3 1 J
-P ~
Condition S
- e. One trip mechanism Restore inoperable 48 hours
£
-, e .1 inoperable for one trip mechanism to RTB. OPERABLE status . -<E- --~_ INSERT]
~- [TNs ERT fs-3~1]* n'-< . r')
~nd ition U Be --i r, - M8BE ; .S4 hGur-s
-R. One Reactor Coolant ------------NOTE-------------
Pump (RCP) Breaker The inoperable channel may be ~ Position channel(per train) inoperable. bypassed for up to 4 hours for surveillance testing of other channels. Place channel in 6 hours trip. INSERT TS3 3.1 -] -Re8CJee- :tHf HMAl: -P-mJE-R - hot+rs
~ Condition W t-e-- < .P-- 7-.-
BYRON - UNITS 1 &2 3 .3 .1 - 8 Amendment 7-6
RTS Instrumentation 3.3.l Table 3.3 . 1-1 (page 2 of 6) Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE
- 6. Overtemperature 6T 1, 2 4 E SR 3.3. 1.1 Refer 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. Overpower 6T 1,2 4 E SR 3.3.1.l Refer t o SR 3.3.1.7 Note 2 SR 3 .3.1.10 SR 3 .3 . 1.15
- 8. Pressurizer Pressure
- a. Low l" 4 K SR 3.3 . 1.1 2 1875 psig SR 3 .3. 1.7 SR 3 .3. 1.10 SR3 .3. l.15
- b. Hi gh 1, 2 4 SR 3 .3. 1.1 ,; 2393 psi g SR 3.3 . 1.7 SR 3 .3. 1.10 SR 3.3 . 1.15
- 9. Pressurizer Water 1c 3 K SR 3.3 . 1.1 ,; 93 . 5% of Level -High SR 3.3. 1.7 i nstrument SR 3 .3. 1.10 span 10 . Reactor Coolant j:e K SR 3.3. 1.l 2 89 .3% of Fl ow- Low (per loop) SR 3 .3. 1.7 l oop minimum SR 3.3 .1. 10 measured fl ow SR 3.3. 1.15 11 . Reactor Coolant Pump (RCPl Breaker Position 1' 4 0-7 R SR 3.3. 1. 13 NA (per train)
( continued) (el Above the P-7 ( Low Power Reactor Trips Block) interlock. BYRON - UNITS 1 &2 3.3.1 - 18 Amendment +7-8
RTS Instrumentation 3.3.l Table 3.3. 1-1 (page 3 of 6) Reacto r Tr ip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 12 . Undervol tage r 4 K SR 3.3. 1.9 2 4920 v RC Ps (per trai nl SR 3 .3. 1.10 SR 3 .3. 1.15 13 . Underfreouency l *-" 4 K SR 3 .3.1.9 2 56 .08 Hz RCPs (per train) SR 3 .3 . 1.10 SR 3.3 .1.15
- 14. Steam Generator CSG)
Water Level - Low Low (per SGl
- a. Unit 1 1,2 4 SR 3 .3.1.1 2 16 . 1% of SR 3 .3. 1.7 narrow range SR 3 .3. 1. 10 i nstrument SR 3.3. 1. 15 span
- b. Unit 2 1, 2 4 SR 3 .3. 1. 1 2 34 .8% of SR 3.3. 1.7 narrow range SR 3 .3. 1. 10 i nstrument SR 3.3. 1. 15 span 15 . Turbi ne Trip
- a. Emergency Tr ip Header Pressure l *' 3 ~7 l SR 3 .3.1. 10 SR 3 .3. 1.14 2 910 psig (per train)
- b. Turbine Th rottle Valve Closure 1' 4
~7 SR 3 .3. 1.10 SR 3.3.1.14 2 1% open (per train)
- 16. Sa f ety Injecti on (SI)
Input from Engineered 1,2 2 trains [Q}-7 M SR 3.3 .1.13 NA Safety Feature Actuation System CESFASl (continued) (el Above the P-7 (Low Power Reacto r Trips Block) interlock . (f) Above the P-8 (Power Range Neutron Fl ux ) interlock. BYRON - UNITS 1 &2 3. 3.1 - 19 Amendment +7-8
RTS Inst rumentation 3.3.l Table 3.3 . 1-1 Cpage 4 of 6J Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 17 . Reactor Trip System Interlocks
- a. Source Range Block Permissive, P-6 2.G 2 [9}-7 8 SR 3 .3 . 1.11 SR 3.3 . 1.12
- 6E-ll amp
- b. Low Power Reactor Trips Block, P-7 (1) P-10 Input 3 ~p SR 3.3. 1.11 SR 3.3.1 . 12 NA (2) P-13 Input 2 [§---?> r SR 3.3. 1. 10 SR 3.3. 1. 12 NA c . Power Range Neutron Flux, P-8 3 ~ r SR 3.3 . 1.11 SR 3 .3. 1.12 s 32 . 1% RTP
- d. Power Range Neutron Flux , P-10 1,2 3 l9}7 8 SR 3.3.1.11 SR 3.3 . 1.12 2 7. 9% RTP and 5 12 . 1% RTP e . Turbine Impulse Pressure , P-13 2 ~--7 r SR 3 .3.1.10 SR 3.3. 1.12
'.'. 12 . 1%
turbi ne power 18 . React or Trip Breakers ( RTBs J ' 1,2 2 trains ~ N SR 3.3. 1.4 NA 3° ' 4° ' 5; 2 trains c SR 3.3 .1.4 NA 19 . Reactor Trip Breaker Undervoltage and Shunt 1,2 1 each per RTB CT} 7 0 SR 3.3 . 1.4 NA Trip Mechanisms J o ' 4 , 5 ' 1 each per RTB c SR 3.3 . 1.4 NA 20 . Automatic Trip Logic 1, 2 2 trains [Q} 7 M SR 3.3 . 1.5 NA 3 ' ' 4 ,, ' 5 ; 2 trains c SR 3.3 . 1.5 ~IA (a) With Rod Control System capab le of rod withdrawa l or one or more rods not fully inserted. CdJ Below the P-6 (Source Range Block Permissive) interlock . (gJ Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB . BYRON - UNITS 1 &2 3.3 . l - 20 Amendment +t-3
ESFAS In strumentati on 3.3.2 3.3 INSTRUME NTATIO N 3.3.2 Engi nee red Safety Fea t ure Actuat i on System (ESFAS) In strumenta t ion LCO 3.3.2 The ESFAS instrument ati on for each Function i n Tabl e 3.3.2 -1 shall be OPERAB LE. APPLI CABI LITY : Accord i ng to Ta bl e 3.3.2-1. ACTIONS - ------- ----- ---------------- ---- ----NOTE ------ ------------ ------------ ----- -- Separate Cond i tion entry i s all owed for each Function. CONDITION REQUIRED ACTION COMPLETION TI ME A. One or more Functions A. l Enter t he Condi t i on Immedi ately with one or more referenced in required channel s or Tabl e 3.3.2-1 for t he t rains i noperabl e. channel(s) or trai n(s). B. One channel B. l Restore channel to 48 hours i noperabl e. OPERABLE status .
/
----@CT I GR '-
~-;-l- B~-i H-MOtJ f;-3-;- f-l8 u-r-s-Mm 8--;--2 . ~ Be-+n- M8HE-§-;- ~94 hettrs (cont in ued)
BYRON - UNI TS 1 &2 3.3 .2 - 1 Amendment 05
ESFAS Instrumentati on 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMP LETION TIME C. One train inoperable. C.l --------NOTE--------- One train may be bypassed fo r up to 4 hours for survei ll ance testing provided the other train is OPERABLE. Restore tra i n to 24 hours OPERABLE sta t us. C. 2*:-1 Be in- ,M,QDE 3 . C~ 2-;-3 Be* in- M9H£--5-; 6D-A&tJrs (continued) BYRON - UN ITS 1 &2 3.3.2 - 2 Amendment -116
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. One channel 0.1 --------NOTE------- -- inoperable. One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in 72 hours trip.
~-***-*----*---{~ICT INSERT j
{};-2;-} Be- i-A -M8DE -3; 8 .2. 2 Be in ~8DE 4. 84 hours (continued) BYRON - UNITS 1 &2 3.3.2 - 3 Amendment 18-6
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment E.1 --------NOTE--------- Pressure channel One additional inoperable. channel may be bypassed for up to 12 hours for surveillance testing. Place channel in 72 hours bypass.
- /& -he-u-rs F. One channel or train F.1 Restore channel or 48 hours inoperable. train to OPERABLE status.
54- hours (continued) BYRON - UNITS 1 &2 3.3.2 - 4 Amendment { 7-6
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME G. One train inoperable. G.l --------NOTE--------- One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE. Restore train to 24 hours OPERABLE status.
-{Rl~.:!_INSERT_]
3-8--~h e-u-r- s H. One channel H.l -- - -----NOTE--------- inoperable. One channel may be bypassed for up to 2 hours for surveil l ance testing provided the other channel is OPERABLE . Place channel in 1 hour trip. (continued) BYRON - UNITS 1 &2 3.3.2 - 5 Amendment i.-l§
ESFAS Instrumentation 3.3. 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME I. One cha nnel I.1 --------NOTE--------- inoperable. The inoperabl e channel may be bypassed for up to 12 hours for survei ll ance testing of other channels. Place channel in 72 hours trip.
--~~l_!_
8R I. 2 *B-c- in-*-MOD& 3 . h el:1rs J. One or more trains J.1 Declare associated Immediately inoperable. auxili ary feedwater pump inoperable. (continued) BYRON - UNITS 1 &2 3.3 .2 - 6 Amendment 7-6
ESFAS In strumenta t i on 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTI ON COMPLETION TI ME K. One channel K.1 --------NOTE --------- inoperable. One channel may be bypassed for up to 12 hours for surveillance testing . Place channel in 72 hours trip. 8---00l:J f-S K-;2 .2- Be i A -MODE 5. (continued) BYRON - UNITS 1 &2 3.3.2 - 7 Amendment 186-
ESFAS Instrumentation 3.3.2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME L. One or more chan nels L.1 Verify interlock is 1 hour inoperable. in required state for existing unit condition . GR h~} Be-i-ri--M8BE-~ 7 - h*8-8-P-S INSERT TS 3.3.2 *MJH Conditions
~ M, N, and 0
-!::-~ Be-~-A - M8BE--4-; 13--flS-lJ r--5 SURVEILLANCE REQUIREMENTS
------------ -------------NOT E-- ------ ----------------------- -----
Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function . SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. In accordance with the Survei ll ance Frequency Control Program SR 3.3.2.2 Perform COT . In accordance wi th the Survei ll ance Frequency Control Program (continued) BYRON - UNITS 1 &2 3.3.2 - 8 Amendment l.f-6
LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 Two channels per bus of the loss of voltage Function , two channel s per bus of the degraded voltage Function and two channels per bus of the low degraded voltage Function sha ll be OPERABLE. APP LICABILITY: MODES 1, 2, 3, and 4; When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown ." ACTIONS
-- -- ---------- -------- ---------NOTE ---------- -- ----- -- ------- -----------
Separate Condition entry is allowed for each Function. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A. l ------ --NOTE------ -- - with one channel on For l oss of vo ltage one or more buses Function, the inoperable . inoperable channel may be bypassed for up to 2 hours for survei ll ance testing of the other channel. Place channel in 1 hour trip. ~-- -------~RICTT B. One or more Functions B.l Restore one channel 1 hour with two channels on for the Function on -.;,;.. one or more buses the affected bu~~ inoperable. OPERABLE status. ~-- IRICT INSERT
-*---- I . --- (contrnued)
- * - - - - -NOTE- - - - - - - -
RICT entry is not permitted for the Loss of Function Condition when the same Function is inoperable on more than one bus. BYRON - UNITS 1 &2 3.3.5 - 1 Amendment l-9.§
Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) LCO 3.4. 11 Each PORV and associated block valve shall be OPERABLE. APPLICABI LITY: MODES 1, 2, and 3. ACTIONS
---- --------- ---------------- -- NOTE ------ ------------------- ------- --- -
Separate Condition entry is al l owed for each PORV and each block valve. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour inoperable and capable power to associated of being manually block valve . cycled. B. One PORV inoperabl e B.1 Close associated 1 hour and not capable of block valve. being manually cycled. AND B.2 Remove power from 1 hour associated block valve. AND B.3 Restore PORV to 72 hours OPERABLE status. ~-- - ----(RICT I NSERfl (continued) BYRON - UNITS 1 &2 3.4.11 - 1 Amendment 14-1
Pressurizer PORVs 3.4.11 ACT IONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C. l Place associated PORV 1 hour inoperable. in manual control. AND C.2 Restore block va l ve 72 hours to OPERABLE status. -E-----~RICI I D. Required Action and D. l Be in MODE 3. 6 hours associated Compl etion Time of Condition A, AND B, or C not met . D.2 Be in MODE 4. 12 hours E. Two PORVs inoperable E.l Be i n MODE 3. 6 hours and not capabl e of being manually cycled. AND E.2 Be in MODE 4. 12 hours F. Two block va l ves F.l Restore one block 2 hours inoperable. valve to OPERAB LE status . G. Required Acti on and G. l Be in MODE 3. 6 hours associ ated Completion Time of Condition F AND not met. G.2 Be in MODE 4. 12 hours BYRON - UNITS 1 &2 3.4.11 - 2 Amendment 1-86
ECCS-Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS-Operating LCD 3.5.2 Two ECCS trains shall be OPERABLE.
--- --- ------ ---- -- ----------NOTES- ---- --- -- ------- -- ------- -
- 1. In MODE 3, both Safety Injection (SI) pump flow paths and a portion of both Residual Heat Removal (RHR) pump flow paths may be isolated by closing the isolation valves for up to 2 hours to perform pressure isolation valve testing per SR 3.4.14.1 .
- 2. In MODE 3, a portion of both Residual Heat Removal (RHR) pump flow paths may be isolated by closing the isolation valves for up to 2 hours to perform pressure isolation valve testing per SR 3.4.14.1, provided an alternate means of cold leg injection is available for each isolated flow path.
APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One train inoperable. A. l Restore train to 7 days OPERABLE status. -- ---i£3J c!I B. Two trains inoperable. B.l Restore one train to 72 hours OPERABLE status. AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available. (continued) BYRON - UNITS 1 &2 3.5.2 - 1 Amendment 86
Contai nment Ai r Locks 3.6 .2 ACTIONS (continued) CONDITION REQUIRED ACTI ON COMPLETION TI ME C. One or mo re C.1 In iti ate act i on to Immed i ately conta inment air l oc ks eva l uate overa 11 inoperabl e for reasons contai nment l eakage other than Cond i t i on A rate per LCO 3.6.1. or B. AND C.2 Verify a door is 1 hour closed in the affected air lock. AND C.3 Restore ai r lock t o 24 hours OPERABLE status. ~-- ----@cf! D. Requi red Act i on and D.1 Be in MODE 3. 6 hours associated Compl et i on Ti me not met. AND D.2 Be in MODE 5. 36 hours BY RON - UN ITS 1 &2 3.6.2 - 4 Amendment 86
Containment Isol ati on Va l ves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Conta inment Isolat ion Va l ves LCO 3.6.3 Each contai nment i solati on valve sha ll be OPERABLE. APP LI CAB IL ITY: MODES 1, 2, 3, and 4. ACTIONS
------- ------ -- -- --- ----- -- -- NOTES ------ --------- --- ----- --------- --- -
- 1. Penet ration f l ow pa th (s) except for 48 inch purge va l ve f l ow paths may be un i solated intermi ttently under admi ni strati ve controls .
- 2. Separate Condition entry i s all owed for each penetrat i on f l ow path .
- 3. Enter appl icabl e Conditi ons and Requi red Actions for syst ems made ino perabl e by conta inment isol ation va l ves .
- 4. Enter appl icable Condi tions and Requi red Acti ons of LCO 3.6.1, "Conta i nment , " when iso l ation va l ve lea kage res ults in exceed i ng the overa l l conta inment lea kage rate accepta nce cr i ter i a.
CONDITI ON REQUI RED ACTION COMPLETION TI ME A. -- - ------NOTE --------- A. l Isolate the affect ed 4 hours Only appl i cabl e to penet rat i on f l ow path penetration f l ow paths by use of at l east -E-* .@-----] C!_.!__NSER!_ wi th two containment one cl osed and i so l ation va l ves . de -act i vated
------------ - - - - -- - - -- automati c or remote manua l va l ve, closed One or more man ual va l ve, blind penetrati on f l ow paths fla nge , or check wit h one contai nment va l ve wit h fl ow iso l at i on va l ve t hrough t he va l ve inoperable except for secured .
purge va l ve l ea kage not wit hin l i mi t . AND (continued) BYRON - UNITS 1 &2 3.6.3 - 1 Amendment -i-86
Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --------NOTES --------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is isolated. Once per 31 days for isolation devices outside containment l_ AND
~allowing 1solat1on J
Prior to
-~*--'
entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment (continued) BYRON - UNITS 1 &2 3.6.3 - 2 Amendment 86
Containment Iso l ati on Valves 3.6. 3 ACTIONS (cont inued) CONDITI ON REQUIRED ACTION COMPLETI ON TIME
- c. ---- -- -- -NOTE--------- c.1 Isol ate the affected 72 hours On ly appl icable to penet rat i on fl ow pat h -{RICT_I NSERT penetrati on f l ow paths by use of at l east
/
wit h on ly one one cl osed and conta i nment isol at i on de -acti vated va l ve and a cl osed automat i c or remote system. ma nual va l ve , cl osed
- -- -- - ------ -- --- - ---- ma nual va l ve , or blind flange .
One or more penetrat i on f l ow pa t hs AND wi t h one conta inment i sol ation va l ve C.2 -- -- ---- NOTES -------- i noperabl e. 1. Isolation devices in hig h radiation areas may be ver ifi ed by use of admi nistrative means.
- 2. Isolati on dev i ces t hat are l oc ked ,
sea l ed, or otherwi se secured may be verified by use of admi ni strat i ve means . Verify t he affected Once per 31 days penet rat ion fl ow path is isolated . D. One or more penetration flow paths D. l Res t ore purge va l ve lea kage to with i n 24 ho urs l_]. folio wing isola ti on wi th one or more li mi ts .
~-
cont ainment purge va l ves not wit hin purge valve l eakage limits. (conti nued) BYRON - UNI TS 1 &2 3.6 .3 - 4 Amendment -H}§
MS IVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Va l ves (MSIVs) LCO 3.7.2 Four MSIVs and their associated actuator trains sha ll be OPERABLE. APPLICABILITY: MODE 1, MODES 2 and 3 except when all MSIVs are cl osed. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV actuator A.1 Restore MSIV actuator 7 days train inoperable. train to OPERABLE status.
--*- RICT I N r_~T
--- J B. Two MSIVs each with one actuator train B.1 Restore one MSIV actuator train to 72 hours ___I --
-- -{R~~_!__I ~§~R~J inoperabl e such that OPERABLE status.
t he inoperable actuator trains are in different ESF Divisions.
- c. Two MSIVs each with C.1 Restore one MSIV 24 hours one actuator train actuator train to inoperable and both OPERAB LE status.
inoperable actuator trains are in the same ESF Division. D. Two MSIV actuator D. l Declare the affected Immediately trains inoperable on MS IV inoperable. t he same MSIV. (continued) BYRON - UNITS 1 &2 3.7.2 - 1 Amendment 8 MS I Vs 3.7.2 ACTIONS (cont i nued) COND ITION REQUIRED ACTI ON COMPLETI ON TI ME E. Three or more MS IV E.1 Declare each affected Immed i ately act uator trains MSIV i noperabl e. inoperable. OR Required Acti on and assoc i ated Completion Time of Conditi on A, B, or C not met. F. One MSIV inoperable in F.1 Restore MSIV to 8 hours MODE 1. OPERABLE status .
--E-- {~_!_C2I I_
G. Required Action and G.1 Be in MODE 2. 6 hours associated Compl et ion Time of Condi t i on F not met . H. ---- -- --- NOTE ----- ---- H.1 Cl ose MSIV. 8 hours Separate Cond i tion entry is allowed for AND each MSIV .
--- - --- -------------- - H.2 Veri fy MSIV is Once per 7 days closed .
One or more MS IV inoperabl e in MODE 2 or 3. I. Req ui red Action and I.1 Be in MODE 3. 6 hours associ ated Compl et i on Time of Cond i tion H AND not met . I. 2 Be in MODE 4. 12 hours BYRON - UN ITS 1 &2 3.7.2 - 2 Amendment +/--8~7-
SG PORVs 3.7 .4 3.7 PLANT SYSTEMS 3.7. 4 Steam Generator (SG) Power Operated Reli ef Valves (PORVs) LCO 3.7 .4 Four SG PORV l ines shal l be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTION COMP LETION TIME A. One SG PORV line ~-- { A.llRestore SG PORV 30 days inoperable. llhe to OPERABLE ""'::- {_PI CT I status. B. Two c-r- mo r-e SG PORV B.1 Restore a-l l
- but one 24 hours lines inoperable. SG PORV l ine to OPERAB LE status .
tt~-~ g_I_ .1 D ". 0J r'-' . Required Acti on and -C. 1 Be in MODE 3. 6 hours associated Completion / Time not met . AND [g] Tc .2 Be i n MODE 4. 12 hours C. Th ree or more SG C.1 Restore all but one SG 24 ho urs PORV lines PORV lines to OPERABLE L--~~:.e rable _______________ :~L~~----- BYRON- UNITS 1 &2 3.7.4 - 1 Amendment +4+/-
AF System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AF) System LCO 3.7.5 Two AF trains shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS -- ---- -- ------- ------ -------- --- --- --NOTE ----- ------ ---------- - -- -- ----------- LCO 3.0.4. b i s not appli cable when entering MODE 1. CONDITION REQUIRED ACTION COMPLETION TIME A. One AF tra in A.1 Restore AF train to 72 hours inoperabl e. OPERAB LE status . .-**. . {~1.f2_! B. Required Acti on and B.l Be in MODE 3. 6 hours associated Compl etion Time of Condi tion A AND not met . B. 2 Be in MODE 4. 12 hours
- c. Two AF trains C. l ---------NOTE --------
inopera bl e. LCO 3.0.3 and all other LCO Required Act i ons requi ring MODE changes are suspended unti l one AF tra i n i s restored to OPERABLE status . Ini tiate acti on t o Immedi ately restore one AF tra in to OPERABLE status . BYRON- UNITS 1 &2 3.7.5 1 Amendment 141-
CC System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CC) System LCO 3.7 .7 The CC System sha ll be OPERAB LE . APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS
------- -------- ----------------NOTE-------------------------------------
Enter appl icable Conditions and Requ i red Actions of LCO 3.4 .6, "RCS Loops-MODE 4," for Residual Heat Removal loops made inoperable by CC. CONDITION REQUIRED ACTION COMPLETION TIME A. One CC fl ow path A.1 Restore CC flow path 7 days inoperable. to OPERABLE status. i!3l~!I B. One required CC pump B.1 Restore required CC 7 days inoperabl e. pump to OPERABLE <E-- @c!__INSERT J status. C. Required Action and C. l Be in MODE 3. 6 hours assoc i ated Completion Ti me of Condition A or AND B not met. C.2 Be in MODE 5. 36 hours BYRON - UNITS 1 &2 3.7.7 - 1 Amendment -1:{}6
SX System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Essential Service Water (SX) System LCO 3.7.8 The following SX trains shall be OPERABLE:
- a. Two unit-specific SX trains; and
- b. One opposite-unit SX train for unit-specific support.
APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One unit-specific SX A.1 --------NOTES-------- train inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources-Operati ng, for 11 Emergency Diesel Generator made inoperable by SX.
- 2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4, for 11 Residual Heat Removal loops made inoperable by sx.
Restore unit-specific 72 hours SX train to OPERABLE ~-~--~T INSERT I status. (continued) BYRON - UNITS 1 &2 3.7.8 - 1 Amendment 98
SX System
- 3. 7.8 ACTIONS (continued)
CONDITION REQUIRED ACTI ON COMPLETION TIME B. Opposite-unit SX tra in B.1 Restore opposite-unit 7 days i noperable. SX train to OPERABLE .1
~--
~---*----*- --t~l ~:!:
status .
- c. Req uired Action and C.l Be in MOOE 3. 6 hours associated Compl etion Time of Conditi on A or ANO B not met.
C.2 Be in MOOE 5. 36 hours BYRON - UN ITS 1 &2 3.7.8 - 2 Amendment 198
AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.l AC Sources-Operating LCD 3.8.1 The following AC electrical sources shall be OPERABLE:
- a. Two qualified circuits per bus between the offsite transmission network and the onsite Class lE AC Electrical Power Distribution System; and
- b. Two Diesel Generators (DGs) capable of supplying the onsite Class lE AC Electrical Power Distribution System.
APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS
-------------- -- ------- -NOTE- --- ----------------- ---- -------- ----
LCD 3.0.4.b is not applicable to DGs. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more buses with A.l Perform SR 3.8.1.1 1 hour one required qualified for the required circuit inoperable. OPERABLE qualified circuits. Once per 8 hours thereafter AND A.2 Restore required 72 hours qualified circuit(s) <---~RICT INSERT] to OPERABLE status. -------,-- (continued) BYRON - UNITS 1 &2 3.8.1 - 1 Amendment -209
AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) 8.5 Restore DG to 14 days OPERABLE status. <(-~---i RICT I NSERT I
- c. Required Action and C. l Restore DG to 72 hours associated Completion OPERABLE status .
Time of Required Action B.l not met. D. One or more buses with D.l Restore one required 24 hours two required qualified qualified circuit per <(- -~CTI circuits inoperable. bus to OPERABLE status. E. One DG inoperable and ------- -----NOTE----------- -- one or more buses with Enter applicable Conditions one required qualified and Required Actions of circuit inoperable. LCO 3.8.9, "Distribution Systems-Operating," when OR Condition E is entered with no AC power source to a One DG inoperable and division. one bus with two ----------- - ----------------- required qualified circuits inoperable. E.l Restore required 12 hours qualified circuit(s) -i£3:~CT I to OPERABLE status. OR E.2 Restore DG to 12 hours OPERAB LE status. **- ~RICT I NSERTj (continued) BYRON - UNITS 1 &2 3.8.l - 3 Amendment ig.g
DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources -Operating LCO 3.8.4 Division 11(21) and Division 12(22) DC electrical power subsystems shall be OPERABLE and not crosstied to the opposite unit. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One battery charger A. l Crosstie 2 hours inoperable. opposite-unit bus with associated OPERABLE battery charger to the affected division. A. 2 Restore battery 2 hours terminal voltage to greater than or equal to the minimum established float voltage . AND A.3 Verify battery float Once per 12 current~ 3 amps . hours AND A.4 Restore battery 7 days charger to OPERABLE ~----~RICT IN_SERT~ status . (continued) BYRON - UNITS 1 &2 3.8.4 - 1 Amendment +2-9
DC Sources-Operating 3.8.4 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. One DC electrical B.1 Open at l east one 204 hours power division crosstie breaker /
~RICT INSER}]
crosstied to between the crosst i ed " opposite-unit DC divisions. electrica l power subsystem that has an inoperable battery charger, wh i le opposite unit is in MODE 1, 2, 3, or 4.
- c. One DC electrica l C.l ---------NOTE--------
power division Only required when crosstied to opposite unit has an opposite -un it DC inoperabl e battery. el ectrica l power - - ------------ ------- subsystem with an inoperabl e source, Verify opposite -unit Once per wh il e opposite unit is DC bus load 12 hours in MODE 5, 6, or : : : 200 amps . defueled. AND C.2 Open at least one crosstie breaker 7 days between the crosstied ~-- *- {R!CI I-divisions. D. One DC el ectrica l D.1 Restore DC el ectrical 2 hours power subsystem power subsystem to inoperable for reasons OPERABLE status . -@CT_!NSERT J other t han Condition A, B, or C. E. Required Action and E.l Be in MODE 3. 6 hours Associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours BYRON - UNITS 1 &2 3.8.4 - 2 Amendment -198
Inverters-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8. 7 Inverters-Operating LCO 3.8.7 Four in strument bus inverters shall be OPERABLE. APPL ICABILI TY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One in strument bus A. l --------NOTE--------- inverter inoperable. Enter appl i cable Conditions and Required Acti ons of LCO 3.8. 9, "Di stri buti on Systems -Operating" with any instrument bus de-energized. Restore in verter to 7 days OPERABLE status . ~* -IT31cTT B. Required Action and B. l Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours BYRON - UNITS 1 &2 3.8.7 - 1 Amendment -E?.§
Distribution Systems -Operat ing 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC el ectri ca l A. l Restore AC el ect ri cal 8 hours power distribution power distribution /
-jRICT INSERT subsystem inoperabl e. subsystem to OPERABLE "-
I status . B. One AC instrument bus B.l Restore AC in strument 2 hours electrica l power bus el ectrica l power ~---~_!_ distribution subsystem distribution inoperable. subsystem to OPERABLE status.
- c. One DC el ectrical C. l Restore DC electrical 2 hours power distribution power distribution -<E--- -<---~RICT I subsystem inoperable. subsystem to OPERABLE status .
D. Required Action and D.l Be i n MODE 3. 6 hours associated Compl etion Time of Conditi on A, AND B, or C not met. D.2 Be in MODE 5. 36 hours (continued) BYRON - UNITS 1 &2 3.8 .9 - 2 Amendment 2-Gfl
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.19 Surveillance Frequency Contro l Program This program provides controls for Surveillance Frequencies . The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operat ion are met.
- a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program .
- b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
- c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program:
5.5.20 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (R ICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following:
- a. The RICT may not exceed 30 days;
- b. A RICT may only be utilized in MODE_1 and 2;
- c. When a RICT is being used, any change to the plant configuration change ,
as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.
- 1. For planned changes, the revised RIC1 must be determined prior to implementation of the change in configuration .
- 2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i .e., not the RICT) or 12 hou rs after the plant configuration change, whichever is less.
- 3. Revising the RICT is not required If the plant configuration change would lower plant risk and would result in a longer RICT.
BYRON - UNITS 1 & 2 5.5 - 24 Amendment+/-++/-
Programs and Man uals 5.5 5.5 Programs and Manua ls
- d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
- 1. Numerically accounting for the increased possibility of CCF in the RICT calcu lation; or
- 2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.
- e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant ; and reflect the operating experience at the plant, as specified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods approved for use with this program, or other methods approved by the NRC for generic use; and any change in the PRA methods to assess risk that are outside these approval boundaries require prior NRC approval.
BYRON - UNITS 1 & 2 5.5 - 25 Amendment+/-++/-
B/B TS INSERTS RICT INSERT In accordance with the Risk Informed Completion Time Program INSERT TS 3.3.1 Condition L L. Requi red Action and L.1 Reduce THERMAL POWER 6 hours assoc iated Completion to< P-7 . Time of Condition Knot met. INSERT TS 3.3.1 Condition N N. Required Action and N.l Reduce THERMAL POWER 6 hours associated Completion to< P-8. Time of Condition M not met. INSERT TS 3.3.1 Condition S S. Required Action and S.1 Be in MODE 2. 6 hours associated Completion Time of Condition R not met. INSERT TS 3.3.1 Condition U U. Required Action and U.1 Be in MODE 3. 6 hours associated Completion Time of Condition B, D, E, 0, P, Q, or T not met.
B/B TS INSERTS INSERT TS 3.3.1 Condition W W. Required Action and W.1 Reduce THERMAL POWER 6 hours associated Completion to< P-7. Time of Condition V not met. INSERT TS 3.3.2 Condition M M. Required Action and M.1 Be in MODE 3. 6 hours associated Completion Time of Conditions B, C, or AND Knot met. M .2 Be in MODE 5. 36 hours INSERT TS 3.3.2 Condition N N. Required Action and N.1 Be in MODE 3. 6 hours associated Completion Time of Conditions D, E, F, AND G, H, or L not met. N.2 Be in MODE 4. 12 hours INSERT TS 3.3.2 Condition 0
- 0. Required Action and 0. 1 Be in MODE 3. 6 hours associated Completion Time of Condition I not met.
2
ATTACHMENT 4 Enclosure 1, Revision 1, to LAR to Adopt Risk Informed Completion Times TSTF-505, Revision 2 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 List of Revised Required Actions to Corresponding PRA Functions
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions
- 1. Introduction Section 4.0, Item 2 of the NRC Final Safety Evaluation (Reference 1 of this Enclosure) for NEI 06-09-A, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines, (Reference 2) identifies the following needed content:
- The license amendment request (LAR) will provide identification of the TS Limiting Conditions for Operation (LCOs) and action requirements to which the RMTS will apply.
- The LAR will provide a comparison of the TS functions to the PRA modeled functions of the structures , systems , and components (SSCs) subject to those LCO actions .
- The comparison should justify that the scope of the PRA model , including applicable success criteria such as number of SSCs required , flow rate , etc., are consistent with licensing basis assumptions (i.e. , 50.46 ECCS flowrates) for each of the TS requirements, or an appropriate disposition or programmatic restriction will be provided.
This enclosure provides confirmation that the Byron and Braidwood Stations (BYR/BWD) PRA models include the necessary scope of SSCs and their functions to address each proposed application of the Risk-Informed Completion Time (RICT) Program to the proposed scope TS LCO Conditions, and provides the information requested for Section 4 .0, Item 2 of the NRC Final Safety Evaluation . The scope of the comparison includes each of the TS LCO conditions and associated required actions within the scope of the RICT Program. The BYR/BWD PRA model has the capability to model directly or through use of a bounding surrogate the risk impact of entering each of the TS LCOs in the scope of the RICT Program . Table E1-1 below lists each TS LCO Condition to which the RICT Program is proposed to be applied and documents the following information regarding the TSs with the associated safety analyses , the analogous PRA functions and the results of the comparison : Column "Tech Spec Description": Lists all of the LCOs and condition statements within the scope of the RICT Program . Column "SSCs Covered by TS LCO Condition": The SSCs addressed by each action requ irement. Column "Modeled in PRA ?": Indicates whether the SSCs addressed by the TS LCO Condition are included in the PRA. Column "Function Covered by TS LCO Condition": A summary of the required functions from the design basis analyses . Column "Design Success Criteria" : A summary of the success criteria from the design basis analyses . Column "PRA Success Criteria" : The function success criteria modeled in the PRA. Column "Comments": Provides the justification or resolution to address any inconsistencies between the TS and PRA functions regarding the scope of SSCs and the success criteria. Where the PRA scope of SSCs is not consistent with the TS, additional information is provided to describe how the LCO condition can be evaluated using appropriate surrogate events . Differences in the success criteria for TS functions are addressed to demonstrate the PRA criteria provide a realistic estimate of the risk of the TS condition as required by NEI 06-09-A, Revision 0-A. E1-1
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions The corresponding SSCs for each TS LCO and the associated TS functions are identified and compared to the PRA. This description also includes the design success criteria and the applicable PRA success criteria . Any differences between the scope or success criteria are described in the table . Scope differences are justified by identifying appropriate surrogate events which permit a risk evaluation to be completed using the CRMP tool for the RICT program . Differences in success criteria typically arise due to the requirement in the PRA standard to make PRAs realistic rather than bounding , whereas design basis criteria are necessarily conservative and bounding . The use of realistic success criteria is necessary to conform to capability Category II of the PRA standard as required by NEI 06-09-A, Revision 0-A. Examples of calculated RICT are provided in Table E1-2 for each individual condition to which the RICT applies (assuming no other SSCs modeled in the PRA are unavailable). These example calculations demonstrate the scope of the SSCs covered by TSs modeled in the PRA. RICTs were calculated for both BYR and BWD; however, due to the close similarity between Unit 1 and Unit 2 at each site , only the Unit 1 RICT result is shown in Table E1-2. Also note that the more limiting of the CDF and LERF RICT result is shown . Following 4b implementation , the actual RICT va lues will be calculated on a plant- and unit-specific basis, using the actual plant configuration and the current revision of the PRA model representing the as-built, as-operated condition of the plant, as required by NEI 06-09-A, Revision 0-A, and the NRC safety evaluation , and may differ from the RICTs presented. E1-2
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3.1.B 3.3.1.B One Manual Two manual Reactor Yes Reactor Trip One of two reactor trip Same (Note4) Reactor Trip Trip Channels Initiation channels channel inoperable. 3.3.1.D 3.3.1.D One Power Four Power Range Yes Reactor Trip Two of four channels Same (Notes 1 and 2) Range Neutron Neutron Flux-High Initiation Flux-High sensors channel inoperable. 3.3.1.E 3.3.1 .E One channel Power Range Yes Reactor Trip Power Range Neutron Same The functions inoperable. Neutron Flux-Low, Initiation Flow-Low: two of four Power Range Power Range channels Neutron Flux-High Neutron Flux-High Positive Rate, Power Range Neutron Positive Rate, Power-Range Flux-H igh Positive Rate: Overtemperature 6- T, Neutron Flux-Low, two of four channels Overpower 6- T, and Pressurizer Pressurizer Overtemperature 6- T: Pressure-High are Pressure-High , SG two of four channels not explicitly Water Level (Low- modeled in PRA, Low) Overpower 6- T: two of but loss of the four channels associated channel (Reference 4, will be used as a Response to DORL Pressurizer Pressure-High : two of four conservative RAl-1) channe ls surrogate in the RICT ca lculation. SG Water Level (Low- (Notes 1 and 2) Low) : two of four channels on any one SG E1-3
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3 .1.K 3.3.1.K One channel RCPs (Undervoltage , Yes Reactor Trip RCP Undervoltage (per Same (Notes 1 and 2) inoperable. Underfrequency) (per Initiation train): two of four train) , Pressurizer channels (Pressure Low, RCP Underfrequency Water Level-H igh) , (per train) : two of four Reactor Coolant Flow-Low (per loop) channels Pressurizer Pressure Low: two of four channe ls Pressurizer Water Level-High: two of three channels Reactor Coolant Flow-Low: two of three channels in any loop 3.3.1.M 3.3.1.M One Turbine Emergency Trip Yes Reactor Trip Two of Three Electro- Same (Notes 1 and 2) Trip channel Header Pressure Trip Initiation Hydraulic (EH) Fluid inoperable. (three sensors) , Pressure switches OR Turbine Throttle Four of Four Turbine Valve Closure (four Throttle Valve limit sensors) switches (Reference 4, Response to EICB RAl-5) 3.3.1.0 3.3.1.0 One train SI Input from ESFAS, Yes Reactor Trip One of two trains Same (Note 3) inoperable. Automatic Trip logic Initiation E1-4
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3.1.P 3.3.1.P One RTB train Reactor Trip Yes Reactor Trip One of two RTBs open Same (Note 5) inoperable. Breakers Initiation 3.3.1.T 3.3.1.T One trip RTB Undervoltage Yes Reacto r Trip One trip mechan ism Same (Notes 3 and 4) mechanism and Shunt Trip Initiation inoperable for Mechanisms one RTB . 3.3.2.B 3.3.2 .B One channel Manual Initiation Yes ESF Actuation SI/Cl Phase A: Actuation Same The functions inoperable. (SI , CS , Cl (Phase A of one switch at one of Conta inment Spray and B Isolation)) two panels and Containment Isolation - Phase B CS/Cl Phase B: Isolation - Actuation of two of two Automatic switches at one of two Actuation Logic panels and Actuation (Reference 4, Response Relays are not to EICB RAl-4) explicitly modeled in PRA, but loss of the associated channe l wi ll be used as a conservative surrogate in the RICT calculation . (Notes 1 and 2) E1-5
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3.2 .C 3.3.2 .C One train Automatic Actuation Yes ESF Actuation One of two trains Same The functions inoperable. Logic and Actuation Containment Spray Relays (SI , CS , Cl and Containment (Phase A and B Isolation - Phase B Isolation , Switchover Isolation - to Containment Automatic Sump) Actuation Logic and Actuation Relays are not explicitly modeled in PRA, but loss of the associated channel will be used as a conservative surrogate in the RICT calculation . (Notes 1 and 2) E1-6
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3.2.D 3.3.2.D One channel SI (Containment Yes ESF Actuation , SI (Containment Same The functions inoperable. Pressure-High 1, P-14: Trips Main Pressure-High 1): two of Steam Line Pressurizer Feed Pumps, three Isolation - Pressure-Low, Trips Main Containment SI (PZR Pressure Low) : Steam Line Pressure Turbine, Closes Pressure High-2 , two of four Low) , Feedwater Steam Line Isolation and SI (steam line pressure Isolation - Steam Steam Line Isolation Discharge Valves low) : two of th ree in one Line Pressure - (Containment steam line Negative Rate-High Pressure-High 2) , are not explicitly Steam Line Pressure Steam Line Isolation modeled in PRA, (Low, Negative Rate- (Containment Pressure-but loss of the High) , High 2) : two of three associated channel Turbine Trip and Steam Line Pressure will be used as a Feedwater Isolation (Low, Negative Rate- conservative (SG Water Level- High): two of th ree in one surrogate in the High High- P-14 ), steam line RICT calculation . Auxiliary Feedwater Turbine Trip and (Notes 1 and 2) (SG Water Level-Low Feedwater Isolation (SG Low) Water Level-High High-P-14): two of four channels on any SG Auxiliary Feedwater (SG Water Level-Low Low) : two of four channels on any SG E1-7
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3.2.G 3.3.2.G One train Automatic Actuation Yes ESF Actuation One of two trains Same inoperable. Logic and Actuation Relays (Steam Line Isolation , Turbine Trip and Feedwater Isolation, Auxiliary Feedwater) 3.3.2.I 3.3.2.I One channel Undervoltage Not ESF Actuation Two of four Same This function is not inoperable. Reactor Coolant explicitly explicitly modeled , Pump (per train) but loss of the associated channel will be used as a conservative surrogate in the RICT calculation. (Notes 1 and 2) 3.3.2.K 3.3.2 .K One channel Switchover to Yes ESF Actuation Two of four Same (Notes 1 and 2) inoperable. Containment Sump (coincident with an SI signal) - Refueling Water Storage Tank (RWST) Level-Low Low E1-8
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.3.5.A 3.3.5 .A One or more There are three types Not Diesel Generator - Two of two channels per Same These channels Functions with of loss of power DG explicitly Loss of Voltage function per bus. are not explicitly one channel on start instrumentation Start as well as modeled , but DG (Reference 4, Response one or more functions , and each 4kV Bus load fail-to-start will be buses function has two to EEOB RAl-2 , Part 2) shedd ing and used as a inoperable. channels : initiating and conservative sequencing surrogate in the
-Loss of Voltage RICT calculation.
-Degraded Voltage
-Low Degraded Voltage 3.3.5.B 3.3.5.B One or more See LCO Condition 3.3 .5.A Functions with two channels on one or more buses inoperable.
3.4.11. 3.4.11. One PORV Two PORVS Yes RCS One PORV One B B inoperable and depressurization , PORV not capable of (Reference 3, Response once through core with One being manually to APLA RAI 11 , Part b) cooling (feed and CV pump cycled . bleed) OR Two PO RVs with One SI pump E1-9
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.4.11. 3.4.11. One block Two PORV block Yes Isolate associated Two PORV Block valves Same c c valve valves PORV closable. inoperable. 3.5.2.A 3.5.2.A One train Two ECCS tra ins Yes Emergency make 3 ECCS subsystems Same inoperable. (ECCS train consists up to the RCS via between two trains such of one Centrifugal injection from the that at least 100% ECCS Charging , one Safety RWST to the cold flow equivalent to a Injection , and one legs, and single operable ECCS Residual Heat recirculation from train is available. Removal the containment subsystem .) sump 3.6.2.C 3.6.2.C One or more Containment Airlocks Not Containment Airlock leakage within Same The containment containment air explicitly integ rity allowable conta inment airlocks are not locks leakage. modeled but their inoperable for unavailability will reasons other be conservatively than Condition analyzed as an Aor B. early containment failure in the RICT calculation. E1-10
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.6.3 .A 3.6.3.A One or more Two active or Yes Containment One of two isolation Same Selected Cl valves penetration passive isolation boundary and devices per penetration . are modeled and flow paths with devices on each fluid minimization of can be used to one penetration line RCS inventory bound the impact containment loss of the failure. isolation valve inoperable except for purge valve leakage not within limit. 3.6.3.C 3.6.3.C One or more One active or Yes Containment Integrity of closed system Same Selected Cl valves penetration passive device on boundary and or containment isolation are modeled and flow paths with each fluid penetration minimization of valve. can be used to one RCS inventory bound the impact containment loss of the failure. isolation valve inoperable. 3.7.2.A 3.7.2.A One MSIV Main Steam Isolation Yes Isolate Main One MSIV closure per Same actuator train Valves (MS IVs) Steam Lines steam generator (one of inoperable. two actuator trains) E1-11
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.7.2.B 3.7.2.B Two MSIVs See LCO Condition 3.7.2.A each with one actuator train inoperable such that the inoperable actuator trains are in different ESF Divisions. 3.7.2.F 3.7.2.F One MSIV Main Steam Isolation Yes Isolate Main Closure of 3 of 4 MS IVs. Same inoperable in Valves (MSIVs) Steam Lines MODE 1. 3.7.4 .A 3.7.4.A One SG PORV Steam Generator Yes Pressure relief Two of four SG PO RVs SGTR: two line inoperable . (SG) Power and plant of four SG Operated Relief coo Id own PO RVs Valves (PORV) open All transients and LOCA with scram and power available: one of four SG PO RVs 3.7.4 .B 3.7.4 .B Two SG PORV See LCO Condition 3.7.4.A lines inoperable. E1-12
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.7.5.A 3.7.5.A One AF train AF valves , flowpath Yes Supply feedwater One of two AF tra ins One AF inoperable. and pumps to steam pump generators to supplying remove RCS 3 SGs OR decay heat One AF pump supplying 2 SGs with manually throttled flow OR One AF pump injecting to 4 SGs (ATWS) 3.7.7.A 3.7 .7.A One CC flow Two CC trains Yes Heat sink for One of two cooling trains Same path comprised of one removing process inoperable. pump and head tank and operating with associated heat from safety valves, heat related exchanger, components instrumentation and during a Design controls. Basis Accident or transient 3.7.7.B 3.7.7.B One required See LCO Condition 3.7 .7.A CC pump inoperable. E1-13
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.7.8.A 3.7.8.A One unit- Two SX trains Yes Provides a heat One of two SX trains per One of two specific SX comprised of SX sink for the unit SX pumps train pumps , valves, removal of on inoperable. strainers and heat process and accident exchangers operating heat unit, 1 SX from safety related pump on components opposite during a Design unit with Basis Accident or crossties transient open. 3.7.8.B 3.7.8.B Opposite-unit One SX train on the Yes Provides a heat One SX train on the One of two SX train opposite unit sink for the opposite unit SX pumps inoperable. comprised of SX removal of on pumps , valves, process and accident strainers, heat operating head unit OR exchangers, and a from safety related one SX cross-tie flowpath components pump on during a Design opposite Basis Accident or unit with transient crossties open . 3.8.1.A Same 3.8.1.A One or more Two qualified circuits Yes Provide power One qualified circuit buses with one between the offsite from offsite between the offsite required transmission network transmiss ion transm ission network qualified circuit and the on site 1E AC network to onsite and the onsite 1E AC inoperable. Electrical Power Class one buses Electrical Power Distribution System . Distribution System . E1-14
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.8 .1.B 3.8.1.B One required Two EDGs capable Yes Provide power to 1 of 2 EDGs per unit Same DG inoperable. of supplying onsite safety related 1E AC Electrical buses when offsite Power Distribution power to them is System lost 3.8.1.D 3.8.1.D One or more See LCO Condition 3.8 .1.A buses with two required qualified circu its inoperable. 3.8 .1.E 3.8.1.E One DG See LCO Condition 3.8 .1.A and 3.8.1. B inoperable and one or more buses with one required qualified circuit inoperable. OR One DG inoperable and one bus with two requ ired qualified circuits inoperable. E1-15
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.8.4.A 3.8.4.A One battery DC Battery chargers Yes Ensure availability One of two DC divisions Same (Note 6) charger of required DC inoperable. power to shut down the reactor and maintain it in a safe condition after an Anticipated Operational Occurrence or a postulated OBA 3.8.4.B 3.8.4 .B One DC DC batteries and Yes Ensure availability One of two DC divisions Same (Note 6) electrical power battery chargers of required DC division power to shut crosstied to down the reactor opposite-unit and maintain it in DC electrical a safe condition power after an subsystem that Anticipated has an Operationa l inoperable Occurrence or a battery charger, postulated OBA while opposite unit is in MODE 1, 2, 3 or 4. E1-16
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.8.4 .C 3.8.4 .C One DC See LCO Condition 3.8.4.B electrical power division crosstied to opposite-unit DC electrical power subsystem with an inoperable source , while opposite unit is in MODE 5, 6, or defueled. 3.8.4 .D 3.8.4.D One DC DC batteries, battery Yes Ensure availability One of two DC divisions Same (Note 6) electrica l power chargers, cabling and of required DC subsystem controls power to shut inoperable for down the reactor reasons other and maintain it in than Condition a safe condition A, B, or C. after an Anticipated Operational Occurrence or a postulated OBA E1-17
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.8.7.A 3.8.7.A One instrument Four inverters per Yes Ensure availability Two of four inverters Same bus inverter unit of AC electrical inoperable. power for the systems instrumentation required to shut down the reactor and maintain it in a safe shutdown condition after an Anticipated Operational Occurrence or a postulated OBA 3.8.9.A 3.8.9.A One AC Two subsystems Yes Ensure availabil ity One of two AC Same electrical power of required AC distribution subsystems distribution power to shut subsystem down the reactor inoperable. and maintain it in a safe condition after an Anticipated Operational Occurrence or a postulated OBA E1 - 18
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1: In Scope TS/LCO Conditions to Corresponding PRA Functions BYR BWD SSCs Covered by Function Covered PRA Tech Spec Modeled Tech Tech by TS LCO Design Success Criteria Success Comments Description TS LCO Condition in PRA Spec Spec Condition Criteria 3.8.9.B 3.8.9.B One AC Two subsystems Yes Ensure availability One of two AC Same instrument bus of required AC distribution subsystems electrical power instrument bus distribution electrica l power to subsystem shut down the inoperable. reactor an d maintain it in a safe condition after an Anticipated Operational Occurrence or a postulated OBA 3.8.9 .C 3.8.9.C One DC Two subsystems Yes Ensure availability One of two DC Same (Note 6) electrical power of required DC distribution subsystems distribution power to shut subsystem down the reactor inoperable . and maintain it in a safe cond ition after an Anticipated Operational Occurrence or a postulated OBA E1-19
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-1 Notes : [1] The reactor protection system is segmented into four distinct but interconnected modules: field transmitters and process sensors, Signal Process Control and Protection System, Solid State Protection System (SSPS), and reactor trip switchgears. Field transmitters provide measurements of the unit parameters to the Signal Process Control and Protection System via separate, redundant channels. The Signal Process Control and Protection System forwards outputs to the SSPS, which consists of two redundant trains , to initiate a reactor trip or actuate Engineering Safety Functions. [2] Depending on the measured parameter, three or four instrumentation channels are provided to ensure protective action when required and to prevent inadvertent isolation resulting from instrumentation malfunctions . The output trip signal of each instrumentation channel initiates a trip logic. Failure of any one trip logic does not result in an inadvertent trip. Generally, if a parameter is used only for input to the protection circuits, three channels with a two-out-of-three logic are sufficient to provide the required reliability and redundancy . If a parameter is used for input to the SSPS and a control function, four channels with a two-out-of-four logic are sufficient. [3] Each instrumentation channel provides input to both trains of the SSPS , which initiates a reactor trip on one-out-of-two logic. Each train of SSPS provides input to the Reactor Trip Breakers (RTBs) by de-energizing the RTB undervoltage coils, which trips open the RTBs , tripping the reactor. One-out-of-two open RTBs will trip the reactor. [4] Each RTB is equipped with a shunt trip device that is energized to trip the RTB open upon receipt of a manual reactor trip signal, thus providing a redundant and diverse trip mechanism . Two Manual Reactor Trip channels provide the signal from reactor trip switches located in the Main Control Room to the RTBs. [5] A trip breaker train consists of all trip breakers associated with a single Reactor Trip System logic train that are racked in , closed, and capable of supplying power to the Rod Control System . [6] PRA Success Criteria for bleed and feed cooling requires one CV pump and one PORV or one SI pump and two PORVs. Each PORV requires power from its respective DC division to perform its safety function for feed and bleed . E1-20
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-2: In Scope TS/LCO Conditions RICT Estimate Tech RICT Estimate 1 *2 *3 LCO Condition Spec BYR BWD 3.3.1.B One Manual Reactor Trip channel inoperable. 30 days 30 days 3.3.1 .D One Power Range Neutron Flux-High channel inoperable. 30 days 30 days 3.3.1.E One channel inoperable. 30 days 30 days 3.3.1 .K One channel inoperable . 30 days 30 days 3.3.1.M One Turbine Trip channel inoperable. 30 days 30 days 3.3.1.0 One train inoperable. 30 days 30 days 3.3.1.P One RTB train inoperable. 30 days 30 days 3.3.1 .T One trip mechanism inoperable for one RTB. 30 days 30 days 3.3.2.B One channel inoperable. 30 days 30 days 3.3.2 .C One train inoperable. 30 days 30 days 3.3.2 .D One channel inoperable. 30 days 30 days 3.3.2.G One train inoperable. 30 days 30 days 3.3.2.1 One channel inoperable . 30 days 30 days 3.3.2.K One channel inoperable . 30 days 30 days 3.3.5.A One or more Functions with one channel on one or more buses inoperable . 30 days 30 days 3.3.5.B One or more Functions with two channels on one or more buses inoperable. 30 days 30 days 3.4.11.B One PORV inoperable and not capable of being manually cycled . 30 days 30 days 3.4 .11.C One block valve inoperable. 30 days 30 days 3.5.2.A One train inoperable. 30 days 30 days One or more containment air locks inoperable for reasons other than Condition 3.6.2.C 177 hrs 175 hrs A or B. One or more penetration flow paths with one containment isolation valve 3.6.3.A 13 hrs 14 hrs inoperable except for purge valve leakage not with in limit One or more penetration flow paths with one containment isolation valve 3.6.3 .C 13 hrs 14 hrs inoperable. 3.7.2.A One MSIV actuator train inoperable . 30 days 30 days Two MS IVs each with one actuator train inoperable such that the inoperable 3.7.2.B 30 days 30 days actuator trains are in different ESF Divisions . 3.7.2.F One MSIV inoperable in MODE 1. 30 days 30 days 3.7.4.A One SG PORV line inoperable. 30 days 30 days 3.7.4.B Two SG PORV lines inoperable . 30 days 30 days 3.7.5.A One AF train inoperable. 139 hrs 196 hrs 3.7.7.A One CC flow path inoperable. 30 days 30 days 3.7.7.B One required CC pump inoperable. 30 days 30 days 3.7.8.A One unit-specific SX train inoperable. 30 days 30 days 3.7.8.B Opposite-unit SX train inoperable. 30 days 30 days 3.8.1.A One or more buses with one required qualified circuit inoperable. 30 days 30 days 3.8.1.B One required DG inoperable. 30 days 30 days 3.8.1 .D One or more buses with two required qualified circuits inoperable . 30 days 30 days One DG inoperable and one or more buses with one required qualified circuit 3.8.1.E inoperable OR One DG inoperable and one bus with two required qualified 581 hrs 616 hrs circuits inoperable. E1-21
Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions Table E1-2: In Scope TS/LCO Conditions RICT Estimate Tech RICT Estimate 1 *2 *3 LCO Condition Spec BYR BWD 3.8.4 .A One battery charger inoperable. 30 days 30 days One DC electrical power division crosstied to opposite-unit DC electrical power 3.8.4 .B subsystem that has an inoperable battery charger, while opposite unit is in 30 days 30 days MODE 1, 2, 3 or 4. One DC electrical power division crosstied to opposite-unit DC electrical power 3.8.4.C subsystem with an inoperable source , while opposite unit is in MODE 5, 6, or 30 days 30 days defueled. One DC electrical power subsystem inoperable for reasons other than 3.8.4.D 38 hrs 55 hrs Condition A, B, or C. 3.8.7.A One instrument bus inverter inoperable. 473 hrs 30 days 3.8.9.A One AC electrical power distribution subsystem inoperable. 26 hrs 23 hrs 3.8.9.B One AC instrument bus electrical power distribution subsystem inoperable. 109 hrs 131 hrs 3.8.9.C One DC electrical power distribution subsystem inoperable. 38 hrs 55 hrs Table E1-2 Notes :
- 1. RICTs were calculated for both units at BYR and BWD; however, due to the close similarity between the Unit 1 and Unit 2 at each site, only the Unit 1 RICT is shown .
Following 4b implementation , the actual RICT values will be calculated on a plant- and unit-specific basis, using the actual plant configuration and the current revision of the PRA model representing the as-built, as-operated condition of the plant, as required by NEI 06-09-A, Revision 0-A and the NRC safety evaluation , and may differ from the RICTs presented.
- 2. RICTs are based on the internal events, internal flood , and internal fire PRA model calculations with seismic and high winds CDF and LERF penalties. RICTs calculated to be greater than 30 days are capped at 30 days based on NEI 06-09-A, Revision 0-A.
RICTs not capped at 30 days are rounded to nearest number of hours.
- 3. Per NEI 06-09-A, Revision 0-A, for cases where the total CDF or LERF is greater than 1E-03/yr or 1E-04/yr, respectively , the RICT Program will not be entered .
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Enclosure 1, Revision 1 List of Revised Required Actions to Corresponding PRA Functions
- 2. References
- 1. Letter from Jennifer M. Golder (NRC) to Biff Bradley (NEI), "Final Safety Evaluation for Nuclear Energy Institute (NEI) Topical Report (TR) NEI 06-09-A, 'Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS)
Guidelines,"' dated May 17, 2007 (ADAMS Accession No. ML071200238)
- 2. Nuclear Energy Institute (NEI) Topical Report (TR) NEI 06-09-A, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS)
Guidelines," Revision 0-A, dated October 12, 2012 (ADAMS Accession No. ML12286A322)
- 3. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, 'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b'," dated September 5, 2019 (ADAMS Accession No. ML19248C699)
- 4. Letter from D. Murray (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information Regarding Application to Revise Braidwood Station and Byron Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, 'Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b'," dated October 7, 2019 (ADAMS Accession No. ML19280D178)
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