ML110210086
| ML110210086 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/20/2011 |
| From: | David Helker Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML110210086 (11) | |
Text
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1 10 CFR 50.90 January 20, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Supplement to the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
References:
1)
Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System dated March 24, 2010 2)
Letter from J. D. Hughey (U.S. Nuclear Regulatory Commission) to M. J.
Pacilio (Exelon Generation Company, LLC), Peach Bottom Atomic Power Station, Units 2 And 3: Nonacceptance Of License Amendment Request Related To Extending Completion Time For Technical Specification 3.1.7, Standby Liquid Control System dated July 12, 2010 3)
Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, Supplement to the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System dated July 23, 2010 By letter to the Nuclear Regulatory Commission (NRC) dated March 24, 2010, Exelon Generation Company, LLC, (Exelon) submitted a request to revise the Technical Specifications (TS) for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed change would revise TS Section 3.1.7, Standby Liquid Control (SLC) System, to extend the completion time for Condition C (i.e., two SLC subsystems inoperable for reasons other than Condition A) from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
By letter to Exelon dated July 12, 2010 (Reference 2), the NRC provided the results of the NRC staffs acceptance review of this amendment request. The NRC staff concluded that additional information was necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Exelon supplemented the License Amendment Request addressing the NRCs information request (Reference 3).
Exel n Nucle 10 CFR 50.90 January 20, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Supplement to the Request for Amendment to Technical Specification 3.1.7, "Standby Liquid Control (SLC) System"
References:
1)
Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Request for Amendment to Technical Specification 3.1.7, "Standby Liquid Control (SLC) System'"I dated March 24, 2010 2)
Letter from J. D. Hughey (U.S. Nuclear Regulatory Commission) to M. J.
Pacilio (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 And 3: Nonacceptance Of License Amendment Request Related To Extending Completion Time For Technical Specification 3.1.7, Standby Liquid Control System" dated July 12, 2010 3)
Letter from P. B. Cowan (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Supplement to the Request for Amendment to Technical Specification 3.1.7, "Standby Liquid Control (SLC) System"" dated July 23, 2010 By letter to the Nuclear Regulatory Commission (NRC) dated March 24, 2010, Exelon Generation Company, LLC, (Exelon) submitted a request to revise the Technical Specifications (TS) for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed change would revise TS Section 3.1.7, "Standby Liquid Control (SLC) System," to extend the completion time for Condition C (i.e., two SLC subsystems inoperable for reasons other than Condition A) from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
By letter to Exelon dated July 12, 2010 (Reference 2), the NRC provided the results of the NRC staff's acceptance review of this amendment request. The NRC staff concluded that additional information was necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Exelon supplemented the License Amendment Request addressing the NRC's information request (Reference 3).
U.S. Nuclear Regulatory Commission January 20, 2011 Page 2 This letter provides an additional supplement to the proposed License Amendment Request.
Specifically, this supplement revises the requested extension of the Completion Time duration from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to provide additional margin beyond what was justified by the Probabilistic Risk Assessment (PRA) analysis. This reduction in the Completion Time is bounded by the evaluation provided in the Reference 1 and Reference 3 letters. Additionally, information supporting defense-in-depth is included in the Reference 3 supplement. A revised set of TS and TS Bases pages reflecting this revision is provided as Attachments 1 and 2, respectively. These pages supersede pages previously submitted under this License Amendment Request.
There is no adverse impact to the No Significant Hazards Consideration Determination because this revision is bounded by the previously submitted evaluation.
There are no additional commitments contained within this letter.
If you have any questions or require additional information, please contact Mr. Doug Walker at (610) 765-5952.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 20th day of January 2011.
Respectfully, David P. Helker Manager
- Licensing and Regulatory Affairs Exelon Generation Company, LLC :
Proposed Markup of PBAPS Technical Specification Pages :
Proposed Markup of PBAPS Technical Specification Bases Pages cc:
USNRC Region I, Regional Administrator USNRC Project Manager, NRR
- Peach Bottom Atomic Power Station USNRC Senior Resident Inspector
- Peach Bottom Atomic Power Station S. T. Gray, State of Maryland R. R. Janati, Bureau of Radiation Protection, Commonwealth of Pennsylvania u.s. Nuclear Regulatory Commission January 20,2011 Page 2 This letter provides an additional supplement to the proposed License Amendment Request.
Specifically, this supplement revises the requested extension of the Completion Time duration from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to provide additional margin beyond what was justified by the Probabilistic Risk Assessment (PRA) analysis. This reduction in the Completion Time is bounded by the evaluation provided in the Reference 1 and Reference 3 letters. Additionally, information supporting defense-in-depth is included in the Reference 3 supplement. A revised set of TS and TS Bases pages reflecting this revision is provided as Attachments 1 and 2, respectively. These pages supersede pages previously submitted under this License Amendment Request.
There is no adverse impact to the No Significant Hazards Consideration Determination because this revision is bounded by the previously submitted evaluation.
There are no additional commitments contained within this letter.
If you have any questions or require additional information, please contact Mr. Doug Walker at (610) 765-5952.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 20th day of January 2011.
Respectfully, David P. Helker Manager - Licensing and Regulatory Affairs Exelon Generation Company, LLC : :
Proposed Markup of PBAPS Technical Specification Pages Proposed Markup of PBAPS Technical Specification Bases Pages cc:
USNRC Region I, Regional Administrator USNRC Project Manager, NRR - Peach Bottom Atomic Power Station USNRC Senior Resident Inspector - Peach Bottom Atomic Power Station S. T. Gray, State of Maryland R. R. Janati, Bureau of Radiation Protection, Commonwealth of Pennsylvania
ATTACHMENT 1 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 NRC Docket Nos. 50-277 and 50-278 Renewed Facility Operating License Nos.
DPR-44 and DPR-56 Supplement to Request for Amendment to Technical Specification 3.1.7 Standby Liquid Control (SLC) System Proposed Markup of PBAPS Technical Specification Pages Unit 2 Unit 3 3.1-21 3.1-21 ATTACHMENT 1 PEACH SOnOM ATOMIC POWER STATION UNITS 2 AND 3 NRC Docket Nos. 50-277 and 50-278 Renewed Facility Operating License Nos.
DPR-44 and DPR-56 Supplement to Request for Amendment to Technical Specification 3.1.7 "Standby Liquid Control (SLC) System" Proposed Markup of PBAPS Technical Specification Pages Unit 2 3.1-21 Unit3 3.1-21
5CC 5ys tern 3.1. /
ACTIONS (continued)
CONDITION REQUIRED ACEEON COMPLETION TIME C.
Iwo SLC subsystems C. I Restore one SLC B hour inoperable Eor reasons subsystem to OPERABLE other than status.
Condition A.
D.
Required Action and D.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as soc i a ted Compi e t i on Time not met.
ANii 0.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify level of sodium pentaborate solution In accordance in the SLC tank is 46%.
with the Survei 1 lance Frequency Control Program.
SR 3.1.7.2 Verify temperature of sodium pentaborate In accordance solution is 53°F.
with the Survei 1 lance Frequency Control Program.
SR 3.1.7.3 Verify temperature of pump suction piping is 53°F.
/
/ A Completion Time (CT) of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be invoked for Condition C when an emergent SLC systemi failure requires entrance into me Condition, provided the following compensating measures are in place within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of entering the CT; I
The Alternate Rod Injection system, both ATWS Recirculation Pump Trip Systems arid the Reactor Protection systems are OPERABLE and protected.
2.
For conditions where the SLC tank is available, the frequency for SR 3.1.7.1 will be increased from once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.
System :aintenance outages and activities that increase plant risk In accordance with the Survei 11 ance Frequency Control Program.
(continued)
Amendment No.
278 LC tern
. 1. 7 d) t.
rr ONS AC con,lnue CONDITION R
IRED ACTlON COMPLETION rIME C.
fwo LC ubsy terns C. 1 Re tor one SLC 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable fo r r asons subsy tern to OPERABLE other t ha n tatu Condition A.
D.
Required Action and D.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
Ml2 D.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify level of sodium pentaborate solution in the SLC tank is
~ 46%.
In accordance with the Surveillance Frequency Control Program.
SR 3.1.7.2 Verify temperature of sodium pentaborate solution is
~ 53°F.
In accordance with the Surveillance Frequency Control Program.
In accordance with the Surveillance Frequency Control Program.
Verify temperature of pump suction piping is
~ 53°F.
3.1.7.3 SR Completion Time (CT) of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be invoked for Condition C when an emergent SLC system requires entrance into me Condition, provided the following compensating measures are in place )---------
within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of entering the CT:
~ (cont i nued) 1.
The Alternate Rod Injection system, both ATWS Recirculation Pump Trip Systems and the Reactor Protection systems are OPERABLE and protected.
2.
For conditions where the SlC tank is available, the frequency for SR 3.1.7.1 will be increased from i once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
t-J System maintenance outages and activities that increase plant risk will be prohibited for the.-/
uration of the CT.
~~
PBA-S 3.121 Amendment No. 278
SLC System 3.1.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
fwo SLC subsystems C.1 Restore one SEC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for reasons subsystem to OPERABLE other than status.
Condition A.
D.
Required Action and D.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
0.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE_REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify level of sodium pentaborate solution In accordance in the SLC tank is 46%.
with the Survei 1 lance Frequency Control Program.
SR 3.1.7.2 Verify temperature of sodium pentaborate In accordance solution is 53°F.
with the Survei 1 lance Frequency Control Program.
In accordance with the Survei 11 ance Frequency Completion Time (CT) of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be invoked for Condition C when an emergent SLC systei failure requires entrance into me Condition, provided the following compensating measures are in placer j
within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of entering the CT:
continued) 1 The Alternate Rod Injection system, both ATWS Recirculation Pump Trip Systems and the Reactors Protection systems are OPERABLE and protected.
I
\\
2.
For conditions where the SLC tank is available, the frequency for SR 3.17.1 will be increased from /
once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.
System maintenance outages and activities that increase plant risk will be prohibed for the riuration of the CT.
BAPS UNIT 3
SR 3.1.7.3 Verify temperature of is 53°F.
pump suction piping Amendment No.
281 LC Sy tern 3.1.1 t.
d)
ACTIONS (can lnue CONDITION REQUIRED ACTION COMPLETION TIME C.
Two SLC subsystems C.l Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for reasons subsystem to OPERABLE oth r than status.
Condition A.
D.
Required Action and 0.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
AND 0.2 Be i n MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify level of sodium pentaborate solution in the SLC tank is
~ 46%.
In accordance with the Surveillance Frequency Control Program.
SR 3.1.7.2 Verify temperature of sodium pentaborate solution is
~ 53°F.
In accordance with the Surveillance Frequency Control Program.
Verify temperature of pump suction piping is
~ 53°F.
3.1.7.3 SR In accordance with the Surveillance Frequency Control r"
_------ 'Program.
~A Completion Time (CT) of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be invoked for Condition C when an emergent SLC syste~1...
failore requires entrance into me Condition, provided the following compensating measures are in p'acEt:=::'~"-'_-------
within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of entering the CT:
_._..( ( contin ued) 1.
The Alternate Rod Injection system, both AlWS Recirculation Pump Trip Systems and the Reactyor Protection systems are OPERABLE and protected.
2.
For conditions where the SLC t,an,k" is available, the frequ"ency for SR 3. 1.7.1 Wi,1I be increased fr"O"m once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
\\
3.
System maintenance outages e;tnd activities that increase plant risk will ""t?.e pr<)hibit~d farthe '." r duration ot the CT.
/',.---r--J~~,_~.,~.~
'~-p~
3.1-21 Amendment No.
281
ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNITS2AND3 NRC Docket Nos. 50-277 and 50-278 Renewed Facility Operating License Nos.
DPR-44 and DPR-56 Supplement to Request for Amendment to Technical Specification 3.1.7,
°Standby Liquid Control (SLC) System Proposed Markup of PBAPS Technical Specification Bases Pages Unit 2 Unit 3 B3.1-43 B3.1-43 B 3.1-47 B 3.1-47 ATTACHMENT 2 PEACH SOnOM ATOMIC POWER STATION UNITS 2 AND 3 NRC Docket Nos. 50-277 and 50-278 Renewed Facility Operating License Nos.
DPR-44 and DPR-56 Supplement to Request for Amendment to Technical Specification 3.1.7, IIStandby Liquid Control (SLC) System" Proposed Markup of PBAPS Technical Specification Bases Pages Unit 2 B 3.1-43 B 3.1-47 Unit 3 B 3.1-43 B 3.1-47
S LC Sy s tern
[3 LI.!
BASES ACTIONS B.1 (conti flood) ova I ability of on OPERABLE subsystem capable of performing the intended SEC System function and the low prohahi ii t,y of a
DBA or severe transi ent occurr i rig concurrent with the fai lure of the Control Rod Drive (CRD)
System to shut down the plant.
C.1 If both SLC Condition A
OPERABLE st of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> probabi li ty the failure D,1 and D.2 If any Required Action and associated Completion Time is not met, the plant must he brought to a
MODE in which the tCO does not apply.
To achieve this status, the plant must be (conti nued) subsystems are inoperable for reasons other than at least one subsystem must he restored to atus within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The allowed Completion Time is considered acceptable given the low of a
DBA or transient occurring concurrent with of the control rods to shut down the reactor.
Insert (Ref.4)
EBAPS UNIT 2
B 3.1-43 Revision No.
85 LC E:?m B
.1.7 BAS ACTION
( on inu v 11 bili 0
n 0 RABLE ubsystem cap ble of performing th int nded LC tem function and th low probability of a DBA or v r tr n ient occurring oncurrent with th failur 0
th Control Rod Drive (CRD) stern to shut down th plant.
If both SLC subsy tem are inoperable for reasons other than Condition A, at 1 tone subsy tem must be restored to OPERABL tatus within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
he allowed Completion Time of 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> i
on idered acceptable given the low probability of a DBA or transi nt occurring concurrent with the fa i1 ure 0
th control rods to shut down the reacto. ~
~
I any uired Action and associated Completion Time is not met, the plant mu t be brought to a MODE in which the LCO does not apply.
To achieve this status, the plant must be PBAPS lJi'HT 2 8 3.1-43 Revision No. 85
SLC System B 3.1.7 BASES SURVEILLANCE SR 3.1.7.10 REQU I REMENTS (conti nued)
Enriched sodi urn pentahorate sol uti on is made by mixing granular, enriched sodium pentaborate with water.
In order to ensure the proper B-10 atom percentage (in accordance with Table 3.1.7-1) is being used, calculations must be performed to verify the actual B-10 enrichment within 8
hours after addi ti on of the sol uti on to the SEC tank.
The calculations may be performed using the results of isotopic tests on the granular sodium pentaborate or vendor certification documents.
The Frequency is acceptable consi den ng that boron cnn chment is yen fi ed during the procurement process and any time boron is added to the SEC tank.
REFERENCES 1.
2.
UFSAR, Section 3.8,4.
3.
==---
4.
RM Documentation No. PB-LAR-05, Revision 0.
PBAPS UNIT 2
B 3.1-47 Revision No.
86 BAS URVE LLA~JC R
UIRE~1 NTS
( ontinued)
SLC tem B
.7 Enriched odium pentaborate solution is mad by mixing gr nular, enriched odium pentaborate with wa r.
In ord r to n ur the pro r B 10 atom percentage (in accordance with Table 3.1.7-1) i being used, calculation must be p rformed to verify the actual B-10 enrichment within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> aft r addition of the solution to the SLC tank.
The c 1 ulations may be performed using the results of i otopic te ts on the granular sodium pentaborate or v ndor rtification documents.
The Frequency is acceptable considering that boron enrichment is verified during the procurement process and any time boron is added to the SLC ta nk.
RE ERDJCES 1.
2.
UFSAR, Section 3.8.4.
3.
\\
4.
RM Documentation No. PB-LAR-05, Revision O.
PBAPS U~JIT 2 B 3.1-47 Revision No. 86
SLC System B 3.1.7 BASES ACTIONS j3+/-j (continued) availability of an OPERABLE subsystem capable of performing the intended SLC System function and the low probability of a
DBA or severe transient occurring concurrent with the failure of the Control Rod Drive (CRD)
System to shut down the plant.
C.1 If both SLC Condition A, OPERABLE sta of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> i
probability the failure D.1 and D.2 If any Required Action and associated Completion Time is not met, the plant must be brought to a
MODE in which the LCO does not apply.
To achieve this status, the plant must be (continued) subsystems are inoperable for reasons other than at least one subsystem must be restored to tus within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The allowed Completion Time s considered acceptable given the low of a
DBA or transient occurring concurrent with of the control rods to shut down the reacto I inserti (Ref. 4)
PBAPS UNIT 3
B 3.1-43 Revision No.
86 BASES ACTIONS SLC System B 3.1. 7 (continued) availability of an OPERABLE subsystem capable of performing the intended SLC System function and the low probability of a DBA or severe transient occurring concurrent with the failure of the Control Rod Drive (CRD) System to shut down the plant.
If both SLC subsystems are inoperable for reasons other than Condition A, at least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The allowed Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is considered acceptable given the low probability of a DBA or transient occurring concurrent with the fai 1ure of the control rods to shut down the reacto. ~
~
0.1 and 0.2 If any Required Action and associated Completion Time is not met, the plant must be brought to a MODE in which the LCO does not apply.
To achieve this status, the plant must be PBAPS UNIT 3 B 3.1-43 Revision No. 86
SLC System B 3.1.7 BASES SURVEILLANCE 5R3i7JQ.
REQU I REMENTS (continued)
Enriched sodi urn pentaborate sd uti on is made by mixing qranul or, cnn ched sodi urn pentaborate with water.
In order to ensure the proper B-iO atom percentage (in accordance with Table 3.i.7l) is being used, calculations must be performed to verify the actual BiO enrichment within 8
hours after addition of the solution to the 5CC tank.
The calculations may be performed using the results of isotopic tests on the granular sodium pentaborate or vendor certi fi cation documents.
The Frequency is acceptable consi den rig that boron cnn chment is verified dun ng the procurement process and any time boron is added to the SLC tank.
REFERENCES 1.
2.
- IJFSAR, Section 3.8.4.
3.
4.
RM Documentation No. PB-LAR-05, Revision 0.
PBAPS UNIT 3
B 3.1-47 Revision No.
87 BAS URV ILLANCE R
REtvJ N (continued)
SLC tem B
.1.7 nri hed sodium pentaborat olution is made by mlxlng r nul r,
ri hed odium pentaborate with wat r.
In order o
n ur h
proper B 10 atom percentage (in accordance with Tabl 3.1.7-1) i being used, calculation must be rformed to v rify th actual B-10 nrichment within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> aft r addition of the solution to the SLC tank.
The lcul tion may be performed using the results of i otopic t
ts on th granular sodium pentaborate or vendor rtification documents.
The Frequency is acceptable onsid ring that boron enrichment is verified during the procurement proc s and any time boron is added to the SLC tank.
REFEREr~CES 1.
2.
UFSAR, Section 3.8.4.
3.
~\\
4.
RM Documentation No. PB-LAR-05, Revision O.
PBAPS U~lIT 3 B 3.1-47 Revision No. 87
Bases Insert The Completion Time (CT) can be extended beyond the initial 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for emergent failures that impact both subsystems of the SLC system (Condition C). The additional Allowed Outage Time is permitted for emergent failures only and cannot be utilized for performance of routine scheduled maintenance. Scheduled preventive and corrective system maintenance will still continue to be limited by the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CT, whereas; emergent maintenance that satisfies Condition C of TS 3.1.7 will be permitted up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to complete repairs. Emergent failures can result from conditions identified during scheduled maintenance if the condition requires entry into Condition C of TS 3.1.7.
Additionally, the compensating measures to protect redundant systems and mitigate the potential for events caused by concurrent maintenance must be implemented prior to exceeding the initial 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CT. These compensatory measures include:
1.
The Alternate Rod Injection system, both ATWS Recirculation Pump Trip Systems and the Reactor Protection systems are Operable and protected.
2.
For conditions where the SLC tank is available, the frequency for SR 3.1.7.1 is increased from once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.
System maintenance outages and activities that increase risk will be prohibited for the duration of the CT.
As stated in Reference 4, the risk assessment that forms the basis for the 24-hour CT assumes one entry per year into Condition C.1. With both SLC subsystems inoperable, the on-line risk would be depicted as Orange, based on the deterministic assessment portion of the Configuration Risk Management Program. In this condition, station procedures require senior management review and approval to remove equipment from service, as well as implementation of compensatory measures to reduce risk, including contingency plans.
Bases Insert The Completion Time (CT) can be extended beyond the initial 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for emergent failures that impact both subsystems of the SLC system (Condition C). The additional Allowed Outage Time is permitted for emergent failures only and cannot be utilized for performance of routine scheduled maintenance. Scheduled preventive and corrective system maintenance will still continue to be limited by the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CT, whereas; emergent maintenance that satisfies Condition C of TS 3.1.7 will be permitted up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete repairs. Emergent failures can result from conditions identified during scheduled maintenance if the condition requires entry into Condition C of TS 3.1.7.
Additionally, the compensating measures to protect redundant systems and mitigate the potential for events caused by concurrent maintenance must be implemented prior to exceeding the initial 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CT. These compensatory measures include:
1.
The Alternate Rod Injection system, both ATWS Recirculation Pump Trip Systems and the Reactor Protection systems are Operable and protected.
2.
For conditions where the SLC tank is available. the frequency for SR 3.1.7.1 is increased from once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.
System maintenance outages and activities that increase risk will be prohibited for the duration of the CT.
As stated in Reference 4, the risk assessment that forms the basis for the 24-hour CT assumes one entry per year into Condition C.1. With both SLC subsystems inoperable.
the on-line risk would be depicted as "Orange." based on the deterministic assessment portion of the Configuration Risk Management Program. In this condition, station procedures require senior management review and approval to remove equipment from service. as well as implementation of compensatory measures to reduce risk, including contingency plans.