RS-13-040, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04: Difference between revisions

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| issue date = 01/24/2013
| issue date = 01/24/2013
| title = Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04
| title = Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04
| author name = Simpson P R
| author name = Simpson P
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:RS-13-040 January 24, 2013 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
{{#Wiki_filter:1 RS-13-040 RS-13-040 10 10 CFR CFR SO.SSa 50.55a January 24, 2013 U. S. Nuclear U. Nuclear Regulatory Regulatory Commission Commission ATTN: Document Control    Control Desk Washington, D.C.
Washington,        D.C. 20555-0001 20SSS-0001 Dresden Nuclear Power Station, Dresden                        Station, Units 22 and 3 Renewed Facility Renewed      Facility Operating Operating License License Nos.
Nos. DPR-19 and DPR-25   DPR-2S NRC Docket Nos. 50-237 SO-237    and 50-249 SO-249


==Subject:==
==Subject:==
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request 15R-04
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection                Inspection Interval Interval Relief Request Request 15R-04 ISR-04


==Reference:==
==Reference:==
 
Letter from from D.D. M.
Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC)) to U. S. NRC,"Dresden Nuclear Power Station, Units 2 and 3, Fifth Interval Inservice Inspection Program Plan and Relief Requests," dated September 28, 2012 In the referenced letter, EGC submitted relief requests associated with the fifth inservice inspection (ISI) interval for Dresden Nuclear Power Station (DNPS), Units 2 and 3. Following discussions with the NRC, it became apparent that additional clarification is required for the NRC to complete its review of Relief Request 15R-04. Therefore, EGC requests to supersede the version of 15R-04 in the referenced letter with the version in the attachment to this letter in its entirety.
M. Gullott Gullott(Exelon (Exelon Generation Generation Company, Company, LLC    LLC (EGC))
EGC continues to request approval of this relief request by September 28, 2013, to support examination of components during the DNPS, Unit 2 Fall 2013 refueling outage which falls within the fifth 10-year ISI interval.
(EGC>> to  to U.
There are no regulatory commitments contained within this letter.
U. S.
Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
S. NRC, NRC, "Dresden Nuclear Power Power Station, Station, Units Units 22 and and3,  3,Fifth Fifth Interval   Inservice Inspection Intervallnservice        Inspection Program Plan Program     Plan and Relief     Requests," dated September Relief Requests,"              September 28,   28, 2012 2012 In the In  the referenced letter, EGC submitted relief             requests associated relief requests  associatedwith  withthe thefifth fifth inservice inservice inspection inspection (ISI)  intervalfor (lSI) interval     forDresden Dresden Nuclear Nuclear Power Station (DNPS), Units 2 and 3.              3. Following Following discussions discussionswithwith the NRC,    it  became    apparent    that additional  clarification  is  required    for  the NRC, it became apparent that additional clarification is required for the NRC to complete its  NRC    to  complete    its review of of Relief Relief Request Request ISR-04.
Exelon Generation Company, LLC
15R-04. Therefore, EGC requests requests to  to supersede supersedethe    theversion versionofof15R-04 ISR-04inin the referenced referenced letterletter with with the version version in in the attachment attachmentto  to this this letter letter in in its its entirety.
entirety.
EGC continues to request approval   approval ofof this relief request by September relief request        September 28,    28, 2013, 2013, to to support support examination of components componentsduring during the theDNPS, DNPS,Unit Unit 22Fall Fall 2013 2013refueling refueling outage outagewhichwhichfalls falls within the fifth fifth 10-year 10-year ISIlSI interval.
interval.
There There areareno noregulatory regulatorycommitments commitmentscontained containedwithin withinthis thisletter.
letter.
Should you have have anyany questions questionsconcerning concerningthis thisletter, letter,please pleasecontact contactMr. Mr.Mitchel MitchelA. A. Mathews Mathews at  at (630) 657-2819.
6S7-2819.
Sin Patrick R. Simpson Manager - Licensing Exelon Generation Generation Company, LLC        LLC


==Attachment:==
==Attachment:==
10 CFR 50.55a Request Number 15R-04, Revision 1 1 RS-13-040 January 24, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20SSS-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-2S NRC Docket Nos. SO-237 and SO-249 10 CFR SO.SSa
==Subject:==
Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request ISR-04
==Reference:==
Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC>> to U. S. NRC, "Dresden Nuclear Power Station, Units 2 and 3, Fifth Intervallnservice Inspection Program Plan and Relief Requests," dated September 28, 2012 In the referenced letter, EGC submitted relief requests associated with the fifth inservice inspection (lSI) interval for Dresden Nuclear Power Station (DNPS), Units 2 and 3. Following discussions with the NRC, it became apparent that additional clarification is required for the NRC to complete its review of Relief Request ISR-04. Therefore, EGC requests to supersede the version of ISR-04 in the referenced letter with the version in the attachment to this letter in its entirety.
EGC continues to request approval of this relief request by September 28, 2013, to support examination of components during the DNPS, Unit 2 Fall 2013 refueling outage which falls within the fifth 10-year lSI interval.
There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 6S7 -2819. Sin Patrick R. Simpson Manager -Licensing Exelon Generation Company, LLC


==Attachment:==
==Attachment:==
10 CFR CFR 50.55a SO.SSa Request Request Number Number 15R-04, ISR-04, Revision Revision 11


10 CFR SO.SSa Request Number ISR-04, Revision 1 ATTACHMENT 10 CFR 50.55a Request Number 15R-04, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
ATTACHMENT 10 CFR SO.SSa 50 .55a Request Number  Number 15R-04,ISR-04, Revision 11 Proposed Alternative In Accordance with 10 Proposed                                                      10 CFR SO.SSa(a)(3)(ii) 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--
                            --Hardship or Unusual Difficulty without Compensating Increase in Level  Level of Quality and Safety--
ASME Code Component(s) Affected:
: 1. ASME Code Component(s)
Code Class:
Component(s) Affected:
Affected:
Code Class:                             3


==Reference:==
==Reference:==
IWD-2500, Table IWD-2500-1 IWD-2500-1 Examination Category:                  D-B Item Number:                            B2.10


Examination Category:
== Description:==
Item Number:
Testing Frequency for Isolation Condenser  Condenser Shell Shell Side Side and Associated Piping Component Number:
Unit No.                            Drawing                            Test Block No.
2                              M-28, M-39                            21CO1, 21C02 21C01, 3                              M-359, M-369                          31CO1, 31C02 31C01,
: 2. Code Applicable          Edition Applicable      Code and EditionAddenda:
and Addenda:
The Inservice Inspection (ISI)    (lSI) Program is based based on  on the theAmerican American Society Societyof  of Mechanical Mechanical Engineers (ASME)          Boiler and (ASME) Boiler        and Pressure      Vessel(B&PV)
Pressure Vessel          (B&PV) Code, Code, Section SectionXI, XI, 2007 2007 Edition Edition through the 2008 Addenda.
Addenda.
: 3. Applicable Applicable Code Requirements:
Table IWD-2500-Table    IWD-2500-1,  1, "Examination "Examination Categories," Examination Examination Category Category D- D-B, B, Item Item Number D2.10, requires 02.10,    requires all allClass Class 33 pressure retaining retaining components components be subject to      to a system leakage leakage test with test with aa VT-2            examination in VT-2 visual examination          in accordance accordance with  with IWD-5220, IWD-5220, "System "System Leakage        Test."
Leakage Test."
This system leakage test is      is to be be conducted conducted once each inspection period.      period.
IWD-5221, IWD-5221,"Pressure,"
                              "Pressure,"states states that that system system leakage test shall    shall be conducted conducted at  at the the system system pressureobtained pressure    obtainedwhile while the thesystem, system,ororportion portionof  ofthe thesystem, system,isisininservice serviceperforming performingits  its normal operating function function or oratat the the system system pressure        developedduring pressure developed        during aatest testconducted conductedto    to verify system verify            operability (e.g.,
system operability    (e.g., to demonstrate demonstrate systemsystemsafety safetyfunction functionororsatisfy satisfytechnical technical specification surveillance requirements).
requirements).
Reason  4. for  Request:
Reason      for Request:
Pursuant to Pursuant    to 10 10 CFR CFR 50.55a(a)(3)(ii),
50.55a(a)(3)(ii), relief relief is is requested requested on  on the the basis basisthat thatconformance conformancewith    with Code requirements the Code      requirements impose imposehardship hardshipwithout without aacompensating compensatingincrease increaseininthe thelevel levelofof quality and safety.
Isolation Condenser The Isolation    Condenserisisnot  notnormally normallyin  in service; service; itit is is normally normally in a standby standby alignment alignment with its with  its shell shell side side vented vented toto the the atmosphere        through aa non-isolable atmosphere through              non-isolable vent vent line.
line. ForFor inservice inservice purposes, each inspection purposes,      eachunit's unit'sIsolation IsolationCondenser Condenserisisdivideddividedinto intotwo twotest testblocks blocks Page 11 of of 5S


==
ATTACHMENT 50.55a Request 10 CFR SO.SSa        Request NumberNumber15R-04,  ISR-04, Revision Revision 11 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
Description:==
Proposed                                                                    SO.SSa(a){3)(ii)
            --Hardship or Unusual Difficulty without Compensating Increase in Increase    in Level Level of  of Quality Quality and and Safety-Safety-(e.g., 21C01 21C01 and and 21C02 21C02for forthe the Unit Unit22Isolation IsolationCondenser Condenser upper  upper and and lower lower portions, portions, respectively). For example, the respectively). For              the DNPS, DNPS, Unit Unit 2 upper and    and lowerlower system leakage leakagetest testblocks blocks are represented representedininFigures Figures15R-04.01 ISR-04.01 and  and15R-04.02 ISR-04.02 below, below, respectively.
respectively.
                                                                                ,/
                                                                              ./
                                                                          ./".
                                                                    ,:~:t ISOLA7iCN CO WE SE' 2--133 2 Figure Figure15R-04.1:
ISR-04.1: Unit Unit 22 Isolation IsolationCondenser CondenserTest      TestBlock BlockNo. No.21C01 21C01 Page 2 of        5 ofS


Component Number:
ATTACHMENT ATTACHMENT 10 CFR 10 CFR 50.55a RequestRequest NumberNumber15R      -04, Revision 11 15R-04, Proposed Alternative Proposed    Alternative In  In Accordance with 10 CFR 50.55a(a)(3)(ii) 50.55a{a){3){ii)
3 IWD-2500, Table IWD-2500-1 D-BB2.10 Testing Frequency for Isolation Condenser Shell Side and Associated Piping Unit No.Drawing Test Block No.
          --Hardship or Unusual Difficulty without Compensating
2 M-28, M-39 21CO1, 21C02 3 M-359, M-369 31CO1, 31C02 2.
          --Hardship Increase in Increase      in Level Level of Quality and Safety--
The Inservice Inspection (ISI) Program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, 2007 Edition through the 2008 Addenda.
4SOLA I: N CUND SER 2-?382 Figure Figure15R-04.2:
3.Applicable Code Requirements:
15R-04.2: Unit Unit 22 Isolation IsolationCondenser CondenserTest  TestBlock BlockNo.
Table IWD-2500-1,"Examination Categories," Examination Category D-B, Item Number D2.10, requires all Class 3 pressure retaining components be subject to a system leakage test with a VT-2 visual examination in accordance with IWD-5220, "System Leakage Test." This system leakage test is to be conducted once each inspection period.
No.21C02 21C02 The system The  system isisnormally normally aligned aligned with with the Isolation Condenser      shell side Condenser shell    side water waterlevel level greater greater than or equal to six (6) than or equal  to six (6) feet  in accordance with Dresden Nuclear Power Station (DNPS),
IWD-5221, "Pressure," states that system leakage test shall be conducted at the system pressure obtained while the system, or portion of the system, is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability (e.g., to demonstrate system safety function or satisfy technical specification surveillance requirements).
in accordance        with  Dresden  Nuclear  Power    Station  (DNPS),
4.
and 33 Technical Units 2 and    Technical Specifications Specifications (TS); (TS); however, however, the theshell shellside sidewater waterlevel levelofofthe the Isolation Condenser Condenser isis administratively administratively maintained between  between 77 feet feet and and7.4 7.4feet feetinin accordance accordancewithwith plant plant procedures.
Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that conformance with the Code requirements impose hardship without a compensating increase in the level of quality and safety.
procedures.
The Isolation Condenser is not normally in service; it is normally in a standby alignment with its shell side vented to the atmosphere through a non-isolable vent line. For inservice inspection purposes, each unit's Isolation Condenser is divided into two test blocks Page 1 of 5 ATTACHMENT 10 CFR SO.SSa Request Number ISR-04, Revision 1 Proposed Alternative In Accordance with 10 CFR SO.SSa(a)(3)(ii)
Page Page 33 of  5 of5
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--1. ASME Code Component(s)
Affected:
Code Class:


==Reference:==
ATTACHMENT ATTACHMENT 10 CFR 10    CFR SO.SSa 50.55a Request Request NumberNumber15R-04,    ISR-04, Revision Revision 11 Proposed Alternative Proposed          Alternative In    In Accordance with 10 CFR SO.SSa{a){3){ii)      50.55a(a)(3)(ii)
 
                    --Hardship or Unusual Difficulty without Compensating
Examination Category:
                    --Hardship Increase in Increase        in Level Level of Quality and        and Safety--
Item Number: 3 IWD-2500, Table IWD-2500-1 D-B B2.10
Isolation IsolationCondenser Condenser system  system operability operability is  is verified verified through performance performance of      of TS TS Surveillance Surveillance Requirement (SR) 3.5.3.4, "Isolation Requirement                              "Isolation Condenser Condenser System    System Heat HeatRemoval RemovalCapability Capability Verification VerificationTest,"          every60 Test,"every        60 months months (Le.,
 
(i.e., during during two  twoof ofthe thethree three inspection inspection periods for DNPSs DNPSs fifthfifthlSIISIinterval).
== Description:==
interval).The Thesystem system pressures pressures developeddevelopedduring  duringthe theperformance performanceofofthis    this TS surveillance meet the Code          Code requirements requirementsof        ofIWD-5221; IWD-5221; however, the          the 60-month 60-month frequency does does not  not meet meetthe theTable TableIWD-2500-1 IWD-2500-1 examinationexamination frequency frequency requirement requirement of    of once perper inspection period. period.
Performance of an additional Isolation      Isolation Condenser Condenser heat      heatremoval removal capability capability testtest solely solely forfor the purposes of performing performing aa system leakage    leakage testtest requires requires aaminimum minimum of      of aa 25%
25% reduction reduction in  in reactor power power to    to perform performthe  theexamination.
examination. This    This presents presents an unnecessary unnecessarytransient transient on  on the the affected DNPS reactor and aa challenge      challenge to  to station station operators.
operators. Additionally, Additionally, as  as previously previously stated, the isolation isolation condenser condenser shell  shell cannot cannotbe    beisolated isolatedand andpressurized pressurizedtotomeet  meetIWD-5221 IWD-5221 examination examination pressure pressure requirements when in a standby alignment. ItIt would be an abnormal activityto activity    tofill fillthetheIsolation IsolationCondenser Condenserto    tothe thetop top simply simplytotoachieve achieve aa slight slight increase increase in static head for the additional additional system          leakage test.
system leakage          test. As  Asan anadditional additionalcomplication, complication, any  any water water added added to to the the isolation isolation condenser condensershell  shelltotoraise raiselevel levelabove abovethe  thenormal normaloperating operatinglevel levelwould would subsequently have to be drained and processed            processed by        by radwaste.
radwaste.
In In summary, summary, imposing imposing aa largelarge transient transient on on the reactor plant to          to accommodate the performance of the Isolation Condenser    Condenser heat  heatremoval removal capability capability verification verification at  at a greater frequency than required  required by  by DNPS DNPS TS  TS and andfilling filling thethe Isolation Isolation Condenser Condenser to the top to perform perform aa third third system system leakage test, present  presenthardshiphardshipwithout without aa compensating compensating increase increaseinin and safety.
quality and 5.
S. Proposed Alternative and Basis for Use:                  Use:
As an alternative, Exelon  Exelon Generation Generation Company, Company, LLC      LLC (EGC) proposes proposes the  the performance performanceof        ofaa system leakage system    leakagetest  testusing usingaaVT-2 VT-2visual visualexamination examinationof        of all all DNPS DNPS UnitsUnits 22 and and 33Isolation Isolation CondenserTest Condenser        TestBlocks Blocks(i.e.,
(Le., Test TestBlocks Blocks 2(3)IC01 2(3)IC01 and    and 2(3)IC02) 2(3)IC02) every 60 months    months during during the performance of TS SR 3.5.3.4 versus once                  once per    per inspection inspection periodperiod as as discussed discussedininTable  Table IWD-2500-1.
IWD-2500-1.
discussedinin the As discussed            theprevious previousparagraph, paragraph,during duringthe    theDNPS DNPSfifth fifth ISI lSI interval interval EGC proposes proposes the leakage that the    leakagetest  testofofIsolation Isolation Condenser CondenserTest      TestBlocks Blocks2(3)IC01 2(3)IC01 (i.e.,(Le., the theupper upperportion portionof of the Isolation the  Isolation Condenser Condenserand      andassociated associatedpiping)piping)will  will only only be be performed performed once  onceeveryevery60  60 months during months      during the performance of TS SR 3.5.3.4            3.5.3.4 versusversus once onceper  perinspection inspectionperiodperiodas  as discussed discussedininTable  TableIWD-2500-1.
IWD-2500-1.
During inspection periods where TS SR During                                                SR 3.5.3.4 3.5.3.4 isis not  not performed performed on    on aaunit's unit'sIsolation Isolation Condenser,an Condenser,        anadditional additionalVT-2 VT-2examination examinationwill      will bebeperformed performedfor    forTest TestBlocks Blocks2(3)IC02 2(3)IC02 (Le., the lower portion (i.e.,                portionof  ofthetheIsolation IsolationCondensers Condensers and        and associated          piping). This associated piping).          This leakage leakage will be performed with test will test                            with Isolation IsolationCondenser Condenser shell    shell side water level at the normal standby        standby level versus versus at  at the the normal normal pressure pressurewhen  whenthe  thesystem systemisisininservice serviceperforming performingitsitsnormal normal operating function operating    function or at the system pressure    pressuredeveloped developedduring  duringaatest  testconducted conductedtotoverify verify system system operability operability as    as discussed discussedininIWD-5221.
IWD-5221.
Page Page 44 of    ofS 5


Testing Frequency for Isolation Condenser Shell Side and Associated Piping Component Number: Unit No. Drawing Test Block No. 2 M-28, M-39 21C01, 21C02 3 M-359, M-369 31C01, 31C02 2. Applicable Code Edition and Addenda: The Inservice Inspection (lSI) Program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, 2007 Edition through the 2008 Addenda. 3. Applicable Code Requirements:
ATTACHMENT ATTACHMENT 10 CFR   50.55a 10 CFR SO.SSa      Request     Number Number 15R-04, ISR-04, Revision 11 Proposed Alternative Proposed      Alternative In In Accordance with    with 10 CFR SO.SSa{a){3){ii) 50.55a(a)(3)(ii)
Table IWD-2500-1, "Examination Categories," Examination Category D-B, Item Number 02.10, requires all Class 3 pressure retaining components be subject to a system leakage test with a VT-2 visual examination in accordance with IWD-5220, "System Leakage Test." This system leakage test is to be conducted once each inspection period. IWD-5221, "Pressure," states that system leakage test shall be conducted at the system pressure obtained while the system, or portion of the system, is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability (e.g., to demonstrate system safety function or satisfy technical specification surveillance requirements).
                              --Hardship or Unusual Difficulty
: 4. Reason for Request: Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is requested on the basis that conformance with the Code requirements impose hardship without a compensating increase in the level of quality and safety. The Isolation Condenser is not normally in service; it is normally in a standby alignment with its shell side vented to the atmosphere through a non-isolable vent line. For inservice inspection purposes, each unit's Isolation Condenser is divided into two test blocks Page 1 of S ATTACHMENT 10 CFR 50.55a Request Number 15R-04, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
                              --Hardship                     Difficulty without without Compensating Compensating Increase in Level Increase        Level ofof Quality Quality and Safety--
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety-(e.g., 21C01 and 21C02 for the Unit 2 Isolation Condenser upper and lower portions, respectively). For example, the DNPS, Unit 2 upper and lower system leakage test blocks are represented in Figures 15R-04.01 and 15R-04.02 below, respectively.
Safety--
ISOLA7iCN CO WE SE' 2--133 2 Figure 15R
The proposed alternative The                alternative isis based based on the hardship hardship imposed imposed by   by the the performance performance of of the heat heat removal     capability verification   test at a greater   frequency     than required removal capability verification test at a greater frequency than required by DNPS TS     by DNPS    TS  and fillingthe filling theIsolation IsolationCondenser Condenserto  tothe thetop toptotoperform performaathirdthirdsystem system leakage leakage test without a compensating increase compensating        increase in in quality quality and safety.
-04.1: Unit 2 Isolation Condenser Test Block No. 21C01 Page 2 of 5 ATTACHMENT 10 CFR SO.SSa Request Number ISR-04, Revision 1 Proposed Alternative In Accordance with 10 CFR SO.SSa(a){3)(ii)  
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety-(e.g., 21C01 and 21C02 for the Unit 2 Isolation Condenser upper and lower portions, respectively).
For example, the DNPS, Unit 2 upper and lower system leakage test blocks are represented in Figures ISR-04.01 and ISR-04.02 below, respectively.
./". ,/ ./ Figure ISR-04.1:
Unit 2 Isolation Condenser Test Block No. 21C01 Page 2 ofS ATTACHMENT 10 CFR 50.55a Request Number 15R
-04, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--
4SOLA I: N CUND SER 2-?382 Figure 15R
-04.2: Unit 2 Isolation Condenser Test Block No. 21C02 The system is normally aligned with the Isolation Condenser shell side water level greater than or equal to six (6) feet in accordance with Dresden Nuclear Power Station (DNPS), Units 2 and 3 Technical Specifications (TS); however, the shell side water level of the Isolation Condenser is administratively maintained between 7 feet and 7.4 feet in accordance with plant procedures.
Page 3 of 5 ATTACHMENT 10 CFR 50.55a Request Number 15R-04, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a{a){3){ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--Figure 15R-04.2:
Unit 2 Isolation Condenser Test Block No. 21C02 The system is normally aligned with the Isolation Condenser shell side water level greater than or equal to six (6) feet in accordance with Dresden Nuclear Power Station (DNPS), Units 2 and 3 Technical Specifications (TS); however, the shell side water level of the Isolation Condenser is administratively maintained between 7 feet and 7.4 feet in accordance with plant procedures.
Page 3 of5 ATTACHMENT 10 CFR 50.55a Request Number 15R-04, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--
Isolation Condenser system operability is verified through performance of TS Surveillance Requirement (SR) 3.5.3.4, "Isolation Condenser System Heat Removal Capability Verification Test," every 60 months (i.e., during two of the three inspection periods for DNPSs fifth ISI interval). The system pressures developed during the performance of this TS surveillance meet the Code requirements of IWD-5221; however, the 60-month frequency does not meet the Table IWD-2500-1 examination frequency requirement of once per inspection period.
Performance of an additional Isolation Condenser heat removal capability test solely for the purposes of performing a system leakage test requires a minimum of a 25% reduction in reactor power to perform the examination. This presents an unnecessary transient on the affected DNPS reactor and a challenge to station operators. Additionally, as previously stated, the isolation condenser shell cannot be isolated and pressurized to meet IWD-5221 examination pressure requirements when in a standby alignment. It would be an abnormal activity to fill the Isolation Condenser to the top simply to achieve a slight increase in static head for the additional system leakage test. As an additional complication, any water added to the isolation condenser shell to raise level above the normal operating level would subsequently have to be drained and processed by radwaste.
In summary, imposing a large transient on the reactor plant to accommodate the performance of the Isolation Condenser heat removal capability verification at a greater frequency than required by DNPS TS and filling the Isolation Condenser to the top to perform a third system leakage test, present hardship without a compensating increase in quality and safety.
5.Proposed Alternative and Basis for Use:
As an alternative, Exelon Generation Company, LLC (EGC) proposes the performance of a system leakage test using a VT-2 visual examination of all DNPS Units 2 and 3 Isolation Condenser Test Blocks (i.e., Test Blocks 2(3)IC01 and 2(3)IC02) every 60 months during the performance of TS SR 3.5.3.4 versus once per inspection period as discussed in Table IWD-2500-1.
As discussed in the previous paragraph, during the DNPS fifth ISI interval EGC proposes that the leakage test of Isolation Condenser Test Blocks 2(3)IC01 (i.e., the upper portion of the Isolation Condenser and associated piping) will only be performed once every 60 months during the performance of TS SR 3.5.3.4 versus once per inspection period as discussed in Table IWD-2500-1.
During inspection periods where TS SR 3.5.3.4 is not performed on a unit's Isolation Condenser, an additional VT-2 examination will be performed for Test Blocks 2(3)IC02 (i.e., the lower portion of the Isolation Condensers and associated piping). This leakage test will be performed with Isolation Condenser shell side water level at the normal standby level versus at the normal pressure when the system is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability as discussed in IWD-5221.
Page 4 of 5 ATTACHMENT 10 CFR SO.SSa Request Number ISR-04, Revision 1 Proposed Alternative In Accordance with 10 CFR SO.SSa{a){3){ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--Isolation Condenser system operability is verified through performance of TS Surveillance Requirement (SR) 3.5.3.4, "Isolation Condenser System Heat Removal Capability Verification Test," every 60 months (Le., during two of the three inspection periods for DNPSs fifth lSI interval).
The system pressures developed during the performance of this TS surveillance meet the Code requirements of IWD-5221; however, the 60-month frequency does not meet the Table IWD-2500-1 examination frequency requirement of once per inspection period. Performance of an additional Isolation Condenser heat removal capability test solely for the purposes of performing a system leakage test requires a minimum of a 25% reduction in reactor power to perform the examination.
This presents an unnecessary transient on the affected DNPS reactor and a challenge to station operators.
Additionally, as previously stated, the isolation condenser shell cannot be isolated and pressurized to meet IWD-5221 examination pressure requirements when in a standby alignment.
It would be an abnormal activity to fill the Isolation Condenser to the top simply to achieve a slight increase in static head for the additional system leakage test. As an additional complication, any water added to the isolation condenser shell to raise level above the normal operating level would subsequently have to be drained and processed by radwaste.
In summary, imposing a large transient on the reactor plant to accommodate the performance of the Isolation Condenser heat removal capability verification at a greater frequency than required by DNPS TS and filling the Isolation Condenser to the top to perform a third system leakage test, present hardship without a compensating increase in quality and safety. S. Proposed Alternative and Basis for Use: As an alternative, Exelon Generation Company, LLC (EGC) proposes the performance of a system leakage test using a VT-2 visual examination of all DNPS Units 2 and 3 Isolation Condenser Test Blocks (Le., Test Blocks 2(3)IC01 and 2(3)IC02) every 60 months during the performance of TS SR 3.5.3.4 versus once per inspection period as discussed in Table IWD-2500-1.
As discussed in the previous paragraph, during the DNPS fifth lSI interval EGC proposes that the leakage test of Isolation Condenser Test Blocks 2(3)IC01 (Le., the upper portion of the Isolation Condenser and associated piping) will only be performed once every 60 months during the performance of TS SR 3.5.3.4 versus once per inspection period as discussed in Table IWD-2500-1.
During inspection periods where TS SR 3.5.3.4 is not performed on a unit's Isolation Condenser, an additional VT-2 examination will be performed for Test Blocks 2(3)IC02 (Le., the lower portion of the Isolation Condensers and associated piping). This leakage test will be performed with Isolation Condenser shell side water level at the normal standby level versus at the normal pressure when the system is in service performing its normal operating function or at the system pressure developed during a test conducted to verify system operability as discussed in IWD-5221.
Page 4 ofS ATTACHMENT 10 CFR 50.55a Request Number 15R-04, Revision 1 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--The proposed alternative is based on the hardship imposed by the performance of the heat removal capability verification test at a greater frequency than required by DNPS TS and filling the Isolation Condenser to the top to perform a third system leakage test without a compensating increase in quality and safety.
6.
6.
Relief is requested for the Fifth Ten-Year Inspection Interval for DNPS, Units 2 and 3.
Duration 6.
7.
of Proposed Duration of Proposed Alternative:
DNPS, Units 2 and 3 fourth inspection interval Relief Request 14R-06 was authorized in an NRC safety evaluation (SE) dated September 4, 2003. The fifth inspection interval relief request (i.e., 15R-04, Revision 1) utilizes a similar approach that was previously approved.Page 5 of 5 ATTACHMENT 10 CFR SO.SSa Request Number ISR-04, Revision 1 Proposed Alternative In Accordance with 10 CFR SO.SSa{a){3){ii)
Alternative:
--Hardship or Unusual Difficulty without Compensating Increase in Level of Quality and Safety--The proposed alternative is based on the hardship imposed by the performance of the heat removal capability verification test at a greater frequency than required by DNPS TS and filling the Isolation Condenser to the top to perform a third system leakage test without a compensating increase in quality and safety. 6. Duration of Proposed Alternative:
Relief isis requested Relief      requested for the Fifth   Ten-Year Inspection Interval Fifth Ten-Year                              for DNPS, Interval for DNPS, Units Units 22 and and 3.
Relief is requested for the Fifth Ten-Year Inspection Interval for DNPS, Units 2 and 3. 7. Precedents:
Precedents:
DNPS, Units 2 and 3 fourth inspection interval Relief Request 14R-06 was authorized in an NRC safety evaluation (SE) dated September 4, 2003. The fifth inspection interval relief request (Le., ISR-04, Revision 1) utilizes a similar approach that was previously approved.
: 7. Precedents:
Page S of S}}
DNPS, Units DNPS,      Units 2 and 3 fourth inspection intervalinterval Relief Request Request 14R-06 14R-06 was authorized authorized in in an NRC safety evaluation evaluation  (SE) dated   September      4,  2003. The  fifth inspection September 4, 2003. The fifth inspection interval  interval relief request relief  request (i.e.,
(Le., 15R-04,    Revision 1)
ISR-04, Revision       1) utilizes utilizes aa similar similar approach approach that was previously previously approved.
Page Page 5S of of 5S}}

Latest revision as of 00:09, 5 November 2019

Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04
ML13025A161
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 01/24/2013
From: Simpson P
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
15R-04, RS-13-040
Download: ML13025A161 (6)


Text

1 RS-13-040 RS-13-040 10 10 CFR CFR SO.SSa 50.55a January 24, 2013 U. S. Nuclear U. Nuclear Regulatory Regulatory Commission Commission ATTN: Document Control Control Desk Washington, D.C.

Washington, D.C. 20555-0001 20SSS-0001 Dresden Nuclear Power Station, Dresden Station, Units 22 and 3 Renewed Facility Renewed Facility Operating Operating License License Nos.

Nos. DPR-19 and DPR-25 DPR-2S NRC Docket Nos. 50-237 SO-237 and 50-249 SO-249

Subject:

Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Inspection Interval Interval Relief Request Request 15R-04 ISR-04

Reference:

Letter from from D.D. M.

M. Gullott Gullott(Exelon (Exelon Generation Generation Company, Company, LLC LLC (EGC))

(EGC>> to to U.

U. S.

S. NRC, NRC, "Dresden Nuclear Power Power Station, Station, Units Units 22 and and3, 3,Fifth Fifth Interval Inservice Inspection Intervallnservice Inspection Program Plan Program Plan and Relief Requests," dated September Relief Requests," September 28, 28, 2012 2012 In the In the referenced letter, EGC submitted relief requests associated relief requests associatedwith withthe thefifth fifth inservice inservice inspection inspection (ISI) intervalfor (lSI) interval forDresden Dresden Nuclear Nuclear Power Station (DNPS), Units 2 and 3. 3. Following Following discussions discussionswithwith the NRC, it became apparent that additional clarification is required for the NRC, it became apparent that additional clarification is required for the NRC to complete its NRC to complete its review of of Relief Relief Request Request ISR-04.

15R-04. Therefore, EGC requests requests to to supersede supersedethe theversion versionofof15R-04 ISR-04inin the referenced referenced letterletter with with the version version in in the attachment attachmentto to this this letter letter in in its its entirety.

entirety.

EGC continues to request approval approval ofof this relief request by September relief request September 28, 28, 2013, 2013, to to support support examination of components componentsduring during the theDNPS, DNPS,Unit Unit 22Fall Fall 2013 2013refueling refueling outage outagewhichwhichfalls falls within the fifth fifth 10-year 10-year ISIlSI interval.

interval.

There There areareno noregulatory regulatorycommitments commitmentscontained containedwithin withinthis thisletter.

letter.

Should you have have anyany questions questionsconcerning concerningthis thisletter, letter,please pleasecontact contactMr. Mr.Mitchel MitchelA. A. Mathews Mathews at at (630) 657-2819.

6S7-2819.

Sin Patrick R. Simpson Manager - Licensing Exelon Generation Generation Company, LLC LLC

Attachment:

Attachment:

10 CFR CFR 50.55a SO.SSa Request Request Number Number 15R-04, ISR-04, Revision Revision 11

ATTACHMENT 10 CFR SO.SSa 50 .55a Request Number Number 15R-04,ISR-04, Revision 11 Proposed Alternative In Accordance with 10 Proposed 10 CFR SO.SSa(a)(3)(ii) 50.55a(a)(3)(ii)

--Hardship or Unusual Difficulty without Compensating Increase in Level Level of Quality and Safety--

1. ASME Code Component(s)

Component(s) Affected:

Affected:

Code Class: 3

Reference:

IWD-2500, Table IWD-2500-1 IWD-2500-1 Examination Category: D-B Item Number: B2.10

Description:

Testing Frequency for Isolation Condenser Condenser Shell Shell Side Side and Associated Piping Component Number:

Unit No. Drawing Test Block No.

2 M-28, M-39 21CO1, 21C02 21C01, 3 M-359, M-369 31CO1, 31C02 31C01,

2. Code Applicable Edition Applicable Code and EditionAddenda:

and Addenda:

The Inservice Inspection (ISI) (lSI) Program is based based on on the theAmerican American Society Societyof of Mechanical Mechanical Engineers (ASME) Boiler and (ASME) Boiler and Pressure Vessel(B&PV)

Pressure Vessel (B&PV) Code, Code, Section SectionXI, XI, 2007 2007 Edition Edition through the 2008 Addenda.

Addenda.

3. Applicable Applicable Code Requirements:

Table IWD-2500-Table IWD-2500-1, 1, "Examination "Examination Categories," Examination Examination Category Category D- D-B, B, Item Item Number D2.10, requires 02.10, requires all allClass Class 33 pressure retaining retaining components components be subject to to a system leakage leakage test with test with aa VT-2 examination in VT-2 visual examination in accordance accordance with with IWD-5220, IWD-5220, "System "System Leakage Test."

Leakage Test."

This system leakage test is is to be be conducted conducted once each inspection period. period.

IWD-5221, IWD-5221,"Pressure,"

"Pressure,"states states that that system system leakage test shall shall be conducted conducted at at the the system system pressureobtained pressure obtainedwhile while the thesystem, system,ororportion portionof ofthe thesystem, system,isisininservice serviceperforming performingits its normal operating function function or oratat the the system system pressure developedduring pressure developed during aatest testconducted conductedto to verify system verify operability (e.g.,

system operability (e.g., to demonstrate demonstrate systemsystemsafety safetyfunction functionororsatisfy satisfytechnical technical specification surveillance requirements).

requirements).

Reason 4. for Request:

Reason for Request:

Pursuant to Pursuant to 10 10 CFR CFR 50.55a(a)(3)(ii),

50.55a(a)(3)(ii), relief relief is is requested requested on on the the basis basisthat thatconformance conformancewith with Code requirements the Code requirements impose imposehardship hardshipwithout without aacompensating compensatingincrease increaseininthe thelevel levelofof quality and safety.

Isolation Condenser The Isolation Condenserisisnot notnormally normallyin in service; service; itit is is normally normally in a standby standby alignment alignment with its with its shell shell side side vented vented toto the the atmosphere through aa non-isolable atmosphere through non-isolable vent vent line.

line. ForFor inservice inservice purposes, each inspection purposes, eachunit's unit'sIsolation IsolationCondenser Condenserisisdivideddividedinto intotwo twotest testblocks blocks Page 11 of of 5S

ATTACHMENT 50.55a Request 10 CFR SO.SSa Request NumberNumber15R-04, ISR-04, Revision Revision 11 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)

Proposed SO.SSa(a){3)(ii)

--Hardship or Unusual Difficulty without Compensating Increase in Increase in Level Level of of Quality Quality and and Safety-Safety-(e.g., 21C01 21C01 and and 21C02 21C02for forthe the Unit Unit22Isolation IsolationCondenser Condenser upper upper and and lower lower portions, portions, respectively). For example, the respectively). For the DNPS, DNPS, Unit Unit 2 upper and and lowerlower system leakage leakagetest testblocks blocks are represented representedininFigures Figures15R-04.01 ISR-04.01 and and15R-04.02 ISR-04.02 below, below, respectively.

respectively.

,/

./

./".

,:~:t ISOLA7iCN CO WE SE' 2--133 2 Figure Figure15R-04.1:

ISR-04.1: Unit Unit 22 Isolation IsolationCondenser CondenserTest TestBlock BlockNo. No.21C01 21C01 Page 2 of 5 ofS

ATTACHMENT ATTACHMENT 10 CFR 10 CFR 50.55a RequestRequest NumberNumber15R -04, Revision 11 15R-04, Proposed Alternative Proposed Alternative In In Accordance with 10 CFR 50.55a(a)(3)(ii) 50.55a{a){3){ii)

--Hardship or Unusual Difficulty without Compensating

--Hardship Increase in Increase in Level Level of Quality and Safety--

4SOLA I: N CUND SER 2-?382 Figure Figure15R-04.2:

15R-04.2: Unit Unit 22 Isolation IsolationCondenser CondenserTest TestBlock BlockNo.

No.21C02 21C02 The system The system isisnormally normally aligned aligned with with the Isolation Condenser shell side Condenser shell side water waterlevel level greater greater than or equal to six (6) than or equal to six (6) feet in accordance with Dresden Nuclear Power Station (DNPS),

in accordance with Dresden Nuclear Power Station (DNPS),

and 33 Technical Units 2 and Technical Specifications Specifications (TS); (TS); however, however, the theshell shellside sidewater waterlevel levelofofthe the Isolation Condenser Condenser isis administratively administratively maintained between between 77 feet feet and and7.4 7.4feet feetinin accordance accordancewithwith plant plant procedures.

procedures.

Page Page 33 of 5 of5

ATTACHMENT ATTACHMENT 10 CFR 10 CFR SO.SSa 50.55a Request Request NumberNumber15R-04, ISR-04, Revision Revision 11 Proposed Alternative Proposed Alternative In In Accordance with 10 CFR SO.SSa{a){3){ii) 50.55a(a)(3)(ii)

--Hardship or Unusual Difficulty without Compensating

--Hardship Increase in Increase in Level Level of Quality and and Safety--

Isolation IsolationCondenser Condenser system system operability operability is is verified verified through performance performance of of TS TS Surveillance Surveillance Requirement (SR) 3.5.3.4, "Isolation Requirement "Isolation Condenser Condenser System System Heat HeatRemoval RemovalCapability Capability Verification VerificationTest," every60 Test,"every 60 months months (Le.,

(i.e., during during two twoof ofthe thethree three inspection inspection periods for DNPSs DNPSs fifthfifthlSIISIinterval).

interval).The Thesystem system pressures pressures developeddevelopedduring duringthe theperformance performanceofofthis this TS surveillance meet the Code Code requirements requirementsof ofIWD-5221; IWD-5221; however, the the 60-month 60-month frequency does does not not meet meetthe theTable TableIWD-2500-1 IWD-2500-1 examinationexamination frequency frequency requirement requirement of of once perper inspection period. period.

Performance of an additional Isolation Isolation Condenser Condenser heat heatremoval removal capability capability testtest solely solely forfor the purposes of performing performing aa system leakage leakage testtest requires requires aaminimum minimum of of aa 25%

25% reduction reduction in in reactor power power to to perform performthe theexamination.

examination. This This presents presents an unnecessary unnecessarytransient transient on on the the affected DNPS reactor and aa challenge challenge to to station station operators.

operators. Additionally, Additionally, as as previously previously stated, the isolation isolation condenser condenser shell shell cannot cannotbe beisolated isolatedand andpressurized pressurizedtotomeet meetIWD-5221 IWD-5221 examination examination pressure pressure requirements when in a standby alignment. ItIt would be an abnormal activityto activity tofill fillthetheIsolation IsolationCondenser Condenserto tothe thetop top simply simplytotoachieve achieve aa slight slight increase increase in static head for the additional additional system leakage test.

system leakage test. As Asan anadditional additionalcomplication, complication, any any water water added added to to the the isolation isolation condenser condensershell shelltotoraise raiselevel levelabove abovethe thenormal normaloperating operatinglevel levelwould would subsequently have to be drained and processed processed by by radwaste.

radwaste.

In In summary, summary, imposing imposing aa largelarge transient transient on on the reactor plant to to accommodate the performance of the Isolation Condenser Condenser heat heatremoval removal capability capability verification verification at at a greater frequency than required required by by DNPS DNPS TS TS and andfilling filling thethe Isolation Isolation Condenser Condenser to the top to perform perform aa third third system system leakage test, present presenthardshiphardshipwithout without aa compensating compensating increase increaseinin and safety.

quality and 5.

S. Proposed Alternative and Basis for Use: Use:

As an alternative, Exelon Exelon Generation Generation Company, Company, LLC LLC (EGC) proposes proposes the the performance performanceof ofaa system leakage system leakagetest testusing usingaaVT-2 VT-2visual visualexamination examinationof of all all DNPS DNPS UnitsUnits 22 and and 33Isolation Isolation CondenserTest Condenser TestBlocks Blocks(i.e.,

(Le., Test TestBlocks Blocks 2(3)IC01 2(3)IC01 and and 2(3)IC02) 2(3)IC02) every 60 months months during during the performance of TS SR 3.5.3.4 versus once once per per inspection inspection periodperiod as as discussed discussedininTable Table IWD-2500-1.

IWD-2500-1.

discussedinin the As discussed theprevious previousparagraph, paragraph,during duringthe theDNPS DNPSfifth fifth ISI lSI interval interval EGC proposes proposes the leakage that the leakagetest testofofIsolation Isolation Condenser CondenserTest TestBlocks Blocks2(3)IC01 2(3)IC01 (i.e.,(Le., the theupper upperportion portionof of the Isolation the Isolation Condenser Condenserand andassociated associatedpiping)piping)will will only only be be performed performed once onceeveryevery60 60 months during months during the performance of TS SR 3.5.3.4 3.5.3.4 versusversus once onceper perinspection inspectionperiodperiodas as discussed discussedininTable TableIWD-2500-1.

IWD-2500-1.

During inspection periods where TS SR During SR 3.5.3.4 3.5.3.4 isis not not performed performed on on aaunit's unit'sIsolation Isolation Condenser,an Condenser, anadditional additionalVT-2 VT-2examination examinationwill will bebeperformed performedfor forTest TestBlocks Blocks2(3)IC02 2(3)IC02 (Le., the lower portion (i.e., portionof ofthetheIsolation IsolationCondensers Condensers and and associated piping). This associated piping). This leakage leakage will be performed with test will test with Isolation IsolationCondenser Condenser shell shell side water level at the normal standby standby level versus versus at at the the normal normal pressure pressurewhen whenthe thesystem systemisisininservice serviceperforming performingitsitsnormal normal operating function operating function or at the system pressure pressuredeveloped developedduring duringaatest testconducted conductedtotoverify verify system system operability operability as as discussed discussedininIWD-5221.

IWD-5221.

Page Page 44 of ofS 5

ATTACHMENT ATTACHMENT 10 CFR 50.55a 10 CFR SO.SSa Request Number Number 15R-04, ISR-04, Revision 11 Proposed Alternative Proposed Alternative In In Accordance with with 10 CFR SO.SSa{a){3){ii) 50.55a(a)(3)(ii)

--Hardship or Unusual Difficulty

--Hardship Difficulty without without Compensating Compensating Increase in Level Increase Level ofof Quality Quality and Safety--

Safety--

The proposed alternative The alternative isis based based on the hardship hardship imposed imposed by by the the performance performance of of the heat heat removal capability verification test at a greater frequency than required removal capability verification test at a greater frequency than required by DNPS TS by DNPS TS and fillingthe filling theIsolation IsolationCondenser Condenserto tothe thetop toptotoperform performaathirdthirdsystem system leakage leakage test without a compensating increase compensating increase in in quality quality and safety.

6.

Duration 6.

of Proposed Duration of Proposed Alternative:

Alternative:

Relief isis requested Relief requested for the Fifth Ten-Year Inspection Interval Fifth Ten-Year for DNPS, Interval for DNPS, Units Units 22 and and 3.

Precedents:

7. Precedents:

DNPS, Units DNPS, Units 2 and 3 fourth inspection intervalinterval Relief Request Request 14R-06 14R-06 was authorized authorized in in an NRC safety evaluation evaluation (SE) dated September 4, 2003. The fifth inspection September 4, 2003. The fifth inspection interval interval relief request relief request (i.e.,

(Le., 15R-04, Revision 1)

ISR-04, Revision 1) utilizes utilizes aa similar similar approach approach that was previously previously approved.

Page Page 5S of of 5S