ML20154M507: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:. _ . . _ . _ - __      _ _ ~ -  - -
{{#Wiki_filter:. _.. _
r-               Commonwealth Ediwn Company Braidwood Generating station -
_ _ ~ -
g           ' 41 4                 Route *I, Box 84
r-Commonwealth Ediwn Company Braidwood Generating station -
                                ' Braceville,IL 60407-9619 j_ .                    Tel 815-458-2801
g
          - (_,)-
' 41 4 Route *I, Box 84
' Braceville,IL 60407-9619 Tel 815-458-2801 j_.
- (_,)-
e October 15,1998 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 - 0001
e October 15,1998 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 - 0001


==Subject:==
==Subject:==
Revision K, Revision 0, and Revision P to the Improved Technical Specifications (ITS) Submittal T!                                           Byron Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-72 and NPF-77 p                                           NRC Docket Numbers: 50-456 and 50-457 v
Revision K, Revision 0, and Revision P to the Improved Technical Specifications (ITS) Submittal T!
Byron Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-72 and NPF-77 p
NRC Docket Numbers: 50-456 and 50-457 v


==Reference:==
==Reference:==
G. Stanley and K. Graesser (Commonwealth Edison) letter to NRC Document Control Desk, " Conversion to the Improved Standard Technical Specifications," dated December 13,1996 The purpose of this letter is to provide Revisions K,0, and P to the referenced ITS
G. Stanley and K. Graesser (Commonwealth Edison) letter to NRC Document Control Desk, " Conversion to the Improved Standard Technical Specifications," dated December 13,1996 The purpose of this letter is to provide Revisions K,0, and P to the referenced ITS submittal. ITS Revision K contains Commonwealth Edison's (Comed's) final Package g
,                                  submittal. ITS Revision K contains Commonwealth Edison's (Comed's) final Package g                                 Closeout for ITS Section 3.4. ITS Revision O is a cleanup package for ITS Sections 1.0/3.0/3.1/3.9/4.0. ITS Revision P contains Comed's final Package Closcout for ITS               /
Closeout for ITS Section 3.4. ITS Revision O is a cleanup package for ITS Sections 1.0/3.0/3.1/3.9/4.0. ITS Revision P contains Comed's final Package Closcout for ITS
/
Section 3.3.
Section 3.3.
Enclosure 1 contains ITS Revision K. Enclosure 2 contains ITS Revision O. Enclosure 3 contains ITS Revision P.
' contains ITS Revision K. Enclosure 2 contains ITS Revision O. Enclosure 3 contains ITS Revision P.
OO w..
OO w..73 Y.
73 Y.
r[-
r[-
        .p
.p
(
(
x)                   O
x)
                  '          9810200320 981015                   Y PDR       ADOCK 05000454 L P-                         PDR
O 9810200320 981015 Y
                                                                    }                                                                     .
PDR ADOCK 05000454 L P-PDR
i A Unicom Company
}
. i A Unicom Company


fx         Document Control Desk t/         October 15,1998 Page 2 -
fx Document Control Desk t/
These Revisions are being provided in the same ten-section format as the initial ITS submittal-I1
October 15,1998 Page 2 -
These Revisions are being provided in the same ten-section format as the initial ITS submittal-
: 1. Byron ITS
: 1. Byron ITS
: 2. Braidwood(Brwd)ITS
: 2. Braidwood(Brwd)ITS
Line 56: Line 62:
Please address any comments or questions regarding this matter to our Nuclear I icensing Department.
Please address any comments or questions regarding this matter to our Nuclear I icensing Department.
y3-
y3-
        !J -       Sincerely, 1
!J -
l l
Sincerely, T'.othy J. Tulon te Vice President Braidwood Nuclear Generating Station
T' .othy J. Tulon                                                                                   ;
. : ITS Revision K : ITS Revision 0 : ITS Revision P cc:
te Vice President Braidwood Nuclear Generating Station Enclosure 1: ITS Revision K Enclosure 2: ITS Revision 0 Enclosure 3: ITS Revision P cc:     NRC Regional Administrator-RegionIII Senior Resident Inspector - Braidwood Senior Resident Inspector- Byron Office of Nuclear Facility Safety -IDNS l'
NRC Regional Administrator-RegionIII Senior Resident Inspector - Braidwood Senior Resident Inspector-Byron Office of Nuclear Facility Safety -IDNS l'
i r~N
i r~N
      ,(     '
,(
l'
l'


un ..n - w . a-.-a,     .aa-.-~.- _. ,, m a ans a >x ..ea.~_ w - r . -ns ..a   +.t..e., .s s e .s.. ..x -
un
                                                                                                              .m.sa-... .-.._,..n.._.
..n w
a-.-a,
.aa-.-~.-
,, m a ans a
>x
..ea.~_
w - r. -ns..a
+.t..e.,
.s s e.s..
..x
.m.sa-...
.-.._,..n.._.
2
2
                          - ATTACHMENT 1                                                                                             I ITS SECTION 3.4 4
- ATTACHMENT 1 ITS SECTION 3.4 RAI REVISED RESPONSES 4
RAI REVISED RESPONSES 0
0 1
I 1
1 I
l l
O
l l
 
1 1
= _.. =
I O


          = _ . . =                                    -
== = - - - -
                                                                        == = - - - -
R sponse to-NRC RAI For ITS S:ction 3.4 09-Oct-98 l
R sponse to-NRC RAI For ITS S:ction 3.4                                   09-Oct-98 l
NRC RAI Number NRC issued Date RAI Status j
NRC RAI Number             NRC issued Date                           RAI Status                                               j i
i. I i
  ,,~_         3.4.1-01                     3/9'98                               Closed i.I
,, ~ _
  =( ,
3.4.1-01 3/9'98 Closed
= (
NRC Description ofissue DOCS L4 and Lil CTS 3/4.2.3 Action a.2 CTS 3/4.2.5 Action ITS 3.4.1 Action B DOC L4 is written tojustify the same change made to both CTS 3/4.2.3 Action a.2 and CTS 3.2.5 Actions. CTS 3.2.3 Action a.2 requires the reduction of THERMAL POWER to < 50% RTP and the reduction of the Power Range Neutron Flus-High Trip Setpoint to 55% RTP within the next 4 hours when RCS total flow is not within limit. CTS 3.2.5 Action requires the DNB related parameters restored within 2 hours or to reduce THERMAL POWER to less than 5% of RATED THERMAL
NRC Description ofissue DOCS L4 and Lil CTS 3/4.2.3 Action a.2 CTS 3/4.2.5 Action ITS 3.4.1 Action B DOC L4 is written tojustify the same change made to both CTS 3/4.2.3 Action a.2 and CTS 3.2.5 Actions. CTS 3.2.3 Action a.2 requires the reduction of THERMAL POWER to < 50% RTP and the reduction of the Power Range Neutron Flus-High Trip Setpoint to 55% RTP within the next 4 hours when RCS total flow is not within limit. CTS 3.2.5 Action requires the DNB related parameters restored within 2 hours or to reduce THERMAL POWER to less than 5% of RATED THERMAL
{
{
POWER within the next 4 hours. Both CTS Actions and 4 hour limit are changed to be ITS 3.4.1 Condition B which                     i specifies a Completion Time of 6 hours to reach Mcde 2. DOC Lil is written tojustify the same change but only to CTS 3.2.5 Actions. Comment: It is recommended that L4 justify Action 3.2.3 only and Li 1 continue tojustify Action 3.2.5 which would not require revision of the CTS markup.
POWER within the next 4 hours. Both CTS Actions and 4 hour limit are changed to be ITS 3.4.1 Condition B which i
Comed Response to issue Comed will revise DOC 3.4-L4 to onlyjustify CTS Action 3.2.3.a.2. DOC 3.4-L4 will be revised to state. " CTS Action 3.2.3.a.2 requires that when the RCS flowrate is outside the region of acceptable operation. within 2 hours reduce THERMAL POWER ... within the next 4 hours. NUREG LCO 3.4.1, Condition A states that with one of the DNB parameters not within limits, a Completion Time of 2 hours is provided to restore the parameter to within limits. In the es ent that Condition A is not met, Condition B requires the plant be placed in MODE 2 within 6 hours. ITS revises the CTS Completion Time from 4 hours to 6 hours, and therefore is considered a Less Restrictive change. Using the general rules of applicability, the unit must be placed in a Mode of non-applicability, whic'nin this case is Mode 2. Reaching MODE 2 in 6 hours is consistent with other LCOs that require the plant to be placed in MODE 2 from MODE 1. Therefore, the Completion Time of 6 hours is reasonable to reach the required unit conditions in an orderly manner." DOC 3.4-LI 1 will be
specifies a Completion Time of 6 hours to reach Mcde 2. DOC Lil is written tojustify the same change but only to CTS 3.2.5 Actions. Comment: It is recommended that L4 justify Action 3.2.3 only and Li 1 continue tojustify Action 3.2.5 which would not require revision of the CTS markup.
    ]   revised to state. " CTS Action 3.2.5 states that with any of the DNB related parameters exceeding its limit, restore the l
Comed Response to issue Comed will revise DOC 3.4-L4 to onlyjustify CTS Action 3.2.3.a.2. DOC 3.4-L4 will be revised to state. " CTS Action 3.2.3.a.2 requires that when the RCS flowrate is outside the region of acceptable operation. within 2 hours reduce THERMAL POWER... within the next 4 hours. NUREG LCO 3.4.1, Condition A states that with one of the DNB parameters not within limits, a Completion Time of 2 hours is provided to restore the parameter to within limits. In the es ent that Condition A is not met, Condition B requires the plant be placed in MODE 2 within 6 hours. ITS revises the CTS Completion Time from 4 hours to 6 hours, and therefore is considered a Less Restrictive change. Using the general rules of applicability, the unit must be placed in a Mode of non-applicability, whic' in this case is Mode 2. Reaching MODE 2 in 6 n
{Q   parameter to within its limit within 2 hours, or reduce THERMAL POWER to less than 5% of RTP within the next 4 hours.
hours is consistent with other LCOs that require the plant to be placed in MODE 2 from MODE 1. Therefore, the Completion Time of 6 hours is reasonable to reach the required unit conditions in an orderly manner." DOC 3.4-LI 1 will be
NUREG LCO 3.4.1, Condition A states that with one of the DNB parameters not within limits, a Completion Time of 2                 l hours is provided to restore the parameter to within limits. In the event that Condition A is not met. Condition B requires the   l plant be placed in MODE 2 within 6 hours. ITS revises the CTS Completion Time from 4 hours to 6 hours, and therefore is considered a Less Restrictive change. Using the general rules of applicability, the unit must be placed in a Mode of non-applicability, which in this case is Mode 2. Reaching MODE 2 in 6 hours is consistent with other LCOs that require the plant to be placed in MODE 2 from MODE 1. Therefore, the Completion Time of 6 hours is reasonable to reach the required unit conditions in an orderly manner." These changes will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
]
revised to state. " CTS Action 3.2.5 states that with any of the DNB related parameters exceeding its limit, restore the
{Q parameter to within its limit within 2 hours, or reduce THERMAL POWER to less than 5% of RTP within the next 4 hours.
l NUREG LCO 3.4.1, Condition A states that with one of the DNB parameters not within limits, a Completion Time of 2 hours is provided to restore the parameter to within limits. In the event that Condition A is not met. Condition B requires the plant be placed in MODE 2 within 6 hours. ITS revises the CTS Completion Time from 4 hours to 6 hours, and therefore is considered a Less Restrictive change. Using the general rules of applicability, the unit must be placed in a Mode of non-applicability, which in this case is Mode 2. Reaching MODE 2 in 6 hours is consistent with other LCOs that require the plant to be placed in MODE 2 from MODE 1. Therefore, the Completion Time of 6 hours is reasonable to reach the required unit conditions in an orderly manner." These changes will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
l 6
l 6
V I
V I
l
l


                      = = = = - - - . - - - _ . -                                  :        -  --
= = = = - - -. - - - _. -
Resp::nse to NRC RAI For ITS S2ction 3.4                             09-oct-98
Resp::nse to NRC RAI For ITS S2ction 3.4 09-oct-98
                                            .., .-L.   '~ ''^ " ~ .        .
.-L.
NRC RAI Number               NRC issued Date                         RAI Status g                 3.4.1-02                       3/9'98                               Closed                                       l l
'~ ''^ " ~.
k)'         NRC Description of issue DOC L35 JFD C6 l
NRC RAI Number NRC issued Date RAI Status g
CTS 4.2.3.5                                                                                                               i CTS 4.2.3.5 requires the determination of RCS total dow rate by a precision heat balance measurement after each fuel l
3.4.1-02 3/9'98 Closed k)'
loading and states that "The 24 hour completion time provisions of Specification 4.0.3 are not applicable" ITS SR 3.4.1.4 requires a precision heat balance measurement every 18 mor.ths and allows for the provisions ofITS SR 3.0.3 to apply.     ,
NRC Description of issue DOC L35 JFD C6 CTS 4.2.3.5 i
DOC L35 as submitted states a precision heat balance measurement will be performed per ITS SR 3.4.1.4. This is           !
CTS 4.2.3.5 requires the determination of RCS total dow rate by a precision heat balance measurement after each fuel loading and states that "The 24 hour completion time provisions of Specification 4.0.3 are not applicable" ITS SR 3.4.1.4 requires a precision heat balance measurement every 18 mor.ths and allows for the provisions ofITS SR 3.0.3 to apply.
acceptable; however, JFD C6 deletes the precision heat balace measurement. Also JFD C6 refers to TSTF 105 which has been rejected. Comment: Revise the submittal to adopt the STS and retain the CTS requirements. Make the justifications   ,
DOC L35 as submitted states a precision heat balance measurement will be performed per ITS SR 3.4.1.4. This is acceptable; however, JFD C6 deletes the precision heat balace measurement. Also JFD C6 refers to TSTF 105 which has been rejected. Comment: Revise the submittal to adopt the STS and retain the CTS requirements. Make the justifications for these two CTS changes consistent.
for these two CTS changes consistent.                                                                                     l Comed Response to issue Revised Response: Comed withdrew TSTF 105 changes from the ITS submittal and retained "by precision heat balance that" in ITS SR 3.4.1.4. LCO JFD 3.4-C6 and Bases JFD 3.4-C6 were deleted. This change is provided in our comprehensive ITS Section 3.4 closecut submittal Revision K.
Comed Response to issue Revised Response: Comed withdrew TSTF 105 changes from the ITS submittal and retained "by precision heat balance that" in ITS SR 3.4.1.4. LCO JFD 3.4-C6 and Bases JFD 3.4-C6 were deleted. This change is provided in our comprehensive ITS Section 3.4 closecut submittal Revision K.
Original Response: Comed will withdraw TSTF-105 changes from the ITS submittal and retain "by precision heat balance that" in ITS SR 3.4.1.4. CTS DOC LAIS, LCO JFD C6, and Bases JFD C6 will be deleted. This change will be provided in     i our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
Original Response: Comed will withdraw TSTF-105 changes from the ITS submittal and retain "by precision heat balance that" in ITS SR 3.4.1.4. CTS DOC LAIS, LCO JFD C6, and Bases JFD C6 will be deleted. This change will be provided in i
NRC RAI Number               NRC lssued Date                           RAI Status n     -
our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
3.4.1-03                     3/9/98                               Closed NRC Description of issue DOC Al.1 CTS 4.2.3.1 CTS 4.2.3.1 states "The provisions of Specification 4.0.4 are not applicable." This CTS requirement is deleted with an editorial AI justification rather than with a specific technicaljustification. Comment Please provide a technical justification for this CTS change.
NRC RAI Number NRC lssued Date RAI Status n
3.4.1-03 3/9/98 Closed NRC Description of issue DOC Al.1 CTS 4.2.3.1 CTS 4.2.3.1 states "The provisions of Specification 4.0.4 are not applicable." This CTS requirement is deleted with an editorial AI justification rather than with a specific technicaljustification. Comment Please provide a technical justification for this CTS change.
Comed Response to issue DOC 3.4-A3 discusses the deletion of this statement. The CTS Markup for CTS SR 4.2.3.1 will be revied to reDeet the correct referuce to DOC 3.4 A3 This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue DOC 3.4-A3 discusses the deletion of this statement. The CTS Markup for CTS SR 4.2.3.1 will be revied to reDeet the correct referuce to DOC 3.4 A3 This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
/
/U 2
U 2


Respons2 to NRC RAI For ITS Section 3A                                   09-Oci-98 NRC RAI Number                     NRC lssued Date                   RAI Status 3.4.1-04                         3l9'98                           Closed NRC Description ofissue JFD P2 JFD BP2 ITS 3.4.1, Applicability Note The Applicability Note is proposed to be moved to a place following the LCO statement as an editorial enhancement to
Respons2 to NRC RAI For ITS Section 3A 09-Oci-98 NRC RAI Number NRC lssued Date RAI Status l
                                                                                                                    ~
3.4.1-04 3 9'98 Closed NRC Description ofissue JFD P2 JFD BP2 ITS 3.4.1, Applicability Note The Applicability Note is proposed to be moved to a place following the LCO statement as an editorial enhancement to preclude misinterpretations ofITS SR 3.0.4. This technical basis is unacceptable. This change occurs trequently m this
preclude misinterpretations ofITS SR 3.0.4. This technical basis is unacceptable. This change occurs trequently m this submittal: therefore, this is a generic change and it should be submitted for review under the STS generic change process.
~
submittal: therefore, this is a generic change and it should be submitted for review under the STS generic change process.
Comment: Revise the submittal to adopt the STS format. The response to this comment should be global over the enttre submittal.
Comment: Revise the submittal to adopt the STS format. The response to this comment should be global over the enttre submittal.
Comed Response to issue No change. Because the relocation of the Note from the Applicability to the LCO has been approved on a plant specific basis for previous submittals (e.g., Ginr.a. Zion, and Vogtle). the WOG determined that this change was below the threshold for a generic change. Therefore, all of the Notes in the Applicability section of the NUREG LCOs have been moved to the LCO section of the ITS LCOs either plant specifically or as a result of a TSTF that was incorporated. The Note applies to exceptions to the ent;re LCO and not to exceptions to the Applicability. Having a Note that modifies the Applicability requirements could imply an exception to the Applicability and thus, could lead to a misinterpretation of SR 3.0.4. Placing the Note in the LCO Section prevents misinterpretation of SR 3.0.4. The following is a list ofITS LCOs in which this convention was adopted. LCOs in which the Note was moved by a plant specific change: 3.1.5,3.1.6.3.3.9,3.4.1,3.4.10, 3.4.12. and 3.9.6 (SR Note moved to LCO); LCOs in which the Note was moved by a TSTF: 3.2.3. 3.5.2. and 3.5.3 (SR Note moved to LCO); LCOs in which the Note was added by a plant specific change: 3.7.12,3.8.5 and 3.9.4; LCOs in which the Note was added by a TSTF: 3.6.3. Comed continues to pursue this change. (See RAls 3.1.5-01,3.1.6-01,3.4.10-03, and'3.4.12-01 item b.)
Comed Response to issue No change. Because the relocation of the Note from the Applicability to the LCO has been approved on a plant specific basis for previous submittals (e.g., Ginr.a. Zion, and Vogtle). the WOG determined that this change was below the threshold for a generic change. Therefore, all of the Notes in the Applicability section of the NUREG LCOs have been moved to the LCO section of the ITS LCOs either plant specifically or as a result of a TSTF that was incorporated. The Note applies to exceptions to the ent;re LCO and not to exceptions to the Applicability. Having a Note that modifies the Applicability requirements could imply an exception to the Applicability and thus, could lead to a misinterpretation of SR 3.0.4. Placing the Note in the LCO Section prevents misinterpretation of SR 3.0.4. The following is a list ofITS LCOs in which this convention was adopted. LCOs in which the Note was moved by a plant specific change: 3.1.5,3.1.6.3.3.9,3.4.1,3.4.10, 3.4.12. and 3.9.6 (SR Note moved to LCO); LCOs in which the Note was moved by a TSTF: 3.2.3. 3.5.2. and 3.5.3 (SR Note moved to LCO); LCOs in which the Note was added by a plant specific change: 3.7.12,3.8.5 and 3.9.4; LCOs in which the Note was added by a TSTF: 3.6.3. Comed continues to pursue this change. (See RAls 3.1.5-01,3.1.6-01,3.4.10-03, and'3.4.12-01 item b.)
[       NRC RAI Number                     NRC lssued Date                   RAI Status 3.4.1-05                         3/9/98                           Closed NRC Description of issue JFD BPI Bases discussion of Applicable Safety Analyses, STS page B 3.4-2 in Applicable Safety Analyses, the second and third sentences regarding the DNB design criterion are not adopted. Why not state the plant specific DNB design criterion as the acceptance limit? Also, this is a not an editorial change but a technical change without a specific technicalju::tification. Comment: Revise the Bases to be consistent with the STS.
[
NRC RAI Number NRC lssued Date RAI Status 3.4.1-05 3/9/98 Closed NRC Description of issue JFD BPI Bases discussion of Applicable Safety Analyses, STS page B 3.4-2 in Applicable Safety Analyses, the second and third sentences regarding the DNB design criterion are not adopted. Why not state the plant specific DNB design criterion as the acceptance limit? Also, this is a not an editorial change but a technical change without a specific technicalju::tification. Comment: Revise the Bases to be consistent with the STS.
Comed Response to issue Revised Response: Comed incorporated the plant specific value of 1.5 in the brackets and added Bases JFD 3.4 B3. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
Comed Response to issue Revised Response: Comed incorporated the plant specific value of 1.5 in the brackets and added Bases JFD 3.4 B3. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
Original Response: Comed will revise the Bases to be consistent with the STS, incorporating the ' plant specific value of "1.5" in the brackets. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
Original Response: Comed will revise the Bases to be consistent with the STS, incorporating the ' plant specific value of "1.5" in the brackets. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
t .
t
\)
\\)
3
3


l R:sponse to NRC RAITE ITS S:ction 3.4                                     09-oct-98 l                       -- .=_:.--         ---==_=.=:- =_ =_
l R:sponse to NRC RAITE ITS S:ction 3.4 09-oct-98 l
l             NRC RAI Number               NRC issued Date                         RAI Status 3.4.1-06                   3'9'98                               Closed NRC description ofissue JFD BP45 '
--.=_:.--
---==_=.=:- =_ =_
l NRC RAI Number NRC issued Date RAI Status 3.4.1-06 3'9'98 Closed NRC description ofissue JFD BP45 '
Bases discussion of Applicable Safety Analyses. STS page B 3.4-2 In the Applicable Safety Analyses, the second paragraph has been replaced with the insert B3.4 2A. Why do the LCO values l
Bases discussion of Applicable Safety Analyses. STS page B 3.4-2 In the Applicable Safety Analyses, the second paragraph has been replaced with the insert B3.4 2A. Why do the LCO values l
not match the value assumed in the safety analyses and reported measurement accuracy in the first and the second paragraph. For example, it appears that the pressurizer limit LCO value should be > 2233.7 (2207 - 26.7) with the reported       )
not match the value assumed in the safety analyses and reported measurement accuracy in the first and the second paragraph. For example, it appears that the pressurizer limit LCO value should be > 2233.7 (2207 - 26.7) with the reported
)
measurement accuracy. Comment: Please revise the text in the insert to clarify the addition of this plant specific text to the Bases.
measurement accuracy. Comment: Please revise the text in the insert to clarify the addition of this plant specific text to the Bases.
          . Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, Comed added a parenthetical psig reference to 2207 psia and changed 26.7 psia to 26.7 psi. This change is provided in our comprehensive ITS Section 3.4 closeout subminal Resision K.
. Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, Comed added a parenthetical psig reference to 2207 psia and changed 26.7 psia to 26.7 psi. This change is provided in our comprehensive ITS Section 3.4 closeout subminal Resision K.
Original Response: No change. ITS LCO 3.4.1 states. "RCS DNB parameters for pressurizer pressure. . shall be within the limits specified below; a. Pressurizer pressure 2219 psig . . ." The Applicable Safety Analpes Section of the Bases for ITS       j LCO 3.4.1 states," Safety Analyses assumed a value of 2207 psia. This value is bounded by the LCO value of 2210 psig               I assuming a measurement accuracy ofless than 26.7 psia." The NRC RAl asked why the pressurizer pressure LCO value did not match the Bases value, stating that the LCO value should be 2233.7 based on using the safety analyses value of 2207 +
Original Response: No change. ITS LCO 3.4.1 states. "RCS DNB parameters for pressurizer pressure.. shall be within the limits specified below; a. Pressurizer pressure 2219 psig..." The Applicable Safety Analpes Section of the Bases for ITS j
LCO 3.4.1 states," Safety Analyses assumed a value of 2207 psia. This value is bounded by the LCO value of 2210 psig assuming a measurement accuracy ofless than 26.7 psia." The NRC RAl asked why the pressurizer pressure LCO value did not match the Bases value, stating that the LCO value should be 2233.7 based on using the safety analyses value of 2207 +
26.7. It is true that adding the safety analyses value (2207 psia) to the measurement accuracy ofless than 26.7 psia yielding a total of 2233.7 psia. The pressurizer value in the ITS is 2219 psig. Therefore,2233.7 psia - 14.7 = 2219 psig. Therefore, the LCO value matches the Bases value, and no change is required.
26.7. It is true that adding the safety analyses value (2207 psia) to the measurement accuracy ofless than 26.7 psia yielding a total of 2233.7 psia. The pressurizer value in the ITS is 2219 psig. Therefore,2233.7 psia - 14.7 = 2219 psig. Therefore, the LCO value matches the Bases value, and no change is required.
                                          .=.::=_.-=:==-==-                                . -    .-
.=.::=_.-=:==-==-
NRC RAI Number             NRC issued Date                         RAI Status p)
NRC RAI Number NRC issued Date RAI Status 3.4.1-07 3/9/98 Closed p)
(f 3.4.1-07 NRC Description of Issue 3/9/98                               Closed JFD BP51 Bases discussion of Actions STS page B 3.4-3 in the Bases discussion of Required Action A.I. all three paragraphs omit portions of the STS text. The deleted text explains the purpose of the Required Actions. JFD PSI states provides no explanation for the these omissions. Comment:
'(f NRC Description of Issue JFD BP51 Bases discussion of Actions STS page B 3.4-3 in the Bases discussion of Required Action A.I. all three paragraphs omit portions of the STS text. The deleted text explains the purpose of the Required Actions. JFD PSI states provides no explanation for the these omissions. Comment:
Revise the Bases to confonn to the STS.
Revise the Bases to confonn to the STS.
Comed Response to issue Comed will revise the Bases to conform to the STS. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the Bases to conform to the STS. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Line 137: Line 163:
4
4


            = = = = = = = = _ .                     . = . = _ - - _ = -     .
= = = = = = = = _.
Respons: to NRC RAI For ITS S:ction 3.4                                 oo-octm
. =. = _ - - _ = -
                                -. 2.   - .- -
Respons: to NRC RAI For ITS S:ction 3.4 oo-octm 2.
                                                                            ~ _. _ _
~ _. _ _
NRC RAI Number             NRC lisued Date                         RAI Status y          3.4.2-01                     3!9/98                               Closed NRC Description of issue DOJ LA29 DOC M9 JFD C2 (Based on superceded TSTF-27 Rev i ?)
NRC RAI Number NRC lisued Date RAI Status 3.4.2-01 3!9/98 Closed y
NRC Description of issue DOJ LA29 DOC M9 JFD C2 (Based on superceded TSTF-27 Rev i ?)
CTS 4.1.1.4.b STS Sk 3 4.2.1 DOC LA29 is not shown on the CTS markup. In addition. the text of LA29 contradicts JFD C2 which is based on TSTF 27 treplaced by Res 2 which is pending). Comment: Withdraw the change to CTS 4.1.1.4.b and adopt STS SR 3.4.2.1.
CTS 4.1.1.4.b STS Sk 3 4.2.1 DOC LA29 is not shown on the CTS markup. In addition. the text of LA29 contradicts JFD C2 which is based on TSTF 27 treplaced by Res 2 which is pending). Comment: Withdraw the change to CTS 4.1.1.4.b and adopt STS SR 3.4.2.1.
Comed Response to issue DOC 3.4 M9 will be revised to state. " CTS 4.l.l.4.b requires the verification of the RCS average temperature every 30 minutes when the reactor i; tritical and the Reactor Coolant System Tavg is less than 557 F with the Ta c Tref deviation alarm not reset. The proposed ITS SR 3.4.2.1 requires verification of the RCS average temperature every 12 hours. " The CTS Markup will be revised such that DOC 3.4-LA29 refers to the Deviation Alarm, and DOC 3.4-M9 only refers to the "12 hours." This is consistent with similar changes in TSTF-27 for ITS LCOs 3.2.3 (CTS SR 4.2.1.1.b) and 3.2.4 (CTS SR 4.2.4.1.b). This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed continues to pursue this change.
Comed Response to issue DOC 3.4 M9 will be revised to state. " CTS 4.l.l.4.b requires the verification of the RCS average temperature every 30 minutes when the reactor i; tritical and the Reactor Coolant System Tavg is less than 557 F with the Ta c Tref deviation alarm not reset. The proposed ITS SR 3.4.2.1 requires verification of the RCS average temperature every 12 hours. " The CTS Markup will be revised such that DOC 3.4-LA29 refers to the Deviation Alarm, and DOC 3.4-M9 only refers to the "12 hours." This is consistent with similar changes in TSTF-27 for ITS LCOs 3.2.3 (CTS SR 4.2.1.1.b) and 3.2.4 (CTS SR 4.2.4.1.b). This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed continues to pursue this change.
NRC RAI Number               NRC issued Date                         RAI Status 3.4.2-02                     3/9/98                               Closed NRC Description of issue JFD BPI Bases for Applicability ofITS 3.4 't. STS markup pages B 3.4 7 and B 3.4 8 V The ITS Bases does not adopt the second paragraph of the Bases for the Applicability of STS 3.4.2 based upon an editorial changejustification. This omission, however, is a technical change and has not been adequatelyjustified. Furthermore, this paragraph is applicable to Byron and Braidwood because STS 3.1.10 (equivalent to CTS 3.10.3) is adopted as ITS 3.1.8.
NRC RAI Number NRC issued Date RAI Status 3.4.2-02 3/9/98 Closed NRC Description of issue JFD BPI Bases for Applicability ofITS 3.4 't. STS markup pages B 3.4 7 and B 3.4 8 V
The ITS Bases does not adopt the second paragraph of the Bases for the Applicability of STS 3.4.2 based upon an editorial changejustification. This omission, however, is a technical change and has not been adequatelyjustified. Furthermore, this paragraph is applicable to Byron and Braidwood because STS 3.1.10 (equivalent to CTS 3.10.3) is adopted as ITS 3.1.8.
Comment: Revise the Bases to adopt the omitted STS paragraph.
Comment: Revise the Bases to adopt the omitted STS paragraph.
Comed Response to issue Comed will revise the Bases to adopt the omitted STS paragraph. This change will be provided in our comprehensive ITS               I Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the Bases to adopt the omitted STS paragraph. This change will be provided in our comprehensive ITS I
O V
Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
l 5
OV l
5


    --            _                .    -          . - - -                .    ~. -.               -              .-        .- . _
~. -.
Response to NRC .RAI For ITS Ssetion 3.4                                     09-oct-98 r
Response to NRC.RAI For ITS Ssetion 3.4 09-oct-98 r
                        =     u-          --    -
=
: r = m :-- -      . . . - -
u-
: r = m :-- -
(
(
NRC RAI Number             NRC Issued Date                         RAI Status 3.4.3-01                   3/9/98                               Closed NRC Description ofissue DOC Mil CTS 3.4.9.1 Action ITS 3.4.3 Action C CTS 3.4.9.1 Action requires an engineering evaluation to be performed, in accordance with the Applicability of"At all times", whenever the pressure or temperature limits for the RCS have been exceeded; however, there is no explicit time hmit provided to complete this evaluation. If these limits have been exceeded with the unit in a condition other than in Mode 1. 2.
NRC RAI Number NRC Issued Date RAI Status 3.4.3-01 3/9/98 Closed NRC Description ofissue DOC Mil CTS 3.4.9.1 Action ITS 3.4.3 Action C CTS 3.4.9.1 Action requires an engineering evaluation to be performed, in accordance with the Applicability of"At all times", whenever the pressure or temperature limits for the RCS have been exceeded; however, there is no explicit time hmit provided to complete this evaluation. If these limits have been exceeded with the unit in a condition other than in Mode 1. 2.
3 or 4 Required Action C.) for ITS 3.4.3 requires action be initiated immediately to restore compliance with the limits for the RCS and Require Action C.2 requires the determination that the RCS is acceptable for continued operation prior to the unit entering Mode 4. The DOC states " CTS 3.4.9.1 does not specify any required action whenever the pressure or tenperature limits for the RCS have been exceeded in a specified condition other than in Mode 1,2,3. or 4. or Mode 5 with RCS pressure 500 psig." This statement ar pears to be in error since the CTS has the same Action regardless of the unit's operating Mode, if the RCS limits are exceeded. Comment: Please revise the submittal with a revised technicaljustification.
3 or 4 Required Action C.) for ITS 3.4.3 requires action be initiated immediately to restore compliance with the limits for the RCS and Require Action C.2 requires the determination that the RCS is acceptable for continued operation prior to the unit entering Mode 4. The DOC states " CTS 3.4.9.1 does not specify any required action whenever the pressure or tenperature limits for the RCS have been exceeded in a specified condition other than in Mode 1,2,3. or 4. or Mode 5 with RCS pressure 500 psig." This statement ar pears to be in error since the CTS has the same Action regardless of the unit's operating Mode, if the RCS limits are exceeded. Comment: Please revise the submittal with a revised technicaljustification.
Comed Response to issue Comed agrees and will revise DOC Mil to state, " CTS LCO 3.4.9.1 does not specify a completion time for whenever the pressure or temperature limits for the RCS have beer exceeded in a specified condition other than in Mode 1,2,3, or 4 or Mode 5. Condition C for ITS 3.4.3 requires that action be initiated immediately to restore compliance with the pressure and temperature limits for the RCS if these limits have been exceeded with the unit in a condition other than in Mode 1,2,3 or
Comed Response to issue Comed agrees and will revise DOC Mil to state, " CTS LCO 3.4.9.1 does not specify a completion time for whenever the pressure or temperature limits for the RCS have beer exceeded in a specified condition other than in Mode 1,2,3, or 4 or Mode 5. Condition C for ITS 3.4.3 requires that action be initiated immediately to restore compliance with the pressure and temperature limits for the RCS if these limits have been exceeded with the unit in a condition other than in Mode 1,2,3 or
: 4. Condition C requires the immediate initiation of action to restore parameters to within limits and the determination that the RCS is acceptable for continued operation prior to the unit entering MODE 4. These requirements are necessary to ensure that the RCPB is retumed to a condition that has been verified by the stress analysis and that the RCPB integrity remains acceptable. This change represents a more restrictive change." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
: 4. Condition C requires the immediate initiation of action to restore parameters to within limits and the determination that the RCS is acceptable for continued operation prior to the unit entering MODE 4. These requirements are necessary to ensure that the RCPB is retumed to a condition that has been verified by the stress analysis and that the RCPB integrity remains acceptable. This change represents a more restrictive change." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
  /
/\\
  \      NRC RAI Number             NRC lssued Date                         RAI Status                                                 l 1
NRC RAI Number NRC lssued Date RAI Status 3.4.3-02 3/9/98 Closed NRC Description of issue Bases for ITS SR 3.4.3.1, STS Bases markup page B 3.415 The second paragraph has not been adopted; however, there is nojustification for this deviation from the STS. There is no identity for tracking this JFD change. Comment: Please revise the submittal to provide a technicaljustification for this JFD or adopt the STS.
3.4.3-02                   3/9/98                               Closed                                                   l
<      NRC Description of issue Bases for ITS SR 3.4.3.1, STS Bases markup page B 3.415 The second paragraph has not been adopted; however, there is nojustification for this deviation from the STS. There is no identity for tracking this JFD change. Comment: Please revise the submittal to provide a technicaljustification for this JFD or adopt the STS.
1 Comed Response to Issue Corr.Ed will revise the submittal to adopt the STS. This change will be provided h our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
1 Comed Response to Issue Corr.Ed will revise the submittal to adopt the STS. This change will be provided h our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
V 6
V 6


Response to NRC RAI For ITS Section 3.4                                   09-octas
Response to NRC RAI For ITS Section 3.4 09-octas
_ __ c               ,
_ __ c j
j NRC RAI Number               NRC issued Date                                 RAI Status                                         l 3.4.4-01                     3'9'98 p)
NRC RAI Number NRC issued Date RAI Status 3.4.4-01 3'9'98 Closed p)
F Closed
F(/
(/     NRC Description of issue JFD BP3                                                                                                                             l Bases for ITS LCO 3.4.4, STS Bases markup pages B 3.4-18 and B 3.4-19                                                             )
NRC Description of issue JFD BP3 Bases for ITS LCO 3.4.4, STS Bases markup pages B 3.4-18 and B 3.4-19
: 1. In the first paragraph, the last sentence is not adopted and the BP3 insert is added. The iurt does state that in addition to all loops in operation that they are also Operable. Secondly. "all" loops need to be stated i , "four" loops are Operable to
)
        . satisfy the movement of this requirement from CTS 3.2.3 to the Bases of 3.4.4 as descrikd in DOC LA 17. Comment:
: 1. In the first paragraph, the last sentence is not adopted and the BP3 insert is added. The iurt does state that in addition to all loops in operation that they are also Operable. Secondly. "all" loops need to be stated i, "four" loops are Operable to
. satisfy the movement of this requirement from CTS 3.2.3 to the Bases of 3.4.4 as descrikd in DOC LA 17. Comment:
Revise the Bases as indicated.
Revise the Bases as indicated.
: b. In the second paragraph, when referring to an Operable SG the phrase "in accor/.ance with the Steam Generator Tube               ;
: b. In the second paragraph, when referring to an Operable SG the phrase "in accor/.ance with the Steam Generator Tube Surveillance Program" is replaced with "providing the necessary heat transfer cap 4bility." These phrases are not techmcally equivalent. This difference is notjustifiable as an editorial enhan tement as indirated by JFD BP3. It is recommended tnat both phrases be used to define an Operable SG rather than one phrase in lieu of the other. Comment: Please resise the submittal to adopt the STS text.
Surveillance Program" is replaced with "providing the necessary heat transfer cap 4bility." These phrases are not techmcally equivalent. This difference is notjustifiable as an editorial enhan tement as indirated by JFD BP3. It is recommended tnat both phrases be used to define an Operable SG rather than one phrase in lieu of the other. Comment: Please resise the submittal to adopt the STS text.
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be prc vided in our comprehensive ITS Section 3.4 closeodt submittal revision upon NRC's concurrence with the Comed Response i to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be prc vided in our comprehensive ITS Section 3.4 closeodt submittal revision upon NRC's concurrence with the Comed Response i to the ITS Section 3.4 RAl.
NRC RAI Number               NRC issued Date                                 RAI Status 3.4.5                   3/9/98                                     Closed NRC Description ofIssue DOC L3 s    DOC L12
NRC RAI Number NRC issued Date RAI Status 3.4.5 3/9/98 Closed NRC Description ofIssue DOC L3 DOC L12 s
  '/     DOC L23                                                                                                                            I C} . JFD P6 l
'/C}.
JFD BP6                                                                                                                             j ITS 3.4.5 Actions                                                                                                                   j CTS 3/4.4.1.2 Actions ITS 3.4.5 and associated Bases are to be revised to separately address the condition of one RCS loop not in operation with the rod control system incapable of rod withdrawal and two RCS loops not in operation with the rod control system capable of rod withdraw. Note: These changes are in addition to an unapproved generic change (TSTF-87 Rev !); and also, these are not plant specific requirements because they are not part of the current licensing basis. This "P" difference is miscategorized under the NEl 96-06 guidelines of Section 2.7, Deviations from the Applicable ISTS. It is a "C" difference. Note that TSTF-87 Revision 2 was approved 10/3/97. Comment: Revise the submittal to adopt Rev 2 to TSTF-87 consistent with plant design.
DOC L23 JFD P6 JFD BP6 j
<        Note to TSB reviewer: Ffollowing Comed's response and before closing this comment, review the revised Actions ofITS 3.4.5 to ensure consistency with either the CTS or Rev 2 to TSTF-87.
ITS 3.4.5 Actions j
Comed Response to issue                         ,
CTS 3/4.4.1.2 Actions ITS 3.4.5 and associated Bases are to be revised to separately address the condition of one RCS loop not in operation with the rod control system incapable of rod withdrawal and two RCS loops not in operation with the rod control system capable of rod withdraw. Note: These changes are in addition to an unapproved generic change (TSTF-87 Rev !); and also, these are not plant specific requirements because they are not part of the current licensing basis. This "P" difference is miscategorized under the NEl 96-06 guidelines of Section 2.7, Deviations from the Applicable ISTS. It is a "C" difference. Note that TSTF-87 Revision 2 was approved 10/3/97. Comment: Revise the submittal to adopt Rev 2 to TSTF-87 consistent with plant design.
Comed wi!I revise LCO and Bases JFDs 3.4-C10 to reference TSTF 87, Revision 2. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI. (See RAI 3.4-01 item 9.) However, Comed continues to pursue the plant specific changes associated with LCO and Bases JFDs 3.4-P6.
Note to TSB reviewer: Ffollowing Comed's response and before closing this comment, review the revised Actions ofITS 3.4.5 to ensure consistency with either the CTS or Rev 2 to TSTF-87.
I l
Comed Response to issue Comed wi!I revise LCO and Bases JFDs 3.4-C10 to reference TSTF 87, Revision 2. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI. (See RAI 3.4-01 item 9.) However, Comed continues to pursue the plant specific changes associated with LCO and Bases JFDs 3.4-P6.
1 G(
G(
l I
~
1
~                                                                                                                                             !


n                     e x == , , _ . . . _           . _ _                  _____=-#,--.
n e x==,, _... _
g                                                         : Response to NRC RAl For ITS Section' 3.4                                   09 Oct 98 l-                                   ._  N.__.           2_-..      -:_        .-
_____=-#,--.
NRC RAI Number             NRC lasued Date                         RAI Status y<                   ' 3.4.5 02                     - 3'9'98                         Closed
g
(         ---
: Response to NRC RAl For ITS Section' 3.4 09 Oct 98 l-N.__.
NRC Description of issue l                   JFD P1 l
2_-.
ll                ' JFD T[1 JFD 19?!
NRC RAI Number NRC lasued Date RAI Status y<
l ITS LCO 3,1.5.a and 3.4.5.b l
' 3.4.5 02
1 f a -The word " Operable" has been inserted before "RCS loop (s)" in LCO 3.4.5. This word is redundant to the LCO statement which already states "RCS loops shall be Operable". The word insertion is not accepted.
- 3'9'98 Closed
(
NRC Description of issue l
JFD P1 ll
' JFD T[1 JFD 19?!
l ITS LCO 3,1.5.a and 3.4.5.b 1
f a -The word " Operable" has been inserted before "RCS loop (s)" in LCO 3.4.5. This word is redundant to the LCO statement which already states "RCS loops shall be Operable". The word insertion is not accepted.
: b. ITS LCO 3.4.5 Note b
: b. ITS LCO 3.4.5 Note b
                  . CTS 3.4.1.2 Footnote
. CTS 3.4.1.2 Footnote
* item (2)
* item (2)
The ITS note is changed as follows " Core outlet temperature is maintained at least 100F below saturation temperature by 100F." The CTS requirement for this note is identical in wording to the STS text. There is no editorial enhancement
The ITS note is changed as follows " Core outlet temperature is maintained at least 100F below saturation temperature by 100F." The CTS requirement for this note is identical in wording to the STS text. There is no editorial enhancement
                  ; perceived in this change. Changes are not accepted.                                                                             ;
; perceived in this change. Changes are not accepted.
: c. ~ Bases ITS LCO 3.4.$, STS Bases markup page B 3.4-23 In the fifth paragraph, item t> is reworded to conform to LCO Note b. This change is also not accepted.                         l Comment: For these three items, revise the submittal to adopt the STS text.                                                     !
: c. ~ Bases ITS LCO 3.4.$, STS Bases markup page B 3.4-23 In the fifth paragraph, item t> is reworded to conform to LCO Note b. This change is also not accepted.
                  ' Comed Response to issue                                                                                                         j Revised Response: Per discussions with the NRC Reviewer, Comed retained the word " OPERABLE". In addition. ITS l      .
Comment: For these three items, revise the submittal to adopt the STS text.
LCOs 3.4.5. 3.4.6,3.4.7iand 3.4.8 Note b was revised to state that the core outlet temperature is maintained greater that, or   i l .. q       ' equal to 10'F below saturation temperature. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
' Comed Response to issue j
' (f Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.6-02,3.4.8-02, and 3.4.8-03.)
Revised Response: Per discussions with the NRC Reviewer, Comed retained the word " OPERABLE". In addition. ITS LCOs 3.4.5. 3.4.6,3.4.7iand 3.4.8 Note b was revised to state that the core outlet temperature is maintained greater that, or l
i l.. q
' equal to 10'F below saturation temperature. This change is provided in our comprehensive ITS Section 3.4 closcout
' (f submittal Revision K.
Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.6-02,3.4.8-02, and 3.4.8-03.)
l l
l l
t 8
t 8
l
l


l
\\
                                                                            - - - . . .                                                    \
R spanse to NRC RAI For ITS S:ction 3.4 09-Oci 98
R spanse to NRC RAI For ITS S:ction 3.4                                   09-Oci 98       )
= = = -
                                      .      _      = = = -                  -
NRC RAI Number -
NRC RAI Number -           NRC issued Date                               RAI Status
NRC issued Date RAI Status
  ;p               3.4.5-03                   3/9'98                                   Closed                                           1 NRC Description ofIssue DOC LS .
;p 3.4.5-03 3/9'98 Closed 1
NRC Description ofIssue DOC LS.
JFD B3 JFD BB3 ITS SR 3.4.5.2 CTS 4.4.1.2.2 Bases for ITS SR 3.4.5.2, STS Bases marktip page B 3.4-26
JFD B3 JFD BB3 ITS SR 3.4.5.2 CTS 4.4.1.2.2 Bases for ITS SR 3.4.5.2, STS Bases marktip page B 3.4-26
: a. This change adds plant specific SG secondary side water level values which are different from those stated in the CTS.
: a. This change adds plant specific SG secondary side water level values which are different from those stated in the CTS.
Line 221: Line 258:
: b. The Bases for ITS SR 3.4.5.2 differs from the STS to conform to the proposed pbnt specific SG secondary side water levels values which are not the same as those stated in the CTS requirements. Comment: How was this change approved by the NRC five years ago but never incorporated into the CTS? Submit additional technicaljustification for this change.
: b. The Bases for ITS SR 3.4.5.2 differs from the STS to conform to the proposed pbnt specific SG secondary side water levels values which are not the same as those stated in the CTS requirements. Comment: How was this change approved by the NRC five years ago but never incorporated into the CTS? Submit additional technicaljustification for this change.
Comed Response to Issue No change. NRC SER and Amendments 34 (Braidwood) and 45 (Byron), dated April 6,1992 approved Comed's request to change the Steam Generator (SG) secondary side narrow range water level to be greater than or equal to 33% for Unit 1 (Westinghouse D4 SGs) and 37% for Unit 2 (Westinghouse D5 SGs). The difference in SG level values between Unit One (41% to 33%) and Unit Two (18% to 37%) is attributable to the CTS LAR encompassing water level serpoint optimization on both units, and SG level tap relocation on Unit Two only. This change was accurately made in CTS Tables 2.2 1 and 3.3-
Comed Response to Issue No change. NRC SER and Amendments 34 (Braidwood) and 45 (Byron), dated April 6,1992 approved Comed's request to change the Steam Generator (SG) secondary side narrow range water level to be greater than or equal to 33% for Unit 1 (Westinghouse D4 SGs) and 37% for Unit 2 (Westinghouse D5 SGs). The difference in SG level values between Unit One (41% to 33%) and Unit Two (18% to 37%) is attributable to the CTS LAR encompassing water level serpoint optimization on both units, and SG level tap relocation on Unit Two only. This change was accurately made in CTS Tables 2.2 1 and 3.3-
: 4. However, CTS page 3/4 4-4 for CTS SR 4.4.1.3.2 was inadvertently tiot changed. In developing the CTS markup for the conversion to ITS, CTS page 3/4 4-4 was used and was marked up to reflect the correct values as approved in Amendments j.
: 4. However, CTS page 3/4 4-4 for CTS SR 4.4.1.3.2 was inadvertently tiot changed. In developing the CTS markup for the conversion to ITS, CTS page 3/4 4-4 was used and was marked up to reflect the correct values as approved in Amendments p) 34 and 45. Although this CTS SR contained the incorrect values, the plants administratively control the water level at greater
p)
: j. (
(
than or equal to 41% which is more conservative. Comed continues to pursue this change. (See RAI 3.4.7-04.)
34 and 45. Although this CTS SR contained the incorrect values, the plants administratively control the water level at greater than or equal to 41% which is more conservative. Comed continues to pursue this change. (See RAI 3.4.7-04.)
NRC RAI Number NRC issued Date RAI Status j
NRC RAI Number             NRC issued Date                               RAI Status                                         j 3.4.5-04                   3/9/98                                   Closed NRC Description of Issue                                                                                                       I JFD BPI Bases for ITS LCO 3.4.5, STS Bases markup page B 3.4 23 in the last paragraph, when referring to an Operable SG, the phrase "in accordance with the Steam Generator Tube Surveillance Program" was not adopted. This phrase is important for stating u6c what additional conditions the SG must be Operable for this LCO. Also, JFD BPI does not adequately justify this difference. Comment: Revise the Bases to adopt the STS text.
3.4.5-04 3/9/98 Closed NRC Description of Issue JFD BPI Bases for ITS LCO 3.4.5, STS Bases markup page B 3.4 23 in the last paragraph, when referring to an Operable SG, the phrase "in accordance with the Steam Generator Tube Surveillance Program" was not adopted. This phrase is important for stating u6c what additional conditions the SG must be Operable for this LCO. Also, JFD BPI does not adequately justify this difference. Comment: Revise the Bases to adopt the STS text.
Comed Response to issue Comed will revise the Bases to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
Comed Response to issue Comed will revise the Bases to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
O V
OV 9
9


(                         ,.    -          . - , . . . . , - . . . .                      _
(
Responsa to NRC RAI For ITS Stetion 3.4                                   09-ocim l
l Responsa to NRC RAI For ITS Stetion 3.4 09-ocim NRC RAI Number NRC issued Date -
NRC RAI Number             NRC issued Date -
RAI Status
RAI Status
                -3.4.5-05                   3'9'98                                 Closed
! c)
! {V c)  NRC D'escription of Issue JFD BPI l       Bases for ITS SR 3.4.5.3, STS Bases markup page B 3.4-26 l
-3.4.5-05 3'9'98 Closed
The Bases discussion reduces requirements about how the safety analysis limits are met and adds a new basis for the 7 day l       Frecuency. JFD BPI does not adequatelyjustify these technical differences from the STS Bases. Comment: Resise the                     ,
! {V NRC D'escription of Issue JFD BPI l
l        submittal to adopt the STS text.
Bases for ITS SR 3.4.5.3, STS Bases markup page B 3.4-26 l
l Comed Response to issue                                                                                                               ;
The Bases discussion reduces requirements about how the safety analysis limits are met and adds a new basis for the 7 day l
      ~ No change. ITS Bases SR 3.4.5.3 was revised to provide a discussion concerning the 7 day Frequency for SR 3.4.5.3. This change was added for consistency and clarification. Other STS SRs contain a brief discussion as to thejustification reason for the specific SR Frequency. This change is no different. STS SR 3.4.5.3 does not contain any information pertammg to the 7 day Frequency. Comed provided additional information to assist the operator and enhance their knowledge -
Frecuency. JFD BPI does not adequatelyjustify these technical differences from the STS Bases. Comment: Resise the l
concerning the reasoning behind the 7 day Frequency. This change does not alter any technical content or philosophy of the               ,
submittal to adopt the STS text.
l        STS. and provides additional information for the user. Comed continues to pursue this change. Comed will. however.
l Comed Response to issue
conform to the STS text for the first and second sentences for the Bases discussion ofITS SR 3.4.5.3.                                   '
~ No change. ITS Bases SR 3.4.5.3 was revised to provide a discussion concerning the 7 day Frequency for SR 3.4.5.3. This change was added for consistency and clarification. Other STS SRs contain a brief discussion as to thejustification reason for the specific SR Frequency. This change is no different. STS SR 3.4.5.3 does not contain any information pertammg to the 7 day Frequency. Comed provided additional information to assist the operator and enhance their knowledge -
                              .:.-= = = . = . =                       - . = . = = .     --
concerning the reasoning behind the 7 day Frequency. This change does not alter any technical content or philosophy of the l
NRC RAI Number             NRC Issued Date                             RAI Status 3.4.6-01                   3/9/98                                 Closed l,
STS. and provides additional information for the user. Comed continues to pursue this change. Comed will. however.
NRC Description of issue                                                                                                                 l DOC A8 l       JFD P7 and BP7                                                                                                                         ,
conform to the STS text for the first and second sentences for the Bases discussion ofITS SR 3.4.5.3.
ITS 3.4.6 Action C                                                                                                                     !
.:.-= = =. =. =
CTS 3/4.4.1.2 Actions lg)
-. =. = =.
(
NRC RAI Number NRC Issued Date RAI Status 3.4.6-01 3/9/98 Closed NRC Description of issue DOC A8 l
v    Unlike the STS. ITS 3.4.6 Action C addresses the condition of two required [RCS or RHR] loops not in operation. This I
JFD P7 and BP7 ITS 3.4.6 Action C lg)
difference is not plant specific because the proposed action requirement is not in the CTS. This is a C-type difference. Also, the CTS markup associated with DOC A8 does not accuratelyjustify the addition of proposed ITS 3.4.6 Action C.                           l Comment: Revise the submittal to adopt the STS action requirements.
CTS 3/4.4.1.2 Actions (v
Comed Response to issue                                                                                                                 l No change. The LCO allows either RCS or RHR loops to satisfy the requirement for decay heat removal in MODE 4. Any combination of two loops Operable may be used to satisfy the LCO. A loop is " required" when the loop is used to satisfy the LCO. Operable loops in excess of the two required to satisfy the LCO are not " required." Condition entry is only necessary when the total number of Operable loops is less than that required by the LCO. NUREG LCO 3.4.6 attempts to account for the designation of required loops by stating, "Two RHR loops inoperable" in Condition A and "Two RCS loops inoperable" in Condition B. The presumption in Condition A is that when two RHR loops are inoperable, two RCS loops are then required. Similarly, Condition B presumes that when two RCS loops are inoperable. two RHR loops are required. This logic does not hold for plants with three or more RCS or RHR loops or for situations in which the plant is using one RHR and one RCS loop to meet the LCO. Although the wording is different than the STS. the intent has not been changed. In addition, the intent of the STS is to provide a Condition where the required loops are either inoperable or not in operation. The STS Condition C accomplishes this by stating all combinations of RCS and RHR loops irioperable or not in operation. This approach was deemed confusing by Operators. In an attempt to clarify Condition C, Comed revised Condition C for two required loops inoperable no matter what combination of RHR or RCS loops. The condition where no loops are in operation is contained in Condition A. This clarification does not change any intent or technical requirements as presented in the STS.
Unlike the STS. ITS 3.4.6 Action C addresses the condition of two required [RCS or RHR] loops not in operation. This difference is not plant specific because the proposed action requirement is not in the CTS. This is a C-type difference. Also, the CTS markup associated with DOC A8 does not accuratelyjustify the addition of proposed ITS 3.4.6 Action C.
l       A similar change was proposed by H.B. Robinson plant and became WOG-109. In addition, TSTF-263 contains similar l
Comment: Revise the submittal to adopt the STS action requirements.
Comed Response to issue No change. The LCO allows either RCS or RHR loops to satisfy the requirement for decay heat removal in MODE 4. Any combination of two loops Operable may be used to satisfy the LCO. A loop is " required" when the loop is used to satisfy the LCO. Operable loops in excess of the two required to satisfy the LCO are not " required." Condition entry is only necessary when the total number of Operable loops is less than that required by the LCO. NUREG LCO 3.4.6 attempts to account for the designation of required loops by stating, "Two RHR loops inoperable" in Condition A and "Two RCS loops inoperable" in Condition B. The presumption in Condition A is that when two RHR loops are inoperable, two RCS loops are then required. Similarly, Condition B presumes that when two RCS loops are inoperable. two RHR loops are required. This logic does not hold for plants with three or more RCS or RHR loops or for situations in which the plant is using one RHR and one RCS loop to meet the LCO. Although the wording is different than the STS. the intent has not been changed. In addition, the intent of the STS is to provide a Condition where the required loops are either inoperable or not in operation. The STS Condition C accomplishes this by stating all combinations of RCS and RHR loops irioperable or not in operation. This approach was deemed confusing by Operators. In an attempt to clarify Condition C, Comed revised Condition C for two required loops inoperable no matter what combination of RHR or RCS loops. The condition where no loops are in operation is contained in Condition A. This clarification does not change any intent or technical requirements as presented in the STS.
l A similar change was proposed by H.B. Robinson plant and became WOG-109. In addition, TSTF-263 contains similar l
changes. The proposed change was approved plant specifically for H.B. Robinson. Comed continues to pursue this change.
changes. The proposed change was approved plant specifically for H.B. Robinson. Comed continues to pursue this change.
(See RAls3.4.7-01,3.4.7-07,3.4.8-01, and 3.4.8-08.)
(See RAls3.4.7-01,3.4.7-07,3.4.8-01, and 3.4.8-08.)
Line 258: Line 295:
i
i


i l                                                         R:sp::nse to NRC RAI For ITS S:ction 3.4                                   oo-Oct-98 l
i l
l          ,
R:sp::nse to NRC RAI For ITS S:ction 3.4 oo-Oct-98 l
          ~
~
                                    -..          .. .      .:.    : = --- ;.-=             . = = . -
NRC RAI Number -
NRC RAI Number -                                                                                                              l i                                                     NRC Issued Date                            RAI Status 3.4.6-02               3/9/98                                   Closed jd               NRC Description of Isst.e
NRC Issued Date RAI Status
                                                                                                                                                      )
: = --- ;.-=
. = =. -
i 3.4.6-02 3/9/98 Closed
,jd NRC Description of Isst.e
)
JFD P1 1TS LCO 3.4.6 l
JFD P1 1TS LCO 3.4.6 l
l
: a. The word " Operable" has been inserted in the last phrase stating with "one OPERABLE loop shall be in operation." This
: a. The word " Operable" has been inserted in the last phrase stating with "one OPERABLE loop shall be in operation." This
                  , word is redundant to the first pan of the LCO statement which already states " ..RCS and RHR loops shall be Operable.
, word is redundant to the first pan of the LCO statement which already states "..RCS and RHR loops shall be Operable.
The word insertion is not accepted.
The word insertion is not accepted.
l
: b. JFD P1 ITS LCO 3.4.6 Note 1.b CTS 3.4.1.3 Footnote
: b. JFD P1 ITS LCO 3.4.6 Note 1.b CTS 3.4.1.3 Footnote
* item (2)                                                                                                   l
* item (2)
        '          The ITS note is changed as follows " Core outlet temperature is maintained at least 100F below saturation temperature b,s _
The ITS note is changed as follows " Core outlet temperature is maintained at least 100F below saturation temperature b,s _
100F " The CTS requirement for this note is identical in wording to the STS text, There is no editorial enhancement perceived in this change.                                                                                                         I l
100F " The CTS requirement for this note is identical in wording to the STS text, There is no editorial enhancement perceived in this change.
: c.         .JFD BPI                                                                                                               l l                           Bases for ITS LCO 3.4.6, S~ S Bases markup page B 3.4-28 in the fifth paragraph, item b is reworded to confonn to the LCO Note 1.b. This change is also net accepted.-
c.
                                                                                                                                                      ]
.JFD BPI l
1 Comment: For the above differences, revise the submittal to adopt the STS text.                                                   I Comed Response to Issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4                 l
l Bases for ITS LCO 3.4.6, S~ S Bases markup page B 3.4-28 in the fifth paragraph, item b is reworded to confonn to the LCO Note 1.b. This change is also net accepted.-
                . closeout submittal Revision K.
]
L                                                                                                                                               l Original Response: Comed will revise the submittal to adopt the STS text This change will be provided in our                       l comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.5-02,3.4.8-02, and 3.4.8-03.)
1 Comment: For the above differences, revise the submittal to adopt the STS text.
I i
Comed Response to Issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4
1 l
. closeout submittal Revision K.
1 I
L l
Original Response: Comed will revise the submittal to adopt the STS text This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.5-02,3.4.8-02, and 3.4.8-03.)
i 1
I I
I I
I i,
I i,
I       \
I
kj lI                                                         I 1
\\
kj lI


R sponse to NRC RAI For ITS Section 3.4                               09-octm
R sponse to NRC RAI For ITS Section 3.4 09-octm
                                                              ~
~
NRC RAI Number                       NRC issued Date                 RAI Status
NRC RAI Number NRC issued Date RAI Status 3.4.6-03 3'9'98 Closed
      ~          3.4.6-03                           3'9'98                       Closed 1
~
(f     NRC Description of issue ITS 3.4.6 Applicability hotes PTLR Letter from Capra (NRC) to Kingsley (Comed) dated 1/21/98 regarding acceptance for referencing of PTLR. and enclosed safety evaluation (SRXB comment) Byron & Braidwood's LTOP analyses account for RCP dynamic head effects and the resultant pressure drop between the location of the limiting vessel material and the pressure transmitter used to actuate the LTOP sy stem. In the LTOP analyses, you assumed all four RCPs and both RHR pumps running when the RCS is above 120'F. and accounted for the maximum resulting head effect. However, for RCS temperature below 120 F you assumed only one RCP is in operation and accounted for the dynamic head effect of that single RCP (in addition to the two RHR pump). Comment:
1 (f
NRC Description of issue ITS 3.4.6 Applicability hotes PTLR Letter from Capra (NRC) to Kingsley (Comed) dated 1/21/98 regarding acceptance for referencing of PTLR. and enclosed safety evaluation (SRXB comment) Byron & Braidwood's LTOP analyses account for RCP dynamic head effects and the resultant pressure drop between the location of the limiting vessel material and the pressure transmitter used to actuate the LTOP sy stem. In the LTOP analyses, you assumed all four RCPs and both RHR pumps running when the RCS is above 120'F. and accounted for the maximum resulting head effect. However, for RCS temperature below 120 F you assumed only one RCP is in operation and accounted for the dynamic head effect of that single RCP (in addition to the two RHR pump). Comment:
Revise the Applicability Notes ofITS 3.4.6 with an additional note consistent with this assumption. This may be submitted in a form similar to the note to Section 3.4.6 which is related to the 50*F primary / secondary difference limit for starting a RCP.
Revise the Applicability Notes ofITS 3.4.6 with an additional note consistent with this assumption. This may be submitted in a form similar to the note to Section 3.4.6 which is related to the 50*F primary / secondary difference limit for starting a RCP.
Comed Response to issue No change. Comed disagrees. The referenced SER accurately reflects the assumptions used in the LTOP analysis for operation above and below 120 F. These are assumptions incorporated in the Staff approved methodology. They do not, however, result in operational restrictions. The net impact of these conditions is to the LTOP setpoint, not the plant operation.
Comed Response to issue No change. Comed disagrees. The referenced SER accurately reflects the assumptions used in the LTOP analysis for operation above and below 120 F. These are assumptions incorporated in the Staff approved methodology. They do not, however, result in operational restrictions. The net impact of these conditions is to the LTOP setpoint, not the plant operation.
The two items that are in Tech Specs (TS) concerning the basis of LTOP setpoints define the initiating events that the LTOP system protects against. These items are,1) the number of ECCS pumps injecting during an LTOP mass injection event (charging pump at full flow), and 2) the temperature difference for the heat injection event (507). These two initiating events are specifically discussed in Section 3.1 of WCAP-14040-NP-A, methodology used to develop cold overpressure j a,   mitigating system setpoint:, and RCS heatup and cooldown limit curves, and the associated SER. Beyond the initiating
The two items that are in Tech Specs (TS) concerning the basis of LTOP setpoints define the initiating events that the LTOP system protects against. These items are,1) the number of ECCS pumps injecting during an LTOP mass injection event (charging pump at full flow), and 2) the temperature difference for the heat injection event (507). These two initiating events are specifically discussed in Section 3.1 of WCAP-14040-NP-A, methodology used to develop cold overpressure a,
(~)   events, other factors are considered in the LTOP setpoint determination. Differential pressure and instrument uncertainty are two of these. The application of these secondary items are administratively controlled by Comed. This concept of l
mitigating system setpoint:, and RCS heatup and cooldown limit curves, and the associated SER. Beyond the initiating j
administrative control was accepted by the Staffin our recent discussions for the approval of the PTLR amendment. TS do not have restrictions on other secondary items (i.e., there are no TS requirements specific to the calibration of the instruments   l involved which will affect the total instrument tolerances applied to the LTOP setpoints). Comed believes that it is not the Staffs intention to include these secondary issues in TS. (Correction Note: This should be a 3.4.7 RAI question, not 3.4.6.)
(~)
events, other factors are considered in the LTOP setpoint determination. Differential pressure and instrument uncertainty are two of these. The application of these secondary items are administratively controlled by Comed. This concept of administrative control was accepted by the Staffin our recent discussions for the approval of the PTLR amendment. TS do not have restrictions on other secondary items (i.e., there are no TS requirements specific to the calibration of the instruments involved which will affect the total instrument tolerances applied to the LTOP setpoints). Comed believes that it is not the Staffs intention to include these secondary issues in TS. (Correction Note: This should be a 3.4.7 RAI question, not 3.4.6.)
Additionally, the mode of applicability for ITS 3.4.6 is mode 4, which corresponds to a minimum temperature of 200 F. The LTOP analysis assumes the most limiting operational parameters in this mode. Noting the different assumption for a condition not addressed by this specification is not desirable.
Additionally, the mode of applicability for ITS 3.4.6 is mode 4, which corresponds to a minimum temperature of 200 F. The LTOP analysis assumes the most limiting operational parameters in this mode. Noting the different assumption for a condition not addressed by this specification is not desirable.
t rm \
t rm
l NY 12
\\
NY l
12


                  *-*+geungap.m.ee     ai         ge   h-g               .seum -me g a.mm-   --e   -em emsumm-   6---     e R:spanSe to'NRC RAI For ITS S:ction 3.4                                       09-oci-98
*-*+geungap.m.ee ai ge h-g
                                                                                                                          . m NRC RAI Number                   NRC Issued Date                                         RAI Status
.seum
        ,,                          3.4.7               3/9'98                                                 Closed NRC Description of Issue
-me g
              ~ JFD P8 ITS 3.4.7 Actions CTS 3'4.4.1.4.1 Actions                                                                                                                   l JFD BP8 l
a.mm-
Unlike the STS. ITS 3.4.7 addresses the condition of a required RHR loop not in operation. These differences are not plant specific because they are not in the CTS. This is a C-type difference. Also, why are there not equivalent CTS DOCS provided for these changes? The CTS does not re6ect these changes. Comment: Revise the submittal to adopt the STS                         j action requirements. Comed is encouraged to propose a generic change to tha STS. See similar comments 3.4.6-01 and                         '
--e
4 3.4.8-01.
-em emsumm-6---
l Comed Response to issue Revised Response: Per discussions with the NRC Reviewer. ITS Condition B was split into two separate Conditions. This                     1 change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.                                                     I Original Response: See Comed Response to RAI 3.4.6-01. (See RAls 3.4.6-01. 3.4.7-07. 3.4.8-01 and 3.J.8-08.)                               ;
e R:spanSe to'NRC RAI For ITS S:ction 3.4 09-oci-98 NRC RAI Number NRC Issued Date
1 NRC RAI Number                   NRC lssued Date                                         RAI Status 3.4.7-02               3/9/98                                                 Closed                                 !
. m RAI Status 3.4.7 3/9'98 Closed NRC Description of Issue
NRC Description of Issue                                                                                                                   l DOC A.I JFD Pl                                                                                                                                     !
~ JFD P8 ITS 3.4.7 Actions CTS 3'4.4.1.4.1 Actions JFD BP8 Unlike the STS. ITS 3.4.7 addresses the condition of a required RHR loop not in operation. These differences are not plant specific because they are not in the CTS. This is a C-type difference. Also, why are there not equivalent CTS DOCS provided for these changes? The CTS does not re6ect these changes. Comment: Revise the submittal to adopt the STS j
a              ITS LCO 3.4.7.b                                                                                                                           !
action requirements. Comed is encouraged to propose a generic change to tha STS. See similar comments 3.4.6-01 and 3.4.8-01.
,'[             CTS 3.4.1.4.1.b                                                                                                                           .
4 Comed Response to issue Revised Response: Per discussions with the NRC Reviewer. ITS Condition B was split into two separate Conditions. This 1
CTS 3/4.4.1.4.1 Action a                                                                                                                   I JFD BPI                                                                                                                                   I Bases for ITS 3.4.7 Applicability, STS Bases markup page B 3.4-33                                                                         '
change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
STS 3.4.7.b is reworded as follows: "The secondary side water level of a least two Steam Generators (SGs) shall be > [17%)
Original Response: See Comed Response to RAI 3.4.6-01. (See RAls 3.4.6-01. 3.4.7-07. 3.4.8-01 and 3.J.8-08.)
OPERABLE." Throughout the STS, an Operable SG means " Operable in accordance with the Steam Generator Tube                                 !
NRC RAI Number NRC lssued Date RAI Status 3.4.7-02 3/9/98 Closed NRC Description of Issue l
Surveillance Program". 'Ihe STS text is very explicit here to require the secondary side water level of an Operable SG to be a condition of Operability for this LCO. These are technical changes to the CTS requirements which are inadequately                         l justined as an editorial change under DOC Al. As presented, this is a less restrictive change to the CTS which requires an                 l "L" DOC. Correspondingly. JFD Pi is inadequate justi6 cation for these changes. These change are not accepted as justi6ed. Comment: Revise the submittal to adopt the STS text.
DOC A.I JFD Pl ITS LCO 3.4.7.b a
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.                                 -l 1
, ' [
l l
CTS 3.4.1.4.1.b CTS 3/4.4.1.4.1 Action a JFD BPI Bases for ITS 3.4.7 Applicability, STS Bases markup page B 3.4-33 STS 3.4.7.b is reworded as follows: "The secondary side water level of a least two Steam Generators (SGs) shall be > [17%)
I i
OPERABLE." Throughout the STS, an Operable SG means " Operable in accordance with the Steam Generator Tube Surveillance Program". 'Ihe STS text is very explicit here to require the secondary side water level of an Operable SG to be a condition of Operability for this LCO. These are technical changes to the CTS requirements which are inadequately justined as an editorial change under DOC Al. As presented, this is a less restrictive change to the CTS which requires an "L" DOC. Correspondingly. JFD Pi is inadequate justi6 cation for these changes. These change are not accepted as justi6ed. Comment: Revise the submittal to adopt the STS text.
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
-l 1
i
, L f
, L f
      \ /-
\\ /-
i a ,
i a,
J-l
J-


Rcsp:nss to NRC RAI Fcr ITS S:ction 3A                                         09-oci-98
Rcsp:nss to NRC RAI Fcr ITS S:ction 3A 09-oci-98
                                        =       . m==_._           :_              u _ . ._ _   ~u NRC RAI Number -           NRC 1ssued Date                               RAI Status _ . , -
=
                          -3.4.7-03                   3/9'98                                       Closed
m==_._
;  lj             NRC Description ofissue
u _.._ _
~u NRC RAI Number -
NRC 1ssued Date RAI Status _., -
-3.4.7-03 3/9'98 Closed lj NRC Description ofissue
: JFD P1 ITS LCO 3.4.7 Note 1.b CTS 3.4.1.4.1 Footnote
: JFD P1 ITS LCO 3.4.7 Note 1.b CTS 3.4.1.4.1 Footnote
* item (2) i a The ITS note differs from the corresponding STS note as follows " Core outlet temperature is maintained at least 100F below saturation temperatore by 100F " The CTS requirement for this note is identical in wording to the STS text. There is no editorial enhancement perceived in this change..
* item (2) i a The ITS note differs from the corresponding STS note as follows " Core outlet temperature is maintained at least 100F below saturation temperatore by 100F " The CTS requirement for this note is identical in wording to the STS text. There is no editorial enhancement perceived in this change..
Line 336: Line 388:
Comed Response to issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Comed Response to issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Original Response: Comed will revise the submittal to adopt the ST3 text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.'
Original Response: Comed will revise the submittal to adopt the ST3 text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.'
    /
X}
X}
    = "
/
NRC RAI Number 3.4.7-04 NRC Issued Date 3/9/98 RAI Status Closed NRC Description of issue JFD B3 DOC L5 ITS SR 3.4.7.2 CTS 3.4.1.4.1.b JFD BB3 Bases for ITS SR 3.4.7.2, STS Bases markup page B 3.4-36 The iTS contains plant specific SG secondary side water level values which are different from the values in the CTS requirements, as discussed in DOC L5. The adequacy of these values can not be verified. There is no acceptable method for approving the new values as presented in these justifications. Also, explain the large difTerence in the values between Units 1 and 2 and why this difference is the exact same for both Byron and Braidwood.
NRC RAI Number NRC Issued Date RAI Status
= "
3.4.7-04 3/9/98 Closed NRC Description of issue JFD B3 DOC L5 ITS SR 3.4.7.2 CTS 3.4.1.4.1.b JFD BB3 Bases for ITS SR 3.4.7.2, STS Bases markup page B 3.4-36 The iTS contains plant specific SG secondary side water level values which are different from the values in the CTS requirements, as discussed in DOC L5. The adequacy of these values can not be verified. There is no acceptable method for approving the new values as presented in these justifications. Also, explain the large difTerence in the values between Units 1 and 2 and why this difference is the exact same for both Byron and Braidwood.
Comment: How was this change approved by the NRC five years ago but not incorporated into the CTS? Revise tne submittal with additional technicaljustification for this change. See similar comment 3.4.5-03.
Comment: How was this change approved by the NRC five years ago but not incorporated into the CTS? Revise tne submittal with additional technicaljustification for this change. See similar comment 3.4.5-03.
Comed Response to issue No change. NRC SER and Amendments 34 (Braidwood) and 45 (Byron), dated April 6,1992 approved Comed's request to
Comed Response to issue No change. NRC SER and Amendments 34 (Braidwood) and 45 (Byron), dated April 6,1992 approved Comed's request to
                ' change the Steam Generator (SG) secondary side narrow range water level to be greater than or equal to 33% for Unit 1 (Westinghouse D4 SGs) and 37% for Unit 2 (Westinghouse D5 SGs). " .is change was accurately made in CTS Tables 2.2-1 and 3.3-4. However, CTS page 3/4 4-4 for CTS SR 4.4.1.3.2 was L advertently not changed. In developing the CTS l                 markup for the conversion to ITS, CTS page 3/4 4-4 was used and was marked up to reflect the correct values as approved in Amendments 34 and 45. Although this CTS SR contained the incorrect values, the plants administratively control the water p [,T level at greater than or equal to 41% which is more conservative. Comed continues to pursue this change. (See RAI 3.4.5-
' change the Steam Generator (SG) secondary side narrow range water level to be greater than or equal to 33% for Unit 1 (Westinghouse D4 SGs) and 37% for Unit 2 (Westinghouse D5 SGs). ".is change was accurately made in CTS Tables 2.2-1 and 3.3-4. However, CTS page 3/4 4-4 for CTS SR 4.4.1.3.2 was L advertently not changed. In developing the CTS l
                ' 03.)
markup for the conversion to ITS, CTS page 3/4 4-4 was used and was marked up to reflect the correct values as approved in Amendments 34 and 45. Although this CTS SR contained the incorrect values, the plants administratively control the water p [,
level at greater than or equal to 41% which is more conservative. Comed continues to pursue this change. (See RAI 3.4.5-T
' 03.)
1a) 14
1a) 14


l:                 - = = . -                     .              = = = = - - - = = - .
l:
- = =. -
= = = = - - - = = -
R:sponse to NRC RAI For ITS Section 3.4 09-Oci 98
R:sponse to NRC RAI For ITS Section 3.4 09-Oci 98
                                          ~
' NRC RAI Number NRC issued Date IUIStatus
!        ' NRC RAI Number                   NRC issued Date                             IUIStatus q            3.4.7 05                       3/9'98                                     Closed
~
  '(,/ NRC Description of issue DOC A25                                                                                                                       ,
3.4.7 05 3/9'98 Closed q
I JFD P39                                                                                                                       )
'(,/
l ITS SR 3.4.7.1 CTS 4.4.1.4.1.2 l
NRC Description of issue DOC A25 I
CTS 4.4.1.4.1.2 states "At least one RHR loop shall be verified in operation and circulating reactor coolant.. " w hich is     i consistent with the STS. Alternatively. ITS SR 3.4.7.1 states this verification is for the " required" RHR loop in operation. ,
JFD P39
,        This change and difference introduces an ambiguity that is not present in the CTS and STS. The SR does not try to             l l        determine which is the ." required" RCS or RHR in operation but explicitly states that any one must be in operation.           1 Comment: Withdraw the change and adopt the STS text.
)
Comed Response to issue No change. The word " required" was added to the SR for verifying one RHR loop is in operation to ensure thar *Se RHR         j loop that is in " operation" is the RHR loop that is designated as the " OPERABLE" loop. This eliminates the possibility of     ,
ITS SR 3.4.7.1 l
crediting a non-operable (as required by the LCO) RHR loop as the RHR loop in operation. Comed continues to pursue this       !
CTS 4.4.1.4.1.2 CTS 4.4.1.4.1.2 states "At least one RHR loop shall be verified in operation and circulating reactor coolant.. " w hich is i
change. (See RAI 3.4.8-06.)                                                                                                   !
consistent with the STS. Alternatively. ITS SR 3.4.7.1 states this verification is for the " required" RHR loop in operation.
                                                                              . - . - . ..                                              I I
This change and difference introduces an ambiguity that is not present in the CTS and STS. The SR does not try to l
NRC RAI Number                   NRC issued Date                             RAI Status                                     '
determine which is the." required" RCS or RHR in operation but explicitly states that any one must be in operation.
l                3.4.7-06                       3/9/98                                     Closed                                     l NRC Description of issue                                                                                                       j DOC M3                                                                                                                         ,
1 Comment: Withdraw the change and adopt the STS text.
CTS 3'.4.1.4.1 Footnote
Comed Response to issue No change. The word " required" was added to the SR for verifying one RHR loop is in operation to ensure thar *Se RHR j
* l f    ITS LCO 3.4.7 Note I l    TSTF-153 (approved 4/l1/97)
loop that is in " operation" is the RHR loop that is designated as the " OPERABLE" loop. This eliminates the possibility of crediting a non-operable (as required by the LCO) RHR loop as the RHR loop in operation. Comed continues to pursue this change. (See RAI 3.4.8-06.)
  %d STS LCO 3.4.7 Note 1 as revised by TSTF 153 does not begin with the word "all" as does the ITS note. Comment: This difference is not justifiable on a plant-specific or editorial basis. Revise the ITS note to conform to the STS as revised by TSTF-153.
NRC RAI Number NRC issued Date RAI Status l
3.4.7-06 3/9/98 Closed NRC Description of issue j
DOC M3 CTS 3'.4.1.4.1 Footnote
* ITS LCO 3.4.7 Note I fl TSTF-153 (approved 4/l1/97)
%d STS LCO 3.4.7 Note 1 as revised by TSTF 153 does not begin with the word "all" as does the ITS note. Comment: This difference is not justifiable on a plant-specific or editorial basis. Revise the ITS note to conform to the STS as revised by TSTF-153.
Comed Response to Issue Comed will revise the ITS note to conform to the STS as revised by TSTF-153. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to Issue Comed will revise the ITS note to conform to the STS as revised by TSTF-153. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
i r
/~%
  /~% 5 l
i r 5
15
l 15


                                =,= = =.:==                                           =
=,= = =.:==
Rsspanse to NRC RAI For ITS Srction 3A                                   09-Octm NRC RAI Number               NRC issued Date                                     RAI Status 3.4.7-07                   3'9'98                                               Closed
=
  .p
Rsspanse to NRC RAI For ITS Srction 3A 09-Octm NRC RAI Number NRC issued Date RAI Status 3.4.7-07 3'9'98 Closed
_V         NRC Description of Issue DOC M13 CTS 3/4.4.1.4.1 Action b STS 3.4.7 Action B ITS 3.4.7 Acticns A, B & C CTS 3.4.1.4.1 Action b provides action with no RHR loop in operation. STS 3.4.7 Action B provides Required Actions with
.p
            ' Required' RHR loops inoperable OR no RHR loop in operation. The compensatory Actions for both the CTS and STS are
_V NRC Description of Issue DOC M13 CTS 3/4.4.1.4.1 Action b STS 3.4.7 Action B ITS 3.4.7 Acticns A, B & C CTS 3.4.1.4.1 Action b provides action with no RHR loop in operation. STS 3.4.7 Action B provides Required Actions with
,            the same. DOC M13 states "lTS 3.4.7 and ITS 3.4.8, Condition C, adds the Condition. two required RHR loops inoperable.
' Required' RHR loops inoperable OR no RHR loop in operation. The compensatory Actions for both the CTS and STS are the same. DOC M13 states "lTS 3.4.7 and ITS 3.4.8, Condition C, adds the Condition. two required RHR loops inoperable.
This Condition does not exist in CTS." Two inoperable RHR loops are the same as no RiiR loops in operation in Mode 5.
This Condition does not exist in CTS." Two inoperable RHR loops are the same as no RiiR loops in operation in Mode 5.
There is no change here but an equivalence between the CTS and the STS which is obscured by the reformatting of the Actions as described by JFD P8. Comment: Withdraw the change and adopt the STS action requirements.
There is no change here but an equivalence between the CTS and the STS which is obscured by the reformatting of the Actions as described by JFD P8. Comment: Withdraw the change and adopt the STS action requirements.
Comed Response to issue Comed disagrees that two inoperable RHR loops is the same as no RHR loops in operation, which is why the DOC was categorized as an 'M' DOC. In addition, NUREG LCOs 3.4.5,3.4.6,3.4.7, and 3.4.8 specify " . shall be OPERABLE and in operation . " indicating two separate and distinct requirements. Therefore, the ITS Actions and SRs were written accordingly. (See RAls 3.4.6-01, 3.4.7-01, 3.4.8-01, and 3.4.8-08.)
Comed Response to issue Comed disagrees that two inoperable RHR loops is the same as no RHR loops in operation, which is why the DOC was categorized as an 'M' DOC. In addition, NUREG LCOs 3.4.5,3.4.6,3.4.7, and 3.4.8 specify ". shall be OPERABLE and in operation. " indicating two separate and distinct requirements. Therefore, the ITS Actions and SRs were written accordingly. (See RAls 3.4.6-01, 3.4.7-01, 3.4.8-01, and 3.4.8-08.)
: v. n. - .         -                        --
: v. n. -.
NRC RAI Number             NRC issued Date                                       RAI Status                         l 3.4.7-01;                   3/9/98                                               Closed I
NRC RAI Number NRC issued Date RAI Status I
NRC Description ofIssue JFD P9 '
3.4.7-01; 3/9/98 Closed NRC Description ofIssue JFD P9 '
ITS SR 3.4.7.1 Note
ITS SR 3.4.7.1 Note
(,w} . CTS 3.4.1.4.1.b
(,w}.
  %.J JFD P9 justifies including n note in ITS SR 3.4.7.1 that the STS does not have. The new Note says "Only required when complying with LCO 3.4.7.b". The CTS do not allow this relaxation of the Operability requirements of CTS 3.4.1.4.1.b.
CTS 3.4.1.4.1.b
l This note would permit a SG to remain inoperable and thus not immediately available, in the event the backup RHR loop   i became inoperable. Also, a note like this should never be buried in the SR but placed in the LCO. There is no less restrictive technical DOC provided for this change. Comment: This change and difference are not justifiable on a plant-specific or editorial basis. Revise the submittal to withdraw the note.
%.J JFD P9 justifies including n note in ITS SR 3.4.7.1 that the STS does not have. The new Note says "Only required when complying with LCO 3.4.7.b". The CTS do not allow this relaxation of the Operability requirements of CTS 3.4.1.4.1.b.
Comed Response to issue Comed disagrees with the statement, "The CTS does not allow this relaxation of the Operability requirements of CTS 3.4.l.4.1.b," but Comed agrees with the statement, "This note would permit a SG to remain inoperable and thus not immediately available, in the event the backup RHR loop became inoperable " CTS SR states, "The secondary side water level of at least two steam generators WHEN REQUIRED shall be . " In addition, NUREG SR 3.4.7.2 states," Verify SG secondary side water levelis greater than or equal to [17]% in REQUIRED SGs." When the LCO is being met with one
This note would permit a SG to remain inoperable and thus not immediately available, in the event the backup RHR loop i
            .RHR loop OPERABLE and in operation and an additional RHR loop OPERABLE, there is no requirement for SGs and therefore SR 3.4.7.2 which verifies SG secondary side water level is not required to be performed. SR 3.4.7.2 is only required to be performed when the LCO is being met with one RHR loop OPERABLE and in operation and the water level of two SGs OPERABLE. However, since SR 3.4.7.2 contains the words " required SGs" the Note will be deleted. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (Correction Note: LCO JFD 3.4-P9 justifies adding a Note in ITS SR 3.4.7.2, not ITS SR 3.4.7.1.)
became inoperable. Also, a note like this should never be buried in the SR but placed in the LCO. There is no less restrictive technical DOC provided for this change. Comment: This change and difference are not justifiable on a plant-specific or editorial basis. Revise the submittal to withdraw the note.
D b
Comed Response to issue Comed disagrees with the statement, "The CTS does not allow this relaxation of the Operability requirements of CTS 3.4.l.4.1.b," but Comed agrees with the statement, "This note would permit a SG to remain inoperable and thus not immediately available, in the event the backup RHR loop became inoperable " CTS SR states, "The secondary side water level of at least two steam generators WHEN REQUIRED shall be. " In addition, NUREG SR 3.4.7.2 states," Verify SG secondary side water levelis greater than or equal to [17]% in REQUIRED SGs." When the LCO is being met with one
i6
.RHR loop OPERABLE and in operation and an additional RHR loop OPERABLE, there is no requirement for SGs and therefore SR 3.4.7.2 which verifies SG secondary side water level is not required to be performed. SR 3.4.7.2 is only required to be performed when the LCO is being met with one RHR loop OPERABLE and in operation and the water level of two SGs OPERABLE. However, since SR 3.4.7.2 contains the words " required SGs" the Note will be deleted. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (Correction Note: LCO JFD 3.4-P9 justifies adding a Note in ITS SR 3.4.7.2, not ITS SR 3.4.7.1.)
Db i6


_ _ _ _ _ .___                      .=. . _ . _ _
.=.. _. _ _
Resprnse to NRC RAI For ITS S:ction 3A                                     09-oct-98
Resprnse to NRC RAI For ITS S:ction 3A 09-oct-98
                                                            -=:-.=.                          .
-=:-.=.
                                                                                                      =: : ._ -
=: :._ -
l             ' NRC RAI Number                      NRC lssued Date                            RAI Status
l
          ~
~
  . ,                l 3 A7-09                         3 998                                       Closed Q-   ' NRC Description ofissue i               JFD Cl4
l 3 A7-09 3 998 Closed
!              ITS LCO 3.4.7 Note 1 CTS 3.4.1.4.1 Footnote
' NRC RAI Number NRC lssued Date RAI Status Q-
' NRC Description ofissue i
JFD Cl4 ITS LCO 3.4.7 Note 1 CTS 3.4.1.4.1 Footnote
* TSTF-153 ITS LCO 3.4.7 Note I contains a proposed change to pennit "All RHR pumps.. " to be de-energized. CTS 3.4.1.4.1 Footnote = only permits "The RHR pump., " or one RHR pump to be de energized. Comment: See comment 3.4.7-06.
* TSTF-153 ITS LCO 3.4.7 Note I contains a proposed change to pennit "All RHR pumps.. " to be de-energized. CTS 3.4.1.4.1 Footnote = only permits "The RHR pump., " or one RHR pump to be de energized. Comment: See comment 3.4.7-06.
Comed Response to issue Comed will revise the ITS note to conform to the STS as revised by TSTF-153. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS
Comed Response to issue Comed will revise the ITS note to conform to the STS as revised by TSTF-153. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RA!. (See RAI 3.4.7-06.)
;              Section 3.4 RA!. (See RAI 3.4.7-06.)
NRC RAI Number NRC Issued Date RAI Status 3.4.7-10 3/9/98 Closed NRC Description ofIssue JFD BPI -
NRC RAI Number                     NRC Issued Date                           RAI Status 3.4.7-10                         3/9/98                                     Closed NRC Description ofIssue JFD BPI -
Bases for ITS LCO 3.4.7, STS Bases markup page B 3.4-33 in the first paragraph, the discussion pertaining to any combination of two RCS or RHR loops does not adopt the reason for
Bases for ITS LCO 3.4.7, STS Bases markup page B 3.4-33 in the first paragraph, the discussion pertaining to any combination of two RCS or RHR loops does not adopt the reason for
              " meeting single failure considerations" and adds in its place to " provide adequate redundancy for decay heat removal" Comment: This difference is not justifiable on a plant-specific or editorial basis. Revise the submittal to adopt the STS text.
" meeting single failure considerations" and adds in its place to " provide adequate redundancy for decay heat removal" Comment: This difference is not justifiable on a plant-specific or editorial basis. Revise the submittal to adopt the STS text.
            = Comed Response to Issue
= Comed Response to Issue
'1    (,)     Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.8-09.)
(,)
NRC RAI Number                   NRC issued Date                           RAI Status 3.4.8-01                         3/9/98                                     Closed NRC Description ofissue JFD P10 -
Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4
'1 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.8-09.)
NRC RAI Number NRC issued Date RAI Status 3.4.8-01 3/9/98 Closed NRC Description ofissue JFD P10 -
ITS 3.4.8 Actions CTS 3/4.4.1.4.2 Actions JFD BPIO ITS 3.4.8 Action A and associated Bases address the Condition of a required RHR loop not in operation, as discussed in JFD P10. STS 3.4.8 Action B, however, addresses this same condition. Thus there is no need to deviate from the format of the STS Actions. In addition, this difference is not plant specific because this requirement is not in the CTS. Therefore, this is a C-type difTerence. Comment: Withdraw the difference and adopt the STS format for the Actions. See similar comments 3.4.6-01 and 3.4.7-01 Comed Response to issue See Comed Response to RAI 3.4.6-01. (See RAls 3.4.6-01,3.4.7-01,3.4.7-07, and 3.4.8-08.)
ITS 3.4.8 Actions CTS 3/4.4.1.4.2 Actions JFD BPIO ITS 3.4.8 Action A and associated Bases address the Condition of a required RHR loop not in operation, as discussed in JFD P10. STS 3.4.8 Action B, however, addresses this same condition. Thus there is no need to deviate from the format of the STS Actions. In addition, this difference is not plant specific because this requirement is not in the CTS. Therefore, this is a C-type difTerence. Comment: Withdraw the difference and adopt the STS format for the Actions. See similar comments 3.4.6-01 and 3.4.7-01 Comed Response to issue See Comed Response to RAI 3.4.6-01. (See RAls 3.4.6-01,3.4.7-01,3.4.7-07, and 3.4.8-08.)
v 17
v 17


                                                                                  = =                   -
= =
R:sponse to NRC RAI For ITS Srctinn 3A                                 09-oct 98
R:sponse to NRC RAI For ITS Srctinn 3A 09-oct 98
:              ,m==--                         .-        _--: - =-
,m==--
NRC RAI Number               NRC lssued Date                             RAI Status
_--: - =-
    ,.              ~ 3.4.8-02                     3'/9'98                                 Closed
NRC RAI Number NRC lssued Date RAI Status
  /       s i       /   NRC Description of issue JFD P1 ITS 3.4.8, LCO Note 1.b CTS 3.4.1.4.2 Footnote " item (2)
~ 3.4.8-02 3'/9'98 Closed
/
s i
/
NRC Description of issue JFD P1 ITS 3.4.8, LCO Note 1.b CTS 3.4.1.4.2 Footnote " item (2)
The ITS note differs from the corresponding STS note as follows: " Core outlet temperature is maintained > 100F below saturation temperature by > 100F." There is no editorial enhancement perceived in this change. Comment: Revise the submittal to adopt the STS presentation Comed Response to issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
The ITS note differs from the corresponding STS note as follows: " Core outlet temperature is maintained > 100F below saturation temperature by > 100F." There is no editorial enhancement perceived in this change. Comment: Revise the submittal to adopt the STS presentation Comed Response to issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Respontes to the iTS Section 3.4 RAl. See RAls 3.4.5-02,3.4.6-02, and 3.4.8-03.
Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Respontes to the iTS Section 3.4 RAl. See RAls 3.4.5-02,3.4.6-02, and 3.4.8-03.
NRC RAI Number               NRC issued Date                             RAI Status 3.4.8-03                     3/9/98                                 Closed NRC Description ofIssue JFD Pl
NRC RAI Number NRC issued Date RAI Status 3.4.8-03 3/9/98 Closed NRC Description ofIssue JFD Pl
              .lTS LCO 3.4.8 '
.lTS LCO 3.4.8 '
The word " Operable" has been inserted in the last phrase of STS LCO 3.4.8 to state that "one OPERABLE RHR loop sball
The word " Operable" has been inserted in the last phrase of STS LCO 3.4.8 to state that "one OPERABLE RHR loop sball
[,_}         be in operation." This word is redundant to the first part of the LCO statement which already states "Two...RHR loops shall
[,_}
(/ -         be Operable, " The word insertion is not accepted. Comment: Revise the submittal to adopt the STS text.
be in operation." This word is redundant to the first part of the LCO statement which already states "Two...RHR loops shall
(/ -
be Operable, " The word insertion is not accepted. Comment: Revise the submittal to adopt the STS text.
Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, this comment was withdrawn.
Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, this comment was withdrawn.
Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI, (See RAls 3.4.5-02,3.4.6-02, and 3.4.8-02.)
Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI, (See RAls 3.4.5-02,3.4.6-02, and 3.4.8-02.)
Line 429: Line 500:
18 l
18 l


                                    -                _ = = =             -
_ = = =
                                                                              -- ==
--==
R:spanse to NRC RAI For ITS Section 3.4                                 09-oct-98
R:spanse to NRC RAI For ITS Section 3.4 09-oct-98
                                                      ~
~
NRC RAI Number             NRC Issued Date                           RAI Status
NRC RAI Number NRC Issued Date RAI Status 3.4.8-04 3'9'98 Closed
  ,,          3.4.8-04                     3'9'98                                 Closed h     NRC Description of issue JFD P32 ITS 3.4.8 Note 1 STS 3.4.8 Note 1 CTS 3.4.1.4.2 Note "
,,h NRC Description of issue JFD P32 ITS 3.4.8 Note 1 STS 3.4.8 Note 1 CTS 3.4.1.4.2 Note "
JFD BP37 ITS 3.4.8 Note i states "All RHR pumps may be [de-energized] for < 1 hour.. " STS 3.4.8 Note I states "All RHR pumps may be de-energized for < 15 minutes when switching from one loop to another.. " CTS Footnote " states only "The RHR pump may be de-eneigized for up to one hour.. "; but does not state a reason for de energizing. JFD P32 deals only with the length of time issue for this difference. It states de-energizing all RHR pumps is consistent with the CTS requirements. but this is not so. Comment: JFD P32 states 15 minutes is adequate to switch loops; if so, why not adopt the STS text as is? If one hour is needed for each pump. then add a note to match the CTS requirement for one RHR pump de-energized at a time.
JFD BP37 ITS 3.4.8 Note i states "All RHR pumps may be [de-energized] for < 1 hour.. " STS 3.4.8 Note I states "All RHR pumps may be de-energized for < 15 minutes when switching from one loop to another.. " CTS Footnote " states only "The RHR pump may be de-eneigized for up to one hour.. "; but does not state a reason for de energizing. JFD P32 deals only with the length of time issue for this difference. It states de-energizing all RHR pumps is consistent with the CTS requirements. but this is not so. Comment: JFD P32 states 15 minutes is adequate to switch loops; if so, why not adopt the STS text as is? If one hour is needed for each pump. then add a note to match the CTS requirement for one RHR pump de-energized at a time.
Revise the suomittal to adopt the STS or revise it consistent with the CTS, as descrioed.
Revise the suomittal to adopt the STS or revise it consistent with the CTS, as descrioed.
Comed Response to Issue No change. It is Byron's and Braidwood's Current Licensing Basis (CLB) to allow de-energizing an RHR pump for I hour         l without stating a reason for the de-energization. LCO JFD 3.4-P32 was only intended tojustify maintaining the CLB of I hour. LCO JFD 3.4-P35 justifies maintaining the CLB for not limiting the de-energization of the RHR pumps to "when switching from one loop to another." Further, since both CTS and ITS require only one RHR loop be in operation. Comed       ,
Comed Response to Issue No change. It is Byron's and Braidwood's Current Licensing Basis (CLB) to allow de-energizing an RHR pump for I hour without stating a reason for the de-energization. LCO JFD 3.4-P32 was only intended tojustify maintaining the CLB of I hour. LCO JFD 3.4-P35 justifies maintaining the CLB for not limiting the de-energization of the RHR pumps to "when switching from one loop to another." Further, since both CTS and ITS require only one RHR loop be in operation. Comed perceives the CTS wording of"The RHR pump may be. " to be equivalent to the ITS wording of"All RHR pumps may be
perceives the CTS wording of"The RHR pump may be . " to be equivalent to the ITS wording of"All RHR pumps may be             !
" Comed disagrees with the statement, "If one hour is needed for each pump, then add a note to match the CTS j
          " Comed disagrees with the statement, "If one hour is needed for each pump, then add a note to match the CTS             j requirement for one RHR pump de-energized at a time." There is neither a restriction for preventing or requiring the second l OPERABLE RHR pump from being in operation. Therefore, the second pump does not need a Note governing its                     l operation. Comed continues to pursue this change. (See RAI 3.4.8-05.)                                                       !
requirement for one RHR pump de-energized at a time." There is neither a restriction for preventing or requiring the second OPERABLE RHR pump from being in operation. Therefore, the second pump does not need a Note governing its operation. Comed continues to pursue this change. (See RAI 3.4.8-05.)
                                                  =       ..
=
U     NRC RAI Number             NRC Issued Date                           RAI Status 3.4.8-05                     3/9/98                               Closed l
U NRC RAI Number NRC Issued Date RAI Status 3.4.8-05 3/9/98 Closed NRC Description of issue JFD P35 ITS LCO 3.4.8 Note 1 STS LCO 3.4.8 Note i CTS 3.4.1.4.2 Note "
NRC Description of issue                                                                                                     '
JFD P35 ITS LCO 3.4.8 Note 1 STS LCO 3.4.8 Note i CTS 3.4.1.4.2 Note "
JFD BP49 Bases for ITS LCO 3.4.8, STS Bases markup page B 3.4-38 ITS LCO 3.4.8 Note I states "All RHR pumps may be removed from operation for < l hour.. " STS 3.4.8 Note I states "All RHR pumrs may be de-energized for < 15 minutes when switching from one loop to another.. " CTS Footnote " states "The RHR pump may be de-energized for up to one hour.. "; without a stated reason for de-energizing. JFD P35 deals only with the stated reason for de-energizing the RHR pumps and misquotes the CTS footnote " as being applicable to all RHR pumps rather than one; so, adopt the STS text as is. If one hour is needed for each pump, then add a note to match the CTS requirement for one RHR pump de-energized at a time. Comment: Revise the submittal to adopt the STS or revise it consistent with the CTS, as described. Recommend coordinating the response to this comment with the response to comment 3.4.8-04.
JFD BP49 Bases for ITS LCO 3.4.8, STS Bases markup page B 3.4-38 ITS LCO 3.4.8 Note I states "All RHR pumps may be removed from operation for < l hour.. " STS 3.4.8 Note I states "All RHR pumrs may be de-energized for < 15 minutes when switching from one loop to another.. " CTS Footnote " states "The RHR pump may be de-energized for up to one hour.. "; without a stated reason for de-energizing. JFD P35 deals only with the stated reason for de-energizing the RHR pumps and misquotes the CTS footnote " as being applicable to all RHR pumps rather than one; so, adopt the STS text as is. If one hour is needed for each pump, then add a note to match the CTS requirement for one RHR pump de-energized at a time. Comment: Revise the submittal to adopt the STS or revise it consistent with the CTS, as described. Recommend coordinating the response to this comment with the response to comment 3.4.8-04.
Comed Response to issue j     See Comed Response to RAI 3.4.8-04.
Comed Response to issue j
See Comed Response to RAI 3.4.8-04.
p?
p?
  \
\\ wJ l
wJ l                                                                       19 l
19 l
l l
l l


(                   .-
(
: =-                                                 . -          = .
: =-
L                                                         Respanse to NRC RAI Fcr ITS Secti n 3.4                                       owoct-98
=.
  ,                    NRC RAI Number             NRC INed Date' ~^                           RAI Status I
L Respanse to NRC RAI Fcr ITS Secti n 3.4 owoct-98 NRC RAI Number NRC INed Date' ~^
      .,m 3.               3.4.8-05                     3/9/98                                   Closed
RAI Status I
,k)                 NRC Description of issue l                   DOC A25 '
.,m.
3.4.8-05 3/9/98 Closed 3
,k)
NRC Description of issue l
DOC A25 '
JFD P39 ITS SR 3.4.8.1.
JFD P39 ITS SR 3.4.8.1.
CTS 4.4.1.4.2 JFD BP39
CTS 4.4.1.4.2 JFD BP39
                  . CTS 4.4.1.4.2 states "At least one RHR loop shall be verified in operation and circulating reactor coolant.. " ITS SR 3.4.8 revises this requirement to state this verification is for the " required" RHR loop in operation. This change introduces an ambiguity that is not present in the STS. The SR does not try to determine which is the " required" RCS or RHR in operation, but explicitly, states thtt any loop must be in operation. Comment: Adopt the STS text which is consistent with the CTS requirement.
. CTS 4.4.1.4.2 states "At least one RHR loop shall be verified in operation and circulating reactor coolant.. " ITS SR 3.4.8 revises this requirement to state this verification is for the " required" RHR loop in operation. This change introduces an ambiguity that is not present in the STS. The SR does not try to determine which is the " required" RCS or RHR in operation, but explicitly, states thtt any loop must be in operation. Comment: Adopt the STS text which is consistent with the CTS requirement.
Comed Response to issue See Comed Response to RAI 3.4.7-05.                                                                                           I
Comed Response to issue See Comed Response to RAI 3.4.7-05.
                                        .y._ ;-- , ,-          -.-
I
NRC RAI Number               NRC Issued Dete                             RAI Status 3.4.8-07                     3/9/98                                   Closed NRC Description of issue DOC M2 CTS 3.4.1.4.2 Footnote *
.y._
NRC RAI Number NRC Issued Dete RAI Status 3.4.8-07 3/9/98 Closed NRC Description of issue DOC M2 CTS 3.4.1.4.2 Footnote *
* ITS LCO 3.4.8 Note Ic
* ITS LCO 3.4.8 Note Ic
      'q     -
'q
                ' CTS 3.4.1.4.2 Footnote " shows the additions of a Note 3 to this footnote; however, the footnote does not match the note in
' CTS 3.4.1.4.2 Footnote " shows the additions of a Note 3 to this footnote; however, the footnote does not match the note in
: the ITS. The wording of this note which is adopted from the STS has been editorially enhanced. The acceptable wording is i
: the ITS. The wording of this note which is adopted from the STS has been editorially enhanced. The acceptable wording is as follows "(3) No draining operations are permitted that would further reduce the RCS water volume." Comment: Revise i
as follows "(3) No draining operations are permitted that would further reduce the RCS water volume." Comment: Revise the CTS markup to be consistent with the 1TS.                                                                                   I Comed Response to issue Comed will revise the CTS markup to be consistent with the ITS. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
the CTS markup to be consistent with the 1TS.
I Comed Response to issue Comed will revise the CTS markup to be consistent with the ITS. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
i l
i l
i                     NRC RAI Number               NRC issued Date                             RAI Status                                         j 3.4.8-08                     3/9/98                                   Closed
i NRC RAI Number NRC issued Date RAI Status j
3.4.8-08 3/9/98 Closed
{
{
NRC Description of Issue DOC M13 CTS 3/4.4.1.4.2 Action b STS 3.4.8 Action B ITS 3.4.8 Action A, B & C CTS 3/4.4.1,4.2 Action b eddresses the Condition of no RHR loop in operation. STS 3.4.8 Action B provides Required Actions with Required RHR loops inoperable OR no RHR loop in operation. The compensatory Actions for both the CTS and STS are the same. DOC M13 states "ITS LCO 3.4.7 and ITS LCO 3.4.8, Condition C, adds the Condition, two required RHR loops inoperable. This Condition does not exist in CTS." Two inoperable RHR loops are the same as no RHR loop in' operation in Mode 5. There is no change here but an equivalence between the CTS and the STS which is obscured by the l                   reformatting of the LCO under JFD P10. Comment: Withdraw the change and adopt the STS Conditions, as written. See
NRC Description of Issue DOC M13 CTS 3/4.4.1.4.2 Action b STS 3.4.8 Action B ITS 3.4.8 Action A, B & C CTS 3/4.4.1,4.2 Action b eddresses the Condition of no RHR loop in operation. STS 3.4.8 Action B provides Required Actions with Required RHR loops inoperable OR no RHR loop in operation. The compensatory Actions for both the CTS and STS are the same. DOC M13 states "ITS LCO 3.4.7 and ITS LCO 3.4.8, Condition C, adds the Condition, two required RHR loops inoperable. This Condition does not exist in CTS." Two inoperable RHR loops are the same as no RHR loop in' operation in Mode 5. There is no change here but an equivalence between the CTS and the STS which is obscured by the l
[                   comment 3.4.7-07.
reformatting of the LCO under JFD P10. Comment: Withdraw the change and adopt the STS Conditions, as written. See
j                   Comed ' Response to issue
[
,(                 See Comed Response to RAI 3.4.7-07.
comment 3.4.7-07.
J' .
j Comed ' Response to issue
,(
J'.
See Comed Response to RAI 3.4.7-07.
20 l-
20 l-


                                  ==_ -                   = = -                   .= - ..
==_ -
Respons: to NRC RAI For ITS Section 3A                                       09-oci-98
= = -
                        = = = = ,~-...= = = =_:: = : _                                   ~ . : .
.= -..
NRC RAI Number               NRC issued Date                         RAI Status n                 3.4.8-09                   3/9/98                               Closed I   \-
Respons: to NRC RAI For ITS Section 3A 09-oci-98
l  () -     ' NRC Description of issue -
= = = =,~-...= = = =_:: = : _
JFD BPI Bases for ITS LCO 3.4.8. STS Bases markup page B 3.4-37 in the first paragraph pertaining to the discussion of any combination of two RCS or RHR loops. the ITS does not adopt the STS reason for " meeting single failure considerations" but adds in its place the words " provide adequate redundancy for decay heat removal" Comment: This is not ajustifiable plant-specific or editorial difference. Revise the submittal to adopt
~. :.
          = the STS text.
NRC RAI Number NRC issued Date RAI Status n
3.4.8-09 3/9/98 Closed I
\\-
() -
' NRC Description of issue -
l JFD BPI Bases for ITS LCO 3.4.8. STS Bases markup page B 3.4-37 in the first paragraph pertaining to the discussion of any combination of two RCS or RHR loops. the ITS does not adopt the STS reason for " meeting single failure considerations" but adds in its place the words " provide adequate redundancy for decay heat removal" Comment: This is not ajustifiable plant-specific or editorial difference. Revise the submittal to adopt
= the STS text.
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revis on upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.7-10.)
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revis on upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.7-10.)
                                = . = . _ = = = _ = = -               = - - - . -====
=. =. _ = = = _ = = -
NRC RAI Number -           NRC issued Date                           RAI Status 3.4.9-01                     3/9/98                               Closed NRC Description ofIssue JFD P40 ITS 3.4.9 Action B CTS 3/4.4.3 Action a ITS 3.4.9 Action B, corresponding to CTS 3/4.43 Action a, allows both required groups of pressurizer hesters to be inoperhble for 72 hours. In this condition, the pressurizer heater function is lost. Also, it is possible under the multiple p         condition entry convention of the STS, that the pressurizer level could be concurrently inoperable. Were this to occur, none e        of the LCO requirements would be met - which produces a loss of function condition for this LCO. Corresponding STS L.     ' 3.4.9 Action B permits only one group of heaters to be inoperable for 72 hours only while an Operable redundant group is Operable. Therefore, this is not consistent with the Bases as the technicaljustification states. NUREG-0452 on which the CTS is based does not permit both pressurizer heater groups to be inoperable.
= - - -. -====
NRC RAI Number -
NRC issued Date RAI Status 3.4.9-01 3/9/98 Closed NRC Description ofIssue JFD P40 ITS 3.4.9 Action B CTS 3/4.4.3 Action a ITS 3.4.9 Action B, corresponding to CTS 3/4.43 Action a, allows both required groups of pressurizer hesters to be inoperhble for 72 hours. In this condition, the pressurizer heater function is lost. Also, it is possible under the multiple p
condition entry convention of the STS, that the pressurizer level could be concurrently inoperable. Were this to occur, none of the LCO requirements would be met - which produces a loss of function condition for this LCO. Corresponding STS e
L.
' 3.4.9 Action B permits only one group of heaters to be inoperable for 72 hours only while an Operable redundant group is Operable. Therefore, this is not consistent with the Bases as the technicaljustification states. NUREG-0452 on which the CTS is based does not permit both pressurizer heater groups to be inoperable.
JFD BP40 JFD BPI JFD BP3 Bases discussions of Required Actions B.1, C.1, and C.2, STS Bases markup page B 3.4-43.
JFD BP40 JFD BPI JFD BP3 Bases discussions of Required Actions B.1, C.1, and C.2, STS Bases markup page B 3.4-43.
Acceptance of the changes to the two Bases discussions listed are continpn. upon resolution of the ditTerences addressed by JFD P40. JFDs BPI and BP3 are linked to JFD BP40. Comment: Reference the NRC safety evaluation which made this change to allow both required groups to be inoperable, or adopt the more restrictive requirements of the STS.
Acceptance of the changes to the two Bases discussions listed are continpn. upon resolution of the ditTerences addressed by JFD P40. JFDs BPI and BP3 are linked to JFD BP40. Comment: Reference the NRC safety evaluation which made this change to allow both required groups to be inoperable, or adopt the more restrictive requirements of the STS.
Line 493: Line 584:
Original Response: The Actions Section of the Bases for ITS LCO 3.4.9 will be revised to state, "If the required groups of pressurizer heaters are inoperable, restoration is required within 72 hours. The Completion Time of 72 hours is reasonable '
Original Response: The Actions Section of the Bases for ITS LCO 3.4.9 will be revised to state, "If the required groups of pressurizer heaters are inoperable, restoration is required within 72 hours. The Completion Time of 72 hours is reasonable '
considering the anticipation that a demand caused by loss of offsite power would be unlikely in this period. Pressure control may be maintained during this time using the remaining pressurizer heater capability." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
considering the anticipation that a demand caused by loss of offsite power would be unlikely in this period. Pressure control may be maintained during this time using the remaining pressurizer heater capability." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
O L).
OL).
21
21


Response to NRC RAI For ITS Section 3.4                                   owoci-98
Response to NRC RAI For ITS Section 3.4 owoci-98
                  ..                      :    -                                                                                          .)
.)
NRC RAI Number               NRC issued Date                           RAI Status s            3.4.9-02                   3/9/98                               Closed l
NRC RAI Number NRC issued Date RAI Status 3.4.9-02 3/9/98 Closed
                                                                                                                                              )
)
NRC Description ofIssue JFD BP41                                                                                                                           '
l s
JFD BP48 l
NRC Description ofIssue JFD BP41 JFD BP48 Bases for ITS LCO 3.4.9, STS Bases markup page B 3.4-41
Bases for ITS LCO 3.4.9, STS Bases markup page B 3.4-41                                                                             )
)
l In the second paragraph of the STS Bases states that the two required pressurizer heater groups are " capable of being             l powered from either the offsite power source or the emergency power supply." The ITS replaces these words with the                   I statement that the heater groups are " capable of being powered from an ESF power supplied bus." and omits mformation
In the second paragraph of the STS Bases states that the two required pressurizer heater groups are " capable of being powered from either the offsite power source or the emergency power supply." The ITS replaces these words with the I
                                                                                                                                              )
statement that the heater groups are " capable of being powered from an ESF power supplied bus." and omits mformation regarding the capability of being powered from an offsite power source. In addition, the ITS adds a sentence to explam that offsite (normal) power is not required for pressurizer heater operability. Comment: The proposed ditTerences from the Bases are unnecessary because the ITS definition of operability requires either emergency or offsite power. not both, for the supported system to be operable. Revise the Bases to adopt the STS wording.
regarding the capability of being powered from an offsite power source. In addition, the ITS adds a sentence to explam that           I offsite (normal) power is not required for pressurizer heater operability. Comment: The proposed ditTerences from the Bases are unnecessary because the ITS definition of operability requires either emergency or offsite power. not both, for the supported system to be operable. Revise the Bases to adopt the STS wording.
)
                                                                                                                                              )
Comed Response to issue ITS LCO 3.4.9 item b is being revised to state, "Two groups of pressurizer heaters OPERABLE with.. and capable of beMe i
Comed Response to issue ITS LCO 3.4.9 item b is being revised to state, "Two groups of pressurizer heaters OPERABLE with . . and capable of beMe           i powered from redundant Engineered Safety Feature (ESF) power supplied buses." Correspondingly, the second paragraph in the LCO Section of the Bases for ITS LCO 3.4.9 is being revised to state, "The LCO requires two groups . , capable of being powered from redundant ESF power supplied buses." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.                         I l'
powered from redundant Engineered Safety Feature (ESF) power supplied buses." Correspondingly, the second paragraph in the LCO Section of the Bases for ITS LCO 3.4.9 is being revised to state, "The LCO requires two groups., capable of being powered from redundant ESF power supplied buses." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
The pressurizer heaters are non-safety related. Plant design consists of a total heater capacity of 1800 kw which is divided into four groups ( A, B, C, and D) with separate controls for the proportional group (C) and the back up groups ( A' B, and D). Heater groups A and D are supplied by non-ESF bus 143, while groups B and C are supplied from non-ESF bus 144.
l The pressurizer heaters are non-safety related. Plant design consists of a total heater capacity of 1800 kw which is divided into four groups ( A, B, C, and D) with separate controls for the proportional group (C) and the back up groups ( A' B, and D). Heater groups A and D are supplied by non-ESF bus 143, while groups B and C are supplied from non-ESF bus 144.
The non-ESF buses servicing the pressurizer heaters (buses 143 and 144) can be powered by either the Unit Auxiliary Transformer (UAT), or the unit specific System Auxiliary Transformer (SAT) which is termed " normal power" per ITS p     Section 3.8. The ESF buses (buses 141 and 142) can be powered by the unit specific SAT (which is termed " normal power" V     per ITS Section 3.8), the opposite-unit SAT (which is termed " reserve power" per ITS Section 3.8), or the emergency diesel generator. The ESF buses must be capable of powering, via a cross-tie. the non-ESF buses to satisfy ITS SR 3.4.9.3.
The non-ESF buses servicing the pressurizer heaters (buses 143 and 144) can be powered by either the Unit Auxiliary Transformer (UAT), or the unit specific System Auxiliary Transformer (SAT) which is termed " normal power" per ITS p
Therefore, the statement in the LCO Section of the Bases for ITS LCO 3.4.9 "The LCO requires two groups . , capable of being powered from redundant ESF power supplied buses" reflects the current plant design. Since the only safety function for pressurizer heaters is in a loss of offsite power condition, normal power is not required for OPERABILITY. That is,
Section 3.8. The ESF buses (buses 141 and 142) can be powered by the unit specific SAT (which is termed " normal power" V
        " normal" power to a non-ESF bus is not required. but rather the non-ESF bus must be capable of being powered from an ESF bus. Comed continues to pursue this change.
per ITS Section 3.8), the opposite-unit SAT (which is termed " reserve power" per ITS Section 3.8), or the emergency diesel generator. The ESF buses must be capable of powering, via a cross-tie. the non-ESF buses to satisfy ITS SR 3.4.9.3.
NRC RAI Number               NRC issued Date                           RAI Status 3.4.9-03                     3/9/98                               Closed NRC Description ofissue JFD BPI Bases for ITS SR 3.4.9.1, STS Bases markup page B 3.4-43 The first sentence of the first paragraph of the listed ITS Bases discussion differs from the STS as follows: "This SR requires that during steady state operation, pressurizer level to be maintained below the nominal upper limit to provide a minimum space for a steam bubble." Comment: This difference is not justifiable on a plant-specific or editorial basis. The STS sentence is clear. Revise the Bases to adopt the STS words.
Therefore, the statement in the LCO Section of the Bases for ITS LCO 3.4.9 "The LCO requires two groups., capable of being powered from redundant ESF power supplied buses" reflects the current plant design. Since the only safety function for pressurizer heaters is in a loss of offsite power condition, normal power is not required for OPERABILITY. That is,
Comed Response to issue Comed will revise the Bases to adopt the STS wording. This change will be provided in our comprehensive iTS Section 3.4 closeout submittal revision upo- RC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
" normal" power to a non-ESF bus is not required. but rather the non-ESF bus must be capable of being powered from an ESF bus. Comed continues to pursue this change.
p a
NRC RAI Number NRC issued Date RAI Status 3.4.9-03 3/9/98 Closed NRC Description ofissue JFD BPI Bases for ITS SR 3.4.9.1, STS Bases markup page B 3.4-43 The first sentence of the first paragraph of the listed ITS Bases discussion differs from the STS as follows: "This SR requires that during steady state operation, pressurizer level to be maintained below the nominal upper limit to provide a minimum space for a steam bubble." Comment: This difference is not justifiable on a plant-specific or editorial basis. The STS sentence is clear. Revise the Bases to adopt the STS words.
22
Comed Response to issue Comed will revise the Bases to adopt the STS wording. This change will be provided in our comprehensive iTS Section 3.4 closeout submittal revision upo-RC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
pa 22


f
f
                                                                                            . = = _
. = = _
R spanse to NRC RAI For ITS S:ctinn 3.4                                       09-Oci-98
R spanse to NRC RAI For ITS S:ctinn 3.4 09-Oci-98
                                      - = .. - . . =           ,                  .- -          -.
- =.. -.. =
NRC RAI Number           . NRC issued Date                               RAI Status
NRC RAI Number
    /
. NRC issued Date RAI Status
x.\^              '3.4.10-01'                 3'/9'98                                   Closed i
'3.4.10-01' 3'/9'98 Closed x.
    .(f             NRC Description cfIssue Not used
/
,                  Comed Response to issue -
\\^
.(f NRC Description cfIssue i
Not used Comed Response to issue -
No response required.
No response required.
NRC RAI Number .             NRC lssued Date                               RAI Status 3.4.10-02                   3'9 98                                   Closed NRC Description ofIssue
NRC RAI Number.
              - DOC M17 CTS 3.4.2.2 and Footnote
NRC lssued Date RAI Status 3.4.10-02 3'9 98 Closed NRC Description ofIssue
- DOC M17 CTS 3.4.2.2 and Footnote
* ITS 3.4.10 Applicability Note CTS 3.4.2.2 and Footnote
* ITS 3.4.10 Applicability Note CTS 3.4.2.2 and Footnote
* requires the pressurizer safety valves to be set within the lift setting limits at normal operating temperature and pressure. The Applicability Note to ITS 3.4.10 allows entry into Mode 3 at normr.i operating temperature and pressure for up to 54 hours to set the lift settings at normal operating temperature and pressure. CTS 3.4.2.2 has no exception to CTS 3.0.4. Thus, if the IST requirements for setting the valves to within 1% of the setpoint are due, there is no basis for entering Mode 3 without first verifying the Operability of the safety valves at normal operating temperature and pressure (perhaps bench testing with a suitable test rig is implied, as opposed to in-situ testing). Assuming the hot setting is required by the IST, and provided that the cold settings have been completed, the ITS note allows entry inte Mode 3, but requires completing the hot settings within 54 hours following entery into Mode 3. This limited time period is sufficient to set the pressurizer safety valves under normal operating ambient conditions. Adoption of the STS allowance granted by this note constitutes a less restrictive change to the CTS. Comment: Revise the submittal by replacing DOC M17 with a less g           restrictive CTS changejustification. In the response to this comment, describe current IST practices for cold and hot setting j      t      of the pressurizer safety valves and how they are consistent with the CTS requirements and whether any changes are needed d           to be consistent with the ITS requirements.
* requires the pressurizer safety valves to be set within the lift setting limits at normal operating temperature and pressure. The Applicability Note to ITS 3.4.10 allows entry into Mode 3 at normr.i operating temperature and pressure for up to 54 hours to set the lift settings at normal operating temperature and pressure. CTS 3.4.2.2 has no exception to CTS 3.0.4. Thus, if the IST requirements for setting the valves to within 1% of the setpoint are due, there is no basis for entering Mode 3 without first verifying the Operability of the safety valves at normal operating temperature and pressure (perhaps bench testing with a suitable test rig is implied, as opposed to in-situ testing). Assuming the hot setting is required by the IST, and provided that the cold settings have been completed, the ITS note allows entry inte Mode 3, but requires completing the hot settings within 54 hours following entery into Mode 3. This limited time period is sufficient to set the pressurizer safety valves under normal operating ambient conditions. Adoption of the STS allowance granted by this note constitutes a less restrictive change to the CTS. Comment: Revise the submittal by replacing DOC M17 with a less g
restrictive CTS changejustification. In the response to this comment, describe current IST practices for cold and hot setting of the pressurizer safety valves and how they are consistent with the CTS requirements and whether any changes are needed j
t d
to be consistent with the ITS requirements.
Comed Response to issue Revised Response: Refer to CTS DOC 3.4 L38. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.'
Comed Response to issue Revised Response: Refer to CTS DOC 3.4 L38. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.'
Original Response: DOC M17 will be changed to an 'L' DOC (less restrictive change), and will state, " CTS 3.4.2.2 Footnote
Original Response: DOC M17 will be changed to an 'L' DOC (less restrictive change), and will state, " CTS 3.4.2.2 Footnote
* require , the pressurizer safety valve lift setting pressure correspond to ambient conditions of the valve at nominal operating temperature and pressure. The Applicability of the CTS requirement is in Modes I,2, and 3. Therefore, complying with the CTS, the lift setting must be set at operating temperature and pressure prior to entering Mode 3. The ITS LCO 3.4.10 LCO Note allows entry into Mode 3 with the lift settings outside the LCO limits. This permits testing and examination of the safety valves at high pressure and temperature near their normal operating range, but only after the valves have had a preliminary cold setting.. This change represents a less restrictive change, and is consistent with NUREG-1431." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
* require, the pressurizer safety valve lift setting pressure correspond to ambient conditions of the valve at nominal operating temperature and pressure. The Applicability of the CTS requirement is in Modes I,2, and 3. Therefore, complying with the CTS, the lift setting must be set at operating temperature and pressure prior to entering Mode 3. The ITS LCO 3.4.10 LCO Note allows entry into Mode 3 with the lift settings outside the LCO limits. This permits testing and examination of the safety valves at high pressure and temperature near their normal operating range, but only after the valves have had a preliminary cold setting.. This change represents a less restrictive change, and is consistent with NUREG-1431." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
1 v' .
1 v'.
23
23


;              -:-=_                 -
-:-=_
                                                          = = . = -               ,
= =. = -
Response to NRC RAI For ITS Section 3.4                                           09-Oci-98
Response to NRC RAI For ITS Section 3.4 09-Oci-98
__..7           _,          .
__..7 NRC RAI Number NRC issued Date RAI Status n
NRC RAI Number               NRC issued Date                             RAI Status n           ' ' 10-03                   3/9/98                                 Closed i   1
' ' 10-03 3/9/98 Closed i
  . V     NRC Description of issue JFD P13 ITS 3.4.10 Applicability Note JFD BPl3 Bases for Applicability ofITS 3.4.10, STS Bases markup page B 3.4-47 i
1
. V NRC Description of issue JFD P13 ITS 3.4.10 Applicability Note JFD BPl3 Bases for Applicability ofITS 3.4.10, STS Bases markup page B 3.4-47 i
The ITS proposes to place the STS 3.4.10' Applicability Note with the LCO statement as an editorial enhancement to preclude misinterpretations ofITS SR 3.0.4. Staff disagrees with this technical basis. This difference is genene and shoulJ be submitted as a generic change to the STS. Comment: Withdraw this deviation from the STS, and adopt the STS format.
The ITS proposes to place the STS 3.4.10' Applicability Note with the LCO statement as an editorial enhancement to preclude misinterpretations ofITS SR 3.0.4. Staff disagrees with this technical basis. This difference is genene and shoulJ be submitted as a generic change to the STS. Comment: Withdraw this deviation from the STS, and adopt the STS format.
This change occurs frequently in this submittal; thus the response to this comment should be global over the whole submittal. This comment likely occurs in other sections. A single response with references to it is acceptable.
This change occurs frequently in this submittal; thus the response to this comment should be global over the whole submittal. This comment likely occurs in other sections. A single response with references to it is acceptable.
Comed Response to issue                                                                                                         1 See Comed Response to RAI 3.4.1-04. (See RAls 3.1.5-01,3.1.6-01,3.4.1-04, and 3.4.12-01 Item b.)
Comed Response to issue See Comed Response to RAI 3.4.1-04. (See RAls 3.1.5-01,3.1.6-01,3.4.1-04, and 3.4.12-01 Item b.)
                                          ~~.~-^r-"-.     ,    ...._.~~                   ~2 I
~~.~-^r-"-.
NRC RAI Number               NRC issued Date                             RAI Status 3.4.10-04                     3/9/98                                 Closed NRC Description of issue JFD P33 ITS SR 3.4.10.1 JFD BP38                                                                                                                         I Bases for ITS SR 3.4.10.1, STS Bases markup page B 3.4-48 n     ITS SR 3.4.10.1 omits the last sentence of STS SR 3.4.10.1, "Following testing, lift settings shall be within 1%". because the (d'
.... _. ~ ~
4 licensee believes the LCO and Bases are inconsistent. The staff disagrees. In addition, omission of this sentence from the
~2 I
                  ^
NRC RAI Number NRC issued Date RAI Status 3.4.10-04 3/9/98 Closed NRC Description of issue JFD P33 ITS SR 3.4.10.1 JFD BP38 Bases for ITS SR 3.4.10.1, STS Bases markup page B 3.4-48 n
STS would require a generic change. Comment: Revise ITS SR 3.4.10.1 to adopt the sentence omitted from STS SR 3.4.10.1.
ITS SR 3.4.10.1 omits the last sentence of STS SR 3.4.10.1, "Following testing, lift settings shall be within 1%". because the (d'
licensee believes the LCO and Bases are inconsistent. The staff disagrees. In addition, omission of this sentence from the 4
^
Revise ITS SR 3.4.10.1 to adopt the sentence omitted from STS SR STS would require a generic change. Comment:
3.4.10.1.
Comed Response to issue Comed will revise ITS SR 3.4.10.1 to adopt the sentence omitted from STS SR 3.4.10.1. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise ITS SR 3.4.10.1 to adopt the sentence omitted from STS SR 3.4.10.1. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
NRC RAI Number               NRC lssued Date                             RAI Stata 3.4.10-05                     3/9/98                                 Closed NRC Description of issue DOC Ml7                                                                                                                         l JFD B43                                                                                                                         I ITS 3.4.10 Applicability Note The Applicability note has been modified in the second sentence by identifying Mode 3 as the " normal operating temperature and pressure" where the lift settings are verified. The insertion of this text is redundant to the earlier sentence where the
NRC RAI Number NRC lssued Date RAI Stata 3.4.10-05 3/9/98 Closed NRC Description of issue DOC Ml7 l
        " ambient (hot) conditions" are discussed.' These changes to the note are not accepted.
JFD B43 ITS 3.4.10 Applicability Note The Applicability note has been modified in the second sentence by identifying Mode 3 as the " normal operating temperature and pressure" where the lift settings are verified. The insertion of this text is redundant to the earlier sentence where the
" ambient (hot) conditions" are discussed.' These changes to the note are not accepted.
Note: This modification is also shown in CTS change with M17 DOC but is not separately identified. Comment: Revise the submittal to adopt the STS text of the Applicability Note.
Note: This modification is also shown in CTS change with M17 DOC but is not separately identified. Comment: Revise the submittal to adopt the STS text of the Applicability Note.
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4
Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
,        closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
(nv)
{
{
l (nv)                                                                                                                                  I i
l i
24 l
24 1
I 1
l
l


                              . m.               ,_              ._ m = _ _ ,                     __
. m.
R:sponse to NRC RAI For ITS S:ction 3.4                                   09-Oct 98 NRC RAI Number               NRC issued Date                           RAI Status
._ m = _ _,
      - --c         3.4.11-01                   3/9/98                                 Closed NRC Description of issue DOC A10 JFD Pl4 DOC L8 JFD Cl2
R:sponse to NRC RAI For ITS S:ction 3.4 09-Oct 98 NRC RAI Number NRC issued Date RAI Status
!            CTS 3/4.4.4 Actions a through d ITS 3.4.11 Actions B, D, E, F, & G JFD BCl3 Bases for ITS Required actions D.1 and D.2. Insert B 3.4-54A, STS Bases markup page B 3.4-54 a The Applicability ofITS 3.4.11 is Modes 1,2. and 3, yet the action requirements never require exiting Mode 3 (RCS average temperature below 350 degrees Fahrenheit), only going to Mode 3 with RCS average temperature below 500 degrees
. --c 3.4.11-01 3/9/98 Closed NRC Description of issue DOC A10 JFD Pl4 DOC L8 JFD Cl2 CTS 3/4.4.4 Actions a through d ITS 3.4.11 Actions B, D, E, F, & G JFD BCl3 Bases for ITS Required actions D.1 and D.2. Insert B 3.4-54A, STS Bases markup page B 3.4-54 a The Applicability ofITS 3.4.11 is Modes 1,2. and 3, yet the action requirements never require exiting Mode 3 (RCS average temperature below 350 degrees Fahrenheit), only going to Mode 3 with RCS average temperature below 500 degrees
            ' Fahrenheit which is addressed by DOC L8 and JFD C12. based on TSTF-l l3 which is still pending with the staff. This is illogical. Comment: Revise the submittal to adopt the STS shutdown requirements which are consistent with the CTS action requirements.
' Fahrenheit which is addressed by DOC L8 and JFD C12. based on TSTF-l l3 which is still pending with the staff. This is illogical. Comment: Revise the submittal to adopt the STS shutdown requirements which are consistent with the CTS action requirements.
: b. The submittal does notjustify adding block valves to STS 3.4.11 Actions Note I and allowing separate Condition entry for inoperable PORVs and block valves. The reasons given in DOC A10 and JFD P14 are insufficient tojustify these changes and differences. The licensee's perception stated in 170C A10 that separate Condition entry is the intent of the CTS action requirements is incorrect. Comment: Revise the submittal with a L-type technicaljustification for allowing separate Condition entry for the PORVs and associated block valves. Revise JFD Pl4 with a plant-specific justification for adding block valves to STS 3.4.11 Actions Note I allowing separate Condition entry. Otherwise, adopt the STS version of the note.
: b. The submittal does notjustify adding block valves to STS 3.4.11 Actions Note I and allowing separate Condition entry for inoperable PORVs and block valves. The reasons given in DOC A10 and JFD P14 are insufficient tojustify these changes and differences. The licensee's perception stated in 170C A10 that separate Condition entry is the intent of the CTS action requirements is incorrect. Comment: Revise the submittal with a L-type technicaljustification for allowing separate Condition entry for the PORVs and associated block valves. Revise JFD Pl4 with a plant-specific justification for adding block valves to STS 3.4.11 Actions Note I allowing separate Condition entry. Otherwise, adopt the STS version of the note.
Comed Response to issue Comed Response to NRC Comment a: Comed will revise the submittal to adopt the STS text and withdraw TSTF-l 13 from Q         the submittal. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's Q         concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed Response to NRC Comment b; TSTF-247 revises NUREG LCO 3.4.l l to allow separate condition entry for each block valve, and thereby eliminating bracketed Required Action F.3. This change was proposed by Byron and Braidwood and has been approved by TSTF LCO JFD 3.4-Pl4 will be revised to state,"NUREG and ITS LCO 3.4.1 I allow separate condition entry for each PORV. The Conditions and Required Actions provide appropriate compensatory measures for separate condition entry. ITS has been modified to add the phrase, " Separate Condition entry is allowed for each PORV and each block valve," consistent with TSTF-247. In the event a PORV becomes inoperable and not capable of being manually cycled (Condition B), the Required Action is to close the associated block valve and remove power from the block valve within 1 hour in accordance with the Bases, once power is removed from the block valve, it is no longer OPERABLE and Condition C is also entered. Per ITS Required Action B.3, the inoperable PORV is to be restored within 72 hours. Required Action C.2 requires the inoperable block valve to be restored to OPERABLE (restore power) within 72 hours. In the event the second PORV becomes inoperable, Condition E Required Actions require the associated block valve to be closed and power removed from the valve, rendering it inoperable. Condition B is re-entered for the second PORV. This results in 2 PORVs and 2 block valves inoperable and Condition F is entered for 2 inoperable block valves. If the first PORV is restored to OPERABLE, Condition E is exited.
Comed Response to issue Comed Response to NRC Comment a: Comed will revise the submittal to adopt the STS text and withdraw TSTF-l 13 from Q
the submittal. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's Q
concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed Response to NRC Comment b; TSTF-247 revises NUREG LCO 3.4.l l to allow separate condition entry for each block valve, and thereby eliminating bracketed Required Action F.3. This change was proposed by Byron and Braidwood and has been approved by TSTF LCO JFD 3.4-Pl4 will be revised to state,"NUREG and ITS LCO 3.4.1 I allow separate condition entry for each PORV. The Conditions and Required Actions provide appropriate compensatory measures for separate condition entry. ITS has been modified to add the phrase, " Separate Condition entry is allowed for each PORV and each block valve," consistent with TSTF-247. In the event a PORV becomes inoperable and not capable of being manually cycled (Condition B), the Required Action is to close the associated block valve and remove power from the block valve within 1 hour in accordance with the Bases, once power is removed from the block valve, it is no longer OPERABLE and Condition C is also entered. Per ITS Required Action B.3, the inoperable PORV is to be restored within 72 hours. Required Action C.2 requires the inoperable block valve to be restored to OPERABLE (restore power) within 72 hours. In the event the second PORV becomes inoperable, Condition E Required Actions require the associated block valve to be closed and power removed from the valve, rendering it inoperable. Condition B is re-entered for the second PORV. This results in 2 PORVs and 2 block valves inoperable and Condition F is entered for 2 inoperable block valves. If the first PORV is restored to OPERABLE, Condition E is exited.
leaving Condition B entry for the second PORV with the remainder ofits 72 hours available in order to restore it to OPERABLE status.13owever, without separate Condition entry for the block valves, the second PORV and associated block valve must be restured to OPERABLE within the initial 72 hour clock of the first block valve. If the second PORV and associated block valve are not restored within this initial 72 hours, Condition D is entered which requires the unit to be shutdown. As provided for the PORVs, the Conditions and Required Actions also provide appropriate compensatory actions for separate condition entry for each block valve. Thus, the Actions Note is modified to allow separate condition entry for each block valve." Comed continues to pursue this change.
leaving Condition B entry for the second PORV with the remainder ofits 72 hours available in order to restore it to OPERABLE status.13owever, without separate Condition entry for the block valves, the second PORV and associated block valve must be restured to OPERABLE within the initial 72 hour clock of the first block valve. If the second PORV and associated block valve are not restored within this initial 72 hours, Condition D is entered which requires the unit to be shutdown. As provided for the PORVs, the Conditions and Required Actions also provide appropriate compensatory actions for separate condition entry for each block valve. Thus, the Actions Note is modified to allow separate condition entry for each block valve." Comed continues to pursue this change.
    /~'N *.
/~'N.
t 25
t 25


                                          ._._____m           _
._._____m R:sp::nse to NRC RAI Fer ITS S:ction 3A 09-oct-98 NRC RAI Number NRC issued Date RAI Status l
R:sp::nse to NRC RAI Fer ITS S:ction 3A                                         09-oct-98 NRC RAI Number               NRC issued Date                         RAI Status                                                             l 73                   3.4.11-02             3'9'98                                   Closed
73 3.4.11-02 3'9'98 Closed
  \s)       NRC Description ofissue DOC Al CTS 4.4.4.1 The first phrase of CTS 4.4.4.1, "In addition to the requirements of the Specif'.; non 4.0.5, each PORY shall be demonstrated . ", has not been retained m the Surveillance Requirements ofITS 3.4.11. This omission is mcorrectly categorized as an administrative change by DOC Al. It is a specific technical change which must be discussed and justitied separately. Comment: Revise the submittal with a technicaljustification for thn CTS change.
'\\s)
NRC Description ofissue DOC Al CTS 4.4.4.1 The first phrase of CTS 4.4.4.1, "In addition to the requirements of the Specif'.; non 4.0.5, each PORY shall be demonstrated. ", has not been retained m the Surveillance Requirements ofITS 3.4.11. This omission is mcorrectly categorized as an administrative change by DOC Al. It is a specific technical change which must be discussed and justitied separately. Comment: Revise the submittal with a technicaljustification for thn CTS change.
Comed Response to issue DOC A33 was created to discuss CTS Specification 4.0.5 relocation. DOC A33 states. " CTS Specification 4.0.5 prosides surveillance requirements for inservice inspection and testing of ASME Code Class 1. 2, and 3 components. In accordance with NUREG-1431, CTS Specification 4.0.5 has been relocated to ITS Specification 5.5.8. " Inservice Testing Program."
Comed Response to issue DOC A33 was created to discuss CTS Specification 4.0.5 relocation. DOC A33 states. " CTS Specification 4.0.5 prosides surveillance requirements for inservice inspection and testing of ASME Code Class 1. 2, and 3 components. In accordance with NUREG-1431, CTS Specification 4.0.5 has been relocated to ITS Specification 5.5.8. " Inservice Testing Program."
The requirements for Inservice Tssting have not changed and are still consistent with ASME Section XI. The requirements for the Inservice inspection are contained in 10 CFR 50.55a and therefore not included in the NUREG. This change has been justified in the ITS submittal as an administrative change throughout the CTS markups since no ASME or CTS laservice hsting requirements were changed. The only change that was made was in relocation of the requirements from CTS 4.0.5 to 113 5.5.8." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.12-07.)
The requirements for Inservice Tssting have not changed and are still consistent with ASME Section XI. The requirements for the Inservice inspection are contained in 10 CFR 50.55a and therefore not included in the NUREG. This change has been justified in the ITS submittal as an administrative change throughout the CTS markups since no ASME or CTS laservice hsting requirements were changed. The only change that was made was in relocation of the requirements from CTS 4.0.5 to 113 5.5.8." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.12-07.)
                                        =.                 - ~ = = = = . = . = _ =                         . . - -
=.
NRC RAI Number               NRC issued Date                         RAI Status s'.4.11-03             3/9/98                                   Closed NRC Description of issue
- ~ = = = =. =. = _ =
  ,- 3 JFD BP3
NRC RAI Number NRC issued Date RAI Status
        )
'.4.11-03 3/9/98 Closed s
(          Bases Background discussion for ITS 3.4.11, STS Bases markup
NRC Description of issue JFD BP3
< 'C       page B 3.4-50 l ne ITS Bases do not adopt the words which state normal power is "from the vital buses from offsite sources but are capable of being powered from emergency power sources"in the fifth paragraph of the Bases Background discussion for STS 3.4.11. This omission appears to contradict the discussion about PORV power sources in JFD. The proposed omission and related editorial changes result in misleading the reader into thinking that the PORVs only have emecgency power sources.
,- 3
(
)
Bases Background discussion for ITS 3.4.11, STS Bases markup
< 'C page B 3.4-50 l ne ITS Bases do not adopt the words which state normal power is "from the vital buses from offsite sources but are capable of being powered from emergency power sources"in the fifth paragraph of the Bases Background discussion for STS 3.4.11. This omission appears to contradict the discussion about PORV power sources in JFD. The proposed omission and related editorial changes result in misleading the reader into thinking that the PORVs only have emecgency power sources.
Comment: Revise the Bases ofITS 3.4.11 to conform to the STS Bases consistent with plant design.
Comment: Revise the Bases ofITS 3.4.11 to conform to the STS Bases consistent with plant design.
Comed kesponse to Issue Comed will revise the Bases ofITS 3.4.11 to conform to the STS Bases. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
Comed kesponse to Issue Comed will revise the Bases ofITS 3.4.11 to conform to the STS Bases. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
o 26
o 26


R:spensa to NRC RAI Fcr ITS Section 3.4                                   09-oci-98
R:spensa to NRC RAI Fcr ITS Section 3.4 09-oci-98
                                -          -..=..:-.         .: -- - -
-..=..:-.
NRC RAI Number               NRC issued Date                         RAI Status
NRC RAI Number NRC issued Date RAI Status
  . ;,3           i3.4.11-04                   3 9/98                                   Closed NRC Description ofissue -
. ;,3 i3.4.11-04 3 9/98 Closed NRC Description ofissue -
DOC LA8 CTS SR 4.4.4.1.a The licensee proposes to move the CTS requirement for Channel Calibration of the PORV actuation instrumentation to the TRM, but does not fully explain why specifying this requirement in TS is not necessary to ensure Operabihty of the PORY actuation instrumentation or how the retained surveillances ensure the Operability of this instrumentation. Commen:: Reuse l
DOC LA8 CTS SR 4.4.4.1.a The licensee proposes to move the CTS requirement for Channel Calibration of the PORV actuation instrumentation to the TRM, but does not fully explain why specifying this requirement in TS is not necessary to ensure Operabihty of the PORY actuation instrumentation or how the retained surveillances ensure the Operability of this instrumentation. Commen:: Reuse DOC LA8 to address the concerns noted.
DOC LA8 to address the concerns noted.
Comed Response to issue Comed will revise the ITS submittal to reflect our proposed resolution to the " Spurious Si at Power" issue. The CTS License Amendment Request (LAR)is expected to be docketed by April,30.1998. An ITS Revisi3n incorporating the CTS LAR will be submitted subsequently.
1 Comed Response to issue                                                                                                         I Comed will revise the ITS submittal to reflect our proposed resolution to the " Spurious Si at Power" issue. The CTS License Amendment Request (LAR)is expected to be docketed by April,30.1998. An ITS Revisi3n incorporating the CTS LAR will be submitted subsequently.                                                                                             l I
l
l
  .V
.V
                                                                                                                                            )
)
i I
i I
I I
I
  /%
/%
27
27


:        =-                                  -
=-
Respons2 to NRC RAI Fcr ITS Secti2n 3.4                                     09-oct-98
Respons2 to NRC RAI Fcr ITS Secti2n 3.4 09-oct-98
                                                      = ~:.              .
= ~:.
NRC RAI Number               NRC issued Date                           RAI Status 3.4.12 01                     3'/9'98                               Closed
NRC RAI Number NRC issued Date RAI Status 3.4.12 01 3'/9'98 Closed
      .f k         NRC D'escription ofissue DOC M7 JFD Pil JFD P19 JFD P21 JFD C9 (WOG 51); CIS (WOG 81)
.f k
NRC D'escription ofissue DOC M7 JFD Pil JFD P19 JFD P21 JFD C9 (WOG 51); CIS (WOG 81)
ITS 3.4.12: LCO, Actions A thru D, and SRs CTS 3/4.4.9.3; CTS 3/4.5.3; CTS 3/4.5.4.1 and CTS 3/4.5.42 ITS 3.4.12 and associated Bases contain extensise deviations from STS 3.4.12.
ITS 3.4.12: LCO, Actions A thru D, and SRs CTS 3/4.4.9.3; CTS 3/4.5.3; CTS 3/4.5.4.1 and CTS 3/4.5.42 ITS 3.4.12 and associated Bases contain extensise deviations from STS 3.4.12.
: a. JFD Pil applies to differences from the STS LCO. Applicability Actions, and SRs so that the ITS properly specify the plant specific limitations of the Byron and Braidwood LTOP system analysis. Comment: Revise JFD P1I to explain how           3 each limitation given in the CTS has changed. Also explain how each corresponding limitation proposed in the ITS reDects     j those changes or reflects an additional limitation based on the LTOP analysis. List each specific limitation from the LTOP analysis and the corresponding limitation in the ITS refer to each specific ITS 3.4.12 requirement. The foregoing request is made to facilitate verification by the staff that the proposed requirements are appropriate and consistent with the LTOP analysis.
: a. JFD Pil applies to differences from the STS LCO. Applicability Actions, and SRs so that the ITS properly specify the plant specific limitations of the Byron and Braidwood LTOP system analysis. Comment: Revise JFD P1I to explain how 3
each limitation given in the CTS has changed. Also explain how each corresponding limitation proposed in the ITS reDects j
those changes or reflects an additional limitation based on the LTOP analysis. List each specific limitation from the LTOP analysis and the corresponding limitation in the ITS refer to each specific ITS 3.4.12 requirement. The foregoing request is made to facilitate verification by the staff that the proposed requirements are appropriate and consistent with the LTOP analysis.
l
l
: b. JFD Pl9 incorporates the Applicability Note into the LCO, which is an unacceptable type of STS generic change proposal common to this submittal. Comment: Revise the submittal to adopt the STS presentation of the note in the Applicability.
: b. JFD Pl9 incorporates the Applicability Note into the LCO, which is an unacceptable type of STS generic change proposal common to this submittal. Comment: Revise the submittal to adopt the STS presentation of the note in the Applicability.
: c. Deviations to the Applicability based on JFD C9 (WOG SI) and CIS (WOG 81) are rejected. Comment: Revise ITS 3.4.12 to adopt the STS Applicability requirements consistent with plant design and current licensing basis.
: c. Deviations to the Applicability based on JFD C9 (WOG SI) and CIS (WOG 81) are rejected. Comment: Revise ITS 3.4.12 to adopt the STS Applicability requirements consistent with plant design and current licensing basis.
      ]-       d. JFD P21 applies to the notes to the SRs.
]-
: d. JFD P21 applies to the notes to the SRs.
* The note to ITS SR 3.4.12.2 appears generic, not plant specific. Thus it is rejected.
* The note to ITS SR 3.4.12.2 appears generic, not plant specific. Thus it is rejected.
* The note to ITS SR 3.4.12.3 is related to the generic movement of the Applicability note to the LCO; thus it is also     l generic. This note is rejected.-                                                                                             1 The note to ITS SR 3.4.12.5 is unnecessary since it only applies to RHR suction valves associated with " required" RHR   j suction relief valves. It is also generic. This note is rejected.                                                             ;
* The note to ITS SR 3.4.12.3 is related to the generic movement of the Applicability note to the LCO; thus it is also generic. This note is rejected.-
The note to ITS SR 3.4.12.6 is unnecessary since it only applies to PORV block valves associated with each " required"   !
The note to ITS SR 3.4.12.5 is unnecessary since it only applies to RHR suction valves associated with " required" RHR j
PORV. It is also generic. This note is rejected.                                                                             ;
suction relief valves. It is also generic. This note is rejected.
Comment: Revise the above SRs by withdrawing the proposed notes.                                                             I
The note to ITS SR 3.4.12.6 is unnecessary since it only applies to PORV block valves associated with each " required" PORV. It is also generic. This note is rejected.
            - e. DOC M7 collectivelyjustifies the changes to the CTS corresponding to the proposed STS deviations noted above and which are considered unacceptable. Comment: Revise DOC M7 as appropriate to be consistent with the resolutioin of the preceding comments.                                                                                                           I Comed Response to issue Comed Response to NRC Comment a: No change. LCO JFD 3.4-P11 does not change any CTS requirements. ITS LCO 3.4.12 item a corresponds to CTS 3.5.3.a footnote; ITS LCO 3.4.12 item b corresponds to CTS SR 4.5.3.2; ITS LCO 3.4.12 item c is a more restrictive requirement as discussed in DOC 3.4-M7; and ITS LCO item d corresponds to CTS 3.4.9.3.a and
Comment: Revise the above SRs by withdrawing the proposed notes.
: b. LCO JFD 3.4-Pi l merely discusses including the requirements associated with ITS LCO 3.4.12 items a and b into the ITS LTOP specification from the CTS ECCS Subsystems enaci&ation 3.5.3. Comed Response to NRC Comment b: See Comed Response to RAI 3.4.1-04. (See RAls 3.1.5-01,3.1.6-01,3.4.1-04, and 3.4.10-03.) Comed Response to NRC Comment c: WOG-51 Revision I will be withdrawn from the submittal. LCO JFDs 3.4-C9 and 3.4-PI, Bases JFDs 3.4-C9 and 3.4-P21, and the markups will be revised accordingly. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed Response to NRC Comment d: SR 3.4.12.2 Note will be deleted based on withdrawing WOG-51 Revision 1. SR 3.4.12.4, SR 3.4.12.5, and SR 3.4.12.6 Notes will be deleted due to being redundant to the use of the word " required" in the SRs
- e. DOC M7 collectivelyjustifies the changes to the CTS corresponding to the proposed STS deviations noted above and which are considered unacceptable. Comment: Revise DOC M7 as appropriate to be consistent with the resolutioin of the preceding comments.
  ,    &      themselves. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's k )     concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.12-03 and 3.4.12-04.) However, SR 3.4.12.3 Note is being retained. Without the Note, whenever the unit enters MODE 4 from MODE 3 the SR would have to 28 l
Comed Response to issue Comed Response to NRC Comment a: No change. LCO JFD 3.4-P11 does not change any CTS requirements. ITS LCO 3.4.12 item a corresponds to CTS 3.5.3.a footnote; ITS LCO 3.4.12 item b corresponds to CTS SR 4.5.3.2; ITS LCO 3.4.12 item c is a more restrictive requirement as discussed in DOC 3.4-M7; and ITS LCO item d corresponds to CTS 3.4.9.3.a and
: b. LCO JFD 3.4-Pi l merely discusses including the requirements associated with ITS LCO 3.4.12 items a and b into the ITS LTOP specification from the CTS ECCS Subsystems enaci&ation 3.5.3. Comed Response to NRC Comment b: See Comed Response to RAI 3.4.1-04. (See RAls 3.1.5-01,3.1.6-01,3.4.1-04, and 3.4.10-03.) Comed Response to NRC Comment c: WOG-51 Revision I will be withdrawn from the submittal. LCO JFDs 3.4-C9 and 3.4-PI, Bases JFDs 3.4-C9 and 3.4-P21, and the markups will be revised accordingly. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed Response to NRC Comment d: SR 3.4.12.2 Note will be deleted based on withdrawing WOG-51 Revision 1. SR 3.4.12.4, SR 3.4.12.5, and SR 3.4.12.6 Notes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's k
)
concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.12-03 and 3.4.12-04.) However, SR 3.4.12.3 Note is being retained. Without the Note, whenever the unit enters MODE 4 from MODE 3 the SR would have to 28 l


          .    ..      .=           =                   - = - = -                      -
.=
R:sponse to NRC RAI For ITS S2ction 3A                                     oo-Oci-98
=
                                          ~                      ~                  ~
- = - = -
be met in MODE 3 prior to enieringliODE 4.' Verifying the accumulator isolated is not a requirement of the LCO unless the
R:sponse to NRC RAI For ITS S2ction 3A oo-Oci-98 be met in MODE 3 prior to enieringliODE 4.' Verifying the accumulator isolated is not a requirement of the LCO unless the
  ',    accumulator pressure is greater than or equal to the maximum RCS pressure for the existmg RCS cold leg temperature
~
/   j   allowed by the P,7 limit curves. Therefore, Comed believes that the use of the " met" Note is justifiable and necessarv to d     reflect the requirements ofITS LCO 3.4.12 and SR 3.4.12.3. Comed Response to NRC Comment e: ITS LCO 3.4.12 requires accumulator isolation whenever accumulator pressure is greater than or equal to the maximum RCS pressure for the existing cold leg temperature allowed in the PTLR. no safety inj:ction pumps capable ofinjecting into the RCS. and a maximum of one charging pump (centrifugal) capable ofinjecting into the RCS. As DOC 3.4-M7 states. CTS LCO 3.4.9.3 does not include requirements for overpressure protection associated with an Si pump capable of injecting into the RCS or two charging (centrifugal) pumps or one charging (positive displacement) pump capable ofinjectmg into the RCS Hou es er CTS 3.5.3.a footnote (ITS LCO 3.4.12 item a) and CTS SR 4.5.3.2 (ITS LCO 3.4.12 item b) contain these same requirements. but the requirements have been moved to the LTOP specification (ITS LCO 3.4.12)in ITS. As DOC 3 t-W also states, CTS LCO 3.4.9.3 does not include requirements for an unisolated accumulator whenever accumulator pressure is creater than or equal to the maximum RCS pressure for the existing cold leg temperature allowed m the PTLR. Therefore.       I ITS LCO 3.4.12 item e is a more restrictive requirement as discussed in DOC 3.4-M7. Even with the changes discussed above in Comed's Responses to NRC Comments a-d. DOC 3.4-M7 justification still remains valid and unchanged.
~
                                  =.                                   -
~
NRC RAI Number             NRC issued Date                         RAI Status 3.4.12-02                   3/9'98                             Closed NRC Description ofissue JFD Pl1 ITS SR 3.4.12.2 The JFD Pil discussion states that the positive displacement charging pump is not allowed to be capable ofinjection during     I the LTOP conditions. Periodic verification that this is so is required by ITS SR 3.4.12.2. Neither this SR nor the Bases for ITS 3.4.1.2, however, specifically mention the positive displacement pump. Note that ITS SR 3.4.12.1 specifically requires verifying the incapability of the Si pumps to inject into the RCS. Comment: Revise ITS SR 3.4.12.2 and appropriate parts       l n     of the Bases for ITS 3.4.12 to specifically address the positive displacement charging pump to make it unambiguous that these requirements and associated Bases apply to it.
accumulator pressure is greater than or equal to the maximum RCS pressure for the existmg RCS cold leg temperature
/
j allowed by the P,7 limit curves. Therefore, Comed believes that the use of the " met" Note is justifiable and necessarv to d
reflect the requirements ofITS LCO 3.4.12 and SR 3.4.12.3. Comed Response to NRC Comment e: ITS LCO 3.4.12 requires accumulator isolation whenever accumulator pressure is greater than or equal to the maximum RCS pressure for the existing cold leg temperature allowed in the PTLR. no safety inj:ction pumps capable ofinjecting into the RCS. and a maximum of one charging pump (centrifugal) capable ofinjecting into the RCS. As DOC 3.4-M7 states. CTS LCO 3.4.9.3 does not include requirements for overpressure protection associated with an Si pump capable of injecting into the RCS or two charging (centrifugal) pumps or one charging (positive displacement) pump capable ofinjectmg into the RCS Hou es er CTS 3.5.3.a footnote (ITS LCO 3.4.12 item a) and CTS SR 4.5.3.2 (ITS LCO 3.4.12 item b) contain these same requirements. but the requirements have been moved to the LTOP specification (ITS LCO 3.4.12)in ITS. As DOC 3 t-W also states, CTS LCO 3.4.9.3 does not include requirements for an unisolated accumulator whenever accumulator pressure is creater than or equal to the maximum RCS pressure for the existing cold leg temperature allowed m the PTLR. Therefore.
ITS LCO 3.4.12 item e is a more restrictive requirement as discussed in DOC 3.4-M7. Even with the changes discussed above in Comed's Responses to NRC Comments a-d. DOC 3.4-M7 justification still remains valid and unchanged.
=.
NRC RAI Number NRC issued Date RAI Status 3.4.12-02 3/9'98 Closed NRC Description ofissue JFD Pl1 ITS SR 3.4.12.2 The JFD Pil discussion states that the positive displacement charging pump is not allowed to be capable ofinjection during the LTOP conditions. Periodic verification that this is so is required by ITS SR 3.4.12.2. Neither this SR nor the Bases for ITS 3.4.1.2, however, specifically mention the positive displacement pump. Note that ITS SR 3.4.12.1 specifically requires verifying the incapability of the Si pumps to inject into the RCS. Comment: Revise ITS SR 3.4.12.2 and appropriate parts n
of the Bases for ITS 3.4.12 to specifically address the positive displacement charging pump to make it unambiguous that these requirements and associated Bases apply to it.
Comed Response to issue No change. LCO 3.4.12 item a and SR 3.4.12.2 added "(centrifugal)" to clarify that the Positive Displacement Pump (PDP) is not allowed to be capable ofinjection during the LTOP conditions. Because this is Byron /Braidwood current licensing basis and has been adequately addressed in training, Comed does not believe it cost or time beneficial to revise the submittal to incorporate this change.
Comed Response to issue No change. LCO 3.4.12 item a and SR 3.4.12.2 added "(centrifugal)" to clarify that the Positive Displacement Pump (PDP) is not allowed to be capable ofinjection during the LTOP conditions. Because this is Byron /Braidwood current licensing basis and has been adequately addressed in training, Comed does not believe it cost or time beneficial to revise the submittal to incorporate this change.
7
7
Line 637: Line 760:
4 29
4 29


_.we.e         8 eis MP g wesp- M " " * * * * " "          "
_.we.e 8
l                                               . Response to NRC RAI For ITS S:ction 3A                                   09-Oci-98 i                         . . .      -.          . ..                          -
eis MP g
l NRC RAI Number               NRC lssued Date                                       R I Status L               3.4.12-03                       3/9'98                                         Closed fm NRC Description ofIssue -
wesp-M " " * * * * " "
DOC A20 l         DOC L10 JFD P38 JFD BP50 CTS 3/4.4.9.3 Action d CTS 4.4.9.3.1.a ITS SR 3.4.12.4 and SR 3.4.1.2.7
l
: a. With the RCS vented per Actions a. b, or c, CTS 3/4.4,9.3 Action d requires verifying every 31 days that the RCS sent path is open. This action requirement is retained (per DOC A20) as ITS SR 3.4.12.4 which contains a note. that for the most part is consistent with the note to corresponding STS SR 3.4.12.5. The ITS note states this verification is only needed w hen   I the RCS vent path is relied upon for pressure relief per compliance with ITS LCO 3:4.12.d.4. As discussed bs JFD P38. the ITS note replaces the STS note words "only required to be performed" with"only required to be met." (Note that the CTS         l markup. insert 3.4-39c and DOC A20, mistakenly shows the ITS note as replacing the STS words with the words "only tequired.") Comment: The concerns expressed in JFD 38 regarding " met" versus " performed" are not valid: this ditTerence would represent a generic change to the STS, as apparently addressed by WOG-87. Revise the note to ITS SR 3.4.12.4 to adopt the words of the corresponding STS note. Also, adopt the affected wording of the STS Bases. Finally. correct the CTS markup error noted above.
. Response to NRC RAI For ITS S:ction 3A 09-Oci-98 i
      . b. When the PORVs are being used for cold overpressure protection, CTS 4.4.9.3.1.a requires performance of an Analog
l NRC RAI Number NRC lssued Date R I Status L
      . Channel Operational Test (ACOT) on the PORV actuation channel every 31 days. ITS SR 3.4.12.7 retains this CTS test requirement and clarifies, per DOC L10, when it is required with a note, that for the most part is consistent with the note in corresponding STS SR 3.4.12.8. The ITS note replaces the STS words "not required to be met" with "not required to be performed" as discussed in JFD 38. Comment: The concerns expressed in JFD 38 reyrding " met" versus " performed" are hV not valid; this difference would represent a generic change to the STS, as apparently addressed by WOG-87. Revise the note to ITS SR 3.4.12.7 to adopt the words of the corresponding STS note. Also, adopt the affected wording of the STS Bases.
3.4.12-03 3/9'98 Closed fm NRC Description ofIssue -
i I
DOC A20 l
DOC L10 JFD P38 JFD BP50 CTS 3/4.4.9.3 Action d CTS 4.4.9.3.1.a ITS SR 3.4.12.4 and SR 3.4.1.2.7
: a. With the RCS vented per Actions a. b, or c, CTS 3/4.4,9.3 Action d requires verifying every 31 days that the RCS sent path is open. This action requirement is retained (per DOC A20) as ITS SR 3.4.12.4 which contains a note. that for the most part is consistent with the note to corresponding STS SR 3.4.12.5. The ITS note states this verification is only needed w hen the RCS vent path is relied upon for pressure relief per compliance with ITS LCO 3:4.12.d.4. As discussed bs JFD P38. the ITS note replaces the STS note words "only required to be performed" with"only required to be met." (Note that the CTS markup. insert 3.4-39c and DOC A20, mistakenly shows the ITS note as replacing the STS words with the words "only tequired.") Comment: The concerns expressed in JFD 38 regarding " met" versus " performed" are not valid: this ditTerence would represent a generic change to the STS, as apparently addressed by WOG-87. Revise the note to ITS SR 3.4.12.4 to adopt the words of the corresponding STS note. Also, adopt the affected wording of the STS Bases. Finally. correct the CTS markup error noted above.
. b. When the PORVs are being used for cold overpressure protection, CTS 4.4.9.3.1.a requires performance of an Analog
. Channel Operational Test (ACOT) on the PORV actuation channel every 31 days. ITS SR 3.4.12.7 retains this CTS test requirement and clarifies, per DOC L10, when it is required with a note, that for the most part is consistent with the note in corresponding STS SR 3.4.12.8. The ITS note replaces the STS words "not required to be met" with "not required to be performed" as discussed in JFD 38. Comment: The concerns expressed in JFD 38 reyrding " met" versus " performed" are h
not valid; this difference would represent a generic change to the STS, as apparently addressed by WOG-87. Revise the note i
V to ITS SR 3.4.12.7 to adopt the words of the corresponding STS note. Also, adopt the affected wording of the STS Bases.
Comed Response to Issue Comed Response to NRC Comment a: Per Comed Response to NRC Comment d for RAI 3.4.12-01, SR 3.4.12.2 Note will be deleted based on withdrawing WOG-51 Revision 1. SR 3.4.12.4, SR 3.4.12.5, and SR 3.4.12.6 Notes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. Therefore, CTS Insert 3.4-39C and DOC 3.4-A20 will be deleted as well. This change will be provided in our comprehensive ITS Section 3,4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI. (See RAls 3.4.12-01 and 3.4.12-04.)
Comed Response to Issue Comed Response to NRC Comment a: Per Comed Response to NRC Comment d for RAI 3.4.12-01, SR 3.4.12.2 Note will be deleted based on withdrawing WOG-51 Revision 1. SR 3.4.12.4, SR 3.4.12.5, and SR 3.4.12.6 Notes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. Therefore, CTS Insert 3.4-39C and DOC 3.4-A20 will be deleted as well. This change will be provided in our comprehensive ITS Section 3,4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI. (See RAls 3.4.12-01 and 3.4.12-04.)
Comed Response to NRC Comment b: "Not required to be met . "is more restrictive than "Not required to be performed .
Comed Response to NRC Comment b: "Not required to be met. "is more restrictive than "Not required to be performed.
          " Since CTS SR 4.4.9.3.1.a does not contain a "SR 3.0.4 is not applicable" allowance, Comed cannot justify the use of the
" Since CTS SR 4.4.9.3.1.a does not contain a "SR 3.0.4 is not applicable" allowance, Comed cannot justify the use of the
        " met" Note. By allowing SR 3.4.12.7 to not be " met," the unit would be allowed to enter the mode of applicability with the required PORV(s) knowingly not being able to pass a COT surveillance. Comed believes that this is not the intent of ITS.
" met" Note. By allowing SR 3.4.12.7 to not be " met," the unit would be allowed to enter the mode of applicability with the required PORV(s) knowingly not being able to pass a COT surveillance. Comed believes that this is not the intent of ITS.
Furthermore, this is not an allowance in CTS. The unit should have every confidence that the PORV is opersole and would pass the Channel Operational Test if performed, but it is not required to be " performed" due to unit conditions. Therefore, the Note should read only "not required to be performed.. " Comed continues to pursue this change.
Furthermore, this is not an allowance in CTS. The unit should have every confidence that the PORV is opersole and would pass the Channel Operational Test if performed, but it is not required to be " performed" due to unit conditions. Therefore, the Note should read only "not required to be performed.. " Comed continues to pursue this change.
  .(v l
.(v 30
30


:      ..                                      - - . _ = . _ - . =
- -. _ =. _ -. =
: l.                                             R:sponse ta NRC RAI For ITS S2ction 3.4                                   09-Oct-98 r
l.
NRC RAI Number             NRC issued Date                           RAI Status m \
R:sponse ta NRC RAI For ITS S2ction 3.4 09-Oct-98 r
3.4.12                   3/9/98                               Closed
NRC RAI Number NRC issued Date RAI Status m
[V '   NRC Description of issue l         JFD P21 l           ITS SR 3.4.12.2. SR 3.4.12.5 and SR 3.4.12.6 STS SR 3.4.12.2, SR 3.4.12.4, and SR 3.4.12.6 i
3.4.12 3/9/98 Closed
[V '
\\
NRC Description of issue l
JFD P21 l
ITS SR 3.4.12.2. SR 3.4.12.5 and SR 3.4.12.6 STS SR 3.4.12.2, SR 3.4.12.4, and SR 3.4.12.6 i
The listed STS SRs do not contain the notes included in the corresponding ITS SRs. as described in the following and somewhat in JFD 21.
The listed STS SRs do not contain the notes included in the corresponding ITS SRs. as described in the following and somewhat in JFD 21.
The note to ITS SR 3.4.12.2 states that the veri 6 cation that no SI pumps are capable ofinjecting into the RCS is "not required to be met during [Sl] pump swap operation. This is a new SR to ensure compliance with new LCO 3.4.12.b. as discussed in DOC M.7. However, the note is not technicallyjustified or even discussed in DOC M.7. Thus, it may be a valid plant-specific difference from the STS. Unfortunately, JFD P21 doesn't justify it either.
The note to ITS SR 3.4.12.2 states that the veri 6 cation that no SI pumps are capable ofinjecting into the RCS is "not required to be met during [Sl] pump swap operation. This is a new SR to ensure compliance with new LCO 3.4.12.b. as discussed in DOC M.7. However, the note is not technicallyjustified or even discussed in DOC M.7. Thus, it may be a valid plant-specific difference from the STS. Unfortunately, JFD P21 doesn't justify it either.
              + The note to ITS SR 3.4.12.5 states that the verification that RHR suction valves are open for each required RHR suction relief path is "only required to be met when complying with LCO 3.4.12.d.2 [two RHR suction relief valves providing the pressure relief capability) or LCO 3.4.12.d.3 [one PORV and one RHR suction relief valve providing the pressure relief capability]." This SR retains the requirements of CTS 4.4.9.3.2, and ensures compliance with LCO 3.4.12.d.2 or LCO 3.4.12.d.3, as applicable.
+ The note to ITS SR 3.4.12.5 states that the verification that RHR suction valves are open for each required RHR suction relief path is "only required to be met when complying with LCO 3.4.12.d.2 [two RHR suction relief valves providing the pressure relief capability) or LCO 3.4.12.d.3 [one PORV and one RHR suction relief valve providing the pressure relief capability]." This SR retains the requirements of CTS 4.4.9.3.2, and ensures compliance with LCO 3.4.12.d.2 or LCO 3.4.12.d.3, as applicable.
* The note to ITS SR 3.4.12.6 states that the verification that each PORV block valve is open for each required PORV is "only required to be met when complying with LCO 3.4.12.d.1 [two PORVs providing the pressure relief capability] or LCO     !
* The note to ITS SR 3.4.12.6 states that the verification that each PORV block valve is open for each required PORV is "only required to be met when complying with LCO 3.4.12.d.1 [two PORVs providing the pressure relief capability] or LCO 3.4.12.dJ. This SR retains the requirements of CTS 4.4.9.3.1.c, and ensures compliance with LCO 3.4.12.d.1 or LCO 3.4.12.d.3, as applicable.
3.4.12.dJ. This SR retains the requirements of CTS 4.4.9.3.1.c, and ensures compliance with LCO 3.4.12.d.1 or LCO 3.4.12.d.3, as applicable.
l The CTS markup does not appear tojustify these notes. Also, JFD 21 is not accepted because it represents a generic
l         The CTS markup does not appear tojustify these notes. Also, JFD 21 is not accepted because it represents a generic editorial change to the STS, and is unnecessary. Comment:(1) Technicallyjustify the note to ITS SR 3.4.12.2 on a plant-t  ('v}    specific basis or withdraw it making appropriate char.ges. (2) Revise the submittal to withdraw the other notes making appropriate changes to the DOCS, JFD 21, and B.ses. The response to this comment may be combined with the response to similar comment 3.4.12-01. Note, the proposec' generic changes represented by these notes are related to WOG 100J Comed Response to issue Per Comed Response to NRC Comment d for F.Al 3.4.12-01, SR 3.4.12.2 Nu will be deleted based on withdrawing WOG.
('v}
l         51. Revision 1 (not WOG-100). SR 3.4.12.4, ER 3.4.12.5 and SR 3.4.12.6 Nmes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. This change will be prov Ued in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses ao the ITS Section 3.4 RAl. (See RAls           j 3.4.12-01 and 3.4.12-03.)
editorial change to the STS, and is unnecessary. Comment:(1) Technicallyjustify the note to ITS SR 3.4.12.2 on a plant-specific basis or withdraw it making appropriate char.ges. (2) Revise the submittal to withdraw the other notes making t
NRC RAI Number             NRC issued Date                           RAI Status 3.4.12-05                   3/9/98                               Closed NRC Description of issue Not used Comed Response to issue No response required.
appropriate changes to the DOCS, JFD 21, and B.ses. The response to this comment may be combined with the response to similar comment 3.4.12-01. Note, the proposec' generic changes represented by these notes are related to WOG 100J Comed Response to issue Per Comed Response to NRC Comment d for F.Al 3.4.12-01, SR 3.4.12.2 Nu will be deleted based on withdrawing WOG.
l
: 51. Revision 1 (not WOG-100). SR 3.4.12.4, ER 3.4.12.5 and SR 3.4.12.6 Nmes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. This change will be prov Ued in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses ao the ITS Section 3.4 RAl. (See RAls j
3.4.12-01 and 3.4.12-03.)
NRC RAI Number NRC issued Date RAI Status 3.4.12-05 3/9/98 Closed NRC Description of issue Not used Comed Response to issue No response required.
l l
l l
4 m
m 4
31
31


__ _            = _ - _         _ , = _
= _ - _
ResponS to NRC RAI For ITS S ction 3.4                                 09-oct 98 NRC RAI Number               NRC issued Date                       RAI Status
_, = _
  %                3.4.12-06                       3'908                             Closed f\
ResponS to NRC RAI For ITS S ction 3.4 09-oct 98 NRC RAI Number NRC issued Date RAI Status 3.4.12-06 3'908 Closed f\\
Q         NRC Description ofissue CTS 4.4.9.3.2, item a and b STS SR 3.4.12.4 ITS SR 3.4.12.5 CTS 4.4.9.3.2 item a and b require that at least once every 72 hours that the RHR suction valves are serified to be open. ITS SR 3.4.12.5 retains this verincation requirement. including the 72-hour Frequency. Corresponding STS SR 3 4.12.4 however. requires this verification every 12 hours. The ITS Basesjustifies the 72-hour Frequency using the STS Bases' justification for the 12 hour Frequency: how can that be acceptable? In addition, the Frequency should be consistent with tne Frequencies of similar verifications of RHR loop Operability specified by ITS SR 3.4.6.1, ITS SR 3.4.7.1 and ITS SR 3.4.8.1. Each of these require that the required RHR loops be verified as Operable and/or in operation every 12 hours.
Q NRC Description ofissue CTS 4.4.9.3.2, item a and b STS SR 3.4.12.4 ITS SR 3.4.12.5 CTS 4.4.9.3.2 item a and b require that at least once every 72 hours that the RHR suction valves are serified to be open. ITS SR 3.4.12.5 retains this verincation requirement. including the 72-hour Frequency. Corresponding STS SR 3 4.12.4 however. requires this verification every 12 hours. The ITS Basesjustifies the 72-hour Frequency using the STS Bases' justification for the 12 hour Frequency: how can that be acceptable? In addition, the Frequency should be consistent with tne Frequencies of similar verifications of RHR loop Operability specified by ITS SR 3.4.6.1, ITS SR 3.4.7.1 and ITS SR 3.4.8.1. Each of these require that the required RHR loops be verified as Operable and/or in operation every 12 hours.
Operable means to verify the position of valves in the flow path which is the same check required by ITS SR 3.4.12.5.
Operable means to verify the position of valves in the flow path which is the same check required by ITS SR 3.4.12.5.
Comment: Revise the submittal to adopt the STS Frequency of 12 hours and add a justification for this more restrictis e surveillance interval. The requirements in the ITS for RHR system ought to be as consistent as are the corresponding           )
Comment: Revise the submittal to adopt the STS Frequency of 12 hours and add a justification for this more restrictis e surveillance interval. The requirements in the ITS for RHR system ought to be as consistent as are the corresponding
)
requirements in the STS.
requirements in the STS.
Comed Resporse to issue No change. Verifying that the RHR suction relief valves are open at least once per 72 hours is current licensing basis.
Comed Resporse to issue No change. Verifying that the RHR suction relief valves are open at least once per 72 hours is current licensing basis.
Furthermore, STS SR 3.4.12.4 is a bracketed surveillance, whereby in the conversion to ITS the utility adds their plant         I specific value. Comed continues to pursue the 72 hour frequency of our current licensing basis.
Furthermore, STS SR 3.4.12.4 is a bracketed surveillance, whereby in the conversion to ITS the utility adds their plant specific value. Comed continues to pursue the 72 hour frequency of our current licensing basis.
NRC RAI Number             NRC Issued Date                       RAI Status 3.4.12-07                     3/9/98                             Closed l NRC Description of issue                                                                                                           ,
NRC RAI Number NRC Issued Date RAI Status 3.4.12-07 3/9/98 Closed l NRC Description of issue h
h      DOC Al                                                                                                                           I JFD BPI CTS 4.4.9.3.2.e ITS SR 3.4.12.5 STS SR 3.4.12.4 CTS 4.4.9.3.2.c requires for the RHR suction relief valves " Testing pursuant to Speci0 cation 4.0.5." The ITS apparently does not retain this specific requirement.
DOC Al I
Also, the Bases ofITS SR 3.4.12.5 does not adopt the text regarding IST contained in the Bases discussion for                   l corresponding STS SR 3.4.12.4. This change and difference are not editorial but are less restrictive technical CTS changes       I which require a separatejustification. Comment: Revise the submittal with additional technicaljustification for deleting the IST program CTS requirements for RHR relief valves. Why is there no SR for testing in accordance with the IST Program for these valves? See comment 3.4.12-11.
JFD BPI CTS 4.4.9.3.2.e ITS SR 3.4.12.5 STS SR 3.4.12.4 CTS 4.4.9.3.2.c requires for the RHR suction relief valves " Testing pursuant to Speci0 cation 4.0.5." The ITS apparently does not retain this specific requirement.
Also, the Bases ofITS SR 3.4.12.5 does not adopt the text regarding IST contained in the Bases discussion for corresponding STS SR 3.4.12.4. This change and difference are not editorial but are less restrictive technical CTS changes which require a separatejustification. Comment: Revise the submittal with additional technicaljustification for deleting the IST program CTS requirements for RHR relief valves. Why is there no SR for testing in accordance with the IST Program for these valves? See comment 3.4.12-11.
Comed Response to issue DOC A33 was created to discuss CTS Specification 4.0.5 relocation. DOC A33 states," CTS Specification 4.0.5 provides
Comed Response to issue DOC A33 was created to discuss CTS Specification 4.0.5 relocation. DOC A33 states," CTS Specification 4.0.5 provides
          . surveillance requirements for inservice inspection and testing of ASME Code Class I,2, and 3 components. In accordance with NUREG-1431, CTS Specification 4.0.5 has been relocated to ITS Specification 5.5.8, " Inservice Testing Program."
. surveillance requirements for inservice inspection and testing of ASME Code Class I,2, and 3 components. In accordance with NUREG-1431, CTS Specification 4.0.5 has been relocated to ITS Specification 5.5.8, " Inservice Testing Program."
The requirements for Inservice Testing have not changed and are still consistent with ASME Section XI. The requirements for the inservice Inspection are contained in 10 CFR 50.55a and the:efore not included in the NUREG. This change has been justified in the ITS submittal as an administrative change thoughout the CTS markups since no ASME or CTS inservice Testing requirements were changed. The only change that was made was in relocation of the regiairements from CTS 4.0.5 to ITS 5.5.8." in addition, Comed will revise the Bases for ITS SR 3.4.12.5 to adopt the STS text stating, "The ASME Code, Section XI (Ref. 7). test per Inservice Testing Program verifies OPERABILITY by proving proper relief valve mechanical motion and by measuring and, if required, adjusting the lift setpoint." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.11-02.)
The requirements for Inservice Testing have not changed and are still consistent with ASME Section XI. The requirements for the inservice Inspection are contained in 10 CFR 50.55a and the:efore not included in the NUREG. This change has been justified in the ITS submittal as an administrative change thoughout the CTS markups since no ASME or CTS inservice Testing requirements were changed. The only change that was made was in relocation of the regiairements from CTS 4.0.5 to ITS 5.5.8." in addition, Comed will revise the Bases for ITS SR 3.4.12.5 to adopt the STS text stating, "The ASME Code, Section XI (Ref. 7). test per Inservice Testing Program verifies OPERABILITY by proving proper relief valve mechanical motion and by measuring and, if required, adjusting the lift setpoint." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.11-02.)
32
32


1                                                                                                                                   ,
1
                    . - - -                        --                        .- .-.                                                \
\\
Rzspons? to NRC RAI For ITS Section 3.4                                     oo-oci98
Rzspons? to NRC RAI For ITS Section 3.4 oo-oci98
                                                  ~
~
NRC RAI Number             NRC lssued Date                               RAI Status 3.4.12-08                     3'9 98                                   Closed
NRC RAI Number NRC lssued Date RAI Status 3.4.12-08 3'9 98 Closed
  .fsy                                                                                                                               1 Q   NRC Description ofissue                                                                                                     '
.fsy Q
JFD P20 CTS 3/4.4.9.3 Action f                                                                                                       I ITS 3.4.12 Actions Note                                                                                                     l 1
NRC Description ofissue JFD P20 CTS 3/4.4.9.3 Action f ITS 3.4.12 Actions Note 1
CTS 3/4.4.9.3 Action f states "The provisions of Specification 3.0.4 are not applicable " Since CTS 3 4.4.9.3 only addresses I the RHR suction relief valves and the PORVs. it appears that this Mode-change restiction exception is retained as the       (
CTS 3/4.4.9.3 Action f states "The provisions of Specification 3.0.4 are not applicable " Since CTS 3 4.4.9.3 only addresses the RHR suction relief valves and the PORVs. it appears that this Mode-change restiction exception is retained as the Actions Note to ITS 3.4.12. This Actions Note states "LCO 3.0.4 is not applicable to the RCS relief vahes." Based on maintaing the CTS allowance, this appears acceptable. This note does not address the RCS vents. The STS, howeser. doe >
Actions Note to ITS 3.4.12. This Actions Note states "LCO 3.0.4 is not applicable to the RCS relief vahes." Based on maintaing the CTS allowance, this appears acceptable. This note does not address the RCS vents. The STS, howeser. doe >     l l
not contain this note. JFD 20 does not adequately explain why it is acceptable to enter into the Applicability ofITS 3.4.12 without first verifying tne Operability of the RCS relief valves that are to be relied upon for overpressure protection. The statement in JFD P20 and the Bases for this note, that the Required Actions for inoperable relief valves provide an acceptable level of safety, is not convincing. In Mode 4. Action E allows 7 days to restore an inoperbale relief val e. In Mode 5 and Mode 6 with the vessel head on, Action F allows 24 hours. And in any of these Modes, Action G allows 8 hours to restore two inoperable relief valves. For any of these conditions and failure to satisfy these Actions, Action G requires depressuring the RCS with an open RCS vent. These Completion Times are consistent with the STS. Yet the STS does not allow an exception to LCO 3.0.4. Comment: Please revise the submittal to provide additional discussion and technical justification for the Actions note.
not contain this note. JFD 20 does not adequately explain why it is acceptable to enter into the Applicability ofITS 3.4.12 i I
j Comed Response to issue CTS 3.4.9.3 requires at least two overpressure protection devices to be OPERABLE. either an RHR suction relief valve or a PORV,in Modes 4,5, and 6 with the reactor vessel head on. In the event that one or both required devices are inoperable.
without first verifying tne Operability of the RCS relief valves that are to be relied upon for overpressure protection. The statement in JFD P20 and the Bases for this note, that the Required Actions for inoperable relief valves provide an acceptable level of safety, is not convincing. In Mode 4. Action E allows 7 days to restore an inoperbale relief val e. In Mode 5 and Mode 6 with the vessel head on, Action F allows 24 hours. And in any of these Modes, Action G allows 8 hours to restore two inoperable relief valves. For any of these conditions and failure to satisfy these Actions, Action G requires depressuring the RCS with an open RCS vent. These Completion Times are consistent with the STS. Yet the STS does not I
allow an exception to LCO 3.0.4. Comment: Please revise the submittal to provide additional discussion and technical justification for the Actions note.
j       Comed Response to issue CTS 3.4.9.3 requires at least two overpressure protection devices to be OPERABLE. either an RHR suction relief valve or a PORV,in Modes 4,5, and 6 with the reactor vessel head on. In the event that one or both required devices are inoperable.
the CTS provides specific actions with Completion Times ranging from 8 hours to 7 days. The CTS also contains Action f which states. "The provisions of Specification 3.0.4 are not applicable." Action f allows changing Modes without having the overpressure protection devices OPERABLE. As previously stated, the inoperability can range from 8 hours to 7 days. The
the CTS provides specific actions with Completion Times ranging from 8 hours to 7 days. The CTS also contains Action f which states. "The provisions of Specification 3.0.4 are not applicable." Action f allows changing Modes without having the overpressure protection devices OPERABLE. As previously stated, the inoperability can range from 8 hours to 7 days. The
(- CTS actions also require that the inoperable device (s) be returned to. OPERABLE or an RCS vent be established (at least 2
(-
(   square inch vent) within the next 8 hours. STS LCO 3.4.12 requires the same pressure relief capabilities be OPERABLE in the same Modes as the CTS. The STS however, adds the RCS vents to the LCO as one of the pressure relief capabilities. In addition, the STS does not allow any LCO 3.0.4 exceptions. Therefore, the pressure relief capabilities required by the LCO must be OPERABLE for any mode changes to occur. The ITS Note is being revised to state,"LCO 3.0.4 is not applicable to the RCS pressure relief capabilities." Adding this Note brings the ITS into compliance with our current licensmg basis.
CTS actions also require that the inoperable device (s) be returned to. OPERABLE or an RCS vent be established (at least 2
Comed believes this to be acceptable since the ITS Required Actions and associated Completion Times are the same as those in the CTS. Therefore, there is no change in any assumptions, calculations or equipment between our current licensing basis and the ITS Thus, no increase in any probability of any accident previously analyzed, no new or different accident introduced. and ' . crease in the margin of safety. Based on the above, Comed will continue to pursue and maintain our current licensing usis by retaining the Actions Note as revised by this RAl. This change . vill be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.
(
square inch vent) within the next 8 hours. STS LCO 3.4.12 requires the same pressure relief capabilities be OPERABLE in the same Modes as the CTS. The STS however, adds the RCS vents to the LCO as one of the pressure relief capabilities. In addition, the STS does not allow any LCO 3.0.4 exceptions. Therefore, the pressure relief capabilities required by the LCO must be OPERABLE for any mode changes to occur. The ITS Note is being revised to state,"LCO 3.0.4 is not applicable to the RCS pressure relief capabilities." Adding this Note brings the ITS into compliance with our current licensmg basis.
Comed believes this to be acceptable since the ITS Required Actions and associated Completion Times are the same as those in the CTS. Therefore, there is no change in any assumptions, calculations or equipment between our current licensing basis and the ITS Thus, no increase in any probability of any accident previously analyzed, no new or different accident introduced. and '. crease in the margin of safety. Based on the above, Comed will continue to pursue and maintain our current licensing usis by retaining the Actions Note as revised by this RAl. This change. vill be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.
33
33


                .=           =._r==_==__==.                             -=                     -
.=
R:sponse to NRC RAI For ITS S:ctinn 3.4                       09-oct-98 NRC H AI Number                     NRC issued Date                           RAI Status 3.4.12 09                               3'9'98                         Closed
=._r==_==__==.
                                                                                                                                          )
-=
i 7, .,. .
R:sponse to NRC RAI For ITS S:ctinn 3.4 09-oct-98 NRC H AI Number NRC issued Date RAI Status 3.4.12 09 3'9'98 Closed i
()       NRC Description ofissue JFD Pl                                                                                                                       1 Bases JFD Pl                                                                                                                 l ITS LCO 3.4.12 The initial words oflTS LCO 3.4.12 differ from the STS as follows: "An LTOP System shall be OPERABLE prosided with:" This difference is not editorial because LTOP is apparently no longer consider-d a system and it no longer requires an Operability requirement. The first part should closely follow the STS wording, as follows: "An LTOP S) stem shall be OPERABLE with:" Comment: The proposed editorial difference from the STS is not justifiable on a plant-specific or             ,
7,.,..
I editorial basis. Revise the LCO to adopt the suggested words and make appropriate language changes m the Bases to conform to the STS.
()
Cc:nEd Response to issue Comed will revise the LCO to adopt the suggested words and make appropriate language changes in the Bases to conform to the STS. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's             ;
NRC Description ofissue JFD Pl Bases JFD Pl ITS LCO 3.4.12 The initial words oflTS LCO 3.4.12 differ from the STS as follows: "An LTOP System shall be OPERABLE prosided with:" This difference is not editorial because LTOP is apparently no longer consider-d a system and it no longer requires an Operability requirement. The first part should closely follow the STS wording, as follows: "An LTOP S) stem shall be OPERABLE with:" Comment: The proposed editorial difference from the STS is not justifiable on a plant-specific or editorial basis. Revise the LCO to adopt the suggested words and make appropriate language changes m the Bases to conform to the STS.
concurrence with the Comed Responses to the ITS Section 3.4 RAI.                                                             '
Cc:nEd Response to issue Comed will revise the LCO to adopt the suggested words and make appropriate language changes in the Bases to conform to the STS. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
            . NRC RAI Number                     NRC issued Date                           RAI Status                                   l 3.4.12 10                               3/9/98                           Closed NRC Description ofIssue Not Used l
. NRC RAI Number NRC issued Date RAI Status 3.4.12 10 3/9/98 Closed NRC Description ofIssue Not Used Comed Response to issue
Comed Response to issue
]
                                                                                                                                          ]
No response required.
_      No response required.                                                                                                         1
\\
  .'    \
\\
                                                                                                                                          \
l l
l l
l l.
l.
("\
("\\
d 34
d 34


l
l Respons; to NRC RAI For ITS Section 3A m-ocim I
!                                        Respons; to NRC RAI For ITS Section 3A                                       m-ocim I
NRC RAI Number NRC issued Date RAI Status 3.4.12 11 3 9'98 Closed' l V_
NRC RAI Number             NRC issued Date                           RAI Status 3.4.12 11                   3 9'98                                 Closed' l V_
NRC Description ofIssue JFD B2 Bases JFD B2 STS SR 3.4.12.7 Bases Background discussion for suction relief valve requirements.
NRC Description ofIssue JFD B2 Bases JFD B2 STS SR 3.4.12.7 Bases Background discussion for suction relief valve requirements.                                                             ;
STS markup page B 3.4-60 Bases JFD P31 ITS does not adopt STS SR 3.4.12.7, serification that each required open RHR suction isolation valve is locked open with i
STS markup page B 3.4-60                                                                                                       1 Bases JFD P31 ITS does not adopt STS SR 3.4.12.7, serification that each required open RHR suction isolation valve is locked open with i     power removed (apparently needed when the associated RHR relief valve is used to satisfy the LCO for overpressure               i protection). JFD B2 and JFD Bases B2 are not detailed enough to determine the validity of this omission. Comment-               !
power removed (apparently needed when the associated RHR relief valve is used to satisfy the LCO for overpressure i
Revise the submittal with plant-specific technicaljustification for this deviation from the STS. The CTS markup page 3 4 5     ]
protection). JFD B2 and JFD Bases B2 are not detailed enough to determine the validity of this omission. Comment-Revise the submittal with plant-specific technicaljustification for this deviation from the STS. The CTS markup page 3 4 5
5 indicates that CTS 4.5.2.d.1)is retained as ITS SR 3.4.14.2. The NRC staff understands that the RHR suction vahe               l autoclosure is no longer a part of the unit design. Note the absence of the autoclosure feature from the umt design was discussed with Kelly Root of Braidwood on 2/13/98 by telcon. However, the information in the submittal does not clearly explain why this design difference necessitates deviations from the STS; niether does it clearly list all such deviations.
]
Note Bases JFD P31 contradicts the preceding stated staff understanding about the autoclosure interlock; JFD P31 states it is a part of the unit design as described in FSAR Section 5.4.7.2.3, but is controlled by procedure. Ifit is part of the unit design, then the STS provisions related to it and associated Bases ought to be adopted to ensure the Operability of the RHR       l relief valves when they are relied upon for RCS overpressure protection to meet ITS LCO 3.4.12. Note FSAR Section                 1 5.4.7.2.3 was reviewed and it supports the absence of the autoclosure interlock from the design. Suggest that JFD P42 be revised to also address not adopting STS SR 3.4.12.7 Comed Response to Issue
5 indicates that CTS 4.5.2.d.1)is retained as ITS SR 3.4.14.2. The NRC staff understands that the RHR suction vahe autoclosure is no longer a part of the unit design. Note the absence of the autoclosure feature from the umt design was discussed with Kelly Root of Braidwood on 2/13/98 by telcon. However, the information in the submittal does not clearly explain why this design difference necessitates deviations from the STS; niether does it clearly list all such deviations.
  . No change. NUREG SR 3.4.12.7, SR 3.4.14.2, and SR 3.4.14.3 are bracketed surveillances. Comed believes that LCO                   l
Note Bases JFD P31 contradicts the preceding stated staff understanding about the autoclosure interlock; JFD P31 states it is a part of the unit design as described in FSAR Section 5.4.7.2.3, but is controlled by procedure. Ifit is part of the unit design, then the STS provisions related to it and associated Bases ought to be adopted to ensure the Operability of the RHR l
[] JFDs 3.4-82 and 3.4-B3 are sufficient forjustifying the deletion ofinformation that is not applicable to Byron and               I
relief valves when they are relied upon for RCS overpressure protection to meet ITS LCO 3.4.12. Note FSAR Section 5.4.7.2.3 was reviewed and it supports the absence of the autoclosure interlock from the design. Suggest that JFD P42 be revised to also address not adopting STS SR 3.4.12.7 Comed Response to Issue No change. NUREG SR 3.4.12.7, SR 3.4.14.2, and SR 3.4.14.3 are bracketed surveillances. Comed believes that LCO
, V  Braidwood, and that this approach is consistent with conversion guide ines and the process used throughout the submittal         I Comed agrees that Bases JFD 3.4-P31 is incorrect in stating that an at toclosure interlock is provided. Bases JFD 3.4-P31       l will be revised to state, "NUREG-1431 SR 3.4.14.3 and associated Bms have been deleted and the Bases for both LCO                 i 3.4.12 and LCO 3.4.14 are revised to omit references to the autoclosure interlock. Only the open permissive interlock             l function is included. This is consistent with CTS SR 4.5.2.d.1 and NRC SER dated 8!31/90 for Amendment 38/25. The interlock is discussed in UFSAR Section 5.4.7.2.3." This JFD discussion is based on the following excerpt from UFSAR Section 5.4.7.2.3. "During plant startup, the inlet isolation valves are shut administratively. However, an alarm is provided to alert the operator in the event that double isolation is not being maintained when RCS pressure increases above 400 psig.
[]
These isola' ion valves are provided with "prevem-upen" interlocks, which are designed to prevent possible exposure of the       ;
JFDs 3.4-82 and 3.4-B3 are sufficient forjustifying the deletion ofinformation that is not applicable to Byron and V
RHR System to normal RCS operating pressure. . . The use of two independently powered motor-operated valves in each of the two inlet lines, along with two independent pressure interlock signals in the opening and alarm circuitry ensures a design which meets applicable single failure criteria." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
Braidwood, and that this approach is consistent with conversion guide ines and the process used throughout the submittal Comed agrees that Bases JFD 3.4-P31 is incorrect in stating that an at toclosure interlock is provided. Bases JFD 3.4-P31 l
will be revised to state, "NUREG-1431 SR 3.4.14.3 and associated Bms have been deleted and the Bases for both LCO 3.4.12 and LCO 3.4.14 are revised to omit references to the autoclosure interlock. Only the open permissive interlock l
function is included. This is consistent with CTS SR 4.5.2.d.1 and NRC SER dated 8!31/90 for Amendment 38/25. The interlock is discussed in UFSAR Section 5.4.7.2.3." This JFD discussion is based on the following excerpt from UFSAR Section 5.4.7.2.3. "During plant startup, the inlet isolation valves are shut administratively. However, an alarm is provided to alert the operator in the event that double isolation is not being maintained when RCS pressure increases above 400 psig.
These isola' ion valves are provided with "prevem-upen" interlocks, which are designed to prevent possible exposure of the RHR System to normal RCS operating pressure... The use of two independently powered motor-operated valves in each of the two inlet lines, along with two independent pressure interlock signals in the opening and alarm circuitry ensures a design which meets applicable single failure criteria." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
l l
l l
!p V
!p V
l                                                                       35
l 35


l l                                                         R:spons2 to NRC RAI For ITS Section 3A                               09-Oct-98 l                                             . - = = . = = = - .                      : .-        .
l l
l             NRC RAI Number                         NRC Issued Date                     RAI Status
R:spons2 to NRC RAI For ITS Section 3A 09-Oct-98 l
[ Vn\
- = =. = = = -.
3.4.12-12 NRC Description ofissue -
l NRC RAI Number NRC Issued Date RAI Status 3.4.12-12 3'/9/98 Closed
3'/9/98                       Closed LA14 l-         CTS 4.5.4.2.1 (Note this is the principal reference for this comment.)
[ n\\
<V NRC Description ofissue -
LA14 l-CTS 4.5.4.2.1 (Note this is the principal reference for this comment.)
CTS 4.5.4.1 and associated Note
CTS 4.5.4.1 and associated Note
* CTS 3.5.4.1
* CTS 3.5.4.1 CTS 3/4.5.4.1 Action CTS 4.5.3.2 11S SR 3.4.12.I Bases for ITS 3.4.12 CTS 4.5.4.2.1 requires at least one Si pump shall be demonstrated available when required every 12 hours. ITS SR 3.4.12.1 verifies no Si pump is capable ofinjecting into the RCS. These two SRs do not appear to be equivalent. but this is implied by the CTS markup, page 3/4 5-10. Also, the discussion in DOC LA14 only :upports removing details about restricting sources of high pressure water injection into the RCS. This change, however, removes details related to the Operability of required SI pump and associated flow path from the RWST to the RCS. Further, the discussion in DOC LA14 does not specifically address (or list) CTS 4.5.4.2.1, so there is a question about whether it applies to the detail removal as indimted in the CTS markup. A new CTS DOC seems to be reqtaired to justify the removing the details of CTS 4.5.4.2.1 to the Bases.
!          CTS 3/4.5.4.1 Action CTS 4.5.3.2 11S SR 3.4.12.I Bases for ITS 3.4.12 CTS 4.5.4.2.1 requires at least one Si pump shall be demonstrated available when required every 12 hours. ITS SR 3.4.12.1 verifies no Si pump is capable ofinjecting into the RCS. These two SRs do not appear to be equivalent. but this is implied by the CTS markup, page 3/4 5-10. Also, the discussion in DOC LA14 only :upports removing details about restricting sources of high pressure water injection into the RCS. This change, however, removes details related to the Operability of required SI pump and associated flow path from the RWST to the RCS. Further, the discussion in DOC LA14 does not specifically address (or list) CTS 4.5.4.2.1, so there is a question about whether it applies to the detail removal as indimted in the CTS markup. A new CTS DOC seems to be reqtaired to justify the removing the details of CTS 4.5.4.2.1 to the Bases.
Comment: Revise the submittal with the indicated technicaljustification. In addition, state where the information, as indicated by the markup of CTS 4.5.4.2.1. is contained in the ITS Bases.
Comment: Revise the submittal with the indicated technicaljustification. In addition, state where the information, as indicated by the markup of CTS 4.5.4.2.1. is contained in the ITS Bases.
Comed Response to issue                                                                                                         1 JFD 3.4-LA14 will be revised to add a paragraph which states, " CTS LCO 3.5.4.2 establishes controls which ensure that           I diverse means ofintroducing makeup water from the RWST to the RCS are available in the event that a loss of inventory or loss of forced circulation occurs which results in a loss of decay heat removal. The LCO requires a Safety injection (SI)       1
Comed Response to issue JFD 3.4-LA14 will be revised to add a paragraph which states, " CTS LCO 3.5.4.2 establishes controls which ensure that I
          - pump and flow path or an adequate RCS vent to allow gravity feed from the RWST to be available when in Mode 5 and 6             l
diverse means ofintroducing makeup water from the RWST to the RCS are available in the event that a loss of inventory or loss of forced circulation occurs which results in a loss of decay heat removal. The LCO requires a Safety injection (SI) 1
  . [N     with the pressurizer level less than or equal to 5 percent. These requirements were added in response to Generic Letter (GL) 88-17. " Loss of Decay Heat Removal." This Specification does not satisfy the Technical Specification Screening Criteria         j (see ITS Section 3.5 DOC RI). Howevet, CTS SR 4.5.4.2.1 also provides Low Temperature (cold) Overpressure Protection             l (LTOP) from inadvertent Si actuatior as indicated in the SER for ByrorvBraidwood Amendment 38'25. Section 2.2 dated             i August 31,1990. This portion of the requirements is retained in ITS SR 3.4.12.1. The detail of demonstrating the                 i availability of the Si pump is relocated to the TRM. The relocation of this information maintains the consistency with           l NUREG 1431. Any change to this requirement is made in accordance with 10 CFR 50.59." This change will be provided in             I our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the             I ITS Section 3.4 RAI.                                                                                                             l l
- pump and flow path or an adequate RCS vent to allow gravity feed from the RWST to be available when in Mode 5 and 6
. [N with the pressurizer level less than or equal to 5 percent. These requirements were added in response to Generic Letter (GL) 88-17. " Loss of Decay Heat Removal." This Specification does not satisfy the Technical Specification Screening Criteria j
(see ITS Section 3.5 DOC RI). Howevet, CTS SR 4.5.4.2.1 also provides Low Temperature (cold) Overpressure Protection (LTOP) from inadvertent Si actuatior as indicated in the SER for ByrorvBraidwood Amendment 38'25. Section 2.2 dated i
August 31,1990. This portion of the requirements is retained in ITS SR 3.4.12.1. The detail of demonstrating the availability of the Si pump is relocated to the TRM. The relocation of this information maintains the consistency with NUREG 1431. Any change to this requirement is made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
l l
l l
l l
l l
f I
l f
x 36 l:
Ix 36 l:


,                                          R:sponse to NRC RAI For ITS Section 3.4                                   09-oct os
R:sponse to NRC RAI For ITS Section 3.4 09-oct os 7
!                                              y       .                              . - ~ -
y
7                                      - - -
. - ~ -
NRC RAI Number             NRC issued Date                               RAI Status j g          3.4.12-13                     3'/9'98                                 Closed NRC Description of Issue l
NRC RAI Number NRC issued Date RAI Status 3.4.12-13 3'/9'98 Closed j g l
l      DOC LA25 CTS 3/4.4.9.3 Action e CTS 3/4.4.9.3 Action e, requires a report to the NRC in the event the specified pressure relief valses are used to mitigate an RCS pressure transient, pursuamt to CTS 6.9.2. This Action is not retained in ITS 3.4.12. but is mosed to the TRM. The i
NRC Description of Issue l
justification in DOC LA25 states it is acceptable to relocate this requirement to the TRM because the Special Report is not approved by the NRC. Staff disagrees. The only acceptable basis for this relocation it whether there exists any redundancy in regulato.y raquirements which control the preparation and submittal of the esent reports to the NRC. Comment: Reuse the submittal to proside additional technicaljustification for moving this reporting requirement to the TRM. If not addressed in response to another similar comment, list the dispostion of all such CTS reporting requirements, and show that the submitted justifications are consistent with the aceptable basis noted above. (i.e., this may be a global comment.)
DOC LA25 CTS 3/4.4.9.3 Action e CTS 3/4.4.9.3 Action e, requires a report to the NRC in the event the specified pressure relief valses are used to mitigate an RCS pressure transient, pursuamt to CTS 6.9.2. This Action is not retained in ITS 3.4.12. but is mosed to the TRM. The justification in DOC LA25 states it is acceptable to relocate this requirement to the TRM because the Special Report is not i
Comed Response to issue Comed will revise DOC LA25 to state, " CTS 3.4.9.3.e provides a requirement to submit a Special Report in accordance with CTS Specification 6.9.2 in the event that the PORVs, the RHR suction relief valves, or the RCS vents are used to mitigate an RCS pressure transient. This requirement is to be relocated to the TRM. Relocating this requirement to the TRM is consistent with other required reports in the CTS. As discussed in Section 5.0 DOC A12. CTS Epecification 6.9.2 has been revised to delete the reference to the submittal location for the Special Reports. The requirements related to report submittal are contained in 10 CFR 50.36,10 CFR 50.72, and 10 CFR 50.73. Since conformance to 10 CFR 50 is a condition of the license, specific identification of this requirement in the TS would be duplicative and is not necessary. In addition, the Special Reporting requirements are deleted from the STS since they do not meet 10 CFR 50.36(c)(2)(ii) criteria for retention in the TS. As such, the relocated requirement is not required to be in the TS to provide adequate protection of the public health and safety. The relocation of this requirement maintains the consistency with NUREG-1431. Any changes to this requirement will be made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS A   Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.
approved by the NRC. Staff disagrees. The only acceptable basis for this relocation it whether there exists any redundancy in regulato.y raquirements which control the preparation and submittal of the esent reports to the NRC. Comment: Reuse the submittal to proside additional technicaljustification for moving this reporting requirement to the TRM. If not addressed in response to another similar comment, list the dispostion of all such CTS reporting requirements, and show that the submitted justifications are consistent with the aceptable basis noted above. (i.e., this may be a global comment.)
Y                                               '~
Comed Response to issue Comed will revise DOC LA25 to state, " CTS 3.4.9.3.e provides a requirement to submit a Special Report in accordance with CTS Specification 6.9.2 in the event that the PORVs, the RHR suction relief valves, or the RCS vents are used to mitigate an RCS pressure transient. This requirement is to be relocated to the TRM. Relocating this requirement to the TRM is consistent with other required reports in the CTS. As discussed in Section 5.0 DOC A12. CTS Epecification 6.9.2 has been revised to delete the reference to the submittal location for the Special Reports. The requirements related to report submittal are contained in 10 CFR 50.36,10 CFR 50.72, and 10 CFR 50.73. Since conformance to 10 CFR 50 is a condition of the license, specific identification of this requirement in the TS would be duplicative and is not necessary. In addition, the Special Reporting requirements are deleted from the STS since they do not meet 10 CFR 50.36(c)(2)(ii) criteria for retention in the TS. As such, the relocated requirement is not required to be in the TS to provide adequate protection of the public health and safety. The relocation of this requirement maintains the consistency with NUREG-1431. Any changes to this requirement will be made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS A
NRC RAI Number               NRC issued Date                             RAI Status 3.4.12-14                   3/9'98                                   Closed NRC Description of issue Not used Comed Response to issue No response required.
Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.
NRC RAI Number               NRC issued Date                             RAI Status 3.4.12-15                   3/9/98                                   Closed NRC Description of issue Not used Comed Response to issue No response required.
Y
  $ \
'~
NRC RAI Number NRC issued Date RAI Status 3.4.12-14 3/9'98 Closed NRC Description of issue Not used Comed Response to issue No response required.
NRC RAI Number NRC issued Date RAI Status 3.4.12-15 3/9/98 Closed NRC Description of issue Not used Comed Response to issue No response required.
\\
l V t
l V t
37
37


1 I
R:spanse to NRC RAI For ITS S:ction 3.4 09-oci-98 NRC RAI Number NRC issued Date RAI Status 3.4.12 16 3'9'98 Closed
R:spanse to NRC RAI For ITS S:ction 3.4                                       09-oci-98   i NRC RAI Number                               NRC issued Date                                     RAI Status 3.4.12 16                                   3'9'98                                             Closed                               !
; : (f~s\\
; : (f~s\
i l
i l               NRC Description of issue f (/ .
NRC Description of issue f (/.
              ' Not used Comed Response to issue No response required.
' Not used Comed Response to issue No response required.
;                NRC RAI Number                               NRC issued Date                                     RAI Status 3.4.12 17                                   3/9'98                                             Closed NRC Description ofissue Bases JFD Pi Bases for ITS SR 3.4.12.7, STS markup page B 3.4 71 The second paragraph of the Bases for STS SR 3.4.12.8 has not been adopted in the Bases for correspondmg ITS SR
NRC RAI Number NRC issued Date RAI Status 3.4.12 17 3/9'98 Closed NRC Description ofissue Bases JFD Pi Bases for ITS SR 3.4.12.7, STS markup page B 3.4 71 The second paragraph of the Bases for STS SR 3.4.12.8 has not been adopted in the Bases for correspondmg ITS SR 3.4.12.7. This omission is not explicitlyjustified.
!              3.4.12.7. This omission is not explicitlyjustified.
Comment: Revise the submittal to adopt the omitted paragraph.
Comment: Revise the submittal to adopt the omitted paragraph.
Comed Response to issue Comed will revise the submittal to adopt the omitted paragraph. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the submittal to adopt the omitted paragraph. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
                                                        .._      _ . . _ . . . ;,.              ..._. _._;..          ._ _7   _
_7 NRC RAI Number NRC issued Date RAI Status 3.4.13-01 3/9/98 Closed
NRC RAI Number                             NRC issued Date                                       RAI Status 3.4.13-01                                   3/9/98                                             Closed
' NRC Description ofIssue Q-Not used Comed Response to issue No response required.
          ' NRC Description ofIssue Q-         Not used Comed Response to issue No response required.
l im i '
l im i '     )
)
    '%J i
'%J i
38
38


i
=
                              =                     . . - . - . - - .      = - - - - -                                                l Respsuse to NRC RAI For ITS Section 3.4                                       09 ocim
= - - - - -
                                  = .. . :.;. ; --- - --                                                                               1 NRC RAI Number           NRC lssued Date                         RAI Status                                               l p           3.4.13-02                 3'9'98                             Closed                                                   j NRC Description of Issue                                                                                                       l DOC LA24 CTS 4.4.6.2.1.a. b. and e CTSs J 1611.a. b, and e require monitoring the containment annosphere radiation monitor the reactor cavity sump discharge, and the containment floor drain sump discharge and inventory at least once per 12 hours. and the reactor head flange leakoff system at least once per 24 hours. DOC LA24 states these surveillances are relocated to the TRM because they are not necessary to ensure RCS operational leakage is maintained within limits. This is not a sufficient technical       j justification. Comment: Revise DOC LA24 with additional technicaljustification for moving these SRs to the TRM.
Respsuse to NRC RAI For ITS Section 3.4 09 ocim
=... :.;. ; --- - --
1 NRC RAI Number NRC lssued Date RAI Status p
3.4.13-02 3'9'98 Closed j
NRC Description of Issue DOC LA24 CTS 4.4.6.2.1.a. b. and e CTSs J 1611.a. b, and e require monitoring the containment annosphere radiation monitor the reactor cavity sump discharge, and the containment floor drain sump discharge and inventory at least once per 12 hours. and the reactor head flange leakoff system at least once per 24 hours. DOC LA24 states these surveillances are relocated to the TRM because they are not necessary to ensure RCS operational leakage is maintained within limits. This is not a sufficient technical j
justification. Comment: Revise DOC LA24 with additional technicaljustification for moving these SRs to the TRM.
Describe how the ITS will ensure RCS operational leakage is maintained within limits.
Describe how the ITS will ensure RCS operational leakage is maintained within limits.
Comed Response to issue Comed will revise DOC LA24 to state," CTS SR 4.4.6.2.1.a. SR 4.4.6.2.1.b. and SR 4.4.6.2.1.e proside requirements for monitoring the containment atmosphere radioactivity, reactor cavity sump discharge, the containment floor drain sump             I discharge, and inventory, and the reactor head flange leakoff. These requirements are being relocated to the Technical Requirements Manual (TRM). These requirements, along with other ITS requirements, provide monitoring functions for               I indicating RCS Operational Leakage. These specific requirements do not meet the 10 CFR 50.36(cK2)(ii) criteria for retention in the STS and therefore the ITS. However, their function provides an additional and independent operational indicator for RCS leakage and needs to be retained in a Licensee Controlled Document. The requirements ofITS LCO 3.4.13 provide adequate assurance that RCS Operational Leakage is maintained within the required limits. The relocated information is not necessary to be in ITS to ensure RCS Operational Leakage is within limits. As such. the relocated information is not required to be in the ITS to provide adequate protection of the public health and safety. The relocation of these requirements maintains the consistency with NUREG 1431. Any change to these requirements will be made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise DOC LA24 to state," CTS SR 4.4.6.2.1.a. SR 4.4.6.2.1.b. and SR 4.4.6.2.1.e proside requirements for monitoring the containment atmosphere radioactivity, reactor cavity sump discharge, the containment floor drain sump discharge, and inventory, and the reactor head flange leakoff. These requirements are being relocated to the Technical Requirements Manual (TRM). These requirements, along with other ITS requirements, provide monitoring functions for indicating RCS Operational Leakage. These specific requirements do not meet the 10 CFR 50.36(cK2)(ii) criteria for retention in the STS and therefore the ITS. However, their function provides an additional and independent operational indicator for RCS leakage and needs to be retained in a Licensee Controlled Document. The requirements ofITS LCO 3.4.13 provide adequate assurance that RCS Operational Leakage is maintained within the required limits. The relocated information is not necessary to be in ITS to ensure RCS Operational Leakage is within limits. As such. the relocated information is not required to be in the ITS to provide adequate protection of the public health and safety. The relocation of these requirements maintains the consistency with NUREG 1431. Any change to these requirements will be made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.
[
[
NRC RAI Number             NRC issued Date                         RAI Status
NRC RAI Number NRC issued Date RAI Status 3.4.13-03 3/9'98 Closed NRC Description ofissue Bases JFD PI Bases for STS 3.4.13 Action B, STS markup page B 3.4-76 The first paragraph. second sentence of the Bases for Required Actions B.1 and B.2 is not adopted. The following is not retained: "It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE." Bases JFD Pl does not explain why this statement is not applicable to Byron & Braidwood. Comment: Revise the submittal to adopt the omitted sentence, w hich is generally applicable to Westinghouse 4-loop design.
{
3.4.13-03                 3/9'98                             Closed NRC Description ofissue Bases JFD PI                                                                                                                     I Bases for STS 3.4.13 Action B, STS markup page B 3.4-76 The first paragraph. second sentence of the Bases for Required Actions B.1 and B.2 is not adopted. The following is not           l retained: "It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE." Bases JFD Pl                 l does not explain why this statement is not applicable to Byron & Braidwood. Comment: Revise the submittal to adopt the omitted sentence, w hich is generally applicable to Westinghouse 4-loop design.
Comed Response to issue Comed will revise the subminal to adopt the omitted sentence. This change will bt provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Rtsponses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the subminal to adopt the omitted sentence. This change will bt provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Rtsponses to the ITS Section 3.4 RAl.
4 39
4 39


r_.             r -     m--    :-      -    -- --
r_.
R:spanse to N~RC RAI For ITS Section 3.4                                       nocim NRC RAI Number               NRC issued Date                           RAI Status n          3.4.13-04                 1 9'98                                     Closed NRC Description ofissue Bases JFD P43 Bases for SR 3.4.13.1, STS markup page B 3.4 77 The fourth paragraph of the Bases discussion of STS SR 3.4.13.1 is not adopted. This text clearly explains that the leakage monitoring requirements of CTS 3/4.4.6.2 are now located in ITS 3.4.15 which is important information rather than just a cross reference in the Bases. This Bases text (and Comment number 3.4.13-02 above) denotes the importance of these monitors for the detection of reactor coolant system pressure boundary leakage and unidentified leakage The omitted Bases text applies. Comment: Revise the Bases to adopt the omitted paragraph.
r -
m--
R:spanse to N~RC RAI For ITS Section 3.4 nocim NRC RAI Number NRC issued Date RAI Status 3.4.13-04 1 9'98 Closed n
NRC Description ofissue Bases JFD P43 Bases for SR 3.4.13.1, STS markup page B 3.4 77 The fourth paragraph of the Bases discussion of STS SR 3.4.13.1 is not adopted. This text clearly explains that the leakage monitoring requirements of CTS 3/4.4.6.2 are now located in ITS 3.4.15 which is important information rather than just a cross reference in the Bases. This Bases text (and Comment number 3.4.13-02 above) denotes the importance of these monitors for the detection of reactor coolant system pressure boundary leakage and unidentified leakage The omitted Bases text applies. Comment: Revise the Bases to adopt the omitted paragraph.
Comed Response to issue Comed will revise the Bases to adopt the omitted paragraph with one exception. The word " automatic" is being deleted since there is no automatic system associated with containment sump level. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the Bases to adopt the omitted paragraph with one exception. The word " automatic" is being deleted since there is no automatic system associated with containment sump level. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
                                --=~.===.=:_=-.                           z         --:
--=~.===.=:_=-.
NRC RAI Number               NRC Issued Date                         RAI Status 3.4.14-01                   3/9/98                                   Closed NRC Description of issue JFD P41 ITS LCO 3.4.14 STS LCO 3.4.14 CTS 4.4.6.2.2
z NRC RAI Number NRC Issued Date RAI Status 3.4.14-01 3/9/98 Closed NRC Description of issue JFD P41 ITS LCO 3.4.14 STS LCO 3.4.14 CTS 4.4.6.2.2
    /%
/%
ITS LCO 3.4.14 states "Each RCS PlV shall be OPERABLE." STS LCO 3.4.14 states " Leakage from each RCS PlV shall lV)  be within limits." JFD P41 states the revision is to reflect both the leakage requirements and the interlock functions requirements. This deviation from the STS is generic and is notjustifiable on a plant-specific basis.
lV)
ITS LCO 3.4.14 states "Each RCS PlV shall be OPERABLE." STS LCO 3.4.14 states " Leakage from each RCS PlV shall be within limits." JFD P41 states the revision is to reflect both the leakage requirements and the interlock functions requirements. This deviation from the STS is generic and is notjustifiable on a plant-specific basis.
Comment: Revise ITS LCO 3.4.14 to conform to STS LCO 3.4.14 win.,n is consistent with CTS 4.4.6.2.2.
Comment: Revise ITS LCO 3.4.14 to conform to STS LCO 3.4.14 win.,n is consistent with CTS 4.4.6.2.2.
Comed Response to Issue Comed will revise ITS LCO 3.4.14 to conform to STS LCO 3.4.14. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to Issue Comed will revise ITS LCO 3.4.14 to conform to STS LCO 3.4.14. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
        - NRC RAI Number             NRC issued Date                           RAI Status 3.4.14-02                   3/9/98                                   Closed NRC Description of issue-JFD P46 ITS 3.4.14 Actions Note 2 ITS 3.4.14 Actions Note 2 differs from the STS note as indicated: " Enter applicable Conditions and Required Actions for
- NRC RAI Number NRC issued Date RAI Status 3.4.14-02 3/9/98 Closed NRC Description of issue-JFD P46 ITS 3.4.14 Actions Note 2 ITS 3.4.14 Actions Note 2 differs from the STS note as indicated: " Enter applicable Conditions and Required Actions for systems if made inoperable by an inoperable PlV " Acceptance of this editorial deviation would require approval of a generic change to the STS addressing all applicable locations in the STS rather than sporadic changes here and there as implied by JFD P46. Besides, the STS presentation is clearer than the proposed deviation. Comment: Revise the Actions note to conform to the STS wording.
;      systems if made inoperable by an inoperable PlV " Acceptance of this editorial deviation would require approval of a
Comed Response to Issue The Note will be revised to adopt the STS wording. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Note: This change is applicable to ITS LCOs 3.3.5, 3.3.6, 3.4.14, 3.6.2, 3.6.3, 3.7.7, 3.7.8, 3.8. I, 3.8.2, and 3.8.7. (See R A is 3.6.2-02, 4 g (v) 3.7.7-04,3.7.8-06, and 3.8.122.)
!      generic change to the STS addressing all applicable locations in the STS rather than sporadic changes here and there as implied by JFD P46. Besides, the STS presentation is clearer than the proposed deviation. Comment: Revise the Actions note to conform to the STS wording.
i 40 i
Comed Response to Issue The Note will be revised to adopt the STS wording. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Note: This 4
g  change is applicable to ITS LCOs 3.3.5, 3.3.6, 3.4.14, 3.6.2, 3.6.3, 3.7.7, 3.7.8, 3.8. I, 3.8.2, and 3.8.7. (See R A is 3.6.2-02, 3.7.7-04,3.7.8-06, and 3.8.122.)
(v)                                              -
i i
40


    ;          T.: . l- ~ * : ~.". .'.L-   , -  . - - . ~ . -           -    .
T.:.
R:sponSe to NRC RAI For ITS S:ction 3A                         09-o ct 9n
l- ~ * : ~."..'.L-
                                                                                          ~
. - -. ~. -
l l
R:sponSe to NRC RAI For ITS S:ction 3A 09-o ct 9n l
NRC RAl Number'                   NRC INu~e'         d Date ~         RAl Status                                                 1 3.4.14 03                                 3/9'98                                                                           I l (n)
NRC RAl Number' NRC INu~e' Date ~
V     NRC Description ofIssue Closed
~
!            JFD Bl JFD B2 ITS 3.4.14 Action A Note j           STS 3.4.14 first attemative Required Action A.2 (bracketed) i h
d RAl Status l
l           ITS 3.4.14 Action A Note has adopted the bracketed phrase "[or the high pressure portion of the system]" in the STS Action l
1 I
A note. However the ITS does not adopt bracketed STS 3.4.14 first alternatise Required Action A.2. pertaining to valses in the high pressure portion of the system. This is an inconsistent usage of the STS. If Comed does not used the first alternate, then this bracketed phrase in the note cannot be adopted. Comment: Revise the submittal to correct this STS technical usage error.
3.4.14 03 3/9'98 Closed l (n) l V NRC Description ofIssue JFD Bl JFD B2 ITS 3.4.14 Action A Note j
l Comed Response to issue l           ITS 3.4.14 Required Action A Note has adopted the bracketed phrase "[or the high pressure portion of the system]" of the
STS 3.4.14 first attemative Required Action A.2 (bracketed) i h
!            NUREG. Comed will revise the submittal to adopt the bracketed first alternative specified in Required Action A.2 to make           j j
l ITS 3.4.14 Action A Note has adopted the bracketed phrase "[or the high pressure portion of the system]" in the STS Action A note. However the ITS does not adopt bracketed STS 3.4.14 first alternatise Required Action A.2. pertaining to valses in the high pressure portion of the system. This is an inconsistent usage of the STS. If Comed does not used the first alternate, then this bracketed phrase in the note cannot be adopted. Comment: Revise the submittal to correct this STS technical usage l
the ITS Note and the Required Actions consistent. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
error.
Comed Response to issue l
ITS 3.4.14 Required Action A Note has adopted the bracketed phrase "[or the high pressure portion of the system]" of the NUREG. Comed will revise the submittal to adopt the bracketed first alternative specified in Required Action A.2 to make j
j the ITS Note and the Required Actions consistent. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
... -. -. =
_=
_=
                                                    . . . - . - . =                    _ - . = _             -
_ -. = _
NRC RAI Number                     NRC issued Date                     RAI Status 3.4.14-04                                 3/9/98                   Closed 1
NRC RAI Number NRC issued Date RAI Status 3.4.14-04 3/9/98 Closed 1
NRC Description ofIssue                                                                                                             l l
NRC Description ofIssue JFD PI ITS 3.4.14 Required Actions A.1 and B.I ITS 3.4.14 Required Action A.I differs from the STS by adding a "de-energized power operated" valve to the list of valve alternatives. And ITS 3.4.14 Required Action B.I differs from corresponding STS 3.4.14 Required Action C.I so only a "de-energized" valve is used instead of a closed manual or de activated automatic valve. These are not editorial deviations but are technical deviations that are not justified by JFD Pl. Comment: Revise the submittal to adopt the STS wording or add a JFD with an appropriate plant-specife justification.
JFD PI ITS 3.4.14 Required Actions A.1 and B.I ITS 3.4.14 Required Action A.I differs from the STS by adding a "de-energized power operated" valve to the list of valve alternatives. And ITS 3.4.14 Required Action B.I differs from corresponding STS 3.4.14 Required Action C.I so only a "de-energized" valve is used instead of a closed manual or de activated automatic valve. These are not editorial deviations but are technical deviations that are not justified by JFD Pl. Comment: Revise the submittal to adopt the STS wording or add a JFD with an appropriate plant-specife justification.
Comed Response to issue Revised Response: Refer to LCO JFD 3.4-48. This change is provided in our comprehensive ITS Section 3.4 c;oseout submittal Revision K.
Comed Response to issue Revised Response: Refer to LCO JFD 3.4-48. This change is provided in our comprehensive ITS Section 3.4 c;oseout submittal Revision K.
I Original Response: Comed will add an LCO JFD to justify this change. The JFD will state, "The references to " manual."
Original Response: Comed will add an LCO JFD to justify this change. The JFD will state, "The references to " manual."
            " remote-manual," " power-operated." " check," and " automatic" is not consistent within the STS. Byron /Braidwood plant specific terminology distinguishes between the classification of valves designated as " power operated" and " automatic."
" remote-manual," " power-operated." " check," and " automatic" is not consistent within the STS. Byron /Braidwood plant specific terminology distinguishes between the classification of valves designated as " power operated" and " automatic."
Automatic valves refer to those valves that require a motive force to actuate, such as air or electric, and receive an automatic actuation signal. Automatic air operated valves and automatic electric operated valves fall into this category. Power operated valves, on the other hand, require a motive force to actuate, such as air or electric, but do not receive an automatic actuation signal. Air power operated valves and electric power operated valves fall into this category. Therefore, including the reference to " power operated" isolation valves reduces the potential for misinterpreting the requirements of the Required Action, while maintaining the assumptions of the accident analysis, and is consistent with plant specific terminology. The words " closed manual or der.ctivated automatic" have been deleted from NUREG Required Action (RA) C.1 due to those classifications of valves not being applicable to the penetrations with the RHR System suction isolation valves. With the RHR System suction isolation valve interlock function inoperable, ITS RA B.I requires that the affected RHR suction penetration be isolated by at least one de-energized power operated valve, i.e., an RHR suction isolation valve." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed l           Responses to the ITS Section 3.4 RAl. (See RAI 3.6.3-07.)
Automatic valves refer to those valves that require a motive force to actuate, such as air or electric, and receive an automatic actuation signal. Automatic air operated valves and automatic electric operated valves fall into this category. Power operated valves, on the other hand, require a motive force to actuate, such as air or electric, but do not receive an automatic actuation signal. Air power operated valves and electric power operated valves fall into this category. Therefore, including the reference to " power operated" isolation valves reduces the potential for misinterpreting the requirements of the Required Action, while maintaining the assumptions of the accident analysis, and is consistent with plant specific terminology. The words " closed manual or der.ctivated automatic" have been deleted from NUREG Required Action (RA) C.1 due to those classifications of valves not being applicable to the penetrations with the RHR System suction isolation valves. With the RHR System suction isolation valve interlock function inoperable, ITS RA B.I requires that the affected RHR suction penetration be isolated by at least one de-energized power operated valve, i.e., an RHR suction isolation valve." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed l
Responses to the ITS Section 3.4 RAl. (See RAI 3.6.3-07.)
t
t
      .( Ji 41
.( J i
41


                      - .= = = = . = = =                         = - ,                 -
-.= = = =. = = =
R:sp:ns: to NRC RAI For ITS SIctinn 3A                                   09-oct 98
= -,
                                        ~                ~                                    ~
R:sp:ns: to NRC RAI For ITS SIctinn 3A 09-oct 98 NRC RAI Number NRC issuid Date RAI Status
NRC RAI Number               NRC issuid Date                           RAI Status
~
    ,m            3.4.14-05                     3/9/98                               Closed by-i NRC Description of Issue
~
          . Not used                                                                                                                       I Comed Response to issue No response required.
~
                    -    z .-         =,==:. ..                     ~         = = . .
3.4.14-05 3/9/98 Closed
NRC RAI Number               NRC issued Date                           RAI Status 3.4.14-06                     3/9'98                               Closed NRC Description ofissue JFD Pl CTS 4.4.6.2.2.b ITS SR 3.4.14.1 The Frequency Note Stating " Prior to entering Mode 2.. " has been editorially changed in ITS SR 3.4.14.1 when the CTS /STS wording for this statement is identical. Comment: Please revise the submittal. The STS text is applicable, clear.
,m by-NRC Description of Issue i
. Not used I
Comed Response to issue No response required.
z.-
=,==:...
~
= =..
NRC RAI Number NRC issued Date RAI Status 3.4.14-06 3/9'98 Closed NRC Description ofissue JFD Pl CTS 4.4.6.2.2.b ITS SR 3.4.14.1 The Frequency Note Stating " Prior to entering Mode 2.. " has been editorially changed in ITS SR 3.4.14.1 when the CTS /STS wording for this statement is identical. Comment: Please revise the submittal. The STS text is applicable, clear.
and should be adopted.
and should be adopted.
Comed Response to issue No change. While Comed agrees that the NUREG text is clest as written, it is not standard ITS format to use "words" in place of equalities and inequalities in ITS. A phrase such as "7 days or more" is not used anywhere else in the NUREG and therefore, Comed continues to pursue this change for consistency throughout ITS.
Comed Response to issue No change. While Comed agrees that the NUREG text is clest as written, it is not standard ITS format to use "words" in place of equalities and inequalities in ITS. A phrase such as "7 days or more" is not used anywhere else in the NUREG and therefore, Comed continues to pursue this change for consistency throughout ITS.
                                                                      = ,.=. .              .
=,.=..
NRC RAI Number             . NRC Issued Date                         RAI Status 3.4.14-07                       3/9/98                               Closed A
NRC RAI Number
(*)     NRC Description ofIssue JFD Pi CTS 3.4.6.2.f footnote
. NRC Issued Date RAI Status 3.4.14-07 3/9/98 Closed A(*)
NRC Description ofIssue JFD Pi CTS 3.4.6.2.f footnote
* ITS SR 3.4.14.1 Bases for STS LCO 3.4.14, STS markup page B 3.4-81 in ITS SR 3.4.14.1, the test pressure for Piv leakage testing differs from the STS requirement because it specifies an
* ITS SR 3.4.14.1 Bases for STS LCO 3.4.14, STS markup page B 3.4-81 in ITS SR 3.4.14.1, the test pressure for Piv leakage testing differs from the STS requirement because it specifies an
            " equivalent" RCS pressure for testing PI'/s. CTS 3.4.6.2.f footnote *, which pertains to defining the equivalent pressure for PlV testing, is moved to the TRM. as explained by DOC LA10, because these details are not needed in the ITS. Note, however, that the last paragraph of the Bases for STS LCO 3.4.14 already contains the information specified by the CTS footnote. Comment: The addition of the modifier " equivalent" is an unnecessary generic change and is not accepted. - Revise the submittal to adopt the STS wording. Revise DOC LA10 to explain that the allowance to use an equivalent pressure is moved to the Bases in addition to the TRM. Suggest augmenting the Bases for ITS SR 3.4.14.1 to explicitly discuss the testing at lower pressures; i.e., at equivalent pressures - scaling the leakage measured at a reduced pressure to the equivalent leakage at the speciflied test pressure for comparison to the specified leakage limit.
" equivalent" RCS pressure for testing PI'/s. CTS 3.4.6.2.f footnote *, which pertains to defining the equivalent pressure for PlV testing, is moved to the TRM. as explained by DOC LA10, because these details are not needed in the ITS. Note, however, that the last paragraph of the Bases for STS LCO 3.4.14 already contains the information specified by the CTS footnote. Comment: The addition of the modifier " equivalent" is an unnecessary generic change and is not accepted. - Revise the submittal to adopt the STS wording. Revise DOC LA10 to explain that the allowance to use an equivalent pressure is moved to the Bases in addition to the TRM. Suggest augmenting the Bases for ITS SR 3.4.14.1 to explicitly discuss the testing at lower pressures; i.e., at equivalent pressures - scaling the leakage measured at a reduced pressure to the equivalent leakage at the speciflied test pressure for comparison to the specified leakage limit.
Comed Response to issue DOC 3.4-LA10 will be revised to state," CTS LCO 3.4.6.2 Footnote
Comed Response to issue DOC 3.4-LA10 will be revised to state," CTS LCO 3.4.6.2 Footnote
* provides details of Pressure Isolation Valve (PlV) test performance for various unit conditions. These details are to be relocated to the ITS Baras. The requirements ofITS SR 3.4.14.1, which include leakage limits stated in terms of equivalent leakage rates with a specified pressure range, are adequate to ensure RCS PlV leakage is within required limits. As a result, the relocated details are not necessary for ensuring RCS PlV leakage is within required limits and do not need to be included in the TS to provided adequate protection of the public health and safety. The relocation of these details maintains the consistency with NUREG-1431. Any change to r-         these details will be made in accordance with the Bases Control Program described in ITS Section 5.5 " In addition, the l-         modifier " equivalent" will be withdrawn from ITS SR 3.4.14.1, and the ITS Bases will be revised to include the details q       associated with the CTS footnote. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal
* provides details of Pressure Isolation Valve (PlV) test performance for various unit conditions. These details are to be relocated to the ITS Baras. The requirements ofITS SR 3.4.14.1, which include leakage limits stated in terms of equivalent leakage rates with a specified pressure range, are adequate to ensure RCS PlV leakage is within required limits. As a result, the relocated details are not necessary for ensuring RCS PlV leakage is within required limits and do not need to be included in the TS to provided adequate protection of the public health and safety. The relocation of these details maintains the consistency with NUREG-1431. Any change to r-these details will be made in accordance with the Bases Control Program described in ITS Section 5.5 " In addition, the l-modifier " equivalent" will be withdrawn from ITS SR 3.4.14.1, and the ITS Bases will be revised to include the details q
        ' revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
associated with the CTS footnote. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal
' revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
42
42


l l                                           Respnnse to NRC RAI For ITS Section 3A                                   oo-Oei98
l l
                                      - =:.                          _.
Respnnse to NRC RAI For ITS Section 3A oo-Oei98
NRC RAI Number             NRC lssued Date                         RAI Status l     ,,          3.4.14 08                   3'9'98                               Closed
- =:.
        ) NRC Description ofissue JFD P26 ITS SR 3.4.14.1 1
NRC RAI Number NRC lssued Date RAI Status l
ITS SR 3.4.14.1 omits the STS' requirement to perform PlV leakage testing at a Frequency in accordance with the Insen ice l Test Program. The ITS requiress the test to be performed at 18 month mtervals but not per the IST Program. JFD P2o and     l Bases JFD P1 for SR 3.4.14.2 do not adequatelyjustify this deviation. Comment: Revise ITS SR 3.4.14.1. and associated Bases, to adopt the STS Frequency of"in accordance with the Insenice Test Program."
3.4.14 08 3'9'98 Closed
l         Comed Response to issue Revised Response: Per discussions with the NRC Reviewer. Comed has adopted the NUREG Frequency for SR 3.4.14.1-This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
)
l l-         Original Response: Comed will revise ITS SR 3.4.14.1 Frequency to state. "In accordance with the Inservice Testing
NRC Description ofissue JFD P26 ITS SR 3.4.14.1 ITS SR 3.4.14.1 omits the STS' requirement to perform PlV leakage testing at a Frequency in accordance with the Insen ice Test Program. The ITS requiress the test to be performed at 18 month mtervals but not per the IST Program. JFD P2o and Bases JFD P1 for SR 3.4.14.2 do not adequatelyjustify this deviation. Comment: Revise ITS SR 3.4.14.1. and associated Bases, to adopt the STS Frequency of"in accordance with the Insenice Test Program."
.          Program." The PlVs are tested in accordance with the Strc. ion's IST Program which was developed in accordance with ASME Section XI requirements. In addition, Comed will delete the 18 month Frequency currently in ITS since the Inservice Testing Program Frequency is also 18 months. It is not standard NUREG format to include specific times with     l Frequencies which are in accordance with Programs, such as "In accordance with the Inservice Testing Program." There is no benefit in stating the same time Frequency for the same SR twice. Comed will revise the ITS Bases for SR 3.4.14.1 to include the STS wording referencing the Inservice Testing Program. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.       l
l Comed Response to issue Revised Response: Per discussions with the NRC Reviewer. Comed has adopted the NUREG Frequency for SR 3.4.14.1-This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
                                                    =         -                          ._
l l-Original Response: Comed will revise ITS SR 3.4.14.1 Frequency to state. "In accordance with the Inservice Testing Program." The PlVs are tested in accordance with the Strc. ion's IST Program which was developed in accordance with ASME Section XI requirements. In addition, Comed will delete the 18 month Frequency currently in ITS since the Inservice Testing Program Frequency is also 18 months. It is not standard NUREG format to include specific times with Frequencies which are in accordance with Programs, such as "In accordance with the Inservice Testing Program." There is no benefit in stating the same time Frequency for the same SR twice. Comed will revise the ITS Bases for SR 3.4.14.1 to include the STS wording referencing the Inservice Testing Program. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
NRC RAI Number             NRC issued Date                         RAI Status 3.4.14-09                   3/9/98                               Closed
l
  =/N     NRC Description of Issue JFD P47 CTS 4.4.6.2.2.b ITS SR 3.4.14.1 Frequency The wording of the third Frequency ofITS SR 3.4.14.1 differs from the STS. Instead of"Within 24 hours following . ,it says "Once within 24 hours after . ." Comment: These editorial changes are unnecessary and notjustificable on an editorial or plant-specific basis. The STS wording is clear. Adopt the STS version of the Frequency.
=
NRC RAI Number NRC issued Date RAI Status 3.4.14-09 3/9/98 Closed
=/N NRC Description of Issue JFD P47 CTS 4.4.6.2.2.b ITS SR 3.4.14.1 Frequency The wording of the third Frequency ofITS SR 3.4.14.1 differs from the STS. Instead of"Within 24 hours following.,it says "Once within 24 hours after.." Comment: These editorial changes are unnecessary and notjustificable on an editorial or plant-specific basis. The STS wording is clear. Adopt the STS version of the Frequency.
Comed Response to Issue Comed will adopt the STS version of the Frequency. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09,3.4.16-05, and 3.4.18-03.)
Comed Response to Issue Comed will adopt the STS version of the Frequency. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09,3.4.16-05, and 3.4.18-03.)
NRC RAI Number           NRC lssued Date                         RAI Status                                           l 3.4.14-10                   3/9/98                               Closed NRC Description ofissue Not used Comed Response to issue No response required.
NRC RAI Number NRC lssued Date RAI Status 3.4.14-10 3/9/98 Closed NRC Description ofissue Not used Comed Response to issue No response required.
t U i
U t
43
i 43
 
l Resp:nse to NRC RAI Fcr ITS S:ction 3A                                      co-oei-98 NRC RAI Number                NRC issued Date                                                  RAI Status 3.4.14 11                            3.'9 98                                                  Closed if3
(,/      ' NRC Description of issue
              ?!)tused Comed Response to issue No response required.
                . - . - . . - _ . = _ . = .=.                      . . - - . . ,.;-.__.                          .
NRC RAI Number                NRC issued Date                                                  RAI Status 3.4.14 12                            3.'9'98                                                  Closed                        j NRC Description ofissue Bases JFD Pl Bases for ITS 3.4.14 Action Notes. STS markup page B 3.4-81 in the first paragraph, the fourth sentence the ITS differs from the STS as follows: " Note 2 requires an evaluation of affected systems Emergency Core Cooling System subsystems if a PlV is inoperable. The ITS wording appears to be less restnctive than the STS wording because some of these PIVs could also be considered to be in the CVCS or RCS Systems. Thus, this may not bejust an editorial change, and may also be generic. Cornment: Revise the Bases to adopt the STS wording.
Comed Response to issue                                                                                                              i Comed will revise the Bases to adopt the STS wording. This ci ange will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.                              l
                                    . _ . . _ .._ _  . ___ . .        .___., . =.; ,
            = NRC RAI Number                  NRC issued Date                                                  RAI Status
        .-          3.4.14-13                            3/9/98                                                  Closed
  !    4 NRC Description of issue '
  %)        Not used Comed Response to issue No response required.
l                                                                                                      44


                  . . -& -                     ._ _ _                :==-
l Resp:nse to NRC RAI Fcr ITS S:ction 3A co-oei-98 NRC RAI Number NRC issued Date RAI Status f3 3.4.14 11 3.'9 98 Closed i(,/
Respanse to NRC RAI For ITS Section 3A                                   oo-oct-98 NRC RAI Number               NRC issued Date                             RAI Status m             3.4.15-01                     3,9.'98                                 Closed                                           1 NRC Description of Issue DOC Ll7                                                                                                                         )
' NRC Description of issue
l          DOC L19 JFD P27 JFD BP27                                                                                                                         I CTS 3.4.6.1.a and c                                                                                                             I CTS 3.4.6.1 Action c '                                                                                                         I ITS 3.4.15 and Action B                                                                                                         !
?!)tused Comed Response to issue No response required.
l CTS 3.4.6.1.a. b. and c define three separate RCS leakage system monitors as required to be Operable. Reg Guide 1.45             I requires this number of diverse monitors and a minimum of two shall always be Operable. STS 3.4.15 contains provisions to I
. -. -.. - _. = _. =.=.
ensure that two diverse monitors are Operable. ITS 3.4.15 and Action B have changed the CTS requirements to combme the
NRC RAI Number NRC issued Date RAI Status 3.4.14 12 3.'9'98 Closed j
NRC Description ofissue Bases JFD Pl Bases for ITS 3.4.14 Action Notes. STS markup page B 3.4-81 in the first paragraph, the fourth sentence the ITS differs from the STS as follows: " Note 2 requires an evaluation of affected systems Emergency Core Cooling System subsystems if a PlV is inoperable. The ITS wording appears to be less restnctive than the STS wording because some of these PIVs could also be considered to be in the CVCS or RCS Systems. Thus, this may not bejust an editorial change, and may also be generic. Cornment: Revise the Bases to adopt the STS wording.
Comed Response to issue i
Comed will revise the Bases to adopt the STS wording. This ci ange will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
.___.,. =.;,
= NRC RAI Number NRC issued Date RAI Status 3.4.14-13 3/9/98 Closed 4
NRC Description of issue '
%)
Not used Comed Response to issue No response required.
l 44
:==-
Respanse to NRC RAI For ITS Section 3A oo-oct-98 NRC RAI Number NRC issued Date RAI Status m
3.4.15-01 3,9.'98 Closed 1
NRC Description of Issue DOC Ll7 l
DOC L19 JFD P27 JFD BP27 CTS 3.4.6.1.a and c CTS 3.4.6.1 Action c '
I ITS 3.4.15 and Action B CTS 3.4.6.1.a. b. and c define three separate RCS leakage system monitors as required to be Operable. Reg Guide 1.45 requires this number of diverse monitors and a minimum of two shall always be Operable. STS 3.4.15 contains provisions to ensure that two diverse monitors are Operable. ITS 3.4.15 and Action B have changed the CTS requirements to combme the
{
{
sepa ate gaseous and particulate monitoring functions into one monitor. The result is that when the one monitor is lost then     '
sepa ate gaseous and particulate monitoring functions into one monitor. The result is that when the one monitor is lost then F
F          both functions are lost. Also. the time permitted for this inoperable condition has been extended from 72 hours to 30 days     i i
both functions are lost. Also. the time permitted for this inoperable condition has been extended from 72 hours to 30 days i
with only the one sump monitor Operable during this period. For a 30 day period, when one of three are inoperable (if             I Condition B was changed to a gaseous or particulate monitor is inoperable) performing SR 3.4.13,1 is acceptable l
i with only the one sump monitor Operable during this period. For a 30 day period, when one of three are inoperable (if Condition B was changed to a gaseous or particulate monitor is inoperable) performing SR 3.4.13,1 is acceptable compensatory action. When two of the three (both gaseous and particulate functions) monitors are inoperable for a 30 day period, SR 3.4.13.1 or grab samples as the next monitoring system is not acceptable because the monitoring response times are greatly extended. This ITS Action B is contrary to the intent of Reg Guide 1.45. Comment: Please provide additional discussion and technicaljustification for this less restrictive change.
compensatory action. When two of the three (both gaseous and particulate functions) monitors are inoperable for a 30 day period, SR 3.4.13.1 or grab samples as the next monitoring system is not acceptable because the monitoring response times         i are greatly extended. This ITS Action B is contrary to the intent of Reg Guide 1.45. Comment: Please provide additional         l discussion and technicaljustification for this less restrictive change.                                                         j Comed Response to issue i
j Comed Response to issue i
Revised Response: Per discussions with the NRC Reviewer, no change required.
Revised Response: Per discussions with the NRC Reviewer, no change required.
Original Response: Comed will rewrite ITS 3.4.15 to incorporate a Condition when one gaseous or particulate containment         )
Original Response: Comed will rewrite ITS 3.4.15 to incorporate a Condition when one gaseous or particulate containment
l         .
)
atmosphere radioactivity monitoring function is lost, and when both the gaseous and particulate containment atmosphere           !
l atmosphere radioactivity monitoring function is lost, and when both the gaseous and particulate containment atmosphere n/
n/       radioactivity monitoring functions are lost. This change will be provided in our comprehensise ITS Section 3.4 closecut
radioactivity monitoring functions are lost. This change will be provided in our comprehensise ITS Section 3.4 closecut
{
{
submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.                                   i NRC RAI Number               NRC lssued Date                           . RAI Status 3.4.15-02                     3/9/98                                   Closed NRC Description of issue Not used Comed Response to issue
submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
                                                                                                                                            )
i NRC RAI Number NRC lssued Date
No response required.                                                                                                           I I
. RAI Status 3.4.15-02 3/9/98 Closed NRC Description of issue Not used Comed Response to issue
!                                                                                                                                            1
)
(                                                                                                                                            l
No response required.
(
(
u                                                                                                                                           ,
(
l t
u t
l                                                                             45 l
l 45 l
l I


                                                                    .      , . =           .                . _ ._-            ..
,. =
:-                                                =       := =
=
l                                               R sponse to NRC RAI For ITS S:ction 3.4                               09-oci.98     ;
:= =
                                                                                                    ~'
l R sponse to NRC RAI For ITS S:ction 3.4 09-oci.98 NRC RAI Numb r RIlssbDa RIl Status
NRC RAI Numb r                     RIlssbDa
~'
                                                ~
l
RIl Status l
~
n          3.4.15                   3/9'98                                         Closed l
3.4.15 3/9'98 Closed n
Q)   NRC D'escription of Issue DOC LA9 CTS 3/4.4.6.1 Action a                                                                               ,
Q)
Bases for ITS 3.4.15 Action B STS markup page B 3.4 89                                                                     l l
NRC D'escription of Issue l
: j.                                                                                                                                   !
DOC LA9 CTS 3/4.4.6.1 Action a Bases for ITS 3.4.15 Action B STS markup page B 3.4 89 l
CTS 3.4.6.1 Action a requires analysis of the containment atmosphere grab samples for gaseous and particulate               j l       radioactivity. DOC LA9 says the specific requirement to analyze the grab samples for both particulate and gaseous actn ity   ,
j.
is a detail which is moved to the ITS Bases. The Bases for ITS 3.4.15 Action B. however. only mentions taking grab           l samples. but does not describe the CTS requirement for analysis. Comment: Even though the proposed discussion in the         ;
CTS 3.4.6.1 Action a requires analysis of the containment atmosphere grab samples for gaseous and particulate j
Bases for ITS 3.4.15 Action B is consistent with the STS, it must be revised so that the statement in DOC LA9 is accurate. I Comed Response to issue The first paragraph of the Actions Section of the Bases for ITS LCO 3.4.15 for Actions B.1 and B.2 will be revised to state. )
l radioactivity. DOC LA9 says the specific requirement to analyze the grab samples for both particulate and gaseous actn ity is a detail which is moved to the ITS Bases. The Bases for ITS 3.4.15 Action B. however. only mentions taking grab samples. but does not describe the CTS requirement for analysis. Comment: Even though the proposed discussion in the Bases for ITS 3.4.15 Action B is consistent with the STS, it must be revised so that the statement in DOC LA9 is accurate.
        "Either grab samp!es of the containment atmosphere must be taken and analyzed for gaseous and particulate radioactivity or   !
Comed Response to issue The first paragraph of the Actions Section of the Bases for ITS LCO 3.4.15 for Actions B.1 and B.2 will be revised to state.
water inventory balances, in accordance . " This change will be provided in our comprehensive ITS Section 3.4 closecut       j submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.                               '
"Either grab samp!es of the containment atmosphere must be taken and analyzed for gaseous and particulate radioactivity or water inventory balances, in accordance. " This change will be provided in our comprehensive ITS Section 3.4 closecut j
NRC RAI Number                   NRC issued Date                                 RAI Status 3.4.I6-01                       3/9/98                                       Closed                                 )
submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
NRC Description ofIssue                                                                                                     !
NRC RAI Number NRC issued Date RAI Status 3.4.I6-01 3/9/98 Closed
Not used                                                                                                                     l Comed Response to issue                                                                                                     i No response required.
)
(o)                                                                                                                               i NRC RAI Number                   NRC issued Date                                 RAI Status 3.4.16-02                     3/9/98                                         Closed NRC Description ofIssue Not used i
NRC Description ofIssue Not used Comed Response to issue No response required.
(o)
NRC RAI Number NRC issued Date RAI Status 3.4.16-02 3/9/98 Closed NRC Description ofIssue Not used i
Comed Response to issue No response required.
Comed Response to issue No response required.
NRC RAI Number                   NRC issued Dcte                                 RAI Status 3.4.16-03                     3/938                                         Closed NRC Description of issue Not used Comed Response to Issue No response required.
NRC RAI Number NRC issued Dcte RAI Status 3.4.16-03 3/938 Closed NRC Description of issue Not used Comed Response to Issue No response required.
l i   /
l i
t f
/
: L l
f t: L l
46                                             l l
46


                                            ~ R$sph~nsh to NRC RAI For ITS S ction 3.4                                   09-oci 98 NRC RAI Number               NRC issued Date                         RAI Status
~ R$sph~nsh to NRC RAI For ITS S ction 3.4 09-oci 98 NRC RAI Number NRC issued Date RAI Status I
  -m            3.4.16-04                     3I 9'98                               Closed
3.4.16-04 3 9'98 Closed
  !  \
-m
V       NRC Description ofIssue JFD P29 CTS Table 4.4-4 Measurement Type 3, Footnote
\\
V NRC Description ofIssue JFD P29 CTS Table 4.4-4 Measurement Type 3, Footnote
* STS SR 3.4.16.3 and Note ITS SR 3.4,16.3 and Note CTS Table 4.4 4 Measurement Type 3. Footnote
* STS SR 3.4.16.3 and Note ITS SR 3.4,16.3 and Note CTS Table 4.4 4 Measurement Type 3. Footnote
* states the timing for the beginning of Frequency for when the E-bar determination is to be taken. STS SR 3.4.1.6.3 states this interval in both the Note and the SR 3.4.16.3. ITS SR 3.4.16.3 only states this timing in the Note. The change is not a plant specific change based upon a current CTS requirement.
* states the timing for the beginning of Frequency for when the E-bar determination is to be taken. STS SR 3.4.1.6.3 states this interval in both the Note and the SR 3.4.16.3. ITS SR 3.4.16.3 only states this timing in the Note. The change is not a plant specific change based upon a current CTS requirement.
Comment: Revise the submittal to adopt the omitted text of STS SR 3.4.16.3.
Comment: Revise the submittal to adopt the omitted text of STS SR 3.4.16.3.
Comed Response to issue Comed will revise the submittal to adopt the omitted text of STS SR 3.4.16.3. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the submittal to adopt the omitted text of STS SR 3.4.16.3. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
NRC RAI Number               NRC issued Date                         RAI Status 3.4.16-05                     3/9/98                               Closed NRC Description ofissue JFD P47 Bases JFD Pl CTS Table 4.4-4, Measurement Type 4b STS SR 3.4.16.2 Frequency and associated Bases ITS SR 3.4.16.2 Frequency and associated Bases In ITS SR 3.4.16.2, the word "once" is added to the STS Frequency which specifies a Frequency of"within" a particular time frame. For this Frequency,"within" is "between 2 and 6 hours after a Thermal Power change of 15% RTP within a I hour period." It is clear that the STS (and CTS) Frequency means once for each such power change. Also, the STS SR Frequency is worded the same as the wording of the Frequency for CTS Table 4.4-4 Measurement Type 4b. Comment: This generic editorial deviation is unnecessary. Revise the Frequency consistent with the STS and CTS. Also withdraw the two apparent generic editorial deviations from the Bases for STS SR 3.4.16.2. In particular, the replacement of" inaccurate" with "less conservative" in the Bases is actually a technical change and is notjustified.
NRC RAI Number NRC issued Date RAI Status 3.4.16-05 3/9/98 Closed NRC Description ofissue JFD P47 Bases JFD Pl CTS Table 4.4-4, Measurement Type 4b STS SR 3.4.16.2 Frequency and associated Bases ITS SR 3.4.16.2 Frequency and associated Bases In ITS SR 3.4.16.2, the word "once" is added to the STS Frequency which specifies a Frequency of"within" a particular time frame. For this Frequency,"within" is "between 2 and 6 hours after a Thermal Power change of 15% RTP within a I hour period." It is clear that the STS (and CTS) Frequency means once for each such power change. Also, the STS SR Frequency is worded the same as the wording of the Frequency for CTS Table 4.4-4 Measurement Type 4b. Comment: This generic editorial deviation is unnecessary. Revise the Frequency consistent with the STS and CTS. Also withdraw the two apparent generic editorial deviations from the Bases for STS SR 3.4.16.2. In particular, the replacement of" inaccurate" with "less conservative" in the Bases is actually a technical change and is notjustified.
Comed Response to issue Comed will revise the Frequency consistent with the STS, and will withdraw the changes to the Bases for STS SR 3.4.16.2.
Comed Response to issue Comed will revise the Frequency consistent with the STS, and will withdraw the changes to the Bases for STS SR 3.4.16.2.
This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09,3.4.14-09, and 3.4.18 03.)
This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09,3.4.14-09, and 3.4.18 03.)
Line 962: Line 1,130:
l
l


Resp:nse to NRC RAI For ITS Section 3.4                               09-Oct 98 NRC RAI Number               NRC lssued Date                           RAI Status i               3.4.16-06                           5 3998                           Closed V     NRC Description ofIssue CTS 3.4.8 Table 4.4-4 Measurement Types 2 and 4b ITS 3.4.16.2 Note if the unit is in Mode 1,2 or 3. CTS 3.4.8 Table 4.4-4 Measurement Type 4b requires an isotopic analy sis of a reactor             l coolant sample for lodine including I 131,1 133, and 1 135 on a Frequency of"between 2 and 6 hours after a Thermal Power change of 15% RTP within a i hour penod." The CTS markup indicates that ITS 3.4.16.2. verification of reactor coolant Dose Equivalent 1-131 specific activity, corresponds to this isotopic analysis. ITS SR 3.4.16.2 contains a note. consistent       1 with the STS, that only requires this test at the CTS Frequency if the unit is in Mode 1, which is less restrictive than the CTS applicability requirement. The submittal contains no technicaljustification for this change in applicability. Notice that the i CTS markup also indicates that ITS SR 3.4.16.2 corresponds to CTS Table 4.4-4 Measurement Type 2, isotopic analysis for             l Dose Equivalent 1 131 concentration, which is only required to be performed in Mode 1, Comment: Add an L-type DOC                   l with technicaljustification for this less restrictive change to the CTS. Explain why ITS SR 3.4.16.2 satisfies the                 I requirements of both Measurement Types 2 and 4b, as implied by the CTS markup.'
Resp:nse to NRC RAI For ITS Section 3.4 09-Oct 98 NRC RAI Number NRC lssued Date RAI Status 5
i 3.4.16-06 3998 Closed V
NRC Description ofIssue CTS 3.4.8 Table 4.4-4 Measurement Types 2 and 4b ITS 3.4.16.2 Note if the unit is in Mode 1,2 or 3. CTS 3.4.8 Table 4.4-4 Measurement Type 4b requires an isotopic analy sis of a reactor coolant sample for lodine including I 131,1 133, and 1 135 on a Frequency of"between 2 and 6 hours after a Thermal Power change of 15% RTP within a i hour penod." The CTS markup indicates that ITS 3.4.16.2. verification of reactor coolant Dose Equivalent 1-131 specific activity, corresponds to this isotopic analysis. ITS SR 3.4.16.2 contains a note. consistent 1
with the STS, that only requires this test at the CTS Frequency if the unit is in Mode 1, which is less restrictive than the CTS applicability requirement. The submittal contains no technicaljustification for this change in applicability. Notice that the i CTS markup also indicates that ITS SR 3.4.16.2 corresponds to CTS Table 4.4-4 Measurement Type 2, isotopic analysis for Dose Equivalent 1 131 concentration, which is only required to be performed in Mode 1, Comment: Add an L-type DOC with technicaljustification for this less restrictive change to the CTS. Explain why ITS SR 3.4.16.2 satisfies the requirements of both Measurement Types 2 and 4b, as implied by the CTS markup.'
Comed Response to Issue Revised Response: Refer to CTS DOC 3.4-L39. This change is provided in our comprehensive 1TS Section 3.4 closeout submittal Revision K.
Comed Response to Issue Revised Response: Refer to CTS DOC 3.4-L39. This change is provided in our comprehensive 1TS Section 3.4 closeout submittal Revision K.
      - Original Response: CorrsEd will revise the submittal to include DOC 3.4-LA30 stating, " CTS Table 4.4-4 Item 2 requires DOSE EQUIVALENT (DE) 1 131 concentration to be determined to be less than or equal to 0.35 pCi/gm for Unit I (1.0 pCi gm for Unit 2) once per 14 days while in Mode 1, item 4 requires an isotopic analysis for lodine including 1-131,1-133, and 1 135 once between 2 and 6 hours following a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1 hour period while in Modes 1,2, and 3 with no limit imposed. NUREG SR 3.4.16.2 requires DE I 131 to be determined once per 14 days and once between 2 and 6 hours after a THERMAL POWER change of greater than or
- Original Response: CorrsEd will revise the submittal to include DOC 3.4-LA30 stating, " CTS Table 4.4-4 Item 2 requires DOSE EQUIVALENT (DE) 1 131 concentration to be determined to be less than or equal to 0.35 pCi/gm for Unit I (1.0 pCi gm for Unit 2) once per 14 days while in Mode 1, item 4 requires an isotopic analysis for lodine including 1-131,1-133, and 1 135 once between 2 and 6 hours following a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1 hour period while in Modes 1,2, and 3 with no limit imposed. NUREG SR 3.4.16.2 requires DE I 131 to be determined once per 14 days and once between 2 and 6 hours after a THERMAL POWER change of greater than or
  .(~ equal to 15% RTP within a i hour period while in Mode 1. NUREG SR 3.4.16.2 places a limit ofless than or equal to 1.0
.(~
(   pCilgm for DE I.131. The NUREG, and therefore ITS, do not require the Isotopic Analysis for 1 131,1-133, or 1 135 to be performed. The purpose for the analysis ofI-131,1 133, and 1 135 with a power change of greater than or equal to 15% is to
equal to 15% RTP within a i hour period while in Mode 1. NUREG SR 3.4.16.2 places a limit ofless than or equal to 1.0
      - trend possible fuel cladding leakage or failure following fast power changes when fuel failure is more apt to occur.
(
pCilgm for DE I.131. The NUREG, and therefore ITS, do not require the Isotopic Analysis for 1 131,1-133, or 1 135 to be performed. The purpose for the analysis ofI-131,1 133, and 1 135 with a power change of greater than or equal to 15% is to
- trend possible fuel cladding leakage or failure following fast power changes when fuel failure is more apt to occur.
Relocating this requirement to the TRM still maintains its SR function for trending any fuel leakage. However, this requirement is not necessary to ensure DE l-131 is maintained. As such, the relocated requirement is not required to be maintained in the ITS, per 10 CFR 50.36(c)(2)(ii), and is not required to provide adequate protection to the public health and safety. Any changes to this requirement will be made in accordance with 10 CFR 50.59." In addition, the Frequency of "Between 2 and 6 hours after a THERMAL POWER change of greater than or equal to 15% RTP within a 1 hour period" will be deleted from NUREG SR 3.4.6.2 Surveillance Requirement and the Surveillance Requirements Section of the Bases for ITS LCO 3.4.16. This change will be provided in our comprehensive ITS Section 3.4 c!oseout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
Relocating this requirement to the TRM still maintains its SR function for trending any fuel leakage. However, this requirement is not necessary to ensure DE l-131 is maintained. As such, the relocated requirement is not required to be maintained in the ITS, per 10 CFR 50.36(c)(2)(ii), and is not required to provide adequate protection to the public health and safety. Any changes to this requirement will be made in accordance with 10 CFR 50.59." In addition, the Frequency of "Between 2 and 6 hours after a THERMAL POWER change of greater than or equal to 15% RTP within a 1 hour period" will be deleted from NUREG SR 3.4.6.2 Surveillance Requirement and the Surveillance Requirements Section of the Bases for ITS LCO 3.4.16. This change will be provided in our comprehensive ITS Section 3.4 c!oseout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.
l 4
l 4
Line 973: Line 1,146:
48 l
48 l


                    = - .                                             .- - - -.. =.
= -.
Response to NRC RAI For ITS Sectica 3.4                                       09-Oct-98 NRC RAI umber                 C5 e       at                           kAlStatus n             3.4.16-07                   i'9'98                                 Closed I
.- - - -.. =.
  .v)     NRC Description ofissue Bases JFD Pl Bases discussion Applicable Safety Analyses. STS markup page B 3.4 93 In the first paragraph, last sentence, the STS text pertaining to the safety ant. lysis assumption for secondary specine reactivity was not adopted. The ITS Bases only retains a redernece to ITS LCO 3.7J 7. This is a technical change (and not an editorial change) which requires an explanation or adoption of the STS text. Comment: Revise the Bases to adopt the STS text.
Response to NRC RAI For ITS Sectica 3.4 09-Oct-98 kAlStatus NRC RAI umber C5 e at n
3.4.16-07 i'9'98 Closed I.v)
NRC Description ofissue Bases JFD Pl Bases discussion Applicable Safety Analyses. STS markup page B 3.4 93 In the first paragraph, last sentence, the STS text pertaining to the safety ant. lysis assumption for secondary specine reactivity was not adopted. The ITS Bases only retains a redernece to ITS LCO 3.7J 7. This is a technical change (and not an editorial change) which requires an explanation or adoption of the STS text. Comment: Revise the Bases to adopt the STS text.
Comed Response to issue Comed will revise the Bases to adopt the STS text. This change will be provided in our comprehensive ITS Section 3 4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
Comed Response to issue Comed will revise the Bases to adopt the STS text. This change will be provided in our comprehensive ITS Section 3 4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
NRC RAI Number             NRC lssued Date                           RAI Status 3.4.16-08                   3/9/98                                 Closed NRC Description of issue Bases JFD P3 Bases discussion Applicable Safety Analyses, STS markup page B 3.4-95 The e:ghth paragraph is not adopted based on editorial enhancement. The omitted text, however, is applicable to a standard plant and should be adoptet In addition, this is a generic technical deviation from the STS. Comment: Revise the Bases to
NRC RAI Number NRC lssued Date RAI Status 3.4.16-08 3/9/98 Closed NRC Description of issue Bases JFD P3 Bases discussion Applicable Safety Analyses, STS markup page B 3.4-95 The e:ghth paragraph is not adopted based on editorial enhancement. The omitted text, however, is applicable to a standard plant and should be adoptet In addition, this is a generic technical deviation from the STS. Comment: Revise the Bases to
          . adopt the omitted STS text.
. adopt the omitted STS text.
Comed Response to issue
Comed Response to issue
  -[(,gl 7   Comed will revise the Bases to adopt the omitted STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
-[ 7 Comed will revise the Bases to adopt the omitted STS text. This change will be provided in our comprehensive ITS Section
NRC RAI Number             NRC lssued Date                           RAI Status 3.4.I7-01                   3/9/98                                 Closed NRC Description ofIssue Bases JFD P3 Bases discussion of Background, STS markup page D 3.4A9 The Bases Background text identified as items a. b and e in the second paragraph is not adopted. This omission is characterized by Bases JFD P3 as a plant specific editorial enhancement. This editorial deviation fro n the STS Bases is generic and could apply to all Westinghouse plants with RCS loop isolation valves. Comment: Revise the Bases to adopt the omitted STS text. See similar comment 3.4.18-04.
(,gl 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
NRC RAI Number NRC lssued Date RAI Status 3.4.I7-01 3/9/98 Closed NRC Description ofIssue Bases JFD P3 Bases discussion of Background, STS markup page D 3.4A9 The Bases Background text identified as items a. b and e in the second paragraph is not adopted. This omission is characterized by Bases JFD P3 as a plant specific editorial enhancement. This editorial deviation fro n the STS Bases is generic and could apply to all Westinghouse plants with RCS loop isolation valves. Comment: Revise the Bases to adopt the omitted STS text. See similar comment 3.4.18-04.
Comed Response to issue Revised Response: Minor changes were made to the Bases for ITS LCO 3.4.17 due to changes associated with ITS 3.4.18 LCO and Bases. This change is provided in our comprehensive ITS Section 3.4 closecut submittal Revision K.
Comed Response to issue Revised Response: Minor changes were made to the Bases for ITS LCO 3.4.17 due to changes associated with ITS 3.4.18 LCO and Bases. This change is provided in our comprehensive ITS Section 3.4 closecut submittal Revision K.
Original Response: The paragraphs omitted from the Background Section of the Bases for ITS LCO 3.4.17 pertaining to ITS LCO 3.4.18 for opening the RCS loop isolation valves will be retained with appropriate changes made to reflect corresponding changes made to ITS LCO 3.4.18. This change will be provided in our comprehensive ITS Section 3.4
Original Response: The paragraphs omitted from the Background Section of the Bases for ITS LCO 3.4.17 pertaining to ITS LCO 3.4.18 for opening the RCS loop isolation valves will be retained with appropriate changes made to reflect corresponding changes made to ITS LCO 3.4.18. This change will be provided in our comprehensive ITS Section 3.4
        . closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI s 3.4. I 8-04.)
. closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI s 3.4. I 8-04.)
  .Q V
.Q V
49 I
49 I


                                          . . , . _            = = = . . =                 --
= = =.. =
Response to NRC RAI For ITS S:ction 3A                                 09-oct-98 1-NRC RAI Number                 NRC issued Date                       RAI Status l                       3.4.17-02                       3/9'98
Response to NRC RAI For ITS S:ction 3A 09-oct-98 1-NRC RAI Number NRC issued Date RAI Status l
  . ,.m                                                                                   Closed i
3.4.17-02 3/9'98 Closed
V)            NRC Description ofissue l                 Bases JFD P44 I                 Bases for ITS LCO 3.4.17 STS Markup page B 3.4-100 -
.,.m iV)
: l.               Bases insert B 3.4 100A JFD P44 states the paragraph was not adopted because the discussion relates to ITS 3.4.18. Staff thinks it is appropriate to state what happens in related LCOs to fully explain the context of the LCO requirements. Thus the omitted STS test should be adopted as applicable. Not doing so would be an unjustified generic deviation from the STS. Note that Bases insert B 3.4100A is acceptable and can be included with suitable editorial changes to accommodate the STS text. Comment: Resise
NRC Description ofissue l
!                the Bases to adopt the omitted STS text.
Bases JFD P44 I
;-                Comed Response to issue Revised Response: Minor changes were made to the Bases for ITS LCO 3.4.17 due to changes associated with ITS 3.4.18 LCO and Bases. This change is provided in our comprehensive ITS Section 3.4 closecut submmal Revision K.
Bases for ITS LCO 3.4.17 STS Markup page B 3.4-100 -
Original Response: Comed will revise the ITS Bases to adopt the omitted STS text, but will also retain Bases insert B3.4-100A as a second paragraph in the LCO Section of the Bases for ITS LCO 3.4.17 This change will be provided in our                   !
l.
comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS               l Section 3.4 RAl.
Bases insert B 3.4 100A JFD P44 states the paragraph was not adopted because the discussion relates to ITS 3.4.18. Staff thinks it is appropriate to state what happens in related LCOs to fully explain the context of the LCO requirements. Thus the omitted STS test should be adopted as applicable. Not doing so would be an unjustified generic deviation from the STS. Note that Bases insert B 3.4100A is acceptable and can be included with suitable editorial changes to accommodate the STS text. Comment: Resise the Bases to adopt the omitted STS text.
n.-    ;                    -
Comed Response to issue Revised Response: Minor changes were made to the Bases for ITS LCO 3.4.17 due to changes associated with ITS 3.4.18 LCO and Bases. This change is provided in our comprehensive ITS Section 3.4 closecut submmal Revision K.
NRC RAI Number                 NRC issued Date                         RAI Status 3.4.17-03                       3/9/98                             Closed NRC Description ofissue Not used n
Original Response: Comed will revise the ITS Bases to adopt the omitted STS text, but will also retain Bases insert B3.4-100A as a second paragraph in the LCO Section of the Bases for ITS LCO 3.4.17 This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.
      )         Comed Response to Issue No response required.
n.-
NRC RAI Number NRC issued Date RAI Status 3.4.17-03 3/9/98 Closed NRC Description ofissue Not used n
)
Comed Response to Issue No response required.
50
50


Respsnse to NRC RAI For ITS Section 3A                                     no-Oct 98
Respsnse to NRC RAI For ITS Section 3A no-Oct 98
                            .m .        _      _ .            ~       _ _ .        _
.m
NRC RAI Number               NRC issued Date                         RAI Status n                 3.4.18-01                   3 '9 +98                             Closed r
~
Q) -         NRC Description of issue DOC A28 DOC L18 JFD P31 Bases JFD P36 Bases JFD P!
NRC RAI Number NRC issued Date RAI Status n
ITS 3.4.18 CTS 3'4.4.1.5.2 ITS 3.4.18 and associated Bases differ significantly from the STS in that the ITS state requirements for conditions needed to unisolate an isolated loop - rather than conditions for maintaining a loop isolated. In addition, the ITS proposes to permit unisolating a loop with the boron concentration in the loop less than the remainder of the RCS, provided that it is greater than the required SDM boron concentration. Note: These changes are not plant specific requirements and are not part of the current licensing basis. This deviation is miscategorized as plant-specific under the NEl 96-06 guidelines of Section 2. '       j Deviations from the Applicable STS. This is a generic deviation from the STS. DOCS A28 and L18 are prepared to                   j implement the P31 deviation in the CTS. Staff can not review these CTS changes until a generic change to the STS                 1 consistent with the deviations addressed by JFD P31 is approved by the staff. Therefore, ITS 3.4.18 and all associated deviations from the STS Bases can not be reviewed at this time. Note: There are also editorial changes categorized as PI         ;
3.4.18-01 3 '9 +98 Closed Q) -
and BPI when thay are changes incorporating the technical change P31. Comment: Revise ITS 3.4.18 to be consistent with           j STS 3.4.18 and CTS 3/4.4.1.5.2.
NRC Description of issue r
1 Comed Response to issue Revised Response: Per discussions with the NRC Reviewer on 9/3/98, Comed has adopted the NUREG format for ITS LCO 3.4.187 (Note: ITS 3.4.18 changes associated with Beyond Scope change #7 were accepted by the Staff at meetings on               j 5/7/98 and 7/8/98, and via telecon on 9/17/98.) This change is provided in our comprehensive ITS Section 3.4 closeout i
DOC A28 DOC L18 JFD P31 Bases JFD P36 Bases JFD P!
ITS 3.4.18 CTS 3'4.4.1.5.2 ITS 3.4.18 and associated Bases differ significantly from the STS in that the ITS state requirements for conditions needed to unisolate an isolated loop - rather than conditions for maintaining a loop isolated. In addition, the ITS proposes to permit unisolating a loop with the boron concentration in the loop less than the remainder of the RCS, provided that it is greater than the required SDM boron concentration. Note: These changes are not plant specific requirements and are not part of the current licensing basis. This deviation is miscategorized as plant-specific under the NEl 96-06 guidelines of Section 2. '
j Deviations from the Applicable STS. This is a generic deviation from the STS. DOCS A28 and L18 are prepared to j
implement the P31 deviation in the CTS. Staff can not review these CTS changes until a generic change to the STS 1
consistent with the deviations addressed by JFD P31 is approved by the staff. Therefore, ITS 3.4.18 and all associated deviations from the STS Bases can not be reviewed at this time. Note: There are also editorial changes categorized as PI and BPI when thay are changes incorporating the technical change P31. Comment: Revise ITS 3.4.18 to be consistent with j
STS 3.4.18 and CTS 3/4.4.1.5.2.
1 Comed Response to issue Revised Response: Per discussions with the NRC Reviewer on 9/3/98, Comed has adopted the NUREG format for ITS LCO 3.4.187 (Note: ITS 3.4.18 changes associated with Beyond Scope change #7 were accepted by the Staff at meetings on j
5/7/98 and 7/8/98, and via telecon on 9/17/98.) This change is provided in our comprehensive ITS Section 3.4 closeout i
submittal Revision K.
submittal Revision K.
l d           Original Response: As discussed with the NRC Reviewer during the April 2,1998 meeting in Rockville. this change is not a         !
d Original Response: As discussed with the NRC Reviewer during the April 2,1998 meeting in Rockville. this change is not a generic change since the only other Westinghouse plants equipped with loop stop valves are Zion and Millstone. Zion is not implementing ITS and Millstone will be pursing an ITS conversion within six months following their restart. Therefore, per conversations with the NRC Reviewer, since Byron and Braidwood are the only operating plants for which this specification applies, Comed will pursue this change as plant specific. NUREG LCO 3.4.18, "RCS isolated Loop Startup," conflicted with the nomenclature of CTS 3.4.1.5.2 " Loop Isolation Valves - Shutdown" by referring to conditions to maintain the loops isolated rather than identifying the requirements needed to unisolate the RCS loop. Along with Comed's response to the LCO 3.4.18 RAls, Comed believes that DOC 3.4-A28 adequately addresses plant specific changes associated with LCO JFD 3.4 P31.
generic change since the only other Westinghouse plants equipped with loop stop valves are Zion and Millstone. Zion is not implementing ITS and Millstone will be pursing an ITS conversion within six months following their restart. Therefore, per conversations with the NRC Reviewer, since Byron and Braidwood are the only operating plants for which this specification applies, Comed will pursue this change as plant specific. NUREG LCO 3.4.18, "RCS isolated Loop Startup," conflicted with the nomenclature of CTS 3.4.1.5.2 " Loop Isolation Valves - Shutdown" by referring to conditions to maintain the loops isolated rather than identifying the requirements needed to unisolate the RCS loop. Along with Comed's response to the LCO 3.4.18 RAls, Comed believes that DOC 3.4-A28 adequately addresses plant specific changes associated with LCO JFD 3.4 P31.
In reference to DOC 3.4-L18, this change was approved in the Zion Safety Evaluation Report for implementation of the improved Technical Specifications as a less restrictive change from Current Licensing Basis (CLB) after the isolated loop boron concentration was greater than or equal to the required cold shutdown boron concentration of the unisolated portion of
In reference to DOC 3.4-L18, this change was approved in the Zion Safety Evaluation Report for implementation of the improved Technical Specifications as a less restrictive change from Current Licensing Basis (CLB) after the isolated loop boron concentration was greater than or equal to the required cold shutdown boron concentration of the unisolated portion of
            ' the RCS. This change was approved by the Staff May 30,1975 for Zion amendment number 9 (DPR-39) for Unit I, and amendment number 6 (DPR-48) for Unit 2. The issuance of the above amendments also allowed the plant the flexibility to not meet the requirements for the cold leg stop valve temperature limitation ofless than or equal to 10 degrees F if the boron concentration was met. Comed believes that requiring the boron concentration in the loop to be unisolated to be higher than the boron concentration required for the entire RCS is unnecessarily restrictive. Proposed ITS LCOs 3.1.1 and 3.9.1 provide adequate requirements to assure reactivity control in Modes 5 and 6, respectively. The justification srpplied to the
' the RCS. This change was approved by the Staff May 30,1975 for Zion amendment number 9 (DPR-39) for Unit I, and amendment number 6 (DPR-48) for Unit 2. The issuance of the above amendments also allowed the plant the flexibility to not meet the requirements for the cold leg stop valve temperature limitation ofless than or equal to 10 degrees F if the boron concentration was met. Comed believes that requiring the boron concentration in the loop to be unisolated to be higher than the boron concentration required for the entire RCS is unnecessarily restrictive. Proposed ITS LCOs 3.1.1 and 3.9.1 provide adequate requirements to assure reactivity control in Modes 5 and 6, respectively. The justification srpplied to the
            - NRC for the previous amendments for Comed's Zion Station supports the less restrictive change for the unique Westinghouse design for four loop plants equipped with loop stop isolation valves. Comed continues to pursue this change on a plant specific basis.
- NRC for the previous amendments for Comed's Zion Station supports the less restrictive change for the unique Westinghouse design for four loop plants equipped with loop stop isolation valves. Comed continues to pursue this change on a plant specific basis.
2 I
2 O
O                                                                                                                                            l 51 l
51


Response to hRC     R RAI For ITS Section 3A                                                                 09 oei m NRC RAI Number                 NRC issued Date                                       RAI Status 3.4.18 02                               3'9'98                                   Closed t_ .
Response to hRC RAI For ITS Section 3A R
() ..                 . NRC Description ofIssue DOC L9 ITS LCO 3.4.18.b -
09 oei m NRC RAI Number NRC issued Date RAI Status 3.4.18 02 3'9'98 Closed t_.()..
. NRC Description ofIssue DOC L9 ITS LCO 3.4.18.b -
ITS 3.4.18 Required Action B.1
ITS 3.4.18 Required Action B.1
: CTS 3'4.4.1.5.2 Action CTS 3/4.4.1.5.2 Action prohibits opening either the hot leg or cold leg stop valves whenever the temperature requirement of
: CTS 3'4.4.1.5.2 Action CTS 3/4.4.1.5.2 Action prohibits opening either the hot leg or cold leg stop valves whenever the temperature requirement of
                          . CTS 3.4.1.5.2.b is not met. ITS 3.4.18 Required Action B.I requires the immediate closure of only the cold leg isolation valve whenever the temperature requirement is not met. consistent with the STS. This change would be acceptable 3mder the                                                   ,
. CTS 3.4.1.5.2.b is not met. ITS 3.4.18 Required Action B.I requires the immediate closure of only the cold leg isolation valve whenever the temperature requirement is not met. consistent with the STS. This change would be acceptable 3mder the STS guidance; however, ITS 3.4.18 differs significantly from the STS, as described in comment 3.4,18 01, Provided that
STS guidance; however, ITS 3.4.18 differs significantly from the STS, as described in comment 3.4,18 01, Provided that
. comment is resolved as requested, the CTS change addressed by DOC L9 will be accepted. Otherwise, the CTS.
                          . comment is resolved as requested, the CTS change addressed by DOC L9 will be accepted. Otherwise, the CTS .
requirements must be retained. Comment: Respond according to the resolution of comment 3.4.18-01.
requirements must be retained. Comment: Respond according to the resolution of comment 3.4.18-01.
Comed Response to issue                                                                                                                                                   -l Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Original Response: With the conditions of CTS 3.4.1.5.2 not met, the actio'n is to not open either the hot leg or the cold leg
Original Response: With the conditions of CTS 3.4.1.5.2 not met, the actio'n is to not open either the hot leg or the cold leg
                          . stop valves. ITS LCO 3.4.18a requires that only the boron concentration be met to open the hot leg loop stop valve, and that the boron concentration and the temperature be met to open the cold leg loop stop valve. The hot leg loop stop valve has no opening interlock on temperature limits, only that the cold leg loop stop valve be closed. With the cold leg stop valve closed, there can be no driving force (delta p) to allow mixing of the fluids in the isolated loop and the operating portion of the RCS.
. stop valves. ITS LCO 3.4.18a requires that only the boron concentration be met to open the hot leg loop stop valve, and that the boron concentration and the temperature be met to open the cold leg loop stop valve. The hot leg loop stop valve has no opening interlock on temperature limits, only that the cold leg loop stop valve be closed. With the cold leg stop valve closed, there can be no driving force (delta p) to allow mixing of the fluids in the isolated loop and the operating portion of the RCS.
                        ' Interlocks are provided on the cold leg stop valve to prevent opening the cold leg stop valve until the hot leg stop valve is open and the temperature requirement is satisfied. An administrative control is placed on the hot and cold leg stop valves to
' Interlocks are provided on the cold leg stop valve to prevent opening the cold leg stop valve until the hot leg stop valve is open and the temperature requirement is satisfied. An administrative control is placed on the hot and cold leg stop valves to prevent opening the valves until the boron concentration requirement is satisfied. Comed believes ITS LCO 3.4.18 Required l C Action B.1 correctly addresses the safety analysis concern of a positive reactivity addition due to the addition of cold water 3
* prevent opening the valves until the boron concentration requirement is satisfied. Comed believes ITS LCO 3.4.18 Required l C
from the isolated loop and is consistent with CTS. Comed continues to pursue this change.
* Action B.1 correctly addresses the safety analysis concern of a positive reactivity addition due to the addition of cold water                                               3
\\
    \                      from the isolated loop and is consistent with CTS. Comed continues to pursue this change.                                                                                   I l
l 1
1 1t
1 t
[.
[.
l LO 52
l LO 52 h -, i y e
                                      ,a h -, i y   ,- -.      < .., -----                ,  e   _y,,     7,,,, ,    , - . . - , .                ._m , ~. -                     .,    . , _
_y,,
                                                                                                                                                                                                  ,-n.
7,,,,
._m
, ~. -
,-n.
,a


_-          ~ - ..                             -==                 -==
~ -..
y                                           Rcsponsa to NRC RAI For ITS Section 3.4                                       09-oct.98 NRC RAI humber               NRC issued Date                           RAI Status
-==
    ~
-==
3.4.18 03                 3 9'98                                 Closed b/   NRC Description ofissue l'     JFD P47 l       ITS SR 3.4.18.1 and SR 3.4.18.2 l       Bases JFD P1 l       Bases for SRs 3.4.18.1 and 2, STS Bases markup page 5 3.4105 1
y Rcsponsa to NRC RAI For ITS Section 3.4 09-oct.98 NRC RAI humber NRC issued Date RAI Status
: a. 'ITS SR 3.4.18.1 and SR 3.4.18.2 have the word "once" insetted before the Frequency it terval because JFD P47 states this provides "...a particular time frame...and... is necessary to comply with the SR" and ITS SR 3.0.2. This change does not l       achieve the stated technical objective because the SR may have to be performed several times in order to actually be withm l-     the time interval " prior" to the opening of the cold leg isolation valve. The adding of"once" to an interval stated as occurring "after" any action, starts a clock which cannot be changed. The adding of"once" to an interval as occurrmg
~
        " prior" to any action does not start a clock, until the action has actually occurred. This proposed change introduces an ambiguity not present in the STS which can cause the SR Frequency to be exceeded. Comment: Adopt the STS Frequencies for ITS SRs 3.4.18.1 and 3.4.18.2.
3.4.18 03 3 9'98 Closed b/
l-     b. Deviations from the STS Bases related to JFD P47 are characterized as editorial under Bases JFD PI, w hen in fact. they a a technical changes. Thus a technicaljustification is required. Comment: Withdraw the Bases deviations and adopt the STS which is clear and accurate as written.
NRC Description ofissue l'
JFD P47 l
ITS SR 3.4.18.1 and SR 3.4.18.2 l
Bases JFD P1 l
Bases for SRs 3.4.18.1 and 2, STS Bases markup page 5 3.4105 1
: a. 'ITS SR 3.4.18.1 and SR 3.4.18.2 have the word "once" insetted before the Frequency it terval because JFD P47 states this provides "...a particular time frame...and... is necessary to comply with the SR" and ITS SR 3.0.2. This change does not l
achieve the stated technical objective because the SR may have to be performed several times in order to actually be withm l-the time interval " prior" to the opening of the cold leg isolation valve. The adding of"once" to an interval stated as occurring "after" any action, starts a clock which cannot be changed. The adding of"once" to an interval as occurrmg
" prior" to any action does not start a clock, until the action has actually occurred. This proposed change introduces an ambiguity not present in the STS which can cause the SR Frequency to be exceeded. Comment: Adopt the STS Frequencies for ITS SRs 3.4.18.1 and 3.4.18.2.
l-
: b. Deviations from the STS Bases related to JFD P47 are characterized as editorial under Bases JFD PI, w hen in fact. they a a technical changes. Thus a technicaljustification is required. Comment: Withdraw the Bases deviations and adopt the STS which is clear and accurate as written.
Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.
Original Response: Comed will revise the Frequency consistent with the STS, and will withdraw the changes to the Bases for STS SRs 3.4.18.1 and 3.4.18.2. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal
Original Response: Comed will revise the Frequency consistent with the STS, and will withdraw the changes to the Bases for STS SRs 3.4.18.1 and 3.4.18.2. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal
()
/~'N revision upon NRC's concu:rence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-()
  /~'N revision upon NRC's concu:rence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09, 3.4. I4-09, and 3.4.16-05.)
09, 3.4. I4-09, and 3.4.16-05.)
NRC RAI Number               NRC lssued Date                           RAI Status 3.4.I8-04                   3/9/98                                 Closed NRC Description ofissue Bases JFD P3 l       Bases Background discussion of ITS 3.4.18. STS markup page B 3.4-103 The Bases Background text identified as paragraphs a. b and c has not been adopted. This omission is stated as a plant specific editorial enhancement; whereas, the omitted text is applicable to all Westinghouse plants with RCS loop isolation valves. The submittal contains no technicaljustification for this change. Comment: Adopt the omitted STS text.
NRC RAI Number NRC lssued Date RAI Status 3.4.I8-04 3/9/98 Closed NRC Description ofissue Bases JFD P3 l
Bases Background discussion of ITS 3.4.18. STS markup page B 3.4-103 The Bases Background text identified as paragraphs a. b and c has not been adopted. This omission is stated as a plant specific editorial enhancement; whereas, the omitted text is applicable to all Westinghouse plants with RCS loop isolation valves. The submittal contains no technicaljustification for this change. Comment: Adopt the omitted STS text.
Se e similar comment 3.4.17-01.
Se e similar comment 3.4.17-01.
Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.
Original Response: The paragraphs omitted from the Background Section of the Bases for ITS LCO 3.4.18 for opening the l       RCS loop isolation valves will be retained with appropriate changes made to reflect corresponding changes made to ITS LCO 3.4.18. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.17-01.)
Original Response: The paragraphs omitted from the Background Section of the Bases for ITS LCO 3.4.18 for opening the l
l f~'N L
RCS loop isolation valves will be retained with appropriate changes made to reflect corresponding changes made to ITS LCO 3.4.18. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.17-01.)
l                                                                         53 I
l f~'N L
l 53 I


_  __          _                    =. = ,                   - - - . - .
=. =,
Response to NRC RAI For ITS Section 3.4                                 09-oct-98 NRC RAI Number               NRC issued Date                             RAI Status
Response to NRC RAI For ITS Section 3.4 09-oct-98 NRC RAI Number NRC issued Date RAI Status 3.4 01 3 9'98 Open - NRC Action Required k
      ,,_              3.4 01                         3 9'98                       Open - NRC Action Required k       NRC Description of issue See table below Proposed changes based on STS generic change proposals that are still pending or that have been rejected. as indicated in the table, should be withdrawn. For each applicable line item, either adopt the STS or maintain the CTS requirementsf See separate correspondence regarding line items for beyond scope changes (reasons 4 and 5) that should have been addressed separately by the licensing project manager and NRR technical staff as appropriate. Line items considered closed are indicated by shading.
NRC Description of issue See table below Proposed changes based on STS generic change proposals that are still pending or that have been rejected. as indicated in the table, should be withdrawn. For each applicable line item, either adopt the STS or maintain the CTS requirementsf See separate correspondence regarding line items for beyond scope changes (reasons 4 and 5) that should have been addressed separately by the licensing project manager and NRR technical staff as appropriate. Line items considered closed are indicated by shading.
* Reasons for exempting change from review:
* Reasons for exempting change from review:
1, Cover letter 1213-96, Attachment #3 Existing and Future Licensing Amendments to be incorporated into ITS.
1, Cover letter 1213-96, Attachment #3 Existing and Future Licensing Amendments to be incorporated into ITS.
Line 1,065: Line 1,265:
: 3. Comed letter 2-24-97, Attachment #I, Generic Changes versus CTS DOCS 4 Cover letter 12-13-96, Attachment #5 Beyond Scope Change (changes that are different than both CTS and ITS).
: 3. Comed letter 2-24-97, Attachment #I, Generic Changes versus CTS DOCS 4 Cover letter 12-13-96, Attachment #5 Beyond Scope Change (changes that are different than both CTS and ITS).
: 5. Cover letter 12-13 96 Attachment #6 Beyond Scope Bracketed Changes 6 Comed letter 2-24 97, Attachment #2, Plant Specific Change Justifications Which are Now in the Generic STS Change Process
: 5. Cover letter 12-13 96 Attachment #6 Beyond Scope Bracketed Changes 6 Comed letter 2-24 97, Attachment #2, Plant Specific Change Justifications Which are Now in the Generic STS Change Process
: 7. Other Reason as identified in comments to this table and/or with the prior approval of the NRC Technical Monitor as referenced, s                Byron /Braidwood Units I and 2 "Beyond Contractor Review Scope (BCRS)" Table Section 3.4. Reactor Coolant System TableLine No.
: 7. Other Reason as identified in comments to this table and/or with the prior approval of the NRC Technical Monitor as referenced, Byron /Braidwood Units I and 2 s
(
"Beyond Contractor Review Scope (BCRS)" Table Section 3.4. Reactor Coolant System TableLine No.
,(
ITS Reference DOC JFD ' Reasons for Exemption of Review.
ITS Reference DOC JFD ' Reasons for Exemption of Review.
Comment (if required) i 234567 1 5.5.9
Comment (if required) i 234567 1 5.5.9
{           5.6.9         X -     - - - - Comed Amendment proposal dated 8-19 Note, ITS
{
          ' Section 5.0, DOC A24 adds the SG 3.0 volt criteria to CTS 4.4.5 for the SG Tube Surveillance Program.
5.6.9 X -
2 3.4.16 - - - X -                 - - - TSTF-3 RI, Not lncorporated 3 3.4.2 L36 Cl BC1               :X^X - _ - .JTSTF-26 approved 9/16/96 4 3.4.2 M9 C2 BC2 - X: X - - - - TSTF-27 Rl; superceded by Rev.2 which is pending 5 3.4.16 - C3 BC3 - X - - - - - TSTF 28 approved 9/16/96 6 Bases for 3.4.13 - BC4 - X - -                   - - TSTF-54, Comed states replaces " identified" with " unidentified" Should adopt Revision I which was approved 4/10/97 7 3.4.15 ' - - - X - -                -
- - - - Comed Amendment proposal dated 8-19 Note, ITS
' Section 5.0, DOC A24 adds the SG 3.0 volt criteria to CTS 4.4.5 for the SG Tube Surveillance Program.
2 3.4.16 - - - X -
- - - TSTF-3 RI, Not lncorporated 3 3.4.2 L36 Cl BC1
:X^X - _ -.JTSTF-26 approved 9/16/96 4 3.4.2 M9 C2 BC2 - X: X - - - - TSTF-27 Rl; superceded by Rev.2 which is pending 5 3.4.16 - C3 BC3 - X - - - - - TSTF 28 approved 9/16/96 6 Bases for 3.4.13 - BC4 - X - -
- - TSTF-54, Comed states replaces " identified" with " unidentified" Should adopt Revision I which was approved 4/10/97 7 3.4.15 ' - - - X - -
TSTF-60. Not incorporated - Comed states contradicts Condition D for entering LCO 3.0.3. Approv d 9/17/96. Comed should adopt.
TSTF-60. Not incorporated - Comed states contradicts Condition D for entering LCO 3.0.3. Approv d 9/17/96. Comed should adopt.
83.4 O
83.4 O
    .Q
[3.4.13]
[3.4.13]
9 3.4.5 Cll     -X. - - - -           TSTF-61, approved 9/17/96; Comed should adopt.
Cll
3.4.9 L3
-X. - - - -
                                                                                    $4 1
TSTF-61, approved 9/17/96; Comed should adopt.
.Q 9 3.4.5 3.4.9 L3
$4 1


                              . . = - . ~ = = = = = - - -                   v =       z- w - .=.
.. = -. ~ = = = = = - - -
R:sponse to NRC RAI Fcr ITS S:ction 3A                               09-Oct                           _
v =
                                          . ,: .--- =.     --u====.=.=.
z-w -.=
:                        ;:        .- ~
R:sponse to NRC RAI Fcr ITS S:ction 3A 09-Oct.,:.--- =.
--u====.=.=.
.- ~
i L23-
i L23-
    -b             L26' CIO P37
-b L26' CIO P37
(. -
(.
                - [P36] BC101 - XIX:-: - X TSTF-87 R1, Comed specifies RA is " Initiate action to place" rather than " Place..'' on Immediate frequency" [Per C. Harbuck P36 is BCRS from typo in JFD C10 ) revision 2 approved 10'3/97: Comed should adopt Revision 2
- [P36] BC101 - XIX:-: - X TSTF-87 R1, Comed specifies RA is " Initiate action to place" rather than " Place..'' on Immediate frequency" [Per C. Harbuck P36 is BCRS from typo in JFD C10 ) revision 2 approved 10'3/97: Comed should adopt Revision 2
: 10. 3.4.9 A13: C5 BC5         ~XL X '- E T -:TSTF-93, 11 3.4.9 . . . X" . _': . .                 TSTF 94, Not incorporated Comed provides brackets for words that were           I incorporated into CTS. Comed should adopt Rev. I which was approved 9'30 97.                                                .
: 10. 3.4.9 A13: C5 BC5
~XL X '- E T -:TSTF-93, 11 3.4.9... X". _':..
TSTF 94, Not incorporated Comed provides brackets for words that were I
incorporated into CTS. Comed should adopt Rev. I which was approved 9'30 97.
12 'T 3.4.1 LAIS C6 BC6' 'X: X-~-T-
12 'T 3.4.1 LAIS C6 BC6' 'X: X-~-T-
                                            -3 ~ TSTF-105 was rejected.
-3 ~ TSTF-105 was rejected.
13: 3.4.191-7 P30 BP35' -:XT !-: :-:X TSTF-108, Not incorporated -Comed states LCO 3.4.19 is for NTOL                       i plants. Per C Harbuck this is not BCRS.                                                                                       ,
13: 3.4.191-7 P30 BP35' -:XT !-: :-:X TSTF-108, Not incorporated -Comed states LCO 3.4.19 is for NTOL i
14' 3.4.ll:,L8 Cl2 BCl33-:X:X:-1 TSTF-ll3 R1, still pending 15 '. 3.4.7 ~ -:BC1 i BP3 ~ - X ~ -~ -T '. '-:TSTF-ll4, approved 12/31/96 16 : 3.~4.13                                                                                                                 i 3.4.15 'L21 L22 L24~~C8' P23 BC8 BP23 -: X .X; V ' ~ TSTF-il6. superceded by Rev i which is pending 17 . Bases 3.4.11' -'.'BCl41-: X: . ~. . -:-:TSTF-151 (WOG-61), Owners Groups asked to modify as suggested by TSB - waiting for response 18 3.4.5
plants. Per C Harbuck this is not BCRS.
14' 3.4.ll:,L8 Cl2 BCl33-:X:X:-1 TSTF-ll3 R1, still pending 15 '. 3.4.7 ~ -:BC1 i BP3 ~ - X ~ -~ -T '. '-:TSTF-ll4, approved 12/31/96 16 : 3.~4.13 i
3.4.15 'L21 L22 L24~~C8' P23 BC8 BP23 -: X.X; V ' ~ TSTF-il6. superceded by Rev i which is pending 17. Bases 3.4.11' -'.'BCl41-: X:. ~.. -:-:TSTF-151 (WOG-61), Owners Groups asked to modify as suggested by TSB - waiting for response 18 3.4.5
[3.4.6]
[3.4.6]
[3.4' .7) '
[3.4'.7) '
    ;      ;    -[3.4.8) A31.Cl4 BC18' -: X. ~X - '.T -J ' TSTF-153 (WOG-63) approved 4/11/97                                                   ,
-[3.4.8) A31.Cl4 BC18' -: X. ~X - '.T -J ' TSTF-153 (WOG-63) approved 4/11/97 V
V            19 3.4.1 A22 C7 BC7' .-:.X X - -J-' - WOG-21                                                                                 )
19 3.4.1 A22 C7 BC7'.-:.X X - -J-' - WOG-21
)
20' 3.4
20' 3.4
                .- [3.4.12] Ll6 C9
.- [3.4.12] Ll6 C9
                . Pil P21 BC9 BPil BP19 BP21
. Pil P21 BC9 BPil BP19 BP21
[Pl7][P19] - X X ' - ' X WOG-51 R1, C9 states generic change is modified by plant specific changes Pf land P21 [P19 is tied to Pil] and [Pl7 is tied to C9]
[Pl7][P19] - X X ' - ' X WOG-51 R1, C9 states generic change is modified by plant specific changes Pf land P21 [P19 is tied to Pil] and [Pl7 is tied to C9]
21     3.4.                                                                                                                   '
21 3.4.
                . [3.4.11] L27 Cl3 BCl3                 .X .X -: - - - WOG-60 L 22 3.4
. [3.4.11] L27 Cl3 BCl3
                , [3.4.9) - BC l7         . X ' . .' - - - WOG-68
.X.X -: - - - WOG-60 L 22 3.4
                . 23 3.4
, [3.4.9) - BC l7
. X '..' - - - WOG-68
. 23 3.4
[3.4.2]
[3.4.2]
[3.4.16] . C15 - X
[3.4.16]. C15 - X
                                                  - - - - WOG 81 24 Bases for Section 3.4
- - - - WOG 81 24 Bases for Section 3.4
                . [All speci-fications]' - ' BC16' :' .X -' - - - - Editorial-1 25 SR 3.4.1.4 Note ~ M 15 P3 - - ~ ~ X -                -
. [All speci-fications]' - ' BC16' :'.X -' - - - - Editorial-1 25 SR 3.4.1.4 Note ~ M 15 P3 - - ~ ~ X -
26 3.4.3 L28 P44 ---X---
26 3.4.3 L28 P44 ---X---
27 3.4.18 LIB
27 3.4.18 LIB
[A28] P31
[A28] P31
[BP36] - - -' X '             ~X" items in bracket are added because both are tied to the P31 change.
[BP36] - - -' X '
~X" items in bracket are added because both are tied to the P31 change.
28 SR 3.4.18.2 Ll4 P4 - - - X - ~ - -
28 SR 3.4.18.2 Ll4 P4 - - - X - ~ - -
                . 291 SRs 3.4.5.2 3.4.6.2
. 291 SRs 3.4.5.2 3.4.6.2
    <'%/  h
< h
* 3.4.7.2, --'.L5
* 3.4.7.2 L5 [B3][Pl] -
                ~ 30 3.4 X - X[B3][Pl]        - are adde'd because both are tied to the L5 change.
, --'. X - X ' Items in bracket are adde'd because both are tied to the L5 change.
                                          ' Items in bracket
'%/
[3.4.12] . . P38       . . - - ' X ~         WOG-087                                                                           i 55 l
~ 30 3.4
l L                                                                                                                     --                    ,
[3.4.12].. P38
.. - - ' X ~
WOG-087 i
55 l
l L


L-                               __ .. _                          - _ . _
L-
                                                                                      .. _ _ z_ m ._ _
.. _ _ z_ m._ _
Rsspense to NRC RAI For ITS Sectisn 3.4                           09-oct-9s       ;
Rsspense to NRC RAI For ITS Sectisn 3.4 09-oct-9s m.-__u 3 1 3.4
                                                            .                ; m.-__u           .
3 1 3.4
([].
([].
' \_/
[3.4. l].^
[3.4. l] .^
P3. - -
- - X ' ' WOG-099 i
32 3.4'
32 3.4'
[3,4.12] -;P21 P3 . - -
' \\_/
                                            - - X ' ' WOG-099
[3,4.12] -;P21
                                                  .-;X -:WOG-100 i'
.-;X -:WOG-100 l
l              33 '3.4 l
33 '3.4 l
              - [3.4.11): ~.PI4: ~..: :-:X: .: WOG-10' 34_ 3.4.                                                                                                                     l l
- [3.4.11): ~.PI4: ~..: :-:X:.: WOG-10' 34_ 3.4.
[3.4.16]~' ~ Pl P45 2-: ~.-:-:-!X: .: Editorial-12
[3.4.16]~' ~ Pl P45 2-: ~.-:-:-!X:.: Editorial-12
;            ' Comed Response to issue Revised Response: Two issues associated with the table remain open.
' Comed Response to issue Revised Response: Two issues associated with the table remain open.
: 1. Regarding items #25 and #31 (RAI BYS 5.0): Per discussions with the NRC Reviewer on 9'3'98. Comed has written a letter to the NRC justifying the 7 days in the Note for ITS SR 3.4.1.4. Concurrently, NRC Reviewer Tony Attard reviewing same changes in TSTF 282. Resolution still pending.
: 1. Regarding items #25 and #31 (RAI BYS 5.0): Per discussions with the NRC Reviewer on 9'3'98. Comed has written a letter to the NRC justifying the 7 days in the Note for ITS SR 3.4.1.4. Concurrently, NRC Reviewer Tony Attard reviewing same changes in TSTF 282. Resolution still pending.
: 2. Regarding item #28 (RAI BYS 8.0): Per discussions with the NRC Reviewer on 9/3/98, Comed has written a letter to the NRC justifying the 4 hour sampling frequency for ITS SR 3.4.18.2. Resolution still pending.
: 2. Regarding item #28 (RAI BYS 8.0): Per discussions with the NRC Reviewer on 9/3/98, Comed has written a letter to the NRC justifying the 4 hour sampling frequency for ITS SR 3.4.18.2. Resolution still pending.
Original Response: See table for Comed Response to RAI 3.4_01._ _ ._ . . _ _ _ _. .
Original Response: See table for Comed Response to RAI 3.4_01._ _._.. _ _ _ _..
Bottom of Report
Bottom of Report
        )
)
l l
l Lv l
l Lv l
56 1
56
I
                                                -                                        .                            .    .                1


ATTACHMENT 2
ATTACHMENT 2
,Q ITS SECTION 3.4 ITS AFFECTED PAGE LIST                                                           I 1
,Q ITS SECTION 3.4 ITS AFFECTED PAGE LIST
1
.l l
                                                                                                    .l 1
l l
l l
O O
O O


    .,_    . _ . . . ,    .  - _ _    . . _ .              -      . . ~ _._ _ . _._ _... .. . ._. . _ . - _ . . . . _ . _ _
.. ~ _._ _. _._ _......._..
l
l ATTACHMENT 2
                                            ;            ATTACHMENT 2
/ 'T ITS SECTION 3.4 hs/
    / 'T                                               ITS SECTION 3.4 hs/                                           ITS AFFECTED PAGE LIST SECTION / TAB         ITS AFFECTED     'RAI PAGE BYRON ITS /           3.4.1-1           3.4-01 #19 p                     ~BRAIDWOOD ITS 3.4.1-2           -3.4'1-02 3.4.2-1 3.4-01 #23 3.4.5-1           3.4.5-02 3.4.5-4           3.4.5-03 l
ITS AFFECTED PAGE LIST SECTION / TAB ITS AFFECTED
3.4.6-1           3.4.6-02 3.4.6-2           3.4.5-03 3.4.6-3 3.4.7-1           3.4.7-02 3.4.7-03 3.4.7-06 3.4.7-09 3.4.7-2           3.4.7-01 3.4.7-02 3.4.7-3             3.4.7-08 3,4.8-1             3.4.8-02 l                                             3.4.9-1             3.4.9-02 n
'RAI PAGE BYRON ITS /
3.4.1-1 3.4-01 #19 p
~BRAIDWOOD ITS 3.4.1-2
-3.4'1-02 3.4.2-1 3.4-01 #23 3.4.5-1 3.4.5-02 3.4.5-4 3.4.5-03 3.4.6-1 3.4.6-02 3.4.6-2 3.4.5-03 3.4.6-3 3.4.7-1 3.4.7-02 3.4.7-03 3.4.7-06 3.4.7-09 3.4.7-2 3.4.7-01 3.4.7-02 3.4.7-3 3.4.7-08 3,4.8-1 3.4.8-02 l
3.4.9-1 3.4.9-02 n
I.
I.
1 l
1 l


        . . . . ~ . _ . _ ._      . _ . . _        . _        . _      _ . . . _ . . _ _ . _ _ _ . _ . _        . _ _ _ _ . . _ _ . . . _ . _ .
.... ~. _. _
t                                                                                                                                                                 )
t
l l
)
ATTACHMENT 2
ATTACHMENT 2 f ' \\s-]-
,    /~                                                               ITS SECTION 3.4 f ' \s-]-                                                      .ITS AFFECTED PAGE LIST'                                                                           l I
/~
SECTION / TAB               ITS AFFECTED                 RAI PAGE 3.4.10-1                     3.4.10-05 l
ITS SECTION 3.4
3.4 10-2'                   3.4.10-04 3.4.11-1                     3.4.11-04 3.4.11-2                     3.4.11-01 r                                                                                     .3.4.11-04 3.4.11-3                     3.4.11                                                                                         3.4.11-04.
.ITS AFFECTED PAGE LIST' SECTION / TAB ITS AFFECTED RAI PAGE 3.4.10-1 3.4.10-05 l
                            .                                                          3.4-01 #21
3.4 10-2' 3.4.10-04 3.4.11-1 3.4.11-04 3.4.11-2 3.4.11-01 r
(''~l/                                               3.4.11-4                     3.4.11-04 3.4.12-1                     3.4.12-01 3.4.12-09 3.4-01 #23 3.4.12-2                     3.4.12-01 3.4.12-08 L
.3.4.11-04 3.4.11-3 3.4.11 3.4.11-04.
3.4.12-4                     3.4.12-01 3.4~.12-5 3.4.13-2                     3.4-01#16
3.4-01 #21
                                                        - 3. 4'.14-1                   3.4.14-01
,'~l
              ,                                                                        3.4.14-02 LO l ':
(' /
2 o
3.4.11-4 3.4.11-04 3.4.12-1 3.4.12-01 3.4.12-09 3.4-01 #23 3.4.12-2 3.4.12-01 3.4.12-08 L
3.4.12-4 3.4.12-01 3.4~.12-5 3.4.13-2 3.4-01#16
- 3. 4'.14-1 3.4.14-01 3.4.14-02 LO 2
l ':
o


ATTACHMENT 2 ITS'SECTION 3.4 l                                       ITS AFFECTED PAGE LIST l
ATTACHMENT 2 ITS'SECTION 3.4 l
SECTION /. TAB       ITS AFFECTED               RAI PAGE 3.4.14-2                 .3.4.14-03 3.4.14-3                   3.4.14-07 3.4.14-08 3.4.14-09 3.4.14-4                   3.4.14-09 3.4.15-1                   3 4-01 #16 3.4.15                 3.4-01 #16
ITS AFFECTED PAGE LIST l
    ,-s                           3.4.16-1                   3.4-01 #23
SECTION /. TAB ITS AFFECTED RAI PAGE 3.4.14-2
(_)s .
.3.4.14-03 3.4.14-3 3.4.14-07 3.4.14-08 3.4.14-09 3.4.14-4 3.4.14-09 3.4.15-1 3 4-01 #16 3.4.15 3.4-01 #16
3.4.16-3                   3.4.16-04 3.4.16-05 3.4.18-1                   3.4.18-01 3.4.18-2                   3.4.18-03 B 3.4.1-2                 3.4.1-05 3.4.1-06 B 3.4.1-3                 3.4-01 #19
,-s 3.4.16-1 3.4-01 #23
:                                  B 3.4.1-4                 3.4.1-07 B 3.4.1-6                 3.4.1-02 3.4-01 #12 i
(_)s.
' ()                                               3 i
3.4.16-3 3.4.16-04 3.4.16-05 3.4.18-1 3.4.18-01 3.4.18-2 3.4.18-03 B 3.4.1-2 3.4.1-05 3.4.1-06 B 3.4.1-3 3.4-01 #19 B 3.4.1-4 3.4.1-07 B 3.4.1-6 3.4.1-02 3.4-01 #12 i' ()
3 i


                                                                  ' ATTACHMENT 2                                                   '
' ATTACHMENT 2
    #~l k-/                                                      ITS SECTION 3.4 ITS AFFECTED PAGE LIST
#~l ITS SECTION 3.4 k-/
                          -SECTION / TAB             ITS AFFECTED               RAI PAGE
ITS AFFECTED PAGE LIST
                                                  - B 3.4.2-3                 3.4.2-02 B 3.4.3-8                 3.4.3-02 B 3.4.4-3                 3.4.4-01 B 3.4 5-3'               ~3.4.5-02 i
-SECTION / TAB ITS AFFECTED RAI PAGE
B 3.4.5-4                 3.4.5-04                                             ,
- B 3.4.2-3 3.4.2-02 B 3.4.3-8 3.4.3-02 B 3.4.4-3 3.4.4-01 B 3.4 5-3'
l B 3.4.5-7                 3.4.5-03                                         -i B 3.4.5-8                 '3.4.5-05 L( )
~3.4.5-02 i
B 3.4.6-2                 3.4.6-02                               .
B 3.4.5-4 3.4.5-04 l
                                                                                                                                    )
B 3.4.5-7 3.4.5-03
B 3.4.6-5~                 3.4.5-03                                             l B.3.4.7-2                 3.4.7-02 3.4.7-10 B 3.4.7-3                 3.4.7-03 B 3.4.7-4                 3.4.7-01 B 3.4;7-5               '3.4.7-01                                             l 3.4.7-03 3.4.7-08 L                                                                                                                                   ,
-i L( )
B 3.4.5-8
'3.4.5-05 B 3.4.6-2 3.4.6-02
)
B 3.4.6-5~
3.4.5-03 B.3.4.7-2 3.4.7-02 3.4.7-10 B 3.4.7-3 3.4.7-03 B 3.4.7-4 3.4.7-01 B 3.4;7-5
'3.4.7-01 3.4.7-03 3.4.7-08 L
I' l:
I' l:
,                                                                          4 l
4 l
y                 y         . + .     y   my.,                                   ~           ,  ..
y y
. +.
y my.,
~


    , . _    - _ . .    . . _ . _ . _ . - . _ . _ _ _ . .      _    . . _ _ _ _ _ - - . _ _ _ . = _ . - - . . _ ._._ . _ .., _ .__ _._. _
.. _ _ _ _ _ - -. _ _ _. = _. - -.. _._._. _.., _.__ _._. _
                                                  -c                 ; ATTACHMENT.E' l'(
-c
l-ITS SECTION 3.4 ITS AFFECTED PAGE LIST                                                               >
; ATTACHMENT.E' l'(
                        '.SECTION / TAB-             ITS AFFECTED                             RAI                                                     -
ITS SECTION 3.4 l-ITS AFFECTED PAGE LIST
PAGE-B 3.4.7-6 i:
'.SECTION / TAB-ITS AFFECTED RAI PAGE-B 3.4.7-6 i:
B 3.4.8-2,                               3.4.8-02                                               ;
B 3.4.8-2, 3.4.8-02 3.4.8-07 k
3.4.8-07                                                 !
3.4.8-09 l
k                                                                                              3.4.8-09 l
[
[
B 3.a.9-2.                               3.4.9-01 B 3.4.9-3                               3.4.9-02 B 3.4.9-5                               3.'4.9-01                                               )
B 3.a.9-2.
3.4.9-01 B 3.4.9-3 3.4.9-02 B 3.4.9-5 3.'4.9-01
)
3.4.9-03 I
3.4.9-03 I
                                                                                                  ~
l [..
B 3.4.9-6                               3.4.1-10 l [.s).    .
B 3.4.9-6 3.4.1-10
B-3.4.11-1                               3.4.11                                         .
~
i                                                     B 3.4.11-2                               3.4.11-04 B 3-4.11 ^
s).
                                                              .                              3.4.11-04                                                 .
B-3.4.11-1 3.4.11.
g l                                                     B 3.4.11-4                             3.4.11-04                       .                      l I
i B 3.4.11-2 3.4.11-04 B 3-4.11 ^
B 3.4.11-5                             3.4.11-04 3.4-1 #21 l                                                     B 3.4.11-6                             3.4.11-02 3.4.11-04 f
3.4.11-04 g
I-i+                                                                                                                                                     5 t
l B 3.4.11-4 3.4.11-04 l
t
I B 3.4.11-5 3.4.11-04 3.4-1 #21 l
B 3.4.11-6 3.4.11-02 3.4.11-04 f
I-i+
5 t
t e


I
I ATTACHNENT2 (l
                            .-            ATTACHNENT2 ITS SECTION 3.4 (l
ITS SECTION 3.4
      's                           ITS AFFECTED PAGE LIST                                     I I
's ITS AFFECTED PAGE LIST SECTION / TAB-ITS AFFECTED RAI PAGE-B 3.4.11-7 3.4.11-01' 3.4.11-04 B 3_.4.11-8 3.4.11-04 3.4'1 #21 B 3.4.11-9 3.4.11-04 B 3.4.12-4 B 3.4.12-9 3.4.12-09 3.4.12-01 B 3.4.12-11 3.4.12-01 3.4.12-08 B 3.4.12-15 3.4.12-01 3.4.12-07 i
l SECTION / TAB-   ITS AFFECTED       RAI PAGE-B 3.4.11-7         3.4.11-01' 3.4.11-04 B 3_.4.11-8         3.4.11-04                                   1 3.4'1 #21 B 3.4.11-9         3.4.11-04 B 3.4.12-4 B 3.4.12-9         3.4.12-09 3.4.12-01 B 3.4.12-11         3.4.12-01 3.4.12-08 B 3.4.12-15         3.4.12-01                           '"
B 3.4.12-16 3.4.12-01 3.4.12-07 B 3.4.12-17 3.
3.4.12-07 i
_?-07 B 3.4.13-2 B 3.4.'13-3 i
B 3.4.12-16         3.4.12-01 3.4.12-07 B 3.4.12-17         3.       _?-07 l
B 3.4.13-6 3'.4.13-03 1
B 3.4.13-2 B 3.4.'13-3 i
B 3.4.13-6           3'.4.13-03                                 1 6
(}~
(}~
6


    . .t
..t ATTACHMENT 2
                          .            ATTACHMENT 2 ITS SECTION 3.4
?( J)
?(
ITS SECTION 3.4
:A J)                            ITS AFFECTED PAGE LIST SECTION / TAB   ITS AFFECTED       RAI-PAGE B 3.4.13-7       ~3.4.13                             B 3.4.13-8 B 3.4.14-4       .3.4.14-12 B 3.4.14-5         3.4.14-03
:A ITS AFFECTED PAGE LIST SECTION / TAB ITS AFFECTED RAI-PAGE B 3.4.13-7
                                                                                              )
~3.4.13 B 3.4.13-8 B 3.4.14-4
B 3.4.14-6         3.4.14-08 B 3.4.14-7       3.4.14-07                                       I
.3.4.14-12 B 3.4.14-5 3.4.14-03
        .                                                                                    \
)
(                           B 3.4.14-8       3.4.14 08 8 3.4.15-3 B 3.4.15-4       3.4-01 #16 l
B 3.4.14-6 3.4.14-08 B 3.4.14-7 3.4.14-07
l l
\\
B 3.4.15-5       3.4-01 #1e                                       i 3.4.15-03 B 3.4.16-1       3.4.16-07 B 3.4.16-3       3.4.16-08 8 3.4.16-6       3.4.16-05 B 3.4.17-1       3.4.17-01
(
B 3.4.14-8 3.4.14 08 8 3.4.15-3 B 3.4.15-4 3.4-01 #16 l
l B 3.4.15-5 3.4-01 #1e i
3.4.15-03 B 3.4.16-1 3.4.16-07 B 3.4.16-3 3.4.16-08 8 3.4.16-6 3.4.16-05 B 3.4.17-1 3.4.17-01
:(}
:(}
v 7
7 v


AHACHMENT 2'
AHACHMENT 2'
    ,m d' '
,md' '
i                                                                        ITS SECTION 3.4 ITS AFFECTED PAGE LIST l                             SECTION-/ TAB                 ITS AFFECTED               RAI PAGE l
ITS SECTION 3.4 i
l B 3.4.17-2                   3.4.17-01
ITS AFFECTED PAGE LIST l
                                                          .B 3.4.17-3                   3.4.17-01 3.4.17-02 i
SECTION-/ TAB ITS AFFECTED RAI PAGE l
B 3.4.18-1                   3.4-18-04 B 3.4.18-2                 .3.4.18-01 i
l B 3.4.17-2 3.4.17-01
l                                                           B 3.4.18-3                   3.4.18-01 3.4.18-03 H
.B 3.4.17-3 3.4.17-01 3.4.17-02 i
  .)
B 3.4.18-1 3.4-18-04 B 3.4.18-2
'(   A 8
.3.4.18-01 i
l' l'
l B 3.4.18-3 3.4.18-01 3.4.18-03 H
l
.)
'(
8 A
l'l' l


                                      ~
~
ATTACHMENT 3 ITS SECTION 3.4 CTS AMENDED PAGE LIST 9
ATTACHMENT 3 ITS SECTION 3.4 CTS AMENDED PAGE LIST 9
O d
O d
l l
i O
iO


LATTACHMENT 3.
LATTACHMENT 3.
A
(
(                                                    ITS SECTION 3.'4-
ITS SECTION 3.'4-A
                                                        -CTS AMENDED PAGE LIST.
-CTS AMENDED PAGE LIST.
SECTION/ TAB         AFFECTED CTS PAGE/ AMENDMENT.#
SECTION/ TAB AFFECTED CTS PAGE/ AMENDMENT.#
3.4' BYRON CTS       3/4 4-2 #96 3/4 4-4'#96                                                                                             j 3/4 4-5 #96                                                                                             s 3/4 4-14.#101                                                                                           1 3/4 4-15 #101                                                                                           '
3.4' BYRON CTS 3/4 4-2 #96 3/4 4-4'#96 j
t 3/4 4-16 #101 3/4 4-17 #101-3/4 4L17b #101 3/4 4-17d #101 3/4.4-27 #101 3/4 4-28 #101                                                                                           i 3/4.4-29 #101                                                                                           l 3/4 4-29a #101-
3/4 4-5 #96 s
                                                  ,3/4.4-311#101 3/4 4-32 #98
3/4 4-14.#101 1
                                                  -3/4 4-33 #98                                                                                           )
3/4 4-15 #101 t
          .                                      3/4 4-34 #98                                                                                             1
3/4 4-16 #101 3/4 4-17 #101-3/4 4L17b #101 3/4 4-17d #101 3/4.4-27 #101 3/4 4-28 #101 3/4.4-29 #101 3/4 4-29a #101-
(^' \,                                   3/4 4-35 #98
,3/4.4-311#101 3/4 4-32 #98
      - k/                                       .3/4 4-36 #98 3/4 4-37 #98 ll I
-3/4 4-33 #98
q L,                 <
)
3/4 4-34 #98
(^' \\,
3/4 4-35 #98
- k/
.3/4 4-36 #98 3/4 4-37 #98 ll I
q L,
i
i
      .'          (.
(.
4    L):                                                               1 I .
1 L):
'a
4 I
    .i
.i'a


l :-
l :-
    .                                                        .                  1 ATTACHMENT 3-i:-93         ::                                                              ITS SECTION 3.4 Li(''
1 ATTACHMENT 3-i:-93 Li(''
ln            :                                                        CTS AMENDED PAGE-LIST L                               '.SECTION/ TAB -           .AFFECTED CTS PAGE/ AMENDMENT #
ITS SECTION 3.4 CTS AMENDED PAGE-LIST ln L
3.4'BRWD CTS.               3/4 4-2 #87                                                                   '
'.SECTION/ TAB -
3/4~4-4 #87.
.AFFECTED CTS PAGE/ AMENDMENT #
                                                            .3/4-4-5 #87 3/4 4-14 #92
3.4'BRWD CTS.
:                                                            3/4 4-15 #92 L'
3/4 4-2 #87 3/4~4-4 #87.
.3/4-4-5 #87 3/4 4-14 #92 3/4 4-15 #92 L'
3/4 4-16'#92-
3/4 4-16'#92-
                                                            '3/4 4-17 #92-L                                                           -3/4 4-17a #92
'3/4 4-17 #92-L
                                                            ^3/4 4-17b #92                               '                                    ^
-3/4 4-17a #92
3/4 4-17c #92-h                                                             3/4 4-17d #92                           -/
^3/4 4-17b #92
l                                                             3/4 4-27 #92-l                                                           '3/4 4-28 #92 3/4 4-29 #92
^
;                                                            3/4 4-29a #92
3/4 4-17c #92-h 3/4 4-17d #92
: l.                                                           3/4 4-31 #92
-/
;                                                            3/4 4-32 #89 3/4 4-33 #89
l 3/4 4-27 #92-l
! : /~_l                                                     '3/4 4-34-#89
'3/4 4-28 #92 3/4 4-29 #92 3/4 4-29a #92 l.
      \s/                       4-                         3/4,4-35 #89
3/4 4-31 #92 3/4 4-32 #89 3/4 4-33 #89
                                                                      ~
! : /~_l
'3/4 4-34-#89
\\s/
4-3/4,4-35 #89
~
l 3/4 4-36 #89
l 3/4 4-36 #89
                                                            '3/4 4;37 #89 i
'3/4 4;37 #89 i
I i
i l-i l
l-i l
I' Il-b L /
I' I
l-b L /'%
2
2
.; d t'
.; d t'
                                    . .                  _            .. ; --. .J_    . - - , ~ , _       , - - - . - ~         _      ,,
.J
. - -, ~, _
, - - -. - ~


e.A A 4 4- - -- 5 m .a . m$,,e A- 2J4,. 4,muJd A- 5.- %du 4. 4me.a 4 d den .. M. ,#.a4 maama pAi.d..m, p w-,3_.2 4_ 4_4., e,.4 Iw seMp.,, Lana.g ATTACHMENT 4 ITS SECTION 3.4 SER TABLES 1
e.A A
i O
4 4-5 m
l 4
.a m$,,e A-2J4,.
1 l
4,muJd A-5.-
1 1
%du
s s
: 4. 4me.a 4 d den M.
,#.a4 maama pAi.d..m, p
w-,3_.2 4_
4_4.,
e,.4 Iw seMp.,, Lana.g ATTACHMENT 4 ITS SECTION 3.4 SER TABLES i
' O 4
1 s
s
)
)
Lo
Lo


      .p                                                                                                                                                                                                                                                                      .
.pV b,, '
V                                                                          b,, '                                                                                                                                                                                 (f Table A - Administrative Changes to CTS Discussion                                                     Description .                                                                                                                                                                       ITS                 CTS ~
(f Table A - Administrative Changes to CTS Discussion Description.
of Change                                                       of Change                                                                                                                                                                     Requirement :       Requirement ITS Section 3.4, Reactor Coolant Systems 3.4 A1               Editorial rewording, reformatting, and renumbering changes were made to conform with                                                                                                                                     3.4                 3/41,3/42,3/4.3,
ITS CTS ~
                        - conventions used in Westinghouse Standard Technical Specifications NUREG-1431(STS).                                                                                                                                                         3/44,3/4.5, 3/4.10
of Change of Change Requirement :
* 3.4 A2               Obsolete, cycle-specific limits regarding Reactor Coolant System (RCS) total flow rate, steam                                                                                                                           LCO 3.4.1.c,       LCO 3.2.3 a, generator water level, and reactor coolant Dose Equivalent 1-131 was deleted.                                                                                                                                           SR 3.4.5 2,         4.4 1.2 2,           ;
Requirement ITS Section 3.4, Reactor Coolant Systems 3.4 A1 Editorial rewording, reformatting, and renumbering changes were made to conform with 3.4 3/41,3/42,3/4.3,
SR 3.4.6.2,         4.4.1.3 2 LCO 3.4.7.b.       LCO 3 4141 b.
- conventions used in Westinghouse Standard Technical Specifications NUREG-1431(STS).
SR 3.4.7.2,         LCO 3.4 8 a, SR 3 4.16.2,       Figure 3 4-2, Figure 3.4.16-1     Table 4.4-4 Note ""
3/44,3/4.5, 3/4.10 3.4 A2 Obsolete, cycle-specific limits regarding Reactor Coolant System (RCS) total flow rate, steam LCO 3.4.1.c, LCO 3.2.3 a, generator water level, and reactor coolant Dose Equivalent 1-131 was deleted.
3.4 A3               Exception to the provisions of CTS 4.0.4 was removed for the associated RCS flow rate                                                                                                                                   SR 3.0.4           4.2.3 1 surveillances. Wording and format of the surveillance and STS SR 3.0.4 make such exceptions unnecessary.
SR 3.4.5 2, 4.4 1.2 2, SR 3.4.6.2, 4.4.1.3 2 LCO 3.4.7.b.
3.4 A4               Action to restore RCS operating loop temperature to within limit was deleted since the option to                                                                                                                         3.4.2 Action A     3.1.1.4 Actions restore out of limit conditions always applies and does not need to be stated.
LCO 3 4141 b.
3.4 A5               Footnote reference to Special Test Exception (STE) Specification 3.10.3 was deleted in _                                                                                                                                 3 4.2 Applicability 3,1,1.4 conformance with STS which reformats the presentation of these STE requirements in the ITS                                                                                                                                                   Applicability Specification to which they apply.
SR 3.4.7.2, LCO 3.4 8 a, t
(By)- Byrora specirc (Bw)- Braidwood specific Byron and Braidwood                                                                                                                                                                                                                                                               A_T BL3 4 1
SR 3 4.16.2, Figure 3 4-2, Figure 3.4.16-1 Table 4.4-4 Note ""
3.4 A3 Exception to the provisions of CTS 4.0.4 was removed for the associated RCS flow rate SR 3.0.4 4.2.3 1 surveillances. Wording and format of the surveillance and STS SR 3.0.4 make such exceptions unnecessary.
3.4 A4 Action to restore RCS operating loop temperature to within limit was deleted since the option to 3.4.2 Action A 3.1.1.4 Actions restore out of limit conditions always applies and does not need to be stated.
3.4 A5 Footnote reference to Special Test Exception (STE) Specification 3.10.3 was deleted in _
3 4.2 Applicability 3,1,1.4 i
conformance with STS which reformats the presentation of these STE requirements in the ITS Applicability Specification to which they apply.
(By)- Byrora specirc (Bw)- Braidwood specific L
Byron and Braidwood A_T BL3 4 1


_s                                                                                                                             ,,                                        (
_s
Table A - Administrative Changes to CTS Discussion                                                     Description                                                                                   ITS                 CTS of Change                                                     of Change                                                                                 Requirement         Requirement 3.4 A6                 Footnote reference to STE Specification 3.10.4 was deleted in conformance with STS which                                         3.4 4 Applicability 3.4.1.1 reformats the presentation of these STE requirements in the ITS Specification to which they                                                           Apphcability apply.
(
3.4 A7                 Footnote reference to STE Specification 3.10.4 was deleted in conformance with STS which                                         3.4.5 Applicability 3.4.1.2 reformats the presentation of these STE requirements in the ITS Specification to which they                                                           Applicabshly apply.
Table A - Administrative Changes to CTS Discussion Description ITS CTS of Change of Change Requirement Requirement 3.4 A6 Footnote reference to STE Specification 3.10.4 was deleted in conformance with STS which 3.4 4 Applicability 3.4.1.1 reformats the presentation of these STE requirements in the ITS Specification to which they Apphcability apply.
3.4 A8               Since the condition "when no reactor coolant or Residual Heat Removal (RHR) loop in                                               3.4.6 Actions       3 4.1.3 Action b operation" implies both required loops are inoperable, the applicable Actions were applied to                                     A and C each condition for clarity. The Action to suspend all operations involving a reduction in boron concentration of the RCS was applied te the condition when no required reactor coolant or RHR loop is in operation as well as when both required loops are inoperable.
3.4 A7 Footnote reference to STE Specification 3.10.4 was deleted in conformance with STS which 3.4.5 Applicability 3.4.1.2 reformats the presentation of these STE requirements in the ITS Specification to which they Applicabshly apply.
3.4 A9               The LCO was revised to include the requirerr.?qt for the pressurizer heaters to have a                                             LCO 3.4.9           LCO 3 4.3 redundant emergency power supply capability to be consistent with the surveillance requirement to demonstrate the cross-tie to the emergency safety feature (ESF) power supply.
3.4 A8 Since the condition "when no reactor coolant or Residual Heat Removal (RHR) loop in 3.4.6 Actions 3 4.1.3 Action b operation" implies both required loops are inoperable, the applicable Actions were applied to A and C each condition for clarity. The Action to suspend all operations involving a reduction in boron concentration of the RCS was applied te the condition when no required reactor coolant or RHR loop is in operation as well as when both required loops are inoperable.
3.4 A10               An explicit allowance for separate condition entry for each pressurizer power operated relief                                     3 4.11 Actions     3.4 4 Actions valve (PORV) and each block vaive was included to clarify current practice for tracking                                           Note 1 a!!owable outage times for each inoperab!2 component.
3.4 A9 The LCO was revised to include the requirerr.?qt for the pressurizer heaters to have a LCO 3.4.9 LCO 3 4.3 redundant emergency power supply capability to be consistent with the surveillance requirement to demonstrate the cross-tie to the emergency safety feature (ESF) power supply.
3.4 A11               Actions to restore pressurizer PORV(s) or block valves were deleted since the option to restore                                   LCO 3 0 2           3 4 4 Actions a b, inoperable components currently exists and does not need to be stated.                                                                                 c, and d (By)- Byron specific (Bw)- Braidwood specif.c Byron and Braidwood                                                                                                                                                                       A_ T BL3 4 2
3.4 A10 An explicit allowance for separate condition entry for each pressurizer power operated relief 3 4.11 Actions 3.4 4 Actions valve (PORV) and each block vaive was included to clarify current practice for tracking Note 1 a!!owable outage times for each inoperab!2 component.
3.4 A11 Actions to restore pressurizer PORV(s) or block valves were deleted since the option to restore LCO 3 0 2 3 4 4 Actions a b, inoperable components currently exists and does not need to be stated.
c, and d (By)- Byron specific (Bw)- Braidwood specif.c Byron and Braidwood A_ T BL3 4 2


                                  .p                                                                                                                                               im L)                                                                                                             Lj                               U Table A - Administrative Changes to CTS                                                         ,
.p im L)
Discussion                                                                         Description .                                     ITS               CTS of Change                                                                               of Change                               Requirement       Requirement 3.4 A12                     Whenever a loop isolation valve is discovered open, compliance with the LCO cannot be             3 4.17 Action B   3.4.1.5.1 Actions.   ,
Lj U
Table A - Administrative Changes to CTS Discussion Description.
ITS CTS of Change of Change Requirement Requirement 3.4 A12 Whenever a loop isolation valve is discovered open, compliance with the LCO cannot be 3 4.17 Action B 3.4.1.5.1 Actions.
reestablished in the Modes of applicability. These requirements are clarified by substituting the phrase " maintain the valves closed" for " suspend startup of the isolated loop" and by adding a note that shutdown of the unit to Mode 5 must be completed.
reestablished in the Modes of applicability. These requirements are clarified by substituting the phrase " maintain the valves closed" for " suspend startup of the isolated loop" and by adding a note that shutdown of the unit to Mode 5 must be completed.
3.4 A13                     Frequency for verifying the capacity of each group of pressurizer heaters was changed from         SR 3 4.9.2       4.4.3.2 "each refueling outage" to the equivalent "18 months," consistent with the length of a fuel cycle.
3.4 A13 Frequency for verifying the capacity of each group of pressurizer heaters was changed from SR 3 4.9.2 4.4.3.2 "each refueling outage" to the equivalent "18 months," consistent with the length of a fuel cycle.
3.4 A14                     The phrase " water level not within limit" was used to clarify the intent with the pressurizer     3.4.9 Action A   3 4 3 Action b "otherwise inoperable."                                                                                                                   ,
3.4 A14 The phrase " water level not within limit" was used to clarify the intent with the pressurizer 3.4.9 Action A 3 4 3 Action b "otherwise inoperable."
3.4 A15                     LCO and Action requirements for steam generator (SG) Operability were incorporated in other       LCO 3 4.4,       3/4 4 5 STS Specifications. The specific surveillance requirements were incorporated in the Steam         LCO 3.4.5, Generator Tube Surveillance Program and replaced by a surveillance to verify steam generator       LCO 3 4.6, tube integrity in accordance with this Program.                                                   LCO 3 4.13 SR 3.4.13 2,5.5 9 3.4 A16                     The requirement to enter LCO 3.0.3 was explicitly stated as an Action for the condition of all     3.4.15 Action D   3.0 3 required RCS Leakage Detection System monitors being inoperable to clarify current requirements.
3.4 A15 LCO and Action requirements for steam generator (SG) Operability were incorporated in other LCO 3 4.4, 3/4 4 5 STS Specifications. The specific surveillance requirements were incorporated in the Steam LCO 3.4.5, Generator Tube Surveillance Program and replaced by a surveillance to verify steam generator LCO 3 4.6, tube integrity in accordance with this Program.
l 3.4 A17                     Obsolete, cycle-specific surveillance extension allowance for the 18 month Channel Calibration     SR 3 4.15'3       4 4.6 1 of the Containment Sump Monitor was deleted.
LCO 3 4.13 SR 3.4.13 2,5.5 9 3.4 A16 The requirement to enter LCO 3.0.3 was explicitly stated as an Action for the condition of all 3.4.15 Action D 3.0 3 i
('By)- Byron spearic (Bw)- Braidwood spearic Byron and Braidwood                                                                                                                                             A_ T BL3 4 3
required RCS Leakage Detection System monitors being inoperable to clarify current requirements.
l 3.4 A17 Obsolete, cycle-specific surveillance extension allowance for the 18 month Channel Calibration SR 3 4.15'3 4 4.6 1 of the Containment Sump Monitor was deleted.
I
('By)- Byron spearic s
(Bw)- Braidwood spearic Byron and Braidwood A_ T BL3 4 3
r
r


                                                                                                                                                                                                                                                                    . 7-,
. 7-,
4 Table A - Administrative Changes to CTS Discussion                                                           Description                                                                                                                                           ITS             CTS of Change                                                             of Change                                                                                                                                       Requirement     Requirement 3.4 A18                     The exception to Specification 4.0.4 allowing entry into Modes 3 or 4 without performing                                                                                                 SR 3.4.14.1 Note 4.4.6.2.2 leakage testing of the RCS pressure isolation valves (PlV) was reworded as a note stating the surveillance is only required to be performed in Modes 1 and 2.
4 Table A - Administrative Changes to CTS Discussion Description ITS CTS of Change of Change Requirement Requirement 3.4 A18 The exception to Specification 4.0.4 allowing entry into Modes 3 or 4 without performing SR 3.4.14.1 Note 4.4.6.2.2 leakage testing of the RCS pressure isolation valves (PlV) was reworded as a note stating the surveillance is only required to be performed in Modes 1 and 2.
3.4 A19                     Explicit allowance was included for separate condition entry for each flow path with leakage                                                                                             3.4.14 Actions - 3.4 6.2 Actions from one or more RCS PlVs not within its leakage limit. Also, direction was included to enter                                                                                             Notes 1 and 2                         ,
3.4 A19 Explicit allowance was included for separate condition entry for each flow path with leakage 3.4.14 Actions -
the applicable LCOs for systems made inoperable by an inoperable PlV to clarify current requirements.
3.4 6.2 Actions from one or more RCS PlVs not within its leakage limit. Also, direction was included to enter Notes 1 and 2 the applicable LCOs for systems made inoperable by an inoperable PlV to clarify current requirements.
3.4 A20                     Not used.
3.4 A20 Not used.
3.4 A21                     Requirements to protect the RCS from overpressurization by safety injection (SI) or charging                                                                                               LCO 3.4.12.b,   SR 4.5 3 2           l pump operation during shutoown Modes were reworded regarding the pumps' capability of                                                                                                     SR 3.4.12.1, injecting into the RCS rather than the pump's inoperability except for certain specified                                                                                                   SR 3.4.12.2                           ;
3.4 A21 Requirements to protect the RCS from overpressurization by safety injection (SI) or charging LCO 3.4.12.b, SR 4.5 3 2 l
evolutions.
pump operation during shutoown Modes were reworded regarding the pumps' capability of SR 3.4.12.1, injecting into the RCS rather than the pump's inoperability except for certain specified SR 3.4.12.2 evolutions.
3.4 A22                     Not used.
3.4 A22 Not used.
3 4 A23                     The LCO for RCS loops in Modes 1 and 2 was revised to clarify that allloops be Operable as                                                                                                 LCO 3.4.4       LCO 3 4.1.1 well as in operation since other Specifications require reactor coolant pumps and steam generators to be Operable.
3 4 A23 The LCO for RCS loops in Modes 1 and 2 was revised to clarify that allloops be Operable as LCO 3.4.4 LCO 3 4.1.1 well as in operation since other Specifications require reactor coolant pumps and steam generators to be Operable.
3.4 A24                     Frequency for verifying the capacity of each group of pressurizer heaters was changed from                                                                                                 SR 3.4.1.4       4.2.3 5 "each refueling outage
3.4 A24 Frequency for verifying the capacity of each group of pressurizer heaters was changed from SR 3.4.1.4 4.2.3 5 "each refueling outage
* to the equivalent "18 months," consistent with the length of a fuel cycle.                                                                                                                             ,
* to the equivalent "18 months," consistent with the length of a fuel cycle.
(By)- Byron specife (Bw) - Br.:idwood spectre                                                                                                                                                                                                                                       ,
(By)- Byron specife (Bw) - Br.:idwood spectre Byron and Braidwood A._T BL3 4 i
Byron and Braidwood                                                                                                                                                                                                                                 A._T BL3 4 i
4
4


                }                                 '
}
l                                                                         J                                                                                                                     *
l J
                                                                                      ,                                                                                            ; G.,
; G.,
4
4 i
                                                                                                  ,                                                                                                              i
't Table A - Administrative Changes to CTS -
                                                                                                                                                                                                                't Table A - Administrative Changes to CTS -
Discussion Description ITS.
Discussion                                                       Description                                                                     ITS .                           CTS-                 i of Change                                                       of Chaetge                                                               Requirement                     Requirement 3.4 A25               Specifications were revised to indicate the RHR loops " required" to be in operation to clarify and         SR 3.4.6.1,                         ;4.4.1.3.3,
CTS-i of Change of Chaetge Requirement Requirement 3.4 A25 Specifications were revised to indicate the RHR loops " required" to be in operation to clarify and SR 3.4.6.1, reference the LCO allowance for the pumps to be removed from operation for Imted periods.
:-                            reference the LCO allowance for the pumps to be removed from operation for Imted periods.                 LCO 3.4.7 Note 2,.                   LCO 3.4.1.4.1,
LCO 3.4.7 Note 2,.
                                                                                                                                  . 3.4.7 Actions,-                           3.4.1.4.1 Actions.                .
;4.4.1.3.3, LCO 3.4.1.4.1,
                                                                                                                                  . SR 3.4.7.1,                               4.4.1.4.1.2, SR 3 4.8.1                           4.4.1.4.2, 3.4 A26             The phrase "with power removed
. 3.4.7 Actions,-
* was deleted from the allowance that PORV block valves                     SR 3 4.11.1                           4.4.4 2                         l need not be tested if they are closed in accordance with specified Action requirements since               Note 1                                                                 ;
3.4.1.4.1 Actions.
opening the block valve by any means is not allowed while in this cOnditkni.
. SR 3.4.7.1, 4.4.1.4.1.2,
I 3.4 A27             CTS was revised to reflect changes reauested in a License Amendment Request dated May 29,                 3.4.11 Actions'                       3.4 4 Actions 1998.
[
3.4 A28             Not used.                                                                                                                                                                         f
SR 3 4.8.1 4.4.1.4.2, 3.4 A26 The phrase "with power removed
.                                                                                                                                                                                                                t t
* was deleted from the allowance that PORV block valves SR 3 4.11.1 4.4.4 2 l
3.4 A29 Actions regarding PORV inoperability due to automatic actuatKm circuitry failure were             .
need not be tested if they are closed in accordance with specified Action requirements since Note 1 opening the block valve by any means is not allowed while in this cOnditkni.
3.4.11 Actions                       ..3.4.4 Actions .
I 3.4 A27 CTS was revised to reflect changes reauested in a License Amendment Request dated May 29, 3.4.11 Actions' 3.4 4 Actions
reformatted for clarification to be conditional upon the capability of the valve being manually and       B and E                                 b and c                         '
}
automatically closed.                                                                                                                           (proposed)                       .
1998.
3.4 A30             Actions pertaining to inoperable PORVs were reformatted for clarification to be conditional upon         3.4.11 Actions A,                       3 4.4 Actions a,                 ,
t 3.4 A28 Not used.
the capability of the valve being manually and automatically closed rather than upon excessive           B, and E                                 b, and c                         :
f t
seat leakage.                                                                                                                                                                     !
3.4 A29 Actions regarding PORV inoperability due to automatic actuatKm circuitry failure were 3.4.11 Actions
4 (By) - Byron specific (Bw)- Braidwood specific                                                                                                                                                                                   I t
..3.4.4 Actions.
Byron and Braidwood                                                                                                                                                                     A_i BL3 4           l 5                                                         .                                                        i L
t reformatted for clarification to be conditional upon the capability of the valve being manually and B and E b and c automatically closed.
f
(proposed) 3.4 A30 Actions pertaining to inoperable PORVs were reformatted for clarification to be conditional upon 3.4.11 Actions A, 3 4.4 Actions a, the capability of the valve being manually and automatically closed rather than upon excessive B, and E b, and c seat leakage.
?
4 (By) - Byron specific (Bw)- Braidwood specific I
t Byron and Braidwood A_i BL3 4 l
5 i
L f


M
M
        'O                         1                                               3                                                               (O?
'O 1
Table A -' Administrative Changes to CTS :                           .,                    ,
3 (O?
,    - Discussion                                                     Description                                                       ITS '             CTS l of Change; of Change .                                                 Requirement       - Requirement       j i
Table A -' Administrative Changes to CTS :
3.4 - A31 -       ' The allowance that reactor coolant or RHR pumps may be deenergized under certam                       LCO 3.4.5 Note,   LCO 3.4.1.2 Note,       ,
- Discussion Description ITS '
conditions was reworded for clarification to allow the pumps to be " removed from operation.'
CTS l of Change; of Change.
                                                                                                                              . LCO 3.4.6 Note 1 : LCO 3 4.1.3 Note.
Requirement
* LCO 3.4.7 Note 1   LCO 3.41.41
- Requirement j
                                                                                                                ~ '
i 3.4 - A31 -
LCO 3.4.8 Note 1   Note, LCO J 3.4.1 A.2 Note
' The allowance that reactor coolant or RHR pumps may be deenergized under certam LCO 3.4.5 Note, LCO 3.4.1.2 Note, conditions was reworded for clarification to allow the pumps to be " removed from operation.'
                                                                                                                                                                          .L 3.4 A32           ' The surveillance to demonstrate the Operability of the
. LCO 3.4.6 Note 1
* cross-tie' for the pressurizer heaters to   . SR 3.4.9.3         4.4.3.3 the ESF power supply was reworded for clanfication to demonstrate the heaters * " capability to                                                   '
: LCO 3 4.1.3 Note.
be powered by* the ESF power supply.                                                                                                             '
LCO 3.4.7 Note 1 LCO 3.41.41
3.4 A33             Explicit statement that inservice inspection and testing activities shall be in addition to other i  - Specification   -4'4.4.1, specified SRs was deleted as an unnecessary steration of current requirements.                       3.4.11             14.4.9.32.c             ,
+
Surveillance Requirements,                             ,
LCO 3.4.8 Note 1 Note, LCO J
SR 3 4.12.5                                 i i
~ '
3.4 A34             Requirements were reformatted to more clearly specify the appropnate Actions to take when a required RHR loop or one or more required steam generators are m' operable in Mode 5 with 3 4.7 Actions B and C 3.4.1.4.1 Action a    j -
3.4.1 A.2 Note
,                        RCS loops filled.                                                                                                                               [
.L 3.4 A32
i i
' The surveillance to demonstrate the Operability of the
1                                                                                                                                                                         .
* cross-tie' for the pressurizer heaters to
(By)- Byron spec:fic (Bw)- Bradwood specire                                                                                                                                                   -
. SR 3.4.9.3 4.4.3.3 the ESF power supply was reworded for clanfication to demonstrate the heaters * " capability to be powered by* the ESF power supply.
Byron and Braidwood                                                                                                                                         A_ IBL3.4 -
3.4 A33 Explicit statement that inservice inspection and testing activities shall be in addition to other
                                                                                        -6                                                                               :
- Specification
:                                                                                                                                                                          )
-4'4.4.1, i
i                                                                                                                                                                         :
specified SRs was deleted as an unnecessary steration of current requirements.
3.4.11 14.4.9.32.c Surveillance Requirements, SR 3 4.12.5 i
i 3.4 A34 Requirements were reformatted to more clearly specify the appropnate Actions to take when a 3 4.7 Actions 3.4.1.4.1 Action a j
required RHR loop or one or more required steam generators are ' operable in Mode 5 with B and C m
RCS loops filled.
[
k i
i 1
(By)- Byron spec:fic
{
(Bw)- Bradwood specire Byron and Braidwood A_ IBL3.4 -
-6
)
i


Table R - Relocated CTS Discussion             Relocated                                                                                                     . Description of                                                                                     'New   Control -
Table R - Relocated CTS Discussion Relocated
of Change                 CTS-                                                                                                         Relocated CTS                                                                                     Location Process     ,
. Description of
CTS Section 3/4.4, Reactor Coolant System 3.4 R1               3/4.4.2.1     Safety Valves - Shutdown                                                                                                                                                                                 TRM.   $50.59 3.4 R2               3/4.4.7       Chemistry                                                                                                                                                                                                 TRM'   $50.59 3.4 R3               3/4.4.9.2     Pressurizer Pressure / Temperature Limits                                                                                                                                                                 TRM'   '650.59
'New Control -
                                                                                                                                                                                                                                                                .3 3.4 R4               3/4.4.10     Structural Integrity (except requirements for reactor coolant pump flywheel)                                                                                                                             TRM-   $50.59       ,
of Change CTS-Relocated CTS Location Process CTS Section 3/4.4, Reactor Coolant System 3.4 R1 3/4.4.2.1 Safety Valves - Shutdown TRM.
3.4 RS               3/4.4.11     RCS Vents                                                                                                                                                                                                 TRM     $53.59 r
$50.59 3.4 R2 3/4.4.7 Chemistry TRM'
$50.59 3.4 R3 3/4.4.9.2 Pressurizer Pressure / Temperature Limits TRM'
'650.59
.3 3.4 R4 3/4.4.10 Structural Integrity (except requirements for reactor coolant pump flywheel)
TRM-
$50.59 3.4 RS 3/4.4.11 RCS Vents TRM
$53.59 r
i L
i L
r l
r l
(By)- Byron speciric (Bw)- Braidwood specific                                                                                                                                                                                                                                         ,
(By)- Byron speciric (Bw)- Braidwood specific Byron and Braidwood 1
Byron and Braidwood                                                                                                                             1                                                                                                     R_IBL3 4   ,
R_IBL3 4


        ,                                                                                  e, 73 Table M - More Restric:.We Changes to CTS Discussion                                                         Description                                                                                                                                                                                                         ITS               CTS of Change                                                                 of Change                                                                                                                                                                                             Requirement       Requirement ITS Section 3.4, Reactor Coolant Systems 3.4 M1               Surveillances were added to require verification of correct breaker alignment and indicated                                                                                                                                                                 SR 3.4.7.3,       N/A power available to the required Residual Heat Removal (RHR) pump that is not in operation                                                                                                                                                                   SR 3.4.8.2 should it need to be placed in operation.
e, 73 Table M - More Restric:.We Changes to CTS Discussion Description ITS CTS of Change of Change Requirement Requirement ITS Section 3.4, Reactor Coolant Systems 3.4 M1 Surveillances were added to require verification of correct breaker alignment and indicated SR 3.4.7.3, N/A power available to the required Residual Heat Removal (RHR) pump that is not in operation SR 3.4.8.2 should it need to be placed in operation.
3.4 M2             The restrictions under which an RHR pump may be de-energized were revised to include a                                                                                                                                                                       LCO 3.4.8 Note 1.c LCO 3.4.1,4 2 Note prohibition of any draining operations that would further reduce the Reactor Coolant System (RCS) water volume.
3.4 M2 The restrictions under which an RHR pump may be de-energized were revised to include a LCO 3.4.8 Note 1.c LCO 3.4.1,4 2 Note prohibition of any draining operations that would further reduce the Reactor Coolant System (RCS) water volume.
3.4 M3             The allowances for removing all required RCS pumps from operation were revised to limit the                                                                                                                                                                 LCO 3 4 5 Note. LCO 3 412 amount of time the RCS is without forced cooling to s 1 hour per 8 hours.                                                                                                                                                                                   LCO 3 4 6 Note 1   LCO 3 4.1.3,       ,
3.4 M3 The allowances for removing all required RCS pumps from operation were revised to limit the LCO 3 4 5 Note.
LCO 3 4.7 Note 1   LCO 3 41.4.1 3.4 M4             With the RHR System suction isolation valve interlock function inoperable, the CTS Emergency                                                                                                                                                                 3.4.14 Action B   3.5.2 Action a Core Cooling System Specification requires restoration of the RHR subsystem to Operable within 7 days. An Action specific to the interlock function was added to require isolating the RHR flow path within 4 hours to protect RHR components from overpressurization.
LCO 3 412 amount of time the RCS is without forced cooling to s 1 hour per 8 hours.
3.4 M5             An Action to shutdown the unit to a Mode in which the LCO does not apply when two or more                                                                                                                                                                   3.4.10 Action B   3.0.3               ,
LCO 3 4 6 Note 1 LCO 3 4.1.3, LCO 3 4.7 Note 1 LCO 3 41.4.1 3.4 M4 With the RHR System suction isolation valve interlock function inoperable, the CTS Emergency 3.4.14 Action B 3.5.2 Action a Core Cooling System Specification requires restoration of the RHR subsystem to Operable within 7 days. An Action specific to the interlock function was added to require isolating the RHR flow path within 4 hours to protect RHR components from overpressurization.
pressurizer valves are inoperable was included rather then defer to LCO 3.0.3 for this requirement. The result is a completion time of 1 hour less to have the unit in Mode 4.
3.4 M5 An Action to shutdown the unit to a Mode in which the LCO does not apply when two or more 3.4.10 Action B 3.0.3 pressurizer valves are inoperable was included rather then defer to LCO 3.0.3 for this requirement. The result is a completion time of 1 hour less to have the unit in Mode 4.
3.4 M6             The completion time for restoring an inoperable pressurizer power operated relief valve (PORV)                                                                                                                                                               3.4.11 Action B   3.4.4 Action b was reduced to 72 hours consistent with other similar component restoration times.
3.4 M6 The completion time for restoring an inoperable pressurizer power operated relief valve (PORV) 3.4.11 Action B 3.4.4 Action b was reduced to 72 hours consistent with other similar component restoration times.
3.4 M7             The Specification for Low Pressure Overpressure Protection (LTOP) was revised to add LCOs,                                                                                                                                                                   3.4.12             3/4 4.9.3 Actions, and Surveillance Requirements for conditions in which the RCS could be overpressurized from unisolated accumulators, safety injection (SI) or charging pumps, or from any other reason LTOP becomes inoperable.
3.4 M7 The Specification for Low Pressure Overpressure Protection (LTOP) was revised to add LCOs, 3.4.12 3/4 4.9.3 Actions, and Surveillance Requirements for conditions in which the RCS could be overpressurized from unisolated accumulators, safety injection (SI) or charging pumps, or from any other reason LTOP becomes inoperable.
(By)- Byron spec fic (Bw)- Braidwood speofic Byron and Braidwood                                                                                           1                                                                                                                                                                                                 M_TBL3 4
(By)- Byron spec fic (Bw)- Braidwood speofic Byron and Braidwood 1
M_TBL3 4


O                                                                           %/                                                                                                                                     v Table M - More Restrictive Changes to CTS s
O
Discussion                                                       'Weription                                                                                                         ITS -                                     'CiS~
%/
of Change                                                             change                                                                                           . Requirement                                 Requirement 3.4 M8               With a SI pump (s) discovered Operabia in the applicable Modes and conditions, the Action to                                                     3.4.12 Action B                           3 5.4.1 Actions restore the Si pump (s) to inoperable status within 4 hours was changed to immediately initiate action to verify no pumps are capable of injecting into the RCS.
v Table M - More Restrictive Changes to CTS s
3.4 M9               The frequency for verification of RCS average temperature was changed to every 12 hours while                                                   SR 3.4.2.1                                 '4.1.1.4 b in the applicable Modes and conditions rather than every 30 minutes only when RCS average                                                                                                                         ,
Discussion
temperature is s 557'F with the Ty -T,,, deviation alarm not reset.
'Weription ITS -
3.4 M10             A completion time of 72 hours was imposed on the Action to determine that the RCS remains                                                       3.4.3 Action A                             3 4.9.1 Action acceptable for continued operation after the RCS temperature or pressure limit has been .
'CiS~
of Change change
. Requirement Requirement 3.4 M8 With a SI pump (s) discovered Operabia in the applicable Modes and conditions, the Action to 3.4.12 Action B 3 5.4.1 Actions restore the Si pump (s) to inoperable status within 4 hours was changed to immediately initiate action to verify no pumps are capable of injecting into the RCS.
3.4 M9 The frequency for verification of RCS average temperature was changed to every 12 hours while SR 3.4.2.1
'4.1.1.4 b in the applicable Modes and conditions rather than every 30 minutes only when RCS average temperature is s 557'F with the T
-T,,, deviation alarm not reset.
y 3.4 M10 A completion time of 72 hours was imposed on the Action to determine that the RCS remains 3.4.3 Action A 3 4.9.1 Action acceptable for continued operation after the RCS temperature or pressure limit has been.
exceeded in Modes 1,2,3 or 4.
exceeded in Modes 1,2,3 or 4.
3.4 M11             The Action to restore RCS temperature and/or pressure to within limit within 30 minutes was                                                     3.4.3 Action C                             3.4.9.1 Actions changed for Modes other than 1,2,3, or 4 to require immediate action to restore the                                                                                                                                                   ,
3.4 M11 The Action to restore RCS temperature and/or pressure to within limit within 30 minutes was 3.4.3 Action C 3.4.9.1 Actions changed for Modes other than 1,2,3, or 4 to require immediate action to restore the parameter (s) to within limit and to determine that the RCS is acceptable for continued operation before entering A4 ode 4.
parameter (s) to within limit and to determine that the RCS is acceptable for continued operation                                                                                                                                     :
t 3.4 M12 Special Test Exception to allow reactor criticality under no flow conditions was deleted. The N/A 3/4.4.10.4 Specification is no longer needed since this testing was only necessary for initial unit startup with a new core.
before entering A4 ode 4.                                                                                                                                                                                                             t 3.4 M12             Special Test Exception to allow reactor criticality under no flow conditions was deleted. The                                                   N/A                                         3/4.4.10.4                               !
3.4 M13 Specifications for RHR operation in Mode 5 conditions do not specify Actions for both loops of 3.4.7 Action D, 3.4.141 Actions,
Specification is no longer needed since this testing was only necessary for initial unit startup with a new core.
,f RHR inoperable. Actions were added to immediately suspend all operations involving a 3_4.8 Action C 3.4.1.4.2 Actions
3.4 M13             Specifications for RHR operation in Mode 5 conditions do not specify Actions for both loops of                                                   3.4.7 Action D,                             3.4.141 Actions,                       ,f RHR inoperable. Actions were added to immediately suspend all operations involving a                                                             3_4.8 Action C                             3.4.1.4.2 Actions reduction of RCS boron concentration and to immediately initiate restoration of one RHR loop to                                                                                                                                       j Operable status.                                                                                                                                                                                                                       !
[
t 3.4 M14             If unable to restore RCS total flow rate to within limit within 2 hours in Mode 1, the Action to                                                 3.4.1 Action B                             3.2.3 Action a 2                           "
reduction of RCS boron concentration and to immediately initiate restoration of one RHR loop to j
reduce Thermal Power was replaced with the Action to place the unit in a Mode in which the LCO does not apply.
Operable status.
                                                                                                                                                                                                                                                              +
t 3.4 M14 If unable to restore RCS total flow rate to within limit within 2 hours in Mode 1, the Action to 3.4.1 Action B 3.2.3 Action a 2 reduce Thermal Power was replaced with the Action to place the unit in a Mode in which the LCO does not apply.
l (By)- Byron specife (Bw)- Braidwood specife Byron and Braidwood                                                                         2                                                                                                                                         M_iBL3 4
+
___________m_l__.  . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _'
l (By)- Byron specife (Bw)- Braidwood specife Byron and Braidwood 2
M_iBL3 4 m l


        . (--                                                                     ,,-~ .                                                                                                                                 ,,.
. (--
                                                                                                                                                                                                                        .- (v l-(    )-                                                                  (
,,-~.
Table M - More Restrictive Changes to CTS                                                                                                                                                     -
(
_a Discussion                                                       Description                                                                                                           ITS                                     CTS.
)-
of Change                                                         of Change                                                                                                     Requirement                         Requirement -
(
3.4 M 15             A time period of 7 days after reaching 90% Rated Thermal Power was stipulated for determining                                                           SR 3.4.1.4 Note                     4.2.3.5 RCS total flow rate by precision heat balance measurement rather than prior to completion of Physics Tests.
.- (v -l Table M - More Restrictive Changes to CTS
3.4 . M16             A time period of 31 days was imposed for sampling and radioanalysis for RCS P. after a                                                                 SR 3.4.16.3 Note                     Table 4 4-4. Note
_a Discussion Description ITS CTS.
* minimum of 2 effective full power days and 20 days of Mode 1 operation.                                                                                                                                       ,
of Change of Change Requirement Requirement -
3.4 M17               Not used.
3.4 M 15 A time period of 7 days after reaching 90% Rated Thermal Power was stipulated for determining SR 3.4.1.4 Note 4.2.3.5 RCS total flow rate by precision heat balance measurement rather than prior to completion of Physics Tests.
3.4 M18               To provide additional assurance that low temperature overpressurization events are prevented,                                                         3.4.12 Applicability                 3.4.5.1 Applicability the Applicabihty was revised so that no Si pumps may be capable of injecting into the RCS, regardless of the pressurizer level.
3.4. M16 A time period of 31 days was imposed for sampling and radioanalysis for RCS P. after a SR 3.4.16.3 Note Table 4 4-4. Note
3.4 M19               The surveillance frequency "in accordance with the Inservice Testing Program" for verifying the                                                       SR 3.4.14.1 '                         4.4.6.2.2 s.
* minimum of 2 effective full power days and 20 days of Mode 1 operation.
3.4 M17 Not used.
3.4 M18 To provide additional assurance that low temperature overpressurization events are prevented, 3.4.12 Applicability 3.4.5.1 Applicability the Applicabihty was revised so that no Si pumps may be capable of injecting into the RCS, regardless of the pressurizer level.
3.4 M19 The surveillance frequency "in accordance with the Inservice Testing Program" for verifying the SR 3.4.14.1 '
4.4.6.2.2 s.
leakage from each RCS pressure isolation valve is within limits was added for consistency with STS.
leakage from each RCS pressure isolation valve is within limits was added for consistency with STS.
4
4
                                                                                                                                                                                                                                                                          )
)
(By)- Byron specife (Bw) - Braidwood specirc Byron and Braidwood                                                                                         3                                                                                                                         M_1 BL3.4
(By)- Byron specife (Bw) - Braidwood specirc Byron and Braidwood 3
_ _ _ _ . _ - _ - . _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _    _ _ _ _ _ _ _ _ _ _              .__.______-m_                            _ . _ _ _                _-
M_1 BL3.4
[
-m


( ...
(...
_y                                                                                   .,                                                        Q Table LA - Details Relocated from CTS Discussion                           CTS                                                   Description of                                 New     Control of Change                       Reference                                             Relocated Details                               Location Process       Type ITS Section 3.4, Reactor Coolant Systems 3.4 LA1                         4.4.1.1               Information describing the characteristics of operating reactor coolant loops.       Bases   ITS 5.5.14       2 3.4 LA2                         LCO 3.4.1.2           Design details listing the components associated with each reactor coolant loop for Bases   ITS 5.5.14       1 Operability.
_y Q
3.4 LA3                         4.4.1.2.3,             Information describing the characteristics of operating reactor coolant or Residual Bases   ITS 5.5.14       2 4.4.1.3.3,             Heat Removal (RHR) loops.
Table LA - Details Relocated from CTS Discussion CTS Description of New Control of Change Reference Relocated Details Location Process Type ITS Section 3.4, Reactor Coolant Systems 3.4 LA1 4.4.1.1 Information describing the characteristics of operating reactor coolant loops.
4.4.1.4.1.2, 4.4.1.4.2 3.4 LA4                         LCO 3.4.1.3           Design details listing each RHR loop and the components associated with each         Bases   ITS 5.5.14       1 reactor coolant loop for Operability.
Bases ITS 5.5.14 2
3.4 LA5                         Not used.
3.4 LA2 LCO 3.4.1.2 Design details listing the components associated with each reactor coolant loop for Bases ITS 5.5.14 1
3.4 LAS                         4.4.31,4.4.3.2         Details describing the testing methods used to demonstrate pressurizer heater       Bases   ITS 5 5.14       3 Operability.
Operability.
3.4 LA7                         Table 4.4-4           Details describing the method used to analyze reactor coolant samples for gross     Bases   ITS 5 5.14       3 Note **               radioactivity.
3.4 LA3 4.4.1.2.3, Information describing the characteristics of operating reactor coolant or Residual Bases ITS 5.5.14 2
3.4 LA8                         Not used.
4.4.1.3.3, Heat Removal (RHR) loops.
3.4 LA9                         3.4.6.1 Action a       Parameters for which containment atmosphere must be analyzed when                   Bases   ITS 5.5.14       3 containment radiation monitors are inoperable.
4.4.1.4.1.2, 4.4.1.4.2 3.4 LA4 LCO 3.4.1.3 Design details listing each RHR loop and the components associated with each Bases ITS 5.5.14 1
Relocated Detail Types 1   Details of System Design                       3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation (By) - Byron specific (Bw)- Braidwood specific Byron and Braidwood                                                                                         1 LA_ i BL 3 4
reactor coolant loop for Operability.
.___ - ___ __._ - . _              __ .__ . - = _ = _ -                 __        ._.__-_-_-_ _ .                      _ _ - _ _ _ . _ _- _ _ = _ - - _ - - _
3.4 LA5 Not used.
3.4 LAS 4.4.31,4.4.3.2 Details describing the testing methods used to demonstrate pressurizer heater Bases ITS 5 5.14 3
Operability.
3.4 LA7 Table 4.4-4 Details describing the method used to analyze reactor coolant samples for gross Bases ITS 5 5.14 3
Note **
radioactivity.
3.4 LA8 Not used.
3.4 LA9 3.4.6.1 Action a Parameters for which containment atmosphere must be analyzed when Bases ITS 5.5.14 3
containment radiation monitors are inoperable.
Relocated Detail Types 1
Details of System Design 3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation (By) - Byron specific (Bw)- Braidwood specific Byron and Braidwood 1
LA_ i BL 3 4
__.__. - = _ = _ -
_ _ - _ _ _. _ _- _ _ = _ - - _ - - _


        - ~             .I       y                                                                                                                                                                                                   l N
- ~
Table LA - Details Relocated from CTS .                                                                                                     -
.I y
                                                                                                                                                                                                                                                                          ?
l N
Discussion                         CTS-                                                               Description of                                                                                 New     Control                             f of Change .                   Reference                                                         Relocated Details                                                                             . Location Process             . Type
Table LA - Details Relocated from CTS.
                    ' 3.4 LA10                     LCO 3.4.6.2.f .       Details fct adjusting allowable pressurizer isolation valve (PlV) leakage when -                                                                 Bases   ITS 5.5.14               3 tested at Reactor Coolant System (RCS) pressures other than that specified.                                                                                                                   J 3.4 LA11                       Table 3.4-1           Listing of RCS PlVs valve identification numbers and functions.                                                                                 Bases   ITS 5.5.14 -               1 3.4 ' LA12                     Not used                                                                                                                                                                                     ,
?
3.4 LA13                       Not used.                                                                                                                                                                                                             !
f Discussion CTS-Description of New Control of Change.
e 3.4 LA14                       4.5.3.2,             Details describing the method used to demonstrate that the safety injection (SI)                                                                 Bases   11 S 5.5.14               3:
Reference Relocated Details
3/4.5.4.1             and charging pumps are incapable of injectog into the RCS during Low                                                                                                                           i Temperature Overpressure Protection (LTOP) conditions.                                                                                                                                           !
. Location Process
4.5.4.2.1             Details describing the method used to demonstrate that the Si pumps are                                                                           TRM     $50.59               '3           5
. Type
.                                                                        incapable of injecting into the RCS during LTOP conditions.                                                                                                                                     l 3.4 LA15                       4.4.9.3.2             Valve identification numbers used for demonstrating Operability of RHR suction                                                                   Bases   ITS 5.514               3 relief valves when used for LTOP.                                                                                                                                                             }
' 3.4 LA10 LCO 3.4.6.2.f.
l t
Details fct adjusting allowable pressurizer isolation valve (PlV) leakage when -
3.4 LA16                       Not used.
Bases ITS 5.5.14 3
3.4 LA17                       LCO 3.2.3             Requirement for maintaining four RCS loops in operation.                                                                                         Bases   ITS 5 5.14               2 3.4 LA18                       4.2.3.5               Method for determining RCS total flow rate.                                                                                                       TRM       50 59                 3'           !
tested at Reactor Coolant System (RCS) pressures other than that specified.
3.4 LA19                       4.2.3.4               Surveillance requirement to perform an 18 month Channel Calibration of the RCS                                                                   TRM       550.59                 3         -!
J 3.4 LA11 Table 3.4-1 Listing of RCS PlVs valve identification numbers and functions.
total flow rate indicators.                                                                                                                                                                     ;
Bases ITS 5.5.14 -
i 4                                                                                                                                                                                                                                                                         !
1
                - Relocated Detad Types 1     Detads of System Design                     3 Procedural Detads for Meeting TS Requirements                                                                                                                                                   '!
{
2 Description of System Operation (By)- Byron specific                                                                                                                                                                                                                                 .r (Bw)- Braidwood specific Byron and Braidwood                                                                                               2                                                                                                         LA_TOL 3 4 1
3.4 ' LA12 Not used 3.4 LA13 Not used.
e 3.4 LA14 4.5.3.2, Details describing the method used to demonstrate that the safety injection (SI)
Bases 11 S 5.5.14 3:
3/4.5.4.1 and charging pumps are incapable of injectog into the RCS during Low i
Temperature Overpressure Protection (LTOP) conditions.
4.5.4.2.1 Details describing the method used to demonstrate that the Si pumps are TRM
$50.59
'3 5
incapable of injecting into the RCS during LTOP conditions.
l
[
3.4 LA15 4.4.9.3.2 Valve identification numbers used for demonstrating Operability of RHR suction Bases ITS 5.514 3
relief valves when used for LTOP.
l
}
t 3.4 LA16 Not used.
3.4 LA17 LCO 3.2.3 Requirement for maintaining four RCS loops in operation.
Bases ITS 5 5.14 2
f 3.4 LA18 4.2.3.5 Method for determining RCS total flow rate.
TRM 50 59 3'
3.4 LA19 4.2.3.4 Surveillance requirement to perform an 18 month Channel Calibration of the RCS TRM 550.59 3
total flow rate indicators.
i 4
- Relocated Detad Types 1
Detads of System Design 3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation j
(By)- Byron specific
.r (Bw)- Braidwood specific h
Byron and Braidwood 2
LA_TOL 3 4 l
1


                                                                                      ^ Tatde LA - Details Retocated from CTS                   ^
^ Tatde LA - Details Retocated from CTS
Discussion               CTS-                                                           : Description of                             New=   ' Control of Change             Reference .                                                     Relocated Details'                         Location : Process       . Type.
^
3.4 LA20-             hot used.
Discussion CTS-
      .3.4 : LA21           LCO 3.4.6.2.c -       Excepting isolated steam generators from RCS leakage limits.                             Bases ITS 5.5.14         3 3.4 LA22.             3.4.91 Actons         Requirement that an engmeering evaluation be performed to determme the effects           Bases ITS 5.514 -       "3 of a temperature or pressure excursion on the structuralintegrity of the RCS.
: Description of New=
3.4 LA23 -           4.4.6,1.c               Requirement to penodically verify the oil separator porton of the containment floor       -TRM     . $50.59         3 drain collection sump has been filled.
' Control of Change Reference.
3.4 LA24             4.4.6.2.1.a.           Surveillance requirements for demonstrating RCS leakage is within snecified "                                       '3-
Relocated Details' Location
                                                                                                                                            ..T R M   $50.59 4.4.6.2.1.b,           limits.
: Process
4.4.6.2 1.e 3.4 LA25             3.4.9.3 Action e       Requirement to submit a Special Report to the Commission in the event that 'edher           TRM-                                                                                                                                                                             $50.59 the pressurizer power operated relief valves, the RHR sucton relief valves, or the RCS vents are used to mitigate an RCS pressure trensient.
. Type.
3.4 LA26             4.4.6.2.2.c.           Requirement to demonstrate each RCS PlV Operable by verifying leakage to be                 TRM_                     .3
3.4 LA20-hot used.
                                                                                                                                                        $50.59 -
.3.4 : LA21 LCO 3.4.6.2.c -
witnin its limit prior to retuming the valve to service following maintenance, repair, or replacement.
Excepting isolated steam generators from RCS leakage limits.
3.4 LA27             Table 3.3-6,           RCS leakage detection instrumentation id3ntification numbers for the containment         ' Bases ITS 5.5.14         1 Table 4.3-3           gaseous and particulate radioactivity monitors.
Bases ITS 5.5.14 3
Relocated Detail Types 1   Details of System Design           3 , . Procedural Detads for Meetmg TS Requwements 2 Description of System Operation (By)- Byron specific (Bw) - Braidwood specife Byron and Braidwood                                                                                   3                               4 i A_TBL3 4
3.4 LA22.
3.4.91 Actons Requirement that an engmeering evaluation be performed to determme the effects Bases ITS 5.514 -
"3 of a temperature or pressure excursion on the structuralintegrity of the RCS.
3.4 LA23 -
4.4.6,1.c Requirement to penodically verify the oil separator porton of the containment floor
-TRM
. $50.59 3
drain collection sump has been filled.
3.4 LA24 4.4.6.2.1.a.
Surveillance requirements for demonstrating RCS leakage is within snecified "
..T R M
$50.59
'3-4.4.6.2.1.b, limits.
4.4.6.2 1.e 3.4 LA25 3.4.9.3 Action e Requirement to submit a Special Report to the Commission in the event that 'edher TRM-
$50.59 the pressurizer power operated relief valves, the RHR sucton relief valves, or the RCS vents are used to mitigate an RCS pressure trensient.
3.4 LA26 4.4.6.2.2.c.
Requirement to demonstrate each RCS PlV Operable by verifying leakage to be TRM_
$50.59 -
.3 witnin its limit prior to retuming the valve to service following maintenance, repair, or replacement.
3.4 LA27 Table 3.3-6, RCS leakage detection instrumentation id3ntification numbers for the containment
' Bases ITS 5.5.14 1
Table 4.3-3 gaseous and particulate radioactivity monitors.
Relocated Detail Types 1
Details of System Design 3,. Procedural Detads for Meetmg TS Requwements 2 Description of System Operation (By)- Byron specific (Bw) - Braidwood specife Byron and Braidwood 3
i A_TBL3 4 4


                                                                                                            ~
~
                  ~Q)'                                                                                         )                                                         \   )
~Q)'
Table LA - Details Relocated from CTS Discussion                       CTS                                           Description of                                         New         Control of Change                 Reference                                           Relocated Details                                   Location           Process       Type 3.4 LA28                 LCO 3.4.6.1 b.     Details of the RCS leakage detection systems regarding the methods used to               -Bases       . ITS 5.514       1, 2 4.4.6.1.b           monitor leakage into the containment floor drain sump and the reactor cavity sump.
)
3.4 LA29                 SR 4.1.1.4.b       Requirement to verify the RCS average temperature is at least 550*F once per 30             TRM                           3
\\ )
                                                                                                                                                                      $50.59 minutes when the reactor is critical and RCS temperature is less than 557*F with the T.,-T,,, Deviation Alarm not reset.
Table LA - Details Relocated from CTS Discussion CTS Description of New Control of Change Reference Relocated Details Location Process Type 3.4 LA28 LCO 3.4.6.1 b.
                                                                                                                                                                                              .I Relocated Detail Types 1   Detads of System Design               3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation (By)- Byron specirc (Bw) - Braidwood specife Byron and Braidwood                                                                                       4                                                           LA_IBL3 4
Details of the RCS leakage detection systems regarding the methods used to
  = . __ . .        . .  . . . . . - , ..    . .
-Bases
                                                                                                  ~. .. - . . . . . . - . .
. ITS 5.514 1, 2 4.4.6.1.b monitor leakage into the containment floor drain sump and the reactor cavity sump.
                                                                                                                                                                                            -J
3.4 LA29 SR 4.1.1.4.b Requirement to verify the RCS average temperature is at least 550*F once per 30 TRM
                                                                                                                              .~..:..--.~. . . .. -. ..
$50.59 3
minutes when the reactor is critical and RCS temperature is less than 557*F with the T.,-T,,, Deviation Alarm not reset.
.I Relocated Detail Types 1
Detads of System Design 3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation (By)- Byron specirc (Bw) - Braidwood specife Byron and Braidwood 4
LA_IBL3 4
=. _..
~.. -...... -..
.~..:..--.~.
-J


N..Y Table L - Less Restrictive Changes to CTS Discussion                                                     Description                                           ITS               CTS             Change of Change                                                     of Change                                       Requirement       Requirement       Category ITS Section 3.4, Reacter Coolant Systems 3.4 L1               Requirements to verify through incore flux mapping and RCS total flow rate               3.2.2,             3.2.3 Actions           111 Vill comparison that the combination of Reactor Coolant System (RCS) total flow rate and       3 4.1             b and c. 4.2.3.2, Nuclear Enthalpy Rise Hot Channel Factor (F2n) are within limits were eliminated                             4.2.3.3 consistent with STS. Individual limits for RCS total flow rate and Fynwere retained in separate Specifications.
N..Y Table L - Less Restrictive Changes to CTS Discussion Description ITS CTS Change of Change of Change Requirement Requirement Category ITS Section 3.4, Reacter Coolant Systems 3.4 L1 Requirements to verify through incore flux mapping and RCS total flow rate 3.2.2, 3.2.3 Actions 111 Vill comparison that the combination of Reactor Coolant System (RCS) total flow rate and 3 4.1 b and c. 4.2.3.2, Nuclear Enthalpy Rise Hot Channel Factor (F2n) are within limits were eliminated 4.2.3.3 consistent with STS. Individual limits for RCS total flow rate and Fynwere retained in separate Specifications.
3.4 L2               The explicit requirement to determine RCS temperature to be a 550*F within 15 '           SR 3.4.2.1,       4.1.1.4.a                 Vi minutes prior to achieving reactor criticality was removed since SR 3.0.4 requires the   SR 3.0.4 performance of this surveillance prior to entering these cc..Jitions specified in the Applicability.
3.4 L2 The explicit requirement to determine RCS temperature to be a 550*F within 15 '
3.4 L3               Requirements were revised to base the number of operating RCS loops on the rod           3 4.5 LCO and     3 41.2 LCO and           I, til withdrawal capability of the Rod Control System rather than on the position of the         Actions A, B and . Actions b and c Reactor Trip System breakers (RTBs) since methods other than opening the RTBs are         C available for preventing an inadvertent rod withdrawal.
SR 3.4.2.1, 4.1.1.4.a Vi minutes prior to achieving reactor criticality was removed since SR 3.0.4 requires the SR 3.0.4 performance of this surveillance prior to entering these cc..Jitions specified in the Applicability.
3.4 L4               The completion tirne for reducing Thermal Power when RCS total flow rate is outside       3.4.1 Action B     3 2.3 Action a.2         IV its limit was relaxed from 4 hours to 6 hours to allow for an orderly transition to a Mode in which the limit is not applicable.
3.4 L3 Requirements were revised to base the number of operating RCS loops on the rod 3 4.5 LCO and 3 41.2 LCO and I, til withdrawal capability of the Rod Control System rather than on the position of the Actions A, B and.
3.4 LS               Not used.
Actions b and c Reactor Trip System breakers (RTBs) since methods other than opening the RTBs are C
l Less Restrictive Change Categones i   Retaxation of t_CO requirements                   V     Relaxation of SR acceptance enteria il Relaxation of Appicability                           VI     Relaxation of Survedlance Frequency                                                                     ,
available for preventing an inadvertent rod withdrawal.
111 Relaxation of Action requirernents                 Vil Deletion of requirements redundant to regulation IV Relaxation of completion tune                       Vill Deletion of Surveinance requirements (By)- Byron spectre (Bw)- Braidwood specirc                                                                                                                                               .
3.4 L4 The completion tirne for reducing Thermal Power when RCS total flow rate is outside 3.4.1 Action B 3 2.3 Action a.2 IV its limit was relaxed from 4 hours to 6 hours to allow for an orderly transition to a Mode in which the limit is not applicable.
Byron and Braidwood                                                                           1 L_i BL3 4
3.4 LS Not used.
l Less Restrictive Change Categones i
Retaxation of t_CO requirements V
Relaxation of SR acceptance enteria il Relaxation of Appicability VI Relaxation of Survedlance Frequency 111 Relaxation of Action requirernents Vil Deletion of requirements redundant to regulation IV Relaxation of completion tune Vill Deletion of Surveinance requirements (By)- Byron spectre (Bw)- Braidwood specirc Byron and Braidwood 1
L_i BL3 4


    ,_ ..                . ._                        .                                        .                          -      ,            . .                                  .          -      .                                                _.                  - m ,
m,
t
t m.
  ,                              m.                                                                                                                                 - - g;                                                                                   w s
- - g; w
                                                                                                                                            .                      y
y
                                                                                                                                                                            }.                                                            ,                .
}.
s_
s_
                                                                                                                                                                                                                                                                                      -l
-l s
                                                                                                                                                                    ; .J'                                                                                       ...                    c i
;.J' c
Table L - Less Restrictive Changes to CTS -
i Table L - Less Restrictive Changes to CTS -
Discussion                                                                                                           Description                                                                 ITS 1                 . CTS           Change.             ,
Discussion Description ITS 1
of Change                                                                                                           of Change'                                           Requirement                             Requirement :     Category               !
. CTS Change.
,                        3.4 a L6_.             'An allowance was included for separate condition entry for each RCS loop isolation                                                             3.4.17 Actions                             3.0.3 :                   . til valve discovered either closed or with power available to its operator. Also, CTS                                                             Note and Action                                                                       !
of Change of Change' Requirement Requirement :
imphcitly requires that, when one or more loop isolabon valves have power avadable,                                                           A                                                                                     i the unit be placed in a Mode in which the LCO does not apply. Required Achons were                                                                                                                                                   ;
Category 3.4 a L6_.
,                                                  relaxed to allow 30 minutes to restore cofii,A=n.= with the LCO by removing power                                                                                                                                                   ,
'An allowance was included for separate condition entry for each RCS loop isolation 3.4.17 Actions 3.0.3 :
from the valve operators.                                                                                                                                                                                         ,                  l 3.4 L7                   The completion time for restoring an RCS pressure isolation valve (PlV) to within its                                                         3'.4.14 Action A-                         3.4 6.2 Action c             IV leakage limit was relaxed from 4 hours to indefinitely provided the compensatory .                                                                                                                                                   [
. til valve discovered either closed or with power available to its operator. Also, CTS Note and Action imphcitly requires that, when one or more loop isolabon valves have power avadable, A
Actions are taken to isolate the high pressure porten of the affected system from the                                                                                                                                               i Iow pressure porten with a specified isolation valve within 4 hours and with a second                                                                                                                                               !
i the unit be placed in a Mode in which the LCO does not apply. Required Achons were relaxed to allow 30 minutes to restore cofii,A=n.= with the LCO by removing power from the valve operators.
specified isolation valve within 72 hours.-
l 3.4 L7 The completion time for restoring an RCS pressure isolation valve (PlV) to within its 3'.4.14 Action A-3.4 6.2 Action c IV leakage limit was relaxed from 4 hours to indefinitely provided the compensatory.
,                        3.4 L8                   Not used.                                                                                                                                                                                                                           ;
[
i                                                                                                                                                                                                                                                                                       ,
Actions are taken to isolate the high pressure porten of the affected system from the i
3.4 L9                   The CTS req airement to maintain both hot and cold legs isolation valves closed until                                                         3.4.18 Action B                           3.4.1.5.2 Actions           lil           ,
Iow pressure porten with a specified isolation valve within 4 hours and with a second specified isolation valve within 72 hours.-
the isolated loop's cold leg temperature is within limits was reforrmhed and rela- '5                                                                                                                                               [
[
;                                                  require closure of only the cold leg isolation valve since this adequately prevem                                                                                                                                                     !
3.4 L8 Not used.
cold water reactivity event.                                                                                                                                                                                                          .
i 3.4 L9 The CTS req airement to maintain both hot and cold legs isolation valves closed until 3.4.18 Action B 3.4.1.5.2 Actions lil the isolated loop's cold leg temperature is within limits was reforrmhed and rela-
i 3.4 L10                 An allowance was added so that the surveillance to perform a Channel Operational -                                                             SR 3.4.12.7                               4.4 9.3.1.a                 VI
'5
,                                                  Test on each pressurizer power operated relief valve (PORV) actuaten chaNel need not be performed until 12 hours after entering the Modes (4) of appk in,ility from Mode
[
: 3.                                                                                                                                                                                                                                   i i
require closure of only the cold leg isolation valve since this adequately prevem cold water reactivity event.
Less Restrictive Change Categores                                                                                                                                                                                                                                     i 1         Relaxation of LCO requirements                                                                         V     Relaxation of SR acceptance enteria                                                                                                           i il Relaxation of Applicatnisty                                                                                     VI   Relaxation of Survenance Frequency til Relaxation of Action requirements                                                                             VII Deletion of requirements redundant to regulation                                                                                               k j                 IV Relaration of completion time                                                                                   Vitt Deletion of Surveillance requirements (By) - Byron specific i                (Bw) - Braidwood specific                                                                                                                                                                                                                                             i Byron and Braidwood                                                                                                                                     2                                                                                           L_TBL3 4 . l
i 3.4 L10 An allowance was added so that the surveillance to perform a Channel Operational -
                                                                                                                                                                                                                                                                                      . t, 1m   2 m._ ____        ...__.-__.__._._.__________________..___-____-__.__m_________m.__m___._                                            _ _ _ _      _      ._.___________________________.m__.__.._
SR 3.4.12.7 4.4 9.3.1.a VI Test on each pressurizer power operated relief valve (PORV) actuaten chaNel need
[
not be performed until 12 hours after entering the Modes (4) of appk in,ility from Mode 3.
i 5
i Less Restrictive Change Categores i
1 Relaxation of LCO requirements V
Relaxation of SR acceptance enteria i
il Relaxation of Applicatnisty VI Relaxation of Survenance Frequency til Relaxation of Action requirements VII Deletion of requirements redundant to regulation k
j IV Relaration of completion time Vitt Deletion of Surveillance requirements
{
i (By) - Byron specific
[
(Bw) - Braidwood specific i
i l
Byron and Braidwood 2
L_TBL3 4. l l
. t 1m 2
m.
m m.
m
.m


            ,a                                                                                                                                                                                \
d D(~
d                                                                                                                 D(~                                                           }
}
Table L - Less Restrictive Changes to CTS Discussion .                                                               Description                                                                 ~ ITS -             CTS         Change of Change                                                                     of Change                                                             Requirement -     Requirement     : Category 3.4 L11               The completion time for reducing power to < 5% RTP when any Departure from -                                                 3.4.1 Action B -   3.2.5 Actions           IV Nucleate Boiling (DNB) parameter limit is exceeded was relaxed from 4 hours to 6 hours to allow for an orderly power reduction to M ade 2.
,a
3.4 L12               CTS 3.0.3 requires that, with only one RCS loop in operation and the RTBs in the                                             3.4.5 Action C     3.4.1.2 Actions .       til closed position (Rod Control System capable of rod withdrawal) and if the Action to                                                             b and c,             ,
\\
open the RTBs is not completed within the required time, the unit be placed in a Mode                                                             3.0.3 (4) in which the LCO does not apply. _ Required Actions were relaxed to allow continued operation in Mode 3 provided three compensatory Actions are taken immedetely.
Table L - Less Restrictive Changes to CTS Discussion.
3.4 L13               Not used.
Description
. 3.4 L14               The frequency for determining the boron concentration of an isolated loop to be                                               SR 3.4.18.2       4.4.1.5.2.2             VI greater than the boron concentration of the operating loops prior to opening the valves c                           of the isolated loop was re! axed from 2 hours to 4 hours to allow adequate time to sample and confirm the analysis results.
~ ITS -
3.4 L15               An exception was included to relax the surveillance requirement that RCS PlV leakage                                         SR 3.4.14.1 -     4.4.6.2.2               VI be venfied whenever the valves are actuated. A note allows PlVs actuated during                                               Note 2 surveillance testing need not be tested more than once if a repetitive testing loop cannot be avoided                                                                                                                             ,
CTS Change of Change of Change Requirement -
ess Restrictive Change Categories I     Relaxation of LCO requirements                       V     Relaxation of SR acceptance enteria                                                                                                   ,
Requirement
ll   Relaxation of App:,c.t,J4                             VI     Relaxatton of Surveillance Frequency lli Relaxaten of Action requirements                         Vil Deletion of requirements redundant to regulation IV Relaxation of completon time                             Vill Deletion of Surveillance requirements i
: Category 3.4 L11 The completion time for reducing power to < 5% RTP when any Departure from -
(By)- Byron specirac                                                                                                                                                                                       '
3.4.1 Action B -
(Bw)- Braidwood specific                                                                                                                                                                                   ,
3.2.5 Actions IV Nucleate Boiling (DNB) parameter limit is exceeded was relaxed from 4 hours to 6 hours to allow for an orderly power reduction to M ade 2.
Byron and Braidwood                                                                                                           3                                                                 L_TBL3 4
3.4 L12 CTS 3.0.3 requires that, with only one RCS loop in operation and the RTBs in the 3.4.5 Action C 3.4.1.2 Actions.
til closed position (Rod Control System capable of rod withdrawal) and if the Action to b and c, open the RTBs is not completed within the required time, the unit be placed in a Mode 3.0.3 (4) in which the LCO does not apply. _ Required Actions were relaxed to allow continued operation in Mode 3 provided three compensatory Actions are taken immedetely.
3.4 L13 Not used.
3.4 L14 The frequency for determining the boron concentration of an isolated loop to be SR 3.4.18.2 4.4.1.5.2.2 VI greater than the boron concentration of the operating loops prior to opening the valves c
of the isolated loop was re! axed from 2 hours to 4 hours to allow adequate time to sample and confirm the analysis results.
3.4 L15 An exception was included to relax the surveillance requirement that RCS PlV leakage SR 3.4.14.1 -
4.4.6.2.2 VI be venfied whenever the valves are actuated. A note allows PlVs actuated during Note 2 surveillance testing need not be tested more than once if a repetitive testing loop cannot be avoided ess Restrictive Change Categories I
Relaxation of LCO requirements V
Relaxation of SR acceptance enteria ll Relaxation of App:,c.t,J4 VI Relaxatton of Surveillance Frequency j
lli Relaxaten of Action requirements Vil Deletion of requirements redundant to regulation IV Relaxation of completon time Vill Deletion of Surveillance requirements i
(By)- Byron specirac (Bw)- Braidwood specific 4
Byron and Braidwood 3
L_TBL3 4 i


n                                                                                                                                         .
n L)
L)                                                                                 J.                                                       ~G Table L - Less Restrictive Chang- + e C iS -
J.
Discussion                                                   Description                                           ITS .           CTS '-         Change.
~G Table L - Less Restrictive Chang- + e C iS -
of Change                                                     of Change                                       Requirement     Requirement     Category 3.4 L16             An exception was included to relax the requirement that a maximum of one centrifugal     3.4.12 Action A LCO 3.5.3.a             1V charging pump may be capable of injection. A note was included in the LCO to allow       Note -
Discussion Description ITS.
CTS '-
Change.
of Change of Change Requirement Requirement Category 3.4 L16 An exception was included to relax the requirement that a maximum of one centrifugal 3.4.12 Action A LCO 3.5.3.a 1V charging pump may be capable of injection. A note was included in the LCO to allow Note -
two pumps capable of injecting into the RCS for s 15 minutes during pump swap ooerations.
two pumps capable of injecting into the RCS for s 15 minutes during pump swap ooerations.
3.4 L17 '           Because of the availability of diverse methods of RCS leakage detection, the             LCO 3 4.15     Table 3.3-6             1V requirement that both containment atmosphere gaseous and particulate radiation           - SR 3.4.15.1,   items 3 and 4, monitors be Operable was relaxed so that only one of the containment atmosphere           SR 3.4.15.2     LCO 3.4 6.1, radioactivity monitors is required Operable.                                             SR 3.4.15 4     4 4 6.1.a 3.4 - L18           The minimum boron concentration to which an isolated loop must be charged prior to       LCO 3.4.18 a,   LCO 3.4.15.2.a.         I, V unisolating it was changed ftom the concentration of the operating loops to that         3R 3.4.18.2     4.4.1.5.2.2 required by shutdown margin (SDM) calculation. This change allows an isolated loop to be unisolated even if the boron concentration of the isolated loop is less than the operating loops as provided the isolated loop concentration meets the applicable SDM requirements.
3.4 L17 '
3.4 L19             With both the containment atmosphere gaseous and particulate radiation monitors           3.4.15 Action B 3.4.6.1 Actions       til, IV inoperable. CTS requires the restoration of one of the monitors within 72 hours. In                       c 1 and c.2 addition, both an RCS inventory balance and grab samples of containr.ient ntmosphere are periodically required as compensatory Actions. These Actions were relaxed to require restoration of one of the monitors within 30 days and performance of either of the compensatory Actions.
Because of the availability of diverse methods of RCS leakage detection, the LCO 3 4.15 Table 3.3-6 1V requirement that both containment atmosphere gaseous and particulate radiation
Less Restrictive Change Categones i     Relaxation of LCO requirements                   V     Relaxation of SR acceptance criteria il Relaxation of Apphcability                           VI     Relaxation of Surveillance Frequency til Relaxation of Acticn requirements                   VII Deletion of requirernents redundant to regulation IV Relaxation of completion time                       Vill Deletion of Surveillance requirements (By) - Byron speceric (Bw)- Braidwood speciric Byron and Braidwood                           ,
- SR 3.4.15.1, items 3 and 4, monitors be Operable was relaxed so that only one of the containment atmosphere SR 3.4.15.2 LCO 3.4 6.1, radioactivity monitors is required Operable.
4                                                          L_1 BL3.4
SR 3.4.15 4 4 4 6.1.a 3.4 - L18 The minimum boron concentration to which an isolated loop must be charged prior to LCO 3.4.18 a, LCO 3.4.15.2.a.
I, V unisolating it was changed ftom the concentration of the operating loops to that 3R 3.4.18.2 4.4.1.5.2.2 required by shutdown margin (SDM) calculation. This change allows an isolated loop to be unisolated even if the boron concentration of the isolated loop is less than the operating loops as provided the isolated loop concentration meets the applicable SDM requirements.
3.4 L19 With both the containment atmosphere gaseous and particulate radiation monitors 3.4.15 Action B 3.4.6.1 Actions til, IV inoperable. CTS requires the restoration of one of the monitors within 72 hours. In c 1 and c.2 addition, both an RCS inventory balance and grab samples of containr.ient ntmosphere are periodically required as compensatory Actions. These Actions were relaxed to require restoration of one of the monitors within 30 days and performance of either of the compensatory Actions.
Less Restrictive Change Categones i
Relaxation of LCO requirements V
Relaxation of SR acceptance criteria il Relaxation of Apphcability VI Relaxation of Surveillance Frequency til Relaxation of Acticn requirements VII Deletion of requirernents redundant to regulation IV Relaxation of completion time Vill Deletion of Surveillance requirements (By) - Byron speceric (Bw)- Braidwood speciric Byron and Braidwood L_1 BL3.4 4


N                                                                                                                       : /O                                                                                                                                                       f' V                                                                                                                                                         D)
f' N
Table L - Less Restrictive Changes to CTS                                                                                                                                                       I Discussion                                                                                   Description                                                                                                                 ITS                                                           . CTS   Change of Change                                                                                       of Change                                                                                                 Requirement                                                   Requirement .         Category 3.4 L20                       Exceptions were included to relax the requirement that all the monitors of the RCS '                                                                                       3.4.15 Actions                                             3.0.4                         II, til Leakage Detection System must be Operable prior to entering or changing Modes of                                                                                           A and B applicability. These changas allow Mode changes if either the containment sump monitor or either of the containment atmosphere radioactivity monitors are inoperable provided that the required compensatory Actions are performed daily.
: /O V
3.4 L21                     With the containment sump flow monitor inoperable, the requirement to restore the                                                                                           3.4.15 Required                                           3.4.6.1 Action b             ' Vi monitor to Operable status within 7. days was relaxed to allow 30 days for restoration                                                                                       Action A.2 provided the compensatory Action to perform a water inventory balance is performed                                                                                                                                                                                             l daily.
D)
3.4 L22                     The interval for performing an RCS water inventory balance was relaxed from once                                                                                             3.4.15 Required                                           3.4.6.1 Action                 IV per 8 hours to once per 24 hours considering the availability of diverse methods of                                                                                         Actions A.1 and                                           c.3 detecting RCS leakage.                                                                                                                                                       B.1.2                                                                                             ;
Table L - Less Restrictive Changes to CTS I
3.4 L23                     CTS 3.0.3 requires that, with two required RCS loops inoperable, the unit be placed in                                                                                       3.4.5 Action F                                             3.0.3                           Ill a Mode (4) in which the LCO does not apply. An explicit condition was included to                                                                                                                                                                                             ,
Discussion Description ITS
allow continued operation in Mode 3 provided three compensatory Actions are taken immediately.
. CTS Change of Change of Change Requirement Requirement.
3.4 L24                     The surveillance to perform an RCS water inventory balance once per 72 hours was                                                                                             SR 3.4.131,                                               4 4 6.2.1.d.                   .VI modified to allow its initial performance 12 hours after establishment of steady state                                                                                       3.4.15 Required                                           3 4 6.1 Action operation rather than requiring the surveillance to be met prior to entering this power                                                                                     Actions A.1 and                                             c.3 condition. Actions requiring the periodic performance of this surveillance were also                                                                                         B.1.2 provided with this allowance for their initial performance.
Category 3.4 L20 Exceptions were included to relax the requirement that all the monitors of the RCS '
Less Restnctive Change Categories I     Relaxation of LCO requirements                                     V     Relaxation of SR acceptance criteria f
3.4.15 Actions 3.0.4 II, til Leakage Detection System must be Operable prior to entering or changing Modes of A and B applicability. These changas allow Mode changes if either the containment sump monitor or either of the containment atmosphere radioactivity monitors are inoperable provided that the required compensatory Actions are performed daily.
11   Relaxation of Applicabihty                                         VI     Relaxation of Surveillance Frequency                                                                                                                                                                                           i Ill Relaxation of Action requirements                                   Vil Deletion of requirements redundant to regulation                                                                                                                                                                                   >
3.4 L21 With the containment sump flow monitor inoperable, the requirement to restore the 3.4.15 Required 3.4.6.1 Action b
IV Relaxation of completion time                                         Vill Deletion of Surveillance requirements                                                                                                                                                                                             >
' Vi monitor to Operable status within 7. days was relaxed to allow 30 days for restoration Action A.2 provided the compensatory Action to perform a water inventory balance is performed l
(By) - Byron spectre (Bw)- Braidwood specife Byron and Braidwood                                                                                                                       5                                                                                                                                                         L_~IBL3 4 i r
daily.
__________-___-m_____________m__-__                            _ - _ _ . _ _ _ _ _ _ _ _      ___+.__r. _
3.4 L22 The interval for performing an RCS water inventory balance was relaxed from once 3.4.15 Required 3.4.6.1 Action IV per 8 hours to once per 24 hours considering the availability of diverse methods of Actions A.1 and c.3 detecting RCS leakage.
B.1.2 3.4 L23 CTS 3.0.3 requires that, with two required RCS loops inoperable, the unit be placed in 3.4.5 Action F 3.0.3 Ill a Mode (4) in which the LCO does not apply. An explicit condition was included to allow continued operation in Mode 3 provided three compensatory Actions are taken immediately.
3.4 L24 The surveillance to perform an RCS water inventory balance once per 72 hours was SR 3.4.131, 4 4 6.2.1.d.
.VI modified to allow its initial performance 12 hours after establishment of steady state 3.4.15 Required 3 4 6.1 Action operation rather than requiring the surveillance to be met prior to entering this power Actions A.1 and c.3 condition. Actions requiring the periodic performance of this surveillance were also B.1.2 provided with this allowance for their initial performance.
Less Restnctive Change Categories f
I Relaxation of LCO requirements V
Relaxation of SR acceptance criteria 11 Relaxation of Applicabihty VI Relaxation of Surveillance Frequency i
Ill Relaxation of Action requirements Vil Deletion of requirements redundant to regulation IV Relaxation of completion time Vill Deletion of Surveillance requirements (By) - Byron spectre (Bw)- Braidwood specife Byron and Braidwood 5
L_~IBL3 4 i
r
-m m
+.
r.


(j _
f~.
f~.
(j _                                                                                                                                          O                                                                                                           V Table L - Less Restrictive Changes to CTS Discussion                                                                                                                 Description                                                                             ITS                                 CTS                 Change of Change                                                                                                                 of Change                                                               Requirement                                 Requirement               Category 3.4 L25               CTS imposes a maximum leakage rate of 1.0 gpm (notwithstanding the provisions for                                                                                         SR 3.4.14.1                                   LCO 3.4.6.2.f.                 V RHR suction motor operated valves in Table 3.4-1) from any RCS PlV. A more                                                                                                                                               Table 3.4-1 meaningfullimitation based on valve size was used to prevent unwarranted repair on                                                                                                                                       Notes larger valves.
O V
3.4 L26               With the pressurizer otherwise inoperable (water level not within limit), the Action                                                                                       3.4.9 Action A                                 3 4 3 Action b                 111 requirements were revised to place the unit in Mode 3 with all rods fully inserted and                                                                                                                                                                                           i the Rod Control System incapable of rod withdrawal rather than Mode 3 with the RTBs open since methods other than opening the RTBs are available for preventing an inadvertent rod withdrawal.                                                                                                                                                                                                                                                     '
Table L - Less Restrictive Changes to CTS Discussion Description ITS CTS Change of Change of Change Requirement Requirement Category 3.4 L25 CTS imposes a maximum leakage rate of 1.0 gpm (notwithstanding the provisions for SR 3.4.14.1 LCO 3.4.6.2.f.
3.4 L27               The 18 month surveillance to operate the PORVs through a complete cycle of travel                                                                                       .
V RHR suction motor operated valves in Table 3.4-1) from any RCS PlV. A more Table 3.4-1 meaningfullimitation based on valve size was used to prevent unwarranted repair on Notes larger valves.
SR 3.4.11.2                                   4 4.4.1.c                     VI was revised to eliminate the explicit requirement to perform the ter' in Mode 3 or 4 and                                                                                   Note requires, instead, the surveillance to be " current' upon entering Modes 1 and 2. STS SR 3.0.4 and Generic Letter 90-06 continue to require its performance in Mode 3 or 4.
3.4 L26 With the pressurizer otherwise inoperable (water level not within limit), the Action 3.4.9 Action A 3 4 3 Action b 111 requirements were revised to place the unit in Mode 3 with all rods fully inserted and i
3.4 L28                 The default Action to reduce the RCS temperature and pressure to < 200'F and                                                                                               3.4.3 Action B                                 3 4.9.1 Actions               ill
the Rod Control System incapable of rod withdrawal rather than Mode 3 with the RTBs open since methods other than opening the RTBs are available for preventing an inadvertent rod withdrawal.
                          < 500 psig, respectively, when any RCS temperature or pressure limit is not restored within 30 minutes was relaxed to place the unit in Mode 5. The temperature in this Mode is equivalent but pressure may exceed 500 psig.
3.4 L27 The 18 month surveillance to operate the PORVs through a complete cycle of travel SR 3.4.11.2 4 4.4.1.c VI was revised to eliminate the explicit requirement to perform the ter' in Mode 3 or 4 and Note requires, instead, the surveillance to be " current' upon entering Modes 1 and 2. STS SR 3.0.4 and Generic Letter 90-06 continue to require its performance in Mode 3 or 4.
3.4 L29                 Not used.
3.4 L28 The default Action to reduce the RCS temperature and pressure to < 200'F and 3.4.3 Action B 3 4.9.1 Actions ill
Less Restrictive Change Categories 1     Relaxation of LCO requirements                                                             V                         Relaxation of SR acceptance criteria 11 Relaxation of Applicability                                                                   VI                         Relaxation of Surveillance Frequency 111 Relaxation of Action requirements                                                           Vil Deletion of requirements redundant to regulation IV Relaxation of completion time                                                                 Vill Deletion of Surveillance requirements (By) - Byron snecific (Bw) - Braidwood speoric Byron and Braidwood                                                                                                                                         6                                                                                                                   L_T BL3.4
< 500 psig, respectively, when any RCS temperature or pressure limit is not restored within 30 minutes was relaxed to place the unit in Mode 5. The temperature in this Mode is equivalent but pressure may exceed 500 psig.
3.4 L29 Not used.
[
Less Restrictive Change Categories 1
Relaxation of LCO requirements V
Relaxation of SR acceptance criteria 11 Relaxation of Applicability VI Relaxation of Surveillance Frequency 111 Relaxation of Action requirements Vil Deletion of requirements redundant to regulation IV Relaxation of completion time Vill Deletion of Surveillance requirements (By) - Byron snecific (Bw) - Braidwood speoric Byron and Braidwood 6
L_T BL3.4


_    .. _ _          ,      <                                                                                        .                  _    >    _m   . -          -.    . _ ..              .            .        . .-. . ~ ..                .
_m
r                                                                                                                                                     ;O;                                                                       O Table L - Less Restrictive Changes to CTS
..-.. ~..
                                                                                                                                                                                                                                                                -i
r
        ~ Discussion                                                                                                                       Description                                                         ITS '           . CTS           . Change
;O; O
        - of Change                                                                                                                         of Change                                                     . Requirement     Rg-i...;nt '       Category 3.4 L30               The applicability has been revised to delete the requirements to comply'with the LCO                                                                                       3.4.16             3/4.4.8,                 11. Ill     !
Table L - Less Restrictive Changes to CTS
and Actions and to penodically verify the RCS specific activity within limits during Table 4.4                             Mode 3 with RCS temperature < 500*F and Modes 4 and 5 due to the unlikely possibility of a steam generator tube rupture during these Modes Similarly, the sampling and analysis requirements when the specific activity of the reactor coolant l
- i
exceeds 100/E Ci/ gram were deleted since exceeding this limit now requires promptly
~ Discussion Description ITS '
,                            placing the unit in a Mode in which the specific activity limits do not apply.
. CTS
. Change
- of Change of Change
. Requirement Rg-i...;nt '
Category 3.4 L30 The applicability has been revised to delete the requirements to comply'with the LCO 3.4.16 3/4.4.8,
: 11. Ill and Actions and to penodically verify the RCS specific activity within limits during Table 4.4 '
Mode 3 with RCS temperature < 500*F and Modes 4 and 5 due to the unlikely possibility of a steam generator tube rupture during these Modes Similarly, the sampling and analysis requirements when the specific activity of the reactor coolant l
exceeds 100/E Ci/ gram were deleted since exceeding this limit now requires promptly placing the unit in a Mode in which the specific activity limits do not apply.
~
~
3.4 L31               Not used:
3.4 L31 Not used:
3.4 L32               An exception was included to relax the requirement that the Dose Equivalent 1-131                                                                                         3.4.16 Action A   3.0.4                   II,111 specific activity must be within limits prior to entering or changing Modes of applicability. This change allows entry into the applicable Modes while relying on the                                                                                                                                             ,
3.4 L32 An exception was included to relax the requirement that the Dose Equivalent 1-131 3.4.16 Action A 3.0.4 II,111 specific activity must be within limits prior to entering or changing Modes of applicability. This change allows entry into the applicable Modes while relying on the required Actions even though the Actions may eventually require exiting the manhc=Na Modes if the limits are not restored within specified times.
required Actions even though the Actions may eventually require exiting the manhc=Na                                                                                                                                               ;
3.4 L33 Not used.
Modes if the limits are not restored within specified times.
3.4. L34 The frequency interval for verifying the reactor coolant gross specific activity is within SR 3.4.16.1 4.4 8 VI limits was relaxed from 72 hoters to 7 days because this interval is adequate to trend Table 4.4-4 I
3.4 L33               Not used.
this parameter.
3.4 . L34             The frequency interval for verifying the reactor coolant gross specific activity is within                                                                               SR 3.4.16.1         4.4 8                     VI         ,
Item 1
limits was relaxed from 72 hoters to 7 days because this interval is adequate to trend                                                                                                       Table 4.4-4 this parameter.                                                                                                                                                                               Item 1 I
{
I f
t t
t t
Less Restnctive Change Categones I     Relaxation of LCO requirernents                                                                                       V     Relaxation of SR acceptance enteria                                                                                     ;
Less Restnctive Change Categones I
,  il Relaxation of Applicability                                                                                               VI     Relaxation of Surveillance Frequency                                                                                     !
Relaxation of LCO requirernents V
111 Relaxation of Actum requirements                                                                                         Vil Deletion of requirements redundant to regulation                                                                           [
Relaxation of SR acceptance enteria il Relaxation of Applicability VI Relaxation of Surveillance Frequency 111 Relaxation of Actum requirements Vil Deletion of requirements redundant to regulation
IV Relaxation of completion time                                                                                             Vill Deleton of Surveillance requirements (By) - Byron specific                                                                                                                                                                                                                                       I (Bw) - Braidwood specific                                                                                                                                                                                                                                     '
[
i Byron and Braidwood                                                                                                                                                 7                                                                         L T BL3 4     i t
IV Relaxation of completion time Vill Deleton of Surveillance requirements (By) - Byron specific I
i t
(Bw) - Braidwood specific i
v
Byron and Braidwood 7
L T BL3 4 i
t i
t v


V-                                                                                                                                                                                                                                                   C                                                                                               U Table L - Less Restrictive Changes to CTS Discussion                                                                                                       Description                                                                                                                                                 ITS                                           OTS._                           Change of Change                                                                                                         of Change                                                                                                                                               Requirement                 Requirement                                             Category 3.4 L35                                                                 The exception to CTS Specification 4.0.3 was eliminated for the surveillance to                                                                                                                   SR 3.4.1.4,                 4.2.3.5                                                       VI determine the RCS total flow rate by precision heat balance after each fuel loading.                                                                                                             SR 3.0.3 This change relaxes the frequency to allow the missed surveillance to be performed in the 24 hour delay period.
V-C U
3.4 L36                                                                 Whenever an RCS operating loop temperature is not within limit, the Action to place                                                                                                               3.4.2 Action A             3.1.14 Actions                                             , lil, IV the unit in Mode 3 was relaxed to place the unit in Mode 2 with k ,, < 1.0 to be consistent with the Applicability. Also the time specified for completing this Action was relaxed from 15 minutes to 30 minutes to allow for an orderly unit shutdown.
Table L - Less Restrictive Changes to CTS Discussion Description ITS OTS._
3.4 L37                                                                 An exception was taken to the LCO requirement that at least one Residual Heat                                                                                                                     LCO 3.4.7                   LCO 3 41.41                                                     i Removal (RHR) loop shall be in operation in Mode 5 with loops filled. The exception                                                                                                               Note 4 allows all RHR loops to be removed from operation during the transition from Mode 5 to Mode 4 when at least one RCS loop is in operation. This change provides equivalent RCS circulation for mitigation of a boron dilution event and an orderly heatup transition to the next Mode.
Change of Change of Change Requirement Requirement Category 3.4 L35 The exception to CTS Specification 4.0.3 was eliminated for the surveillance to SR 3.4.1.4, 4.2.3.5 VI determine the RCS total flow rate by precision heat balance after each fuel loading.
3.4 L38                                                                 The requirements for pressurizer safety valves was relaxed to allow entry into the                                                                                                                 LCO 3.4.10 Note             LCO 3 4.2 2                                                 I, VI Mode of applicability without the lift settings having been verified within limits in order to set them at nominal operating temperature and pressure. 54 hours following entry into Mode 3 is allowed for this adjustment provided the valves have had a preliminary cold setting.
SR 3.0.3 This change relaxes the frequency to allow the missed surveillance to be performed in the 24 hour delay period.
i Less Restrir%e Change Categories 1     Relaxation of LCO requirernents                                                                     V     Relaxation of SR acceptance criteria 11 Retaxation of Appicability                                                                               VI     Relaxation of Surveillance f requency                                                                                                                                                                                                                                     ,
3.4 L36 Whenever an RCS operating loop temperature is not within limit, the Action to place 3.4.2 Action A 3.1.14 Actions
Ill Relaxation of Acton requirernents                                                                       VII Deleton of requirements redundant to regulation                                                                                                                                                                                                                             "
, lil, IV the unit in Mode 3 was relaxed to place the unit in Mode 2 with k,, < 1.0 to be consistent with the Applicability. Also the time specified for completing this Action was relaxed from 15 minutes to 30 minutes to allow for an orderly unit shutdown.
IV Relaxation of completion tune                                                                           Vill Deleton of Surveillance requirements (By)- Byron specifec (Bw) - Braufwood specific Byron and Braidwood                                                                                                                                                                                                                                               8                                                                                                 L_1BL3 4
3.4 L37 An exception was taken to the LCO requirement that at least one Residual Heat LCO 3.4.7 LCO 3 41.41 i
Removal (RHR) loop shall be in operation in Mode 5 with loops filled. The exception Note 4 allows all RHR loops to be removed from operation during the transition from Mode 5 to Mode 4 when at least one RCS loop is in operation. This change provides equivalent RCS circulation for mitigation of a boron dilution event and an orderly heatup transition to the next Mode.
3.4 L38 The requirements for pressurizer safety valves was relaxed to allow entry into the LCO 3.4.10 Note LCO 3 4.2 2 I, VI Mode of applicability without the lift settings having been verified within limits in order to set them at nominal operating temperature and pressure. 54 hours following entry into Mode 3 is allowed for this adjustment provided the valves have had a preliminary cold setting.
i Less Restrir%e Change Categories 1
Relaxation of LCO requirernents V
Relaxation of SR acceptance criteria 11 Retaxation of Appicability VI Relaxation of Surveillance f requency Ill Relaxation of Acton requirernents VII Deleton of requirements redundant to regulation IV Relaxation of completion tune Vill Deleton of Surveillance requirements (By)- Byron specifec (Bw) - Braufwood specific Byron and Braidwood 8
L_1BL3 4


j-~)Q d
q:
q:
                  - s,f                                                                                           j-~)Q
- s,f
(_                                                                                                               d Table L - Less Restrictive Changes to CTS ~
(_
Discussion -                                                           Description                                                                         ' ITS                     CTS-                             Change of Change                                                               of Change                                                                   Requirement     Requirement                                     . Category 3.4 L39                       The Modes in which sampling and analysis of reactor coolant for isotopic lodine is                           SR 3.4.16.2             Table 4.44                                                 VI' required to be performed following power level changes > 15% RTP within a 1 hour.                                                     Items 2 and 4.b period was relaxed from Modes 1,2, and 3 to Mode 1 where fuel failure is more apt to occur and where RTP changes of this magnitude are of concem.                                                                                                                                              .
Table L - Less Restrictive Changes to CTS ~
i f
Discussion -
I e
Description
L l
' ITS CTS-Change of Change of Change Requirement Requirement
                                                                        ~
. Category 3.4 L39 The Modes in which sampling and analysis of reactor coolant for isotopic lodine is SR 3.4.16.2 Table 4.44 VI' required to be performed following power level changes > 15% RTP within a 1 hour.
b Less Restrictive Change Categories                                                                                                                                                                                                           [
Items 2 and 4.b period was relaxed from Modes 1,2, and 3 to Mode 1 where fuel failure is more apt to occur and where RTP changes of this magnitude are of concem.
t     Relaxation of LCO requirements                             V     Relaxation of SR acceptance crites.a                                                                                                                                 l 11 Relaxation of Apphcabitity                                   VI     Relaxation of Surveillance Frequency ill Relaxatsn of Action requirements                             V11 Deletion of requirements redundant to regulatoon IV Relaxation of completion time                               - Vill Deletion of Surveillance requwements
i C
f I
e L
[
l
~
e b
Less Restrictive Change Categories
[
t Relaxation of LCO requirements V
Relaxation of SR acceptance crites.a l
11 Relaxation of Apphcabitity VI Relaxation of Surveillance Frequency ill Relaxatsn of Action requirements V11 Deletion of requirements redundant to regulatoon IV Relaxation of completion time
- Vill Deletion of Surveillance requwements
[
[
f (By)- Byron speofc (Bw)- Braidwood specific                                                                                                                                                                                                                   -}
f (By)- Byron speofc (Bw)- Braidwood specific
Byron and Braidwood                                                                                         9                                                         .
-}
I _1 BL3 4 l L
Byron and Braidwood 9
I _1 BL3 4 l
L


ENCLOSURE 1 l                                 ITS REVISION K ITS SECTION 3.4 i
ENCLOSURE 1 l
ITS REVISION K ITS SECTION 3.4 i
O l0
O l0


3.4 Q BYRON ITS i
3.4 Q
BYRON ITS i
J 4
J 4
I l
I l

Latest revision as of 23:54, 10 December 2024

Forwards Revs K,O & P to 961213 ITS Submittal.Rev K Contains Final Package Closeout for ITS Section 3.4,rev O Is Cleanup Package for ITS Sections 1.0/3.0/3.1/3.9/4.0 & Rev P Contains Final Package Closeout for ITS Section 3.3
ML20154M507
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 10/15/1998
From: Tulon T
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20154M512 List:
References
NUDOCS 9810200320
Download: ML20154M507 (96)
v • d • e


Text

. _.. _

_ _ ~ -

r-Commonwealth Ediwn Company Braidwood Generating station -

g

' 41 4 Route *I, Box 84

' Braceville,IL 60407-9619 Tel 815-458-2801 j_.

- (_,)-

e October 15,1998 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 - 0001

Subject:

Revision K, Revision 0, and Revision P to the Improved Technical Specifications (ITS) Submittal T!

Byron Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Docket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-72 and NPF-77 p

NRC Docket Numbers: 50-456 and 50-457 v

Reference:

G. Stanley and K. Graesser (Commonwealth Edison) letter to NRC Document Control Desk, " Conversion to the Improved Standard Technical Specifications," dated December 13,1996 The purpose of this letter is to provide Revisions K,0, and P to the referenced ITS submittal. ITS Revision K contains Commonwealth Edison's (Comed's) final Package g

Closeout for ITS Section 3.4. ITS Revision O is a cleanup package for ITS Sections 1.0/3.0/3.1/3.9/4.0. ITS Revision P contains Comed's final Package Closcout for ITS

/

Section 3.3.

' contains ITS Revision K. Enclosure 2 contains ITS Revision O. Enclosure 3 contains ITS Revision P.

OO w..73 Y.

r[-

.p

(

x)

O 9810200320 981015 Y

PDR ADOCK 05000454 L P-PDR

}

. i A Unicom Company

fx Document Control Desk t/

October 15,1998 Page 2 -

These Revisions are being provided in the same ten-section format as the initial ITS submittal-

1. Byron ITS
2. Braidwood(Brwd)ITS
3. Byron CTS Markups
4. Brwd CTS Markups
5. CTS Discussion of Changes (DOCS)
6. LCO Markups
7. LCO Justification for Differences (JFDs)
8. Bases Markups
9. Bases JFDs
10. No Significant Hazards Consideration (NSHC)

Please address any comments or questions regarding this matter to our Nuclear I icensing Department.

y3-

!J -

Sincerely, T'.othy J. Tulon te Vice President Braidwood Nuclear Generating Station

. : ITS Revision K : ITS Revision 0 : ITS Revision P cc:

NRC Regional Administrator-RegionIII Senior Resident Inspector - Braidwood Senior Resident Inspector-Byron Office of Nuclear Facility Safety -IDNS l'

i r~N

,(

l'

un

..n w

a-.-a,

.aa-.-~.-

,, m a ans a

>x

..ea.~_

w - r. -ns..a

+.t..e.,

.s s e.s..

..x

.m.sa-...

.-.._,..n.._.

2

- ATTACHMENT 1 ITS SECTION 3.4 RAI REVISED RESPONSES 4

0 1

1 I

O

_..

== = - - - -

R sponse to-NRC RAI For ITS S:ction 3.4 09-Oct-98 l

NRC RAI Number NRC issued Date RAI Status j

i. I i

,, ~ _

3.4.1-01 3/9'98 Closed

= (

NRC Description ofissue DOCS L4 and Lil CTS 3/4.2.3 Action a.2 CTS 3/4.2.5 Action ITS 3.4.1 Action B DOC L4 is written tojustify the same change made to both CTS 3/4.2.3 Action a.2 and CTS 3.2.5 Actions. CTS 3.2.3 Action a.2 requires the reduction of THERMAL POWER to < 50% RTP and the reduction of the Power Range Neutron Flus-High Trip Setpoint to 55% RTP within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when RCS total flow is not within limit. CTS 3.2.5 Action requires the DNB related parameters restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or to reduce THERMAL POWER to less than 5% of RATED THERMAL

{

POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Both CTS Actions and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit are changed to be ITS 3.4.1 Condition B which i

specifies a Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to reach Mcde 2. DOC Lil is written tojustify the same change but only to CTS 3.2.5 Actions. Comment: It is recommended that L4 justify Action 3.2.3 only and Li 1 continue tojustify Action 3.2.5 which would not require revision of the CTS markup.

Comed Response to issue Comed will revise DOC 3.4-L4 to onlyjustify CTS Action 3.2.3.a.2. DOC 3.4-L4 will be revised to state. " CTS Action 3.2.3.a.2 requires that when the RCS flowrate is outside the region of acceptable operation. within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> reduce THERMAL POWER... within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. NUREG LCO 3.4.1, Condition A states that with one of the DNB parameters not within limits, a Completion Time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is provided to restore the parameter to within limits. In the es ent that Condition A is not met, Condition B requires the plant be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ITS revises the CTS Completion Time from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and therefore is considered a Less Restrictive change. Using the general rules of applicability, the unit must be placed in a Mode of non-applicability, whic' in this case is Mode 2. Reaching MODE 2 in 6 n

hours is consistent with other LCOs that require the plant to be placed in MODE 2 from MODE 1. Therefore, the Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable to reach the required unit conditions in an orderly manner." DOC 3.4-LI 1 will be

]

revised to state. " CTS Action 3.2.5 states that with any of the DNB related parameters exceeding its limit, restore the

{Q parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or reduce THERMAL POWER to less than 5% of RTP within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l NUREG LCO 3.4.1, Condition A states that with one of the DNB parameters not within limits, a Completion Time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is provided to restore the parameter to within limits. In the event that Condition A is not met. Condition B requires the plant be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ITS revises the CTS Completion Time from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and therefore is considered a Less Restrictive change. Using the general rules of applicability, the unit must be placed in a Mode of non-applicability, which in this case is Mode 2. Reaching MODE 2 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is consistent with other LCOs that require the plant to be placed in MODE 2 from MODE 1. Therefore, the Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable to reach the required unit conditions in an orderly manner." These changes will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

l 6

V I

l

= = = = - - -. - - - _. -

Resp::nse to NRC RAI For ITS S2ction 3.4 09-oct-98

.-L.

'~ ^ " ~.

NRC RAI Number NRC issued Date RAI Status g

3.4.1-02 3/9'98 Closed k)'

NRC Description of issue DOC L35 JFD C6 CTS 4.2.3.5 i

CTS 4.2.3.5 requires the determination of RCS total dow rate by a precision heat balance measurement after each fuel loading and states that "The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time provisions of Specification 4.0.3 are not applicable" ITS SR 3.4.1.4 requires a precision heat balance measurement every 18 mor.ths and allows for the provisions ofITS SR 3.0.3 to apply.

DOC L35 as submitted states a precision heat balance measurement will be performed per ITS SR 3.4.1.4. This is acceptable; however, JFD C6 deletes the precision heat balace measurement. Also JFD C6 refers to TSTF 105 which has been rejected. Comment: Revise the submittal to adopt the STS and retain the CTS requirements. Make the justifications for these two CTS changes consistent.

Comed Response to issue Revised Response: Comed withdrew TSTF 105 changes from the ITS submittal and retained "by precision heat balance that" in ITS SR 3.4.1.4. LCO JFD 3.4-C6 and Bases JFD 3.4-C6 were deleted. This change is provided in our comprehensive ITS Section 3.4 closecut submittal Revision K.

Original Response: Comed will withdraw TSTF-105 changes from the ITS submittal and retain "by precision heat balance that" in ITS SR 3.4.1.4. CTS DOC LAIS, LCO JFD C6, and Bases JFD C6 will be deleted. This change will be provided in i

our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

NRC RAI Number NRC lssued Date RAI Status n

3.4.1-03 3/9/98 Closed NRC Description of issue DOC Al.1 CTS 4.2.3.1 CTS 4.2.3.1 states "The provisions of Specification 4.0.4 are not applicable." This CTS requirement is deleted with an editorial AI justification rather than with a specific technicaljustification. Comment Please provide a technical justification for this CTS change.

Comed Response to issue DOC 3.4-A3 discusses the deletion of this statement. The CTS Markup for CTS SR 4.2.3.1 will be revied to reDeet the correct referuce to DOC 3.4 A3 This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

/U 2

Respons2 to NRC RAI For ITS Section 3A 09-Oci-98 NRC RAI Number NRC lssued Date RAI Status l

3.4.1-04 3 9'98 Closed NRC Description ofissue JFD P2 JFD BP2 ITS 3.4.1, Applicability Note The Applicability Note is proposed to be moved to a place following the LCO statement as an editorial enhancement to preclude misinterpretations ofITS SR 3.0.4. This technical basis is unacceptable. This change occurs trequently m this

~

submittal: therefore, this is a generic change and it should be submitted for review under the STS generic change process.

Comment: Revise the submittal to adopt the STS format. The response to this comment should be global over the enttre submittal.

Comed Response to issue No change. Because the relocation of the Note from the Applicability to the LCO has been approved on a plant specific basis for previous submittals (e.g., Ginr.a. Zion, and Vogtle). the WOG determined that this change was below the threshold for a generic change. Therefore, all of the Notes in the Applicability section of the NUREG LCOs have been moved to the LCO section of the ITS LCOs either plant specifically or as a result of a TSTF that was incorporated. The Note applies to exceptions to the ent;re LCO and not to exceptions to the Applicability. Having a Note that modifies the Applicability requirements could imply an exception to the Applicability and thus, could lead to a misinterpretation of SR 3.0.4. Placing the Note in the LCO Section prevents misinterpretation of SR 3.0.4. The following is a list ofITS LCOs in which this convention was adopted. LCOs in which the Note was moved by a plant specific change: 3.1.5,3.1.6.3.3.9,3.4.1,3.4.10, 3.4.12. and 3.9.6 (SR Note moved to LCO); LCOs in which the Note was moved by a TSTF: 3.2.3. 3.5.2. and 3.5.3 (SR Note moved to LCO); LCOs in which the Note was added by a plant specific change: 3.7.12,3.8.5 and 3.9.4; LCOs in which the Note was added by a TSTF: 3.6.3. Comed continues to pursue this change. (See RAls 3.1.5-01,3.1.6-01,3.4.10-03, and'3.4.12-01 item b.)

[

NRC RAI Number NRC lssued Date RAI Status 3.4.1-05 3/9/98 Closed NRC Description of issue JFD BPI Bases discussion of Applicable Safety Analyses, STS page B 3.4-2 in Applicable Safety Analyses, the second and third sentences regarding the DNB design criterion are not adopted. Why not state the plant specific DNB design criterion as the acceptance limit? Also, this is a not an editorial change but a technical change without a specific technicalju::tification. Comment: Revise the Bases to be consistent with the STS.

Comed Response to issue Revised Response: Comed incorporated the plant specific value of 1.5 in the brackets and added Bases JFD 3.4 B3. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.

Original Response: Comed will revise the Bases to be consistent with the STS, incorporating the ' plant specific value of "1.5" in the brackets. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

t

\\)

3

l R:sponse to NRC RAITE ITS S:ction 3.4 09-oct-98 l

--.=_:.--

---==_=.=:- =_ =_

l NRC RAI Number NRC issued Date RAI Status 3.4.1-06 3'9'98 Closed NRC description ofissue JFD BP45 '

Bases discussion of Applicable Safety Analyses. STS page B 3.4-2 In the Applicable Safety Analyses, the second paragraph has been replaced with the insert B3.4 2A. Why do the LCO values l

not match the value assumed in the safety analyses and reported measurement accuracy in the first and the second paragraph. For example, it appears that the pressurizer limit LCO value should be > 2233.7 (2207 - 26.7) with the reported

)

measurement accuracy. Comment: Please revise the text in the insert to clarify the addition of this plant specific text to the Bases.

. Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, Comed added a parenthetical psig reference to 2207 psia and changed 26.7 psia to 26.7 psi. This change is provided in our comprehensive ITS Section 3.4 closeout subminal Resision K.

Original Response: No change. ITS LCO 3.4.1 states. "RCS DNB parameters for pressurizer pressure.. shall be within the limits specified below; a. Pressurizer pressure 2219 psig..." The Applicable Safety Analpes Section of the Bases for ITS j

LCO 3.4.1 states," Safety Analyses assumed a value of 2207 psia. This value is bounded by the LCO value of 2210 psig assuming a measurement accuracy ofless than 26.7 psia." The NRC RAl asked why the pressurizer pressure LCO value did not match the Bases value, stating that the LCO value should be 2233.7 based on using the safety analyses value of 2207 +

26.7. It is true that adding the safety analyses value (2207 psia) to the measurement accuracy ofless than 26.7 psia yielding a total of 2233.7 psia. The pressurizer value in the ITS is 2219 psig. Therefore,2233.7 psia - 14.7 = 2219 psig. Therefore, the LCO value matches the Bases value, and no change is required.

.=.::=_.-=:==-==-

NRC RAI Number NRC issued Date RAI Status 3.4.1-07 3/9/98 Closed p)

'(f NRC Description of Issue JFD BP51 Bases discussion of Actions STS page B 3.4-3 in the Bases discussion of Required Action A.I. all three paragraphs omit portions of the STS text. The deleted text explains the purpose of the Required Actions. JFD PSI states provides no explanation for the these omissions. Comment:

Revise the Bases to confonn to the STS.

Comed Response to issue Comed will revise the Bases to conform to the STS. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

l 4

4

= = = = = = = = _.

. =. = _ - - _ = -

Respons: to NRC RAI For ITS S:ction 3.4 oo-octm 2.

~ _. _ _

NRC RAI Number NRC lisued Date RAI Status 3.4.2-01 3!9/98 Closed y

NRC Description of issue DOJ LA29 DOC M9 JFD C2 (Based on superceded TSTF-27 Rev i ?)

CTS 4.1.1.4.b STS Sk 3 4.2.1 DOC LA29 is not shown on the CTS markup. In addition. the text of LA29 contradicts JFD C2 which is based on TSTF 27 treplaced by Res 2 which is pending). Comment: Withdraw the change to CTS 4.1.1.4.b and adopt STS SR 3.4.2.1.

Comed Response to issue DOC 3.4 M9 will be revised to state. " CTS 4.l.l.4.b requires the verification of the RCS average temperature every 30 minutes when the reactor i; tritical and the Reactor Coolant System Tavg is less than 557 F with the Ta c Tref deviation alarm not reset. The proposed ITS SR 3.4.2.1 requires verification of the RCS average temperature every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. " The CTS Markup will be revised such that DOC 3.4-LA29 refers to the Deviation Alarm, and DOC 3.4-M9 only refers to the "12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />." This is consistent with similar changes in TSTF-27 for ITS LCOs 3.2.3 (CTS SR 4.2.1.1.b) and 3.2.4 (CTS SR 4.2.4.1.b). This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed continues to pursue this change.

NRC RAI Number NRC issued Date RAI Status 3.4.2-02 3/9/98 Closed NRC Description of issue JFD BPI Bases for Applicability ofITS 3.4 't. STS markup pages B 3.4 7 and B 3.4 8 V

The ITS Bases does not adopt the second paragraph of the Bases for the Applicability of STS 3.4.2 based upon an editorial changejustification. This omission, however, is a technical change and has not been adequatelyjustified. Furthermore, this paragraph is applicable to Byron and Braidwood because STS 3.1.10 (equivalent to CTS 3.10.3) is adopted as ITS 3.1.8.

Comment: Revise the Bases to adopt the omitted STS paragraph.

Comed Response to issue Comed will revise the Bases to adopt the omitted STS paragraph. This change will be provided in our comprehensive ITS I

Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

OV l

5

~. -.

Response to NRC.RAI For ITS Ssetion 3.4 09-oct-98 r

=

u-

r = m :-- -

(

NRC RAI Number NRC Issued Date RAI Status 3.4.3-01 3/9/98 Closed NRC Description ofissue DOC Mil CTS 3.4.9.1 Action ITS 3.4.3 Action C CTS 3.4.9.1 Action requires an engineering evaluation to be performed, in accordance with the Applicability of"At all times", whenever the pressure or temperature limits for the RCS have been exceeded; however, there is no explicit time hmit provided to complete this evaluation. If these limits have been exceeded with the unit in a condition other than in Mode 1. 2.

3 or 4 Required Action C.) for ITS 3.4.3 requires action be initiated immediately to restore compliance with the limits for the RCS and Require Action C.2 requires the determination that the RCS is acceptable for continued operation prior to the unit entering Mode 4. The DOC states " CTS 3.4.9.1 does not specify any required action whenever the pressure or tenperature limits for the RCS have been exceeded in a specified condition other than in Mode 1,2,3. or 4. or Mode 5 with RCS pressure 500 psig." This statement ar pears to be in error since the CTS has the same Action regardless of the unit's operating Mode, if the RCS limits are exceeded. Comment: Please revise the submittal with a revised technicaljustification.

Comed Response to issue Comed agrees and will revise DOC Mil to state, " CTS LCO 3.4.9.1 does not specify a completion time for whenever the pressure or temperature limits for the RCS have beer exceeded in a specified condition other than in Mode 1,2,3, or 4 or Mode 5. Condition C for ITS 3.4.3 requires that action be initiated immediately to restore compliance with the pressure and temperature limits for the RCS if these limits have been exceeded with the unit in a condition other than in Mode 1,2,3 or

4. Condition C requires the immediate initiation of action to restore parameters to within limits and the determination that the RCS is acceptable for continued operation prior to the unit entering MODE 4. These requirements are necessary to ensure that the RCPB is retumed to a condition that has been verified by the stress analysis and that the RCPB integrity remains acceptable. This change represents a more restrictive change." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

/\\

NRC RAI Number NRC lssued Date RAI Status 3.4.3-02 3/9/98 Closed NRC Description of issue Bases for ITS SR 3.4.3.1, STS Bases markup page B 3.415 The second paragraph has not been adopted; however, there is nojustification for this deviation from the STS. There is no identity for tracking this JFD change. Comment: Please revise the submittal to provide a technicaljustification for this JFD or adopt the STS.

1 Comed Response to Issue Corr.Ed will revise the submittal to adopt the STS. This change will be provided h our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

V 6

Response to NRC RAI For ITS Section 3.4 09-octas

_ __ c j

NRC RAI Number NRC issued Date RAI Status 3.4.4-01 3'9'98 Closed p)

F(/

NRC Description of issue JFD BP3 Bases for ITS LCO 3.4.4, STS Bases markup pages B 3.4-18 and B 3.4-19

)

1. In the first paragraph, the last sentence is not adopted and the BP3 insert is added. The iurt does state that in addition to all loops in operation that they are also Operable. Secondly. "all" loops need to be stated i, "four" loops are Operable to

. satisfy the movement of this requirement from CTS 3.2.3 to the Bases of 3.4.4 as descrikd in DOC LA 17. Comment:

Revise the Bases as indicated.

b. In the second paragraph, when referring to an Operable SG the phrase "in accor/.ance with the Steam Generator Tube Surveillance Program" is replaced with "providing the necessary heat transfer cap 4bility." These phrases are not techmcally equivalent. This difference is notjustifiable as an editorial enhan tement as indirated by JFD BP3. It is recommended tnat both phrases be used to define an Operable SG rather than one phrase in lieu of the other. Comment: Please resise the submittal to adopt the STS text.

Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be prc vided in our comprehensive ITS Section 3.4 closeodt submittal revision upon NRC's concurrence with the Comed Response i to the ITS Section 3.4 RAl.

NRC RAI Number NRC issued Date RAI Status 3.4.5 3/9/98 Closed NRC Description ofIssue DOC L3 DOC L12 s

'/C}.

DOC L23 JFD P6 JFD BP6 j

ITS 3.4.5 Actions j

CTS 3/4.4.1.2 Actions ITS 3.4.5 and associated Bases are to be revised to separately address the condition of one RCS loop not in operation with the rod control system incapable of rod withdrawal and two RCS loops not in operation with the rod control system capable of rod withdraw. Note: These changes are in addition to an unapproved generic change (TSTF-87 Rev !); and also, these are not plant specific requirements because they are not part of the current licensing basis. This "P" difference is miscategorized under the NEl 96-06 guidelines of Section 2.7, Deviations from the Applicable ISTS. It is a "C" difference. Note that TSTF-87 Revision 2 was approved 10/3/97. Comment: Revise the submittal to adopt Rev 2 to TSTF-87 consistent with plant design.

Note to TSB reviewer: Ffollowing Comed's response and before closing this comment, review the revised Actions ofITS 3.4.5 to ensure consistency with either the CTS or Rev 2 to TSTF-87.

Comed Response to issue Comed wi!I revise LCO and Bases JFDs 3.4-C10 to reference TSTF 87, Revision 2. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI. (See RAI 3.4-01 item 9.) However, Comed continues to pursue the plant specific changes associated with LCO and Bases JFDs 3.4-P6.

G(

~

n e x==,, _... _

_____=-#,--.

g

Response to NRC RAl For ITS Section' 3.4 09 Oct 98 l-N.__.

2_-.

NRC RAI Number NRC lasued Date RAI Status y<

' 3.4.5 02

- 3'9'98 Closed

(

NRC Description of issue l

JFD P1 ll

' JFD T[1 JFD 19?!

l ITS LCO 3,1.5.a and 3.4.5.b 1

f a -The word " Operable" has been inserted before "RCS loop (s)" in LCO 3.4.5. This word is redundant to the LCO statement which already states "RCS loops shall be Operable". The word insertion is not accepted.

b. ITS LCO 3.4.5 Note b

. CTS 3.4.1.2 Footnote

  • item (2)

The ITS note is changed as follows " Core outlet temperature is maintained at least 100F below saturation temperature by 100F." The CTS requirement for this note is identical in wording to the STS text. There is no editorial enhancement

perceived in this change. Changes are not accepted.
c. ~ Bases ITS LCO 3.4.$, STS Bases markup page B 3.4-23 In the fifth paragraph, item t> is reworded to conform to LCO Note b. This change is also not accepted.

Comment: For these three items, revise the submittal to adopt the STS text.

' Comed Response to issue j

Revised Response: Per discussions with the NRC Reviewer, Comed retained the word " OPERABLE". In addition. ITS LCOs 3.4.5. 3.4.6,3.4.7iand 3.4.8 Note b was revised to state that the core outlet temperature is maintained greater that, or l

i l.. q

' equal to 10'F below saturation temperature. This change is provided in our comprehensive ITS Section 3.4 closcout

' (f submittal Revision K.

Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.6-02,3.4.8-02, and 3.4.8-03.)

l l

t 8

l

\\

R spanse to NRC RAI For ITS S:ction 3.4 09-Oci 98

= = = -

NRC RAI Number -

NRC issued Date RAI Status

p 3.4.5-03 3/9'98 Closed 1

NRC Description ofIssue DOC LS.

JFD B3 JFD BB3 ITS SR 3.4.5.2 CTS 4.4.1.2.2 Bases for ITS SR 3.4.5.2, STS Bases marktip page B 3.4-26

a. This change adds plant specific SG secondary side water level values which are different from those stated in the CTS.

DOC L5 justifies the new values. The adequacy of these values can not be verified. There is no acceptable method for approving the new values as presented in these JFDs. Comment: Revise the submittal to explain the large difference in the values between Units I and 2 and why this difference is the exact same for both Byron and Braidwood.

b. The Bases for ITS SR 3.4.5.2 differs from the STS to conform to the proposed pbnt specific SG secondary side water levels values which are not the same as those stated in the CTS requirements. Comment: How was this change approved by the NRC five years ago but never incorporated into the CTS? Submit additional technicaljustification for this change.

Comed Response to Issue No change. NRC SER and Amendments 34 (Braidwood) and 45 (Byron), dated April 6,1992 approved Comed's request to change the Steam Generator (SG) secondary side narrow range water level to be greater than or equal to 33% for Unit 1 (Westinghouse D4 SGs) and 37% for Unit 2 (Westinghouse D5 SGs). The difference in SG level values between Unit One (41% to 33%) and Unit Two (18% to 37%) is attributable to the CTS LAR encompassing water level serpoint optimization on both units, and SG level tap relocation on Unit Two only. This change was accurately made in CTS Tables 2.2 1 and 3.3-

4. However, CTS page 3/4 4-4 for CTS SR 4.4.1.3.2 was inadvertently tiot changed. In developing the CTS markup for the conversion to ITS, CTS page 3/4 4-4 was used and was marked up to reflect the correct values as approved in Amendments p) 34 and 45. Although this CTS SR contained the incorrect values, the plants administratively control the water level at greater
j. (

than or equal to 41% which is more conservative. Comed continues to pursue this change. (See RAI 3.4.7-04.)

NRC RAI Number NRC issued Date RAI Status j

3.4.5-04 3/9/98 Closed NRC Description of Issue JFD BPI Bases for ITS LCO 3.4.5, STS Bases markup page B 3.4 23 in the last paragraph, when referring to an Operable SG, the phrase "in accordance with the Steam Generator Tube Surveillance Program" was not adopted. This phrase is important for stating u6c what additional conditions the SG must be Operable for this LCO. Also, JFD BPI does not adequately justify this difference. Comment: Revise the Bases to adopt the STS text.

Comed Response to issue Comed will revise the Bases to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

OV 9

(

l Responsa to NRC RAI For ITS Stetion 3.4 09-ocim NRC RAI Number NRC issued Date -

RAI Status

! c)

-3.4.5-05 3'9'98 Closed

! {V NRC D'escription of Issue JFD BPI l

Bases for ITS SR 3.4.5.3, STS Bases markup page B 3.4-26 l

The Bases discussion reduces requirements about how the safety analysis limits are met and adds a new basis for the 7 day l

Frecuency. JFD BPI does not adequatelyjustify these technical differences from the STS Bases. Comment: Resise the l

submittal to adopt the STS text.

l Comed Response to issue

~ No change. ITS Bases SR 3.4.5.3 was revised to provide a discussion concerning the 7 day Frequency for SR 3.4.5.3. This change was added for consistency and clarification. Other STS SRs contain a brief discussion as to thejustification reason for the specific SR Frequency. This change is no different. STS SR 3.4.5.3 does not contain any information pertammg to the 7 day Frequency. Comed provided additional information to assist the operator and enhance their knowledge -

concerning the reasoning behind the 7 day Frequency. This change does not alter any technical content or philosophy of the l

STS. and provides additional information for the user. Comed continues to pursue this change. Comed will. however.

conform to the STS text for the first and second sentences for the Bases discussion ofITS SR 3.4.5.3.

.:.-= = =. =. =

-. =. = =.

NRC RAI Number NRC Issued Date RAI Status 3.4.6-01 3/9/98 Closed NRC Description of issue DOC A8 l

JFD P7 and BP7 ITS 3.4.6 Action C lg)

CTS 3/4.4.1.2 Actions (v

Unlike the STS. ITS 3.4.6 Action C addresses the condition of two required [RCS or RHR] loops not in operation. This difference is not plant specific because the proposed action requirement is not in the CTS. This is a C-type difference. Also, the CTS markup associated with DOC A8 does not accuratelyjustify the addition of proposed ITS 3.4.6 Action C.

Comment: Revise the submittal to adopt the STS action requirements.

Comed Response to issue No change. The LCO allows either RCS or RHR loops to satisfy the requirement for decay heat removal in MODE 4. Any combination of two loops Operable may be used to satisfy the LCO. A loop is " required" when the loop is used to satisfy the LCO. Operable loops in excess of the two required to satisfy the LCO are not " required." Condition entry is only necessary when the total number of Operable loops is less than that required by the LCO. NUREG LCO 3.4.6 attempts to account for the designation of required loops by stating, "Two RHR loops inoperable" in Condition A and "Two RCS loops inoperable" in Condition B. The presumption in Condition A is that when two RHR loops are inoperable, two RCS loops are then required. Similarly, Condition B presumes that when two RCS loops are inoperable. two RHR loops are required. This logic does not hold for plants with three or more RCS or RHR loops or for situations in which the plant is using one RHR and one RCS loop to meet the LCO. Although the wording is different than the STS. the intent has not been changed. In addition, the intent of the STS is to provide a Condition where the required loops are either inoperable or not in operation. The STS Condition C accomplishes this by stating all combinations of RCS and RHR loops irioperable or not in operation. This approach was deemed confusing by Operators. In an attempt to clarify Condition C, Comed revised Condition C for two required loops inoperable no matter what combination of RHR or RCS loops. The condition where no loops are in operation is contained in Condition A. This clarification does not change any intent or technical requirements as presented in the STS.

l A similar change was proposed by H.B. Robinson plant and became WOG-109. In addition, TSTF-263 contains similar l

changes. The proposed change was approved plant specifically for H.B. Robinson. Comed continues to pursue this change.

(See RAls3.4.7-01,3.4.7-07,3.4.8-01, and 3.4.8-08.)

l 10 i

i

i l

R:sp::nse to NRC RAI For ITS S:ction 3.4 oo-Oct-98 l

~

NRC RAI Number -

NRC Issued Date RAI Status

= --- ;.-=

. = =. -

i 3.4.6-02 3/9/98 Closed

,jd NRC Description of Isst.e

)

JFD P1 1TS LCO 3.4.6 l

a. The word " Operable" has been inserted in the last phrase stating with "one OPERABLE loop shall be in operation." This

, word is redundant to the first pan of the LCO statement which already states "..RCS and RHR loops shall be Operable.

The word insertion is not accepted.

b. JFD P1 ITS LCO 3.4.6 Note 1.b CTS 3.4.1.3 Footnote
  • item (2)

The ITS note is changed as follows " Core outlet temperature is maintained at least 100F below saturation temperature b,s _

100F " The CTS requirement for this note is identical in wording to the STS text, There is no editorial enhancement perceived in this change.

c.

.JFD BPI l

l Bases for ITS LCO 3.4.6, S~ S Bases markup page B 3.4-28 in the fifth paragraph, item b is reworded to confonn to the LCO Note 1.b. This change is also net accepted.-

]

1 Comment: For the above differences, revise the submittal to adopt the STS text.

Comed Response to Issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4

. closeout submittal Revision K.

L l

Original Response: Comed will revise the submittal to adopt the STS text This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.5-02,3.4.8-02, and 3.4.8-03.)

i 1

I I

I i,

I

\\

kj lI

R sponse to NRC RAI For ITS Section 3.4 09-octm

~

NRC RAI Number NRC issued Date RAI Status 3.4.6-03 3'9'98 Closed

~

1 (f

NRC Description of issue ITS 3.4.6 Applicability hotes PTLR Letter from Capra (NRC) to Kingsley (Comed) dated 1/21/98 regarding acceptance for referencing of PTLR. and enclosed safety evaluation (SRXB comment) Byron & Braidwood's LTOP analyses account for RCP dynamic head effects and the resultant pressure drop between the location of the limiting vessel material and the pressure transmitter used to actuate the LTOP sy stem. In the LTOP analyses, you assumed all four RCPs and both RHR pumps running when the RCS is above 120'F. and accounted for the maximum resulting head effect. However, for RCS temperature below 120 F you assumed only one RCP is in operation and accounted for the dynamic head effect of that single RCP (in addition to the two RHR pump). Comment:

Revise the Applicability Notes ofITS 3.4.6 with an additional note consistent with this assumption. This may be submitted in a form similar to the note to Section 3.4.6 which is related to the 50*F primary / secondary difference limit for starting a RCP.

Comed Response to issue No change. Comed disagrees. The referenced SER accurately reflects the assumptions used in the LTOP analysis for operation above and below 120 F. These are assumptions incorporated in the Staff approved methodology. They do not, however, result in operational restrictions. The net impact of these conditions is to the LTOP setpoint, not the plant operation.

The two items that are in Tech Specs (TS) concerning the basis of LTOP setpoints define the initiating events that the LTOP system protects against. These items are,1) the number of ECCS pumps injecting during an LTOP mass injection event (charging pump at full flow), and 2) the temperature difference for the heat injection event (507). These two initiating events are specifically discussed in Section 3.1 of WCAP-14040-NP-A, methodology used to develop cold overpressure a,

mitigating system setpoint:, and RCS heatup and cooldown limit curves, and the associated SER. Beyond the initiating j

(~)

events, other factors are considered in the LTOP setpoint determination. Differential pressure and instrument uncertainty are two of these. The application of these secondary items are administratively controlled by Comed. This concept of administrative control was accepted by the Staffin our recent discussions for the approval of the PTLR amendment. TS do not have restrictions on other secondary items (i.e., there are no TS requirements specific to the calibration of the instruments involved which will affect the total instrument tolerances applied to the LTOP setpoints). Comed believes that it is not the Staffs intention to include these secondary issues in TS. (Correction Note: This should be a 3.4.7 RAI question, not 3.4.6.)

Additionally, the mode of applicability for ITS 3.4.6 is mode 4, which corresponds to a minimum temperature of 200 F. The LTOP analysis assumes the most limiting operational parameters in this mode. Noting the different assumption for a condition not addressed by this specification is not desirable.

t rm

\\

NY l

12

  • -*+geungap.m.ee ai ge h-g

.seum

-me g

a.mm-

--e

-em emsumm-6---

e R:spanSe to'NRC RAI For ITS S:ction 3.4 09-oci-98 NRC RAI Number NRC Issued Date

. m RAI Status 3.4.7 3/9'98 Closed NRC Description of Issue

~ JFD P8 ITS 3.4.7 Actions CTS 3'4.4.1.4.1 Actions JFD BP8 Unlike the STS. ITS 3.4.7 addresses the condition of a required RHR loop not in operation. These differences are not plant specific because they are not in the CTS. This is a C-type difference. Also, why are there not equivalent CTS DOCS provided for these changes? The CTS does not re6ect these changes. Comment: Revise the submittal to adopt the STS j

action requirements. Comed is encouraged to propose a generic change to tha STS. See similar comments 3.4.6-01 and 3.4.8-01.

4 Comed Response to issue Revised Response: Per discussions with the NRC Reviewer. ITS Condition B was split into two separate Conditions. This 1

change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.

Original Response: See Comed Response to RAI 3.4.6-01. (See RAls 3.4.6-01. 3.4.7-07. 3.4.8-01 and 3.J.8-08.)

NRC RAI Number NRC lssued Date RAI Status 3.4.7-02 3/9/98 Closed NRC Description of Issue l

DOC A.I JFD Pl ITS LCO 3.4.7.b a

, ' [

CTS 3.4.1.4.1.b CTS 3/4.4.1.4.1 Action a JFD BPI Bases for ITS 3.4.7 Applicability, STS Bases markup page B 3.4-33 STS 3.4.7.b is reworded as follows: "The secondary side water level of a least two Steam Generators (SGs) shall be > [17%)

OPERABLE." Throughout the STS, an Operable SG means " Operable in accordance with the Steam Generator Tube Surveillance Program". 'Ihe STS text is very explicit here to require the secondary side water level of an Operable SG to be a condition of Operability for this LCO. These are technical changes to the CTS requirements which are inadequately justined as an editorial change under DOC Al. As presented, this is a less restrictive change to the CTS which requires an "L" DOC. Correspondingly. JFD Pi is inadequate justi6 cation for these changes. These change are not accepted as justi6ed. Comment: Revise the submittal to adopt the STS text.

Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

-l 1

i

, L f

\\ /-

i a,

J-

Rcsp:nss to NRC RAI Fcr ITS S:ction 3A 09-oci-98

=

m==_._

u _.._ _

~u NRC RAI Number -

NRC 1ssued Date RAI Status _., -

-3.4.7-03 3/9'98 Closed lj NRC Description ofissue

JFD P1 ITS LCO 3.4.7 Note 1.b CTS 3.4.1.4.1 Footnote
  • item (2) i a The ITS note differs from the corresponding STS note as follows " Core outlet temperature is maintained at least 100F below saturation temperatore by 100F " The CTS requirement for this note is identical in wording to the STS text. There is no editorial enhancement perceived in this change..

l_

JFD BPI -

Bases for ITS LCO 3.4.7, STS Bases markup page B 3.4-34 b in the third paragraph, item b is reworded to conform to LCO Note 1.b.

Comment: The above differences are not justifiable on a plant-specific or editorial basis. Revise the submittal to adopt the STS text.-

Comed Response to issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.

Original Response: Comed will revise the submittal to adopt the ST3 text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.'

X}

/

NRC RAI Number NRC Issued Date RAI Status

= "

3.4.7-04 3/9/98 Closed NRC Description of issue JFD B3 DOC L5 ITS SR 3.4.7.2 CTS 3.4.1.4.1.b JFD BB3 Bases for ITS SR 3.4.7.2, STS Bases markup page B 3.4-36 The iTS contains plant specific SG secondary side water level values which are different from the values in the CTS requirements, as discussed in DOC L5. The adequacy of these values can not be verified. There is no acceptable method for approving the new values as presented in these justifications. Also, explain the large difTerence in the values between Units 1 and 2 and why this difference is the exact same for both Byron and Braidwood.

Comment: How was this change approved by the NRC five years ago but not incorporated into the CTS? Revise tne submittal with additional technicaljustification for this change. See similar comment 3.4.5-03.

Comed Response to issue No change. NRC SER and Amendments 34 (Braidwood) and 45 (Byron), dated April 6,1992 approved Comed's request to

' change the Steam Generator (SG) secondary side narrow range water level to be greater than or equal to 33% for Unit 1 (Westinghouse D4 SGs) and 37% for Unit 2 (Westinghouse D5 SGs). ".is change was accurately made in CTS Tables 2.2-1 and 3.3-4. However, CTS page 3/4 4-4 for CTS SR 4.4.1.3.2 was L advertently not changed. In developing the CTS l

markup for the conversion to ITS, CTS page 3/4 4-4 was used and was marked up to reflect the correct values as approved in Amendments 34 and 45. Although this CTS SR contained the incorrect values, the plants administratively control the water p [,

level at greater than or equal to 41% which is more conservative. Comed continues to pursue this change. (See RAI 3.4.5-T

' 03.)

1a) 14

l:

- = =. -

= = = = - - - = = -

R:sponse to NRC RAI For ITS Section 3.4 09-Oci 98

' NRC RAI Number NRC issued Date IUIStatus

~

3.4.7 05 3/9'98 Closed q

'(,/

NRC Description of issue DOC A25 I

JFD P39

)

ITS SR 3.4.7.1 l

CTS 4.4.1.4.1.2 CTS 4.4.1.4.1.2 states "At least one RHR loop shall be verified in operation and circulating reactor coolant.. " w hich is i

consistent with the STS. Alternatively. ITS SR 3.4.7.1 states this verification is for the " required" RHR loop in operation.

This change and difference introduces an ambiguity that is not present in the CTS and STS. The SR does not try to l

determine which is the." required" RCS or RHR in operation but explicitly states that any one must be in operation.

1 Comment: Withdraw the change and adopt the STS text.

Comed Response to issue No change. The word " required" was added to the SR for verifying one RHR loop is in operation to ensure thar *Se RHR j

loop that is in " operation" is the RHR loop that is designated as the " OPERABLE" loop. This eliminates the possibility of crediting a non-operable (as required by the LCO) RHR loop as the RHR loop in operation. Comed continues to pursue this change. (See RAI 3.4.8-06.)

NRC RAI Number NRC issued Date RAI Status l

3.4.7-06 3/9/98 Closed NRC Description of issue j

DOC M3 CTS 3'.4.1.4.1 Footnote

%d STS LCO 3.4.7 Note 1 as revised by TSTF 153 does not begin with the word "all" as does the ITS note. Comment: This difference is not justifiable on a plant-specific or editorial basis. Revise the ITS note to conform to the STS as revised by TSTF-153.

Comed Response to Issue Comed will revise the ITS note to conform to the STS as revised by TSTF-153. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

/~%

i r 5

l 15

,= = =.:=

=

Rsspanse to NRC RAI For ITS Srction 3A 09-Octm NRC RAI Number NRC issued Date RAI Status 3.4.7-07 3'9'98 Closed

.p

_V NRC Description of Issue DOC M13 CTS 3/4.4.1.4.1 Action b STS 3.4.7 Action B ITS 3.4.7 Acticns A, B & C CTS 3.4.1.4.1 Action b provides action with no RHR loop in operation. STS 3.4.7 Action B provides Required Actions with

' Required' RHR loops inoperable OR no RHR loop in operation. The compensatory Actions for both the CTS and STS are the same. DOC M13 states "lTS 3.4.7 and ITS 3.4.8, Condition C, adds the Condition. two required RHR loops inoperable.

This Condition does not exist in CTS." Two inoperable RHR loops are the same as no RiiR loops in operation in Mode 5.

There is no change here but an equivalence between the CTS and the STS which is obscured by the reformatting of the Actions as described by JFD P8. Comment: Withdraw the change and adopt the STS action requirements.

Comed Response to issue Comed disagrees that two inoperable RHR loops is the same as no RHR loops in operation, which is why the DOC was categorized as an 'M' DOC. In addition, NUREG LCOs 3.4.5,3.4.6,3.4.7, and 3.4.8 specify ". shall be OPERABLE and in operation. " indicating two separate and distinct requirements. Therefore, the ITS Actions and SRs were written accordingly. (See RAls 3.4.6-01, 3.4.7-01, 3.4.8-01, and 3.4.8-08.)

v. n. -.

NRC RAI Number NRC issued Date RAI Status I

3.4.7-01; 3/9/98 Closed NRC Description ofIssue JFD P9 '

ITS SR 3.4.7.1 Note

(,w}.

CTS 3.4.1.4.1.b

%.J JFD P9 justifies including n note in ITS SR 3.4.7.1 that the STS does not have. The new Note says "Only required when complying with LCO 3.4.7.b". The CTS do not allow this relaxation of the Operability requirements of CTS 3.4.1.4.1.b.

This note would permit a SG to remain inoperable and thus not immediately available, in the event the backup RHR loop i

became inoperable. Also, a note like this should never be buried in the SR but placed in the LCO. There is no less restrictive technical DOC provided for this change. Comment: This change and difference are not justifiable on a plant-specific or editorial basis. Revise the submittal to withdraw the note.

Comed Response to issue Comed disagrees with the statement, "The CTS does not allow this relaxation of the Operability requirements of CTS 3.4.l.4.1.b," but Comed agrees with the statement, "This note would permit a SG to remain inoperable and thus not immediately available, in the event the backup RHR loop became inoperable " CTS SR states, "The secondary side water level of at least two steam generators WHEN REQUIRED shall be. " In addition, NUREG SR 3.4.7.2 states," Verify SG secondary side water levelis greater than or equal to [17]% in REQUIRED SGs." When the LCO is being met with one

.RHR loop OPERABLE and in operation and an additional RHR loop OPERABLE, there is no requirement for SGs and therefore SR 3.4.7.2 which verifies SG secondary side water level is not required to be performed. SR 3.4.7.2 is only required to be performed when the LCO is being met with one RHR loop OPERABLE and in operation and the water level of two SGs OPERABLE. However, since SR 3.4.7.2 contains the words " required SGs" the Note will be deleted. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (Correction Note: LCO JFD 3.4-P9 justifies adding a Note in ITS SR 3.4.7.2, not ITS SR 3.4.7.1.)

Db i6

.=.. _. _ _

Resprnse to NRC RAI For ITS S:ction 3A 09-oct-98

-=:-.=.

=: :._ -

l

~

l 3 A7-09 3 998 Closed

' NRC RAI Number NRC lssued Date RAI Status Q-

' NRC Description ofissue i

JFD Cl4 ITS LCO 3.4.7 Note 1 CTS 3.4.1.4.1 Footnote

  • TSTF-153 ITS LCO 3.4.7 Note I contains a proposed change to pennit "All RHR pumps.. " to be de-energized. CTS 3.4.1.4.1 Footnote = only permits "The RHR pump., " or one RHR pump to be de energized. Comment: See comment 3.4.7-06.

Comed Response to issue Comed will revise the ITS note to conform to the STS as revised by TSTF-153. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RA!. (See RAI 3.4.7-06.)

NRC RAI Number NRC Issued Date RAI Status 3.4.7-10 3/9/98 Closed NRC Description ofIssue JFD BPI -

Bases for ITS LCO 3.4.7, STS Bases markup page B 3.4-33 in the first paragraph, the discussion pertaining to any combination of two RCS or RHR loops does not adopt the reason for

" meeting single failure considerations" and adds in its place to " provide adequate redundancy for decay heat removal" Comment: This difference is not justifiable on a plant-specific or editorial basis. Revise the submittal to adopt the STS text.

= Comed Response to Issue

(,)

Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4

'1 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.8-09.)

NRC RAI Number NRC issued Date RAI Status 3.4.8-01 3/9/98 Closed NRC Description ofissue JFD P10 -

ITS 3.4.8 Actions CTS 3/4.4.1.4.2 Actions JFD BPIO ITS 3.4.8 Action A and associated Bases address the Condition of a required RHR loop not in operation, as discussed in JFD P10. STS 3.4.8 Action B, however, addresses this same condition. Thus there is no need to deviate from the format of the STS Actions. In addition, this difference is not plant specific because this requirement is not in the CTS. Therefore, this is a C-type difTerence. Comment: Withdraw the difference and adopt the STS format for the Actions. See similar comments 3.4.6-01 and 3.4.7-01 Comed Response to issue See Comed Response to RAI 3.4.6-01. (See RAls 3.4.6-01,3.4.7-01,3.4.7-07, and 3.4.8-08.)

v 17

R:sponse to NRC RAI For ITS Srctinn 3A 09-oct 98

,m==--

_--: - =-

NRC RAI Number NRC lssued Date RAI Status

~ 3.4.8-02 3'/9'98 Closed

/

s i

/

NRC Description of issue JFD P1 ITS 3.4.8, LCO Note 1.b CTS 3.4.1.4.2 Footnote " item (2)

The ITS note differs from the corresponding STS note as follows: " Core outlet temperature is maintained > 100F below saturation temperature by > 100F." There is no editorial enhancement perceived in this change. Comment: Revise the submittal to adopt the STS presentation Comed Response to issue Revised Response: See RAI 3.4.5-02 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.

Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Respontes to the iTS Section 3.4 RAl. See RAls 3.4.5-02,3.4.6-02, and 3.4.8-03.

NRC RAI Number NRC issued Date RAI Status 3.4.8-03 3/9/98 Closed NRC Description ofIssue JFD Pl

.lTS LCO 3.4.8 '

The word " Operable" has been inserted in the last phrase of STS LCO 3.4.8 to state that "one OPERABLE RHR loop sball

[,_}

be in operation." This word is redundant to the first part of the LCO statement which already states "Two...RHR loops shall

(/ -

be Operable, " The word insertion is not accepted. Comment: Revise the submittal to adopt the STS text.

Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, this comment was withdrawn.

Original Response: Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI, (See RAls 3.4.5-02,3.4.6-02, and 3.4.8-02.)

1 Q

Y l

18 l

_ = = =

--==

R:spanse to NRC RAI For ITS Section 3.4 09-oct-98

~

NRC RAI Number NRC Issued Date RAI Status 3.4.8-04 3'9'98 Closed

,,h NRC Description of issue JFD P32 ITS 3.4.8 Note 1 STS 3.4.8 Note 1 CTS 3.4.1.4.2 Note "

JFD BP37 ITS 3.4.8 Note i states "All RHR pumps may be [de-energized] for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.. " STS 3.4.8 Note I states "All RHR pumps may be de-energized for < 15 minutes when switching from one loop to another.. " CTS Footnote " states only "The RHR pump may be de-eneigized for up to one hour.. "; but does not state a reason for de energizing. JFD P32 deals only with the length of time issue for this difference. It states de-energizing all RHR pumps is consistent with the CTS requirements. but this is not so. Comment: JFD P32 states 15 minutes is adequate to switch loops; if so, why not adopt the STS text as is? If one hour is needed for each pump. then add a note to match the CTS requirement for one RHR pump de-energized at a time.

Revise the suomittal to adopt the STS or revise it consistent with the CTS, as descrioed.

Comed Response to Issue No change. It is Byron's and Braidwood's Current Licensing Basis (CLB) to allow de-energizing an RHR pump for I hour without stating a reason for the de-energization. LCO JFD 3.4-P32 was only intended tojustify maintaining the CLB of I hour. LCO JFD 3.4-P35 justifies maintaining the CLB for not limiting the de-energization of the RHR pumps to "when switching from one loop to another." Further, since both CTS and ITS require only one RHR loop be in operation. Comed perceives the CTS wording of"The RHR pump may be. " to be equivalent to the ITS wording of"All RHR pumps may be

" Comed disagrees with the statement, "If one hour is needed for each pump, then add a note to match the CTS j

requirement for one RHR pump de-energized at a time." There is neither a restriction for preventing or requiring the second OPERABLE RHR pump from being in operation. Therefore, the second pump does not need a Note governing its operation. Comed continues to pursue this change. (See RAI 3.4.8-05.)

=

U NRC RAI Number NRC Issued Date RAI Status 3.4.8-05 3/9/98 Closed NRC Description of issue JFD P35 ITS LCO 3.4.8 Note 1 STS LCO 3.4.8 Note i CTS 3.4.1.4.2 Note "

JFD BP49 Bases for ITS LCO 3.4.8, STS Bases markup page B 3.4-38 ITS LCO 3.4.8 Note I states "All RHR pumps may be removed from operation for < l hour.. " STS 3.4.8 Note I states "All RHR pumrs may be de-energized for < 15 minutes when switching from one loop to another.. " CTS Footnote " states "The RHR pump may be de-energized for up to one hour.. "; without a stated reason for de-energizing. JFD P35 deals only with the stated reason for de-energizing the RHR pumps and misquotes the CTS footnote " as being applicable to all RHR pumps rather than one; so, adopt the STS text as is. If one hour is needed for each pump, then add a note to match the CTS requirement for one RHR pump de-energized at a time. Comment: Revise the submittal to adopt the STS or revise it consistent with the CTS, as described. Recommend coordinating the response to this comment with the response to comment 3.4.8-04.

Comed Response to issue j

See Comed Response to RAI 3.4.8-04.

p?

\\ wJ l

19 l

l l

(

=-

=.

L Respanse to NRC RAI Fcr ITS Secti n 3.4 owoct-98 NRC RAI Number NRC INed Date' ~^

RAI Status I

.,m.

3.4.8-05 3/9/98 Closed 3

,k)

NRC Description of issue l

DOC A25 '

JFD P39 ITS SR 3.4.8.1.

CTS 4.4.1.4.2 JFD BP39

. CTS 4.4.1.4.2 states "At least one RHR loop shall be verified in operation and circulating reactor coolant.. " ITS SR 3.4.8 revises this requirement to state this verification is for the " required" RHR loop in operation. This change introduces an ambiguity that is not present in the STS. The SR does not try to determine which is the " required" RCS or RHR in operation, but explicitly, states thtt any loop must be in operation. Comment: Adopt the STS text which is consistent with the CTS requirement.

Comed Response to issue See Comed Response to RAI 3.4.7-05.

I

.y._

NRC RAI Number NRC Issued Dete RAI Status 3.4.8-07 3/9/98 Closed NRC Description of issue DOC M2 CTS 3.4.1.4.2 Footnote *

'q

' CTS 3.4.1.4.2 Footnote " shows the additions of a Note 3 to this footnote; however, the footnote does not match the note in

the ITS. The wording of this note which is adopted from the STS has been editorially enhanced. The acceptable wording is as follows "(3) No draining operations are permitted that would further reduce the RCS water volume." Comment: Revise i

the CTS markup to be consistent with the 1TS.

I Comed Response to issue Comed will revise the CTS markup to be consistent with the ITS. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

i l

i NRC RAI Number NRC issued Date RAI Status j

3.4.8-08 3/9/98 Closed

{

NRC Description of Issue DOC M13 CTS 3/4.4.1.4.2 Action b STS 3.4.8 Action B ITS 3.4.8 Action A, B & C CTS 3/4.4.1,4.2 Action b eddresses the Condition of no RHR loop in operation. STS 3.4.8 Action B provides Required Actions with Required RHR loops inoperable OR no RHR loop in operation. The compensatory Actions for both the CTS and STS are the same. DOC M13 states "ITS LCO 3.4.7 and ITS LCO 3.4.8, Condition C, adds the Condition, two required RHR loops inoperable. This Condition does not exist in CTS." Two inoperable RHR loops are the same as no RHR loop in' operation in Mode 5. There is no change here but an equivalence between the CTS and the STS which is obscured by the l

reformatting of the LCO under JFD P10. Comment: Withdraw the change and adopt the STS Conditions, as written. See

[

comment 3.4.7-07.

j Comed ' Response to issue

,(

J'.

See Comed Response to RAI 3.4.7-07.

20 l-

==_ -

= = -

.= -..

Respons: to NRC RAI For ITS Section 3A 09-oci-98

= = = =,~-...= = = =_:: = : _

~. :.

NRC RAI Number NRC issued Date RAI Status n

3.4.8-09 3/9/98 Closed I

\\-

() -

' NRC Description of issue -

l JFD BPI Bases for ITS LCO 3.4.8. STS Bases markup page B 3.4-37 in the first paragraph pertaining to the discussion of any combination of two RCS or RHR loops. the ITS does not adopt the STS reason for " meeting single failure considerations" but adds in its place the words " provide adequate redundancy for decay heat removal" Comment: This is not ajustifiable plant-specific or editorial difference. Revise the submittal to adopt

= the STS text.

Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revis on upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.7-10.)

=. =. _ = = = _ = = -

- - -. -===

NRC RAI Number -

NRC issued Date RAI Status 3.4.9-01 3/9/98 Closed NRC Description ofIssue JFD P40 ITS 3.4.9 Action B CTS 3/4.4.3 Action a ITS 3.4.9 Action B, corresponding to CTS 3/4.43 Action a, allows both required groups of pressurizer hesters to be inoperhble for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this condition, the pressurizer heater function is lost. Also, it is possible under the multiple p

condition entry convention of the STS, that the pressurizer level could be concurrently inoperable. Were this to occur, none of the LCO requirements would be met - which produces a loss of function condition for this LCO. Corresponding STS e

L.

' 3.4.9 Action B permits only one group of heaters to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only while an Operable redundant group is Operable. Therefore, this is not consistent with the Bases as the technicaljustification states. NUREG-0452 on which the CTS is based does not permit both pressurizer heater groups to be inoperable.

JFD BP40 JFD BPI JFD BP3 Bases discussions of Required Actions B.1, C.1, and C.2, STS Bases markup page B 3.4-43.

Acceptance of the changes to the two Bases discussions listed are continpn. upon resolution of the ditTerences addressed by JFD P40. JFDs BPI and BP3 are linked to JFD BP40. Comment: Reference the NRC safety evaluation which made this change to allow both required groups to be inoperable, or adopt the more restrictive requirements of the STS.

Comed Response to issue Revised Response: Per discussions with the NRC Reviewer, INSERT B 3.4-41 A has been added to the Background Section of the Bases for ITS LCO 3.4.9. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.

Original Response: The Actions Section of the Bases for ITS LCO 3.4.9 will be revised to state, "If the required groups of pressurizer heaters are inoperable, restoration is required within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is reasonable '

considering the anticipation that a demand caused by loss of offsite power would be unlikely in this period. Pressure control may be maintained during this time using the remaining pressurizer heater capability." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

OL).

21

Response to NRC RAI For ITS Section 3.4 owoci-98

.)

NRC RAI Number NRC issued Date RAI Status 3.4.9-02 3/9/98 Closed

)

l s

NRC Description ofIssue JFD BP41 JFD BP48 Bases for ITS LCO 3.4.9, STS Bases markup page B 3.4-41

)

In the second paragraph of the STS Bases states that the two required pressurizer heater groups are " capable of being powered from either the offsite power source or the emergency power supply." The ITS replaces these words with the I

statement that the heater groups are " capable of being powered from an ESF power supplied bus." and omits mformation regarding the capability of being powered from an offsite power source. In addition, the ITS adds a sentence to explam that offsite (normal) power is not required for pressurizer heater operability. Comment: The proposed ditTerences from the Bases are unnecessary because the ITS definition of operability requires either emergency or offsite power. not both, for the supported system to be operable. Revise the Bases to adopt the STS wording.

)

Comed Response to issue ITS LCO 3.4.9 item b is being revised to state, "Two groups of pressurizer heaters OPERABLE with.. and capable of beMe i

powered from redundant Engineered Safety Feature (ESF) power supplied buses." Correspondingly, the second paragraph in the LCO Section of the Bases for ITS LCO 3.4.9 is being revised to state, "The LCO requires two groups., capable of being powered from redundant ESF power supplied buses." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

l The pressurizer heaters are non-safety related. Plant design consists of a total heater capacity of 1800 kw which is divided into four groups ( A, B, C, and D) with separate controls for the proportional group (C) and the back up groups ( A' B, and D). Heater groups A and D are supplied by non-ESF bus 143, while groups B and C are supplied from non-ESF bus 144.

The non-ESF buses servicing the pressurizer heaters (buses 143 and 144) can be powered by either the Unit Auxiliary Transformer (UAT), or the unit specific System Auxiliary Transformer (SAT) which is termed " normal power" per ITS p

Section 3.8. The ESF buses (buses 141 and 142) can be powered by the unit specific SAT (which is termed " normal power" V

per ITS Section 3.8), the opposite-unit SAT (which is termed " reserve power" per ITS Section 3.8), or the emergency diesel generator. The ESF buses must be capable of powering, via a cross-tie. the non-ESF buses to satisfy ITS SR 3.4.9.3.

Therefore, the statement in the LCO Section of the Bases for ITS LCO 3.4.9 "The LCO requires two groups., capable of being powered from redundant ESF power supplied buses" reflects the current plant design. Since the only safety function for pressurizer heaters is in a loss of offsite power condition, normal power is not required for OPERABILITY. That is,

" normal" power to a non-ESF bus is not required. but rather the non-ESF bus must be capable of being powered from an ESF bus. Comed continues to pursue this change.

NRC RAI Number NRC issued Date RAI Status 3.4.9-03 3/9/98 Closed NRC Description ofissue JFD BPI Bases for ITS SR 3.4.9.1, STS Bases markup page B 3.4-43 The first sentence of the first paragraph of the listed ITS Bases discussion differs from the STS as follows: "This SR requires that during steady state operation, pressurizer level to be maintained below the nominal upper limit to provide a minimum space for a steam bubble." Comment: This difference is not justifiable on a plant-specific or editorial basis. The STS sentence is clear. Revise the Bases to adopt the STS words.

Comed Response to issue Comed will revise the Bases to adopt the STS wording. This change will be provided in our comprehensive iTS Section 3.4 closeout submittal revision upo-RC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

pa 22

f

. = = _

R spanse to NRC RAI For ITS S:ctinn 3.4 09-Oci-98

- =.. -.. =

NRC RAI Number

. NRC issued Date RAI Status

'3.4.10-01' 3'/9'98 Closed x.

/

\\^

.(f NRC Description cfIssue i

Not used Comed Response to issue -

No response required.

NRC RAI Number.

NRC lssued Date RAI Status 3.4.10-02 3'9 98 Closed NRC Description ofIssue

- DOC M17 CTS 3.4.2.2 and Footnote

  • ITS 3.4.10 Applicability Note CTS 3.4.2.2 and Footnote
  • requires the pressurizer safety valves to be set within the lift setting limits at normal operating temperature and pressure. The Applicability Note to ITS 3.4.10 allows entry into Mode 3 at normr.i operating temperature and pressure for up to 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> to set the lift settings at normal operating temperature and pressure. CTS 3.4.2.2 has no exception to CTS 3.0.4. Thus, if the IST requirements for setting the valves to within 1% of the setpoint are due, there is no basis for entering Mode 3 without first verifying the Operability of the safety valves at normal operating temperature and pressure (perhaps bench testing with a suitable test rig is implied, as opposed to in-situ testing). Assuming the hot setting is required by the IST, and provided that the cold settings have been completed, the ITS note allows entry inte Mode 3, but requires completing the hot settings within 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> following entery into Mode 3. This limited time period is sufficient to set the pressurizer safety valves under normal operating ambient conditions. Adoption of the STS allowance granted by this note constitutes a less restrictive change to the CTS. Comment: Revise the submittal by replacing DOC M17 with a less g

restrictive CTS changejustification. In the response to this comment, describe current IST practices for cold and hot setting of the pressurizer safety valves and how they are consistent with the CTS requirements and whether any changes are needed j

t d

to be consistent with the ITS requirements.

Comed Response to issue Revised Response: Refer to CTS DOC 3.4 L38. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.'

Original Response: DOC M17 will be changed to an 'L' DOC (less restrictive change), and will state, " CTS 3.4.2.2 Footnote

  • require, the pressurizer safety valve lift setting pressure correspond to ambient conditions of the valve at nominal operating temperature and pressure. The Applicability of the CTS requirement is in Modes I,2, and 3. Therefore, complying with the CTS, the lift setting must be set at operating temperature and pressure prior to entering Mode 3. The ITS LCO 3.4.10 LCO Note allows entry into Mode 3 with the lift settings outside the LCO limits. This permits testing and examination of the safety valves at high pressure and temperature near their normal operating range, but only after the valves have had a preliminary cold setting.. This change represents a less restrictive change, and is consistent with NUREG-1431." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

1 v'.

23

-:-=_

= =. = -

Response to NRC RAI For ITS Section 3.4 09-Oci-98

__..7 NRC RAI Number NRC issued Date RAI Status n

' ' 10-03 3/9/98 Closed i

1

. V NRC Description of issue JFD P13 ITS 3.4.10 Applicability Note JFD BPl3 Bases for Applicability ofITS 3.4.10, STS Bases markup page B 3.4-47 i

The ITS proposes to place the STS 3.4.10' Applicability Note with the LCO statement as an editorial enhancement to preclude misinterpretations ofITS SR 3.0.4. Staff disagrees with this technical basis. This difference is genene and shoulJ be submitted as a generic change to the STS. Comment: Withdraw this deviation from the STS, and adopt the STS format.

This change occurs frequently in this submittal; thus the response to this comment should be global over the whole submittal. This comment likely occurs in other sections. A single response with references to it is acceptable.

Comed Response to issue See Comed Response to RAI 3.4.1-04. (See RAls 3.1.5-01,3.1.6-01,3.4.1-04, and 3.4.12-01 Item b.)

~~.~-^r-"-.

.... _. ~ ~

~2 I

NRC RAI Number NRC issued Date RAI Status 3.4.10-04 3/9/98 Closed NRC Description of issue JFD P33 ITS SR 3.4.10.1 JFD BP38 Bases for ITS SR 3.4.10.1, STS Bases markup page B 3.4-48 n

ITS SR 3.4.10.1 omits the last sentence of STS SR 3.4.10.1, "Following testing, lift settings shall be within 1%". because the (d'

licensee believes the LCO and Bases are inconsistent. The staff disagrees. In addition, omission of this sentence from the 4

^

Revise ITS SR 3.4.10.1 to adopt the sentence omitted from STS SR STS would require a generic change. Comment:

3.4.10.1.

Comed Response to issue Comed will revise ITS SR 3.4.10.1 to adopt the sentence omitted from STS SR 3.4.10.1. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

NRC RAI Number NRC lssued Date RAI Stata 3.4.10-05 3/9/98 Closed NRC Description of issue DOC Ml7 l

JFD B43 ITS 3.4.10 Applicability Note The Applicability note has been modified in the second sentence by identifying Mode 3 as the " normal operating temperature and pressure" where the lift settings are verified. The insertion of this text is redundant to the earlier sentence where the

" ambient (hot) conditions" are discussed.' These changes to the note are not accepted.

Note: This modification is also shown in CTS change with M17 DOC but is not separately identified. Comment: Revise the submittal to adopt the STS text of the Applicability Note.

Comed Response to issue Comed will revise the submittal to adopt the STS text. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

(nv)

{

l i

24 1

l

. m.

._ m = _ _,

R:sponse to NRC RAI For ITS S:ction 3.4 09-Oct 98 NRC RAI Number NRC issued Date RAI Status

. --c 3.4.11-01 3/9/98 Closed NRC Description of issue DOC A10 JFD Pl4 DOC L8 JFD Cl2 CTS 3/4.4.4 Actions a through d ITS 3.4.11 Actions B, D, E, F, & G JFD BCl3 Bases for ITS Required actions D.1 and D.2. Insert B 3.4-54A, STS Bases markup page B 3.4-54 a The Applicability ofITS 3.4.11 is Modes 1,2. and 3, yet the action requirements never require exiting Mode 3 (RCS average temperature below 350 degrees Fahrenheit), only going to Mode 3 with RCS average temperature below 500 degrees

' Fahrenheit which is addressed by DOC L8 and JFD C12. based on TSTF-l l3 which is still pending with the staff. This is illogical. Comment: Revise the submittal to adopt the STS shutdown requirements which are consistent with the CTS action requirements.

b. The submittal does notjustify adding block valves to STS 3.4.11 Actions Note I and allowing separate Condition entry for inoperable PORVs and block valves. The reasons given in DOC A10 and JFD P14 are insufficient tojustify these changes and differences. The licensee's perception stated in 170C A10 that separate Condition entry is the intent of the CTS action requirements is incorrect. Comment: Revise the submittal with a L-type technicaljustification for allowing separate Condition entry for the PORVs and associated block valves. Revise JFD Pl4 with a plant-specific justification for adding block valves to STS 3.4.11 Actions Note I allowing separate Condition entry. Otherwise, adopt the STS version of the note.

Comed Response to issue Comed Response to NRC Comment a: Comed will revise the submittal to adopt the STS text and withdraw TSTF-l 13 from Q

the submittal. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's Q

concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed Response to NRC Comment b; TSTF-247 revises NUREG LCO 3.4.l l to allow separate condition entry for each block valve, and thereby eliminating bracketed Required Action F.3. This change was proposed by Byron and Braidwood and has been approved by TSTF LCO JFD 3.4-Pl4 will be revised to state,"NUREG and ITS LCO 3.4.1 I allow separate condition entry for each PORV. The Conditions and Required Actions provide appropriate compensatory measures for separate condition entry. ITS has been modified to add the phrase, " Separate Condition entry is allowed for each PORV and each block valve," consistent with TSTF-247. In the event a PORV becomes inoperable and not capable of being manually cycled (Condition B), the Required Action is to close the associated block valve and remove power from the block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in accordance with the Bases, once power is removed from the block valve, it is no longer OPERABLE and Condition C is also entered. Per ITS Required Action B.3, the inoperable PORV is to be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Required Action C.2 requires the inoperable block valve to be restored to OPERABLE (restore power) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In the event the second PORV becomes inoperable, Condition E Required Actions require the associated block valve to be closed and power removed from the valve, rendering it inoperable. Condition B is re-entered for the second PORV. This results in 2 PORVs and 2 block valves inoperable and Condition F is entered for 2 inoperable block valves. If the first PORV is restored to OPERABLE, Condition E is exited.

leaving Condition B entry for the second PORV with the remainder ofits 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> available in order to restore it to OPERABLE status.13owever, without separate Condition entry for the block valves, the second PORV and associated block valve must be restured to OPERABLE within the initial 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock of the first block valve. If the second PORV and associated block valve are not restored within this initial 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, Condition D is entered which requires the unit to be shutdown. As provided for the PORVs, the Conditions and Required Actions also provide appropriate compensatory actions for separate condition entry for each block valve. Thus, the Actions Note is modified to allow separate condition entry for each block valve." Comed continues to pursue this change.

/~'N.

t 25

._._____m R:sp::nse to NRC RAI Fer ITS S:ction 3A 09-oct-98 NRC RAI Number NRC issued Date RAI Status l

73 3.4.11-02 3'9'98 Closed

'\\s)

NRC Description ofissue DOC Al CTS 4.4.4.1 The first phrase of CTS 4.4.4.1, "In addition to the requirements of the Specif'.; non 4.0.5, each PORY shall be demonstrated. ", has not been retained m the Surveillance Requirements ofITS 3.4.11. This omission is mcorrectly categorized as an administrative change by DOC Al. It is a specific technical change which must be discussed and justitied separately. Comment: Revise the submittal with a technicaljustification for thn CTS change.

Comed Response to issue DOC A33 was created to discuss CTS Specification 4.0.5 relocation. DOC A33 states. " CTS Specification 4.0.5 prosides surveillance requirements for inservice inspection and testing of ASME Code Class 1. 2, and 3 components. In accordance with NUREG-1431, CTS Specification 4.0.5 has been relocated to ITS Specification 5.5.8. " Inservice Testing Program."

The requirements for Inservice Tssting have not changed and are still consistent with ASME Section XI. The requirements for the Inservice inspection are contained in 10 CFR 50.55a and therefore not included in the NUREG. This change has been justified in the ITS submittal as an administrative change throughout the CTS markups since no ASME or CTS laservice hsting requirements were changed. The only change that was made was in relocation of the requirements from CTS 4.0.5 to 113 5.5.8." This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.12-07.)

=.

- ~ = = = =. =. = _ =

NRC RAI Number NRC issued Date RAI Status

'.4.11-03 3/9/98 Closed s

NRC Description of issue JFD BP3

,- 3

(

)

Bases Background discussion for ITS 3.4.11, STS Bases markup

< 'C page B 3.4-50 l ne ITS Bases do not adopt the words which state normal power is "from the vital buses from offsite sources but are capable of being powered from emergency power sources"in the fifth paragraph of the Bases Background discussion for STS 3.4.11. This omission appears to contradict the discussion about PORV power sources in JFD. The proposed omission and related editorial changes result in misleading the reader into thinking that the PORVs only have emecgency power sources.

Comment: Revise the Bases ofITS 3.4.11 to conform to the STS Bases consistent with plant design.

Comed kesponse to Issue Comed will revise the Bases ofITS 3.4.11 to conform to the STS Bases. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

o 26

R:spensa to NRC RAI Fcr ITS Section 3.4 09-oci-98

-..=..:-.

NRC RAI Number NRC issued Date RAI Status

. ;,3 i3.4.11-04 3 9/98 Closed NRC Description ofissue -

DOC LA8 CTS SR 4.4.4.1.a The licensee proposes to move the CTS requirement for Channel Calibration of the PORV actuation instrumentation to the TRM, but does not fully explain why specifying this requirement in TS is not necessary to ensure Operabihty of the PORY actuation instrumentation or how the retained surveillances ensure the Operability of this instrumentation. Commen:: Reuse DOC LA8 to address the concerns noted.

Comed Response to issue Comed will revise the ITS submittal to reflect our proposed resolution to the " Spurious Si at Power" issue. The CTS License Amendment Request (LAR)is expected to be docketed by April,30.1998. An ITS Revisi3n incorporating the CTS LAR will be submitted subsequently.

l

.V

)

i I

I

/%

27

=-

Respons2 to NRC RAI Fcr ITS Secti2n 3.4 09-oct-98

= ~:.

NRC RAI Number NRC issued Date RAI Status 3.4.12 01 3'/9'98 Closed

.f k

NRC D'escription ofissue DOC M7 JFD Pil JFD P19 JFD P21 JFD C9 (WOG 51); CIS (WOG 81)

ITS 3.4.12: LCO, Actions A thru D, and SRs CTS 3/4.4.9.3; CTS 3/4.5.3; CTS 3/4.5.4.1 and CTS 3/4.5.42 ITS 3.4.12 and associated Bases contain extensise deviations from STS 3.4.12.

a. JFD Pil applies to differences from the STS LCO. Applicability Actions, and SRs so that the ITS properly specify the plant specific limitations of the Byron and Braidwood LTOP system analysis. Comment: Revise JFD P1I to explain how 3

each limitation given in the CTS has changed. Also explain how each corresponding limitation proposed in the ITS reDects j

those changes or reflects an additional limitation based on the LTOP analysis. List each specific limitation from the LTOP analysis and the corresponding limitation in the ITS refer to each specific ITS 3.4.12 requirement. The foregoing request is made to facilitate verification by the staff that the proposed requirements are appropriate and consistent with the LTOP analysis.

l

b. JFD Pl9 incorporates the Applicability Note into the LCO, which is an unacceptable type of STS generic change proposal common to this submittal. Comment: Revise the submittal to adopt the STS presentation of the note in the Applicability.
c. Deviations to the Applicability based on JFD C9 (WOG SI) and CIS (WOG 81) are rejected. Comment: Revise ITS 3.4.12 to adopt the STS Applicability requirements consistent with plant design and current licensing basis.

]-

d. JFD P21 applies to the notes to the SRs.
  • The note to ITS SR 3.4.12.2 appears generic, not plant specific. Thus it is rejected.
  • The note to ITS SR 3.4.12.3 is related to the generic movement of the Applicability note to the LCO; thus it is also generic. This note is rejected.-

The note to ITS SR 3.4.12.5 is unnecessary since it only applies to RHR suction valves associated with " required" RHR j

suction relief valves. It is also generic. This note is rejected.

The note to ITS SR 3.4.12.6 is unnecessary since it only applies to PORV block valves associated with each " required" PORV. It is also generic. This note is rejected.

Comment: Revise the above SRs by withdrawing the proposed notes.

- e. DOC M7 collectivelyjustifies the changes to the CTS corresponding to the proposed STS deviations noted above and which are considered unacceptable. Comment: Revise DOC M7 as appropriate to be consistent with the resolutioin of the preceding comments.

Comed Response to issue Comed Response to NRC Comment a: No change. LCO JFD 3.4-P11 does not change any CTS requirements. ITS LCO 3.4.12 item a corresponds to CTS 3.5.3.a footnote; ITS LCO 3.4.12 item b corresponds to CTS SR 4.5.3.2; ITS LCO 3.4.12 item c is a more restrictive requirement as discussed in DOC 3.4-M7; and ITS LCO item d corresponds to CTS 3.4.9.3.a and

b. LCO JFD 3.4-Pi l merely discusses including the requirements associated with ITS LCO 3.4.12 items a and b into the ITS LTOP specification from the CTS ECCS Subsystems enaci&ation 3.5.3. Comed Response to NRC Comment b: See Comed Response to RAI 3.4.1-04. (See RAls 3.1.5-01,3.1.6-01,3.4.1-04, and 3.4.10-03.) Comed Response to NRC Comment c: WOG-51 Revision I will be withdrawn from the submittal. LCO JFDs 3.4-C9 and 3.4-PI, Bases JFDs 3.4-C9 and 3.4-P21, and the markups will be revised accordingly. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Comed Response to NRC Comment d: SR 3.4.12.2 Note will be deleted based on withdrawing WOG-51 Revision 1. SR 3.4.12.4, SR 3.4.12.5, and SR 3.4.12.6 Notes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's k

)

concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.4.12-03 and 3.4.12-04.) However, SR 3.4.12.3 Note is being retained. Without the Note, whenever the unit enters MODE 4 from MODE 3 the SR would have to 28 l

.=

=

- = - = -

R:sponse to NRC RAI For ITS S2ction 3A oo-Oci-98 be met in MODE 3 prior to enieringliODE 4.' Verifying the accumulator isolated is not a requirement of the LCO unless the

~

~

~

accumulator pressure is greater than or equal to the maximum RCS pressure for the existmg RCS cold leg temperature

/

j allowed by the P,7 limit curves. Therefore, Comed believes that the use of the " met" Note is justifiable and necessarv to d

reflect the requirements ofITS LCO 3.4.12 and SR 3.4.12.3. Comed Response to NRC Comment e: ITS LCO 3.4.12 requires accumulator isolation whenever accumulator pressure is greater than or equal to the maximum RCS pressure for the existing cold leg temperature allowed in the PTLR. no safety inj:ction pumps capable ofinjecting into the RCS. and a maximum of one charging pump (centrifugal) capable ofinjecting into the RCS. As DOC 3.4-M7 states. CTS LCO 3.4.9.3 does not include requirements for overpressure protection associated with an Si pump capable of injecting into the RCS or two charging (centrifugal) pumps or one charging (positive displacement) pump capable ofinjectmg into the RCS Hou es er CTS 3.5.3.a footnote (ITS LCO 3.4.12 item a) and CTS SR 4.5.3.2 (ITS LCO 3.4.12 item b) contain these same requirements. but the requirements have been moved to the LTOP specification (ITS LCO 3.4.12)in ITS. As DOC 3 t-W also states, CTS LCO 3.4.9.3 does not include requirements for an unisolated accumulator whenever accumulator pressure is creater than or equal to the maximum RCS pressure for the existing cold leg temperature allowed m the PTLR. Therefore.

ITS LCO 3.4.12 item e is a more restrictive requirement as discussed in DOC 3.4-M7. Even with the changes discussed above in Comed's Responses to NRC Comments a-d. DOC 3.4-M7 justification still remains valid and unchanged.

=.

NRC RAI Number NRC issued Date RAI Status 3.4.12-02 3/9'98 Closed NRC Description ofissue JFD Pl1 ITS SR 3.4.12.2 The JFD Pil discussion states that the positive displacement charging pump is not allowed to be capable ofinjection during the LTOP conditions. Periodic verification that this is so is required by ITS SR 3.4.12.2. Neither this SR nor the Bases for ITS 3.4.1.2, however, specifically mention the positive displacement pump. Note that ITS SR 3.4.12.1 specifically requires verifying the incapability of the Si pumps to inject into the RCS. Comment: Revise ITS SR 3.4.12.2 and appropriate parts n

of the Bases for ITS 3.4.12 to specifically address the positive displacement charging pump to make it unambiguous that these requirements and associated Bases apply to it.

Comed Response to issue No change. LCO 3.4.12 item a and SR 3.4.12.2 added "(centrifugal)" to clarify that the Positive Displacement Pump (PDP) is not allowed to be capable ofinjection during the LTOP conditions. Because this is Byron /Braidwood current licensing basis and has been adequately addressed in training, Comed does not believe it cost or time beneficial to revise the submittal to incorporate this change.

7

/

4 29

_.we.e 8

eis MP g

wesp-M " " * * * * " "

l

. Response to NRC RAI For ITS S:ction 3A 09-Oci-98 i

l NRC RAI Number NRC lssued Date R I Status L

3.4.12-03 3/9'98 Closed fm NRC Description ofIssue -

DOC A20 l

DOC L10 JFD P38 JFD BP50 CTS 3/4.4.9.3 Action d CTS 4.4.9.3.1.a ITS SR 3.4.12.4 and SR 3.4.1.2.7

a. With the RCS vented per Actions a. b, or c, CTS 3/4.4,9.3 Action d requires verifying every 31 days that the RCS sent path is open. This action requirement is retained (per DOC A20) as ITS SR 3.4.12.4 which contains a note. that for the most part is consistent with the note to corresponding STS SR 3.4.12.5. The ITS note states this verification is only needed w hen the RCS vent path is relied upon for pressure relief per compliance with ITS LCO 3:4.12.d.4. As discussed bs JFD P38. the ITS note replaces the STS note words "only required to be performed" with"only required to be met." (Note that the CTS markup. insert 3.4-39c and DOC A20, mistakenly shows the ITS note as replacing the STS words with the words "only tequired.") Comment: The concerns expressed in JFD 38 regarding " met" versus " performed" are not valid: this ditTerence would represent a generic change to the STS, as apparently addressed by WOG-87. Revise the note to ITS SR 3.4.12.4 to adopt the words of the corresponding STS note. Also, adopt the affected wording of the STS Bases. Finally. correct the CTS markup error noted above.

. b. When the PORVs are being used for cold overpressure protection, CTS 4.4.9.3.1.a requires performance of an Analog

. Channel Operational Test (ACOT) on the PORV actuation channel every 31 days. ITS SR 3.4.12.7 retains this CTS test requirement and clarifies, per DOC L10, when it is required with a note, that for the most part is consistent with the note in corresponding STS SR 3.4.12.8. The ITS note replaces the STS words "not required to be met" with "not required to be performed" as discussed in JFD 38. Comment: The concerns expressed in JFD 38 reyrding " met" versus " performed" are h

not valid; this difference would represent a generic change to the STS, as apparently addressed by WOG-87. Revise the note i

V to ITS SR 3.4.12.7 to adopt the words of the corresponding STS note. Also, adopt the affected wording of the STS Bases.

Comed Response to Issue Comed Response to NRC Comment a: Per Comed Response to NRC Comment d for RAI 3.4.12-01, SR 3.4.12.2 Note will be deleted based on withdrawing WOG-51 Revision 1. SR 3.4.12.4, SR 3.4.12.5, and SR 3.4.12.6 Notes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. Therefore, CTS Insert 3.4-39C and DOC 3.4-A20 will be deleted as well. This change will be provided in our comprehensive ITS Section 3,4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI. (See RAls 3.4.12-01 and 3.4.12-04.)

Comed Response to NRC Comment b: "Not required to be met. "is more restrictive than "Not required to be performed.

" Since CTS SR 4.4.9.3.1.a does not contain a "SR 3.0.4 is not applicable" allowance, Comed cannot justify the use of the

" met" Note. By allowing SR 3.4.12.7 to not be " met," the unit would be allowed to enter the mode of applicability with the required PORV(s) knowingly not being able to pass a COT surveillance. Comed believes that this is not the intent of ITS.

Furthermore, this is not an allowance in CTS. The unit should have every confidence that the PORV is opersole and would pass the Channel Operational Test if performed, but it is not required to be " performed" due to unit conditions. Therefore, the Note should read only "not required to be performed.. " Comed continues to pursue this change.

.(v 30

- -. _ =. _ -. =

l.

R:sponse ta NRC RAI For ITS S2ction 3.4 09-Oct-98 r

NRC RAI Number NRC issued Date RAI Status m

3.4.12 3/9/98 Closed

[V '

\\

NRC Description of issue l

JFD P21 l

ITS SR 3.4.12.2. SR 3.4.12.5 and SR 3.4.12.6 STS SR 3.4.12.2, SR 3.4.12.4, and SR 3.4.12.6 i

The listed STS SRs do not contain the notes included in the corresponding ITS SRs. as described in the following and somewhat in JFD 21.

The note to ITS SR 3.4.12.2 states that the veri 6 cation that no SI pumps are capable ofinjecting into the RCS is "not required to be met during [Sl] pump swap operation. This is a new SR to ensure compliance with new LCO 3.4.12.b. as discussed in DOC M.7. However, the note is not technicallyjustified or even discussed in DOC M.7. Thus, it may be a valid plant-specific difference from the STS. Unfortunately, JFD P21 doesn't justify it either.

+ The note to ITS SR 3.4.12.5 states that the verification that RHR suction valves are open for each required RHR suction relief path is "only required to be met when complying with LCO 3.4.12.d.2 [two RHR suction relief valves providing the pressure relief capability) or LCO 3.4.12.d.3 [one PORV and one RHR suction relief valve providing the pressure relief capability]." This SR retains the requirements of CTS 4.4.9.3.2, and ensures compliance with LCO 3.4.12.d.2 or LCO 3.4.12.d.3, as applicable.

l The CTS markup does not appear tojustify these notes. Also, JFD 21 is not accepted because it represents a generic

('v}

editorial change to the STS, and is unnecessary. Comment:(1) Technicallyjustify the note to ITS SR 3.4.12.2 on a plant-specific basis or withdraw it making appropriate char.ges. (2) Revise the submittal to withdraw the other notes making t

appropriate changes to the DOCS, JFD 21, and B.ses. The response to this comment may be combined with the response to similar comment 3.4.12-01. Note, the proposec' generic changes represented by these notes are related to WOG 100J Comed Response to issue Per Comed Response to NRC Comment d for F.Al 3.4.12-01, SR 3.4.12.2 Nu will be deleted based on withdrawing WOG.

l

51. Revision 1 (not WOG-100). SR 3.4.12.4, ER 3.4.12.5 and SR 3.4.12.6 Nmes will be deleted due to being redundant to the use of the word " required" in the SRs themselves. This change will be prov Ued in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses ao the ITS Section 3.4 RAl. (See RAls j

3.4.12-01 and 3.4.12-03.)

NRC RAI Number NRC issued Date RAI Status 3.4.12-05 3/9/98 Closed NRC Description of issue Not used Comed Response to issue No response required.

l l

m 4

31

= _ - _

_, = _

ResponS to NRC RAI For ITS S ction 3.4 09-oct 98 NRC RAI Number NRC issued Date RAI Status 3.4.12-06 3'908 Closed f\\

Q NRC Description ofissue CTS 4.4.9.3.2, item a and b STS SR 3.4.12.4 ITS SR 3.4.12.5 CTS 4.4.9.3.2 item a and b require that at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that the RHR suction valves are serified to be open. ITS SR 3.4.12.5 retains this verincation requirement. including the 72-hour Frequency. Corresponding STS SR 3 4.12.4 however. requires this verification every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The ITS Basesjustifies the 72-hour Frequency using the STS Bases' justification for the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency: how can that be acceptable? In addition, the Frequency should be consistent with tne Frequencies of similar verifications of RHR loop Operability specified by ITS SR 3.4.6.1, ITS SR 3.4.7.1 and ITS SR 3.4.8.1. Each of these require that the required RHR loops be verified as Operable and/or in operation every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Operable means to verify the position of valves in the flow path which is the same check required by ITS SR 3.4.12.5.

Comment: Revise the submittal to adopt the STS Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and add a justification for this more restrictis e surveillance interval. The requirements in the ITS for RHR system ought to be as consistent as are the corresponding

)

requirements in the STS.

Comed Resporse to issue No change. Verifying that the RHR suction relief valves are open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is current licensing basis.

Furthermore, STS SR 3.4.12.4 is a bracketed surveillance, whereby in the conversion to ITS the utility adds their plant specific value. Comed continues to pursue the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> frequency of our current licensing basis.

NRC RAI Number NRC Issued Date RAI Status 3.4.12-07 3/9/98 Closed l NRC Description of issue h

DOC Al I

JFD BPI CTS 4.4.9.3.2.e ITS SR 3.4.12.5 STS SR 3.4.12.4 CTS 4.4.9.3.2.c requires for the RHR suction relief valves " Testing pursuant to Speci0 cation 4.0.5." The ITS apparently does not retain this specific requirement.

Also, the Bases ofITS SR 3.4.12.5 does not adopt the text regarding IST contained in the Bases discussion for corresponding STS SR 3.4.12.4. This change and difference are not editorial but are less restrictive technical CTS changes which require a separatejustification. Comment: Revise the submittal with additional technicaljustification for deleting the IST program CTS requirements for RHR relief valves. Why is there no SR for testing in accordance with the IST Program for these valves? See comment 3.4.12-11.

Comed Response to issue DOC A33 was created to discuss CTS Specification 4.0.5 relocation. DOC A33 states," CTS Specification 4.0.5 provides

. surveillance requirements for inservice inspection and testing of ASME Code Class I,2, and 3 components. In accordance with NUREG-1431, CTS Specification 4.0.5 has been relocated to ITS Specification 5.5.8, " Inservice Testing Program."

The requirements for Inservice Testing have not changed and are still consistent with ASME Section XI. The requirements for the inservice Inspection are contained in 10 CFR 50.55a and the:efore not included in the NUREG. This change has been justified in the ITS submittal as an administrative change thoughout the CTS markups since no ASME or CTS inservice Testing requirements were changed. The only change that was made was in relocation of the regiairements from CTS 4.0.5 to ITS 5.5.8." in addition, Comed will revise the Bases for ITS SR 3.4.12.5 to adopt the STS text stating, "The ASME Code,Section XI (Ref. 7). test per Inservice Testing Program verifies OPERABILITY by proving proper relief valve mechanical motion and by measuring and, if required, adjusting the lift setpoint." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.11-02.)

32

1

\\

Rzspons? to NRC RAI For ITS Section 3.4 oo-oci98

~

NRC RAI Number NRC lssued Date RAI Status 3.4.12-08 3'9 98 Closed

.fsy Q

NRC Description ofissue JFD P20 CTS 3/4.4.9.3 Action f ITS 3.4.12 Actions Note 1

CTS 3/4.4.9.3 Action f states "The provisions of Specification 3.0.4 are not applicable " Since CTS 3 4.4.9.3 only addresses the RHR suction relief valves and the PORVs. it appears that this Mode-change restiction exception is retained as the Actions Note to ITS 3.4.12. This Actions Note states "LCO 3.0.4 is not applicable to the RCS relief vahes." Based on maintaing the CTS allowance, this appears acceptable. This note does not address the RCS vents. The STS, howeser. doe >

not contain this note. JFD 20 does not adequately explain why it is acceptable to enter into the Applicability ofITS 3.4.12 without first verifying tne Operability of the RCS relief valves that are to be relied upon for overpressure protection. The statement in JFD P20 and the Bases for this note, that the Required Actions for inoperable relief valves provide an acceptable level of safety, is not convincing. In Mode 4. Action E allows 7 days to restore an inoperbale relief val e. In Mode 5 and Mode 6 with the vessel head on, Action F allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. And in any of these Modes, Action G allows 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore two inoperable relief valves. For any of these conditions and failure to satisfy these Actions, Action G requires depressuring the RCS with an open RCS vent. These Completion Times are consistent with the STS. Yet the STS does not allow an exception to LCO 3.0.4. Comment: Please revise the submittal to provide additional discussion and technical justification for the Actions note.

j Comed Response to issue CTS 3.4.9.3 requires at least two overpressure protection devices to be OPERABLE. either an RHR suction relief valve or a PORV,in Modes 4,5, and 6 with the reactor vessel head on. In the event that one or both required devices are inoperable.

the CTS provides specific actions with Completion Times ranging from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 7 days. The CTS also contains Action f which states. "The provisions of Specification 3.0.4 are not applicable." Action f allows changing Modes without having the overpressure protection devices OPERABLE. As previously stated, the inoperability can range from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 7 days. The

(-

CTS actions also require that the inoperable device (s) be returned to. OPERABLE or an RCS vent be established (at least 2

(

square inch vent) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. STS LCO 3.4.12 requires the same pressure relief capabilities be OPERABLE in the same Modes as the CTS. The STS however, adds the RCS vents to the LCO as one of the pressure relief capabilities. In addition, the STS does not allow any LCO 3.0.4 exceptions. Therefore, the pressure relief capabilities required by the LCO must be OPERABLE for any mode changes to occur. The ITS Note is being revised to state,"LCO 3.0.4 is not applicable to the RCS pressure relief capabilities." Adding this Note brings the ITS into compliance with our current licensmg basis.

Comed believes this to be acceptable since the ITS Required Actions and associated Completion Times are the same as those in the CTS. Therefore, there is no change in any assumptions, calculations or equipment between our current licensing basis and the ITS Thus, no increase in any probability of any accident previously analyzed, no new or different accident introduced. and '. crease in the margin of safety. Based on the above, Comed will continue to pursue and maintain our current licensing usis by retaining the Actions Note as revised by this RAl. This change. vill be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.

33

.=

=._r==_==__==.

-=

R:sponse to NRC RAI For ITS S:ctinn 3.4 09-oct-98 NRC H AI Number NRC issued Date RAI Status 3.4.12 09 3'9'98 Closed i

7,.,..

()

NRC Description ofissue JFD Pl Bases JFD Pl ITS LCO 3.4.12 The initial words oflTS LCO 3.4.12 differ from the STS as follows: "An LTOP System shall be OPERABLE prosided with:" This difference is not editorial because LTOP is apparently no longer consider-d a system and it no longer requires an Operability requirement. The first part should closely follow the STS wording, as follows: "An LTOP S) stem shall be OPERABLE with:" Comment: The proposed editorial difference from the STS is not justifiable on a plant-specific or editorial basis. Revise the LCO to adopt the suggested words and make appropriate language changes m the Bases to conform to the STS.

Cc:nEd Response to issue Comed will revise the LCO to adopt the suggested words and make appropriate language changes in the Bases to conform to the STS. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

. NRC RAI Number NRC issued Date RAI Status 3.4.12 10 3/9/98 Closed NRC Description ofIssue Not Used Comed Response to issue

]

No response required.

\\

\\

l l

l.

("\\

d 34

l Respons; to NRC RAI For ITS Section 3A m-ocim I

NRC RAI Number NRC issued Date RAI Status 3.4.12 11 3 9'98 Closed' l V_

NRC Description ofIssue JFD B2 Bases JFD B2 STS SR 3.4.12.7 Bases Background discussion for suction relief valve requirements.

STS markup page B 3.4-60 Bases JFD P31 ITS does not adopt STS SR 3.4.12.7, serification that each required open RHR suction isolation valve is locked open with i

power removed (apparently needed when the associated RHR relief valve is used to satisfy the LCO for overpressure i

protection). JFD B2 and JFD Bases B2 are not detailed enough to determine the validity of this omission. Comment-Revise the submittal with plant-specific technicaljustification for this deviation from the STS. The CTS markup page 3 4 5

]

5 indicates that CTS 4.5.2.d.1)is retained as ITS SR 3.4.14.2. The NRC staff understands that the RHR suction vahe autoclosure is no longer a part of the unit design. Note the absence of the autoclosure feature from the umt design was discussed with Kelly Root of Braidwood on 2/13/98 by telcon. However, the information in the submittal does not clearly explain why this design difference necessitates deviations from the STS; niether does it clearly list all such deviations.

Note Bases JFD P31 contradicts the preceding stated staff understanding about the autoclosure interlock; JFD P31 states it is a part of the unit design as described in FSAR Section 5.4.7.2.3, but is controlled by procedure. Ifit is part of the unit design, then the STS provisions related to it and associated Bases ought to be adopted to ensure the Operability of the RHR l

relief valves when they are relied upon for RCS overpressure protection to meet ITS LCO 3.4.12. Note FSAR Section 5.4.7.2.3 was reviewed and it supports the absence of the autoclosure interlock from the design. Suggest that JFD P42 be revised to also address not adopting STS SR 3.4.12.7 Comed Response to Issue No change. NUREG SR 3.4.12.7, SR 3.4.14.2, and SR 3.4.14.3 are bracketed surveillances. Comed believes that LCO

[]

JFDs 3.4-82 and 3.4-B3 are sufficient forjustifying the deletion ofinformation that is not applicable to Byron and V

Braidwood, and that this approach is consistent with conversion guide ines and the process used throughout the submittal Comed agrees that Bases JFD 3.4-P31 is incorrect in stating that an at toclosure interlock is provided. Bases JFD 3.4-P31 l

will be revised to state, "NUREG-1431 SR 3.4.14.3 and associated Bms have been deleted and the Bases for both LCO 3.4.12 and LCO 3.4.14 are revised to omit references to the autoclosure interlock. Only the open permissive interlock l

function is included. This is consistent with CTS SR 4.5.2.d.1 and NRC SER dated 8!31/90 for Amendment 38/25. The interlock is discussed in UFSAR Section 5.4.7.2.3." This JFD discussion is based on the following excerpt from UFSAR Section 5.4.7.2.3. "During plant startup, the inlet isolation valves are shut administratively. However, an alarm is provided to alert the operator in the event that double isolation is not being maintained when RCS pressure increases above 400 psig.

These isola' ion valves are provided with "prevem-upen" interlocks, which are designed to prevent possible exposure of the RHR System to normal RCS operating pressure... The use of two independently powered motor-operated valves in each of the two inlet lines, along with two independent pressure interlock signals in the opening and alarm circuitry ensures a design which meets applicable single failure criteria." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

l l

!p V

l 35

l l

R:spons2 to NRC RAI For ITS Section 3A 09-Oct-98 l

- = =. = = = -.

l NRC RAI Number NRC Issued Date RAI Status 3.4.12-12 3'/9/98 Closed

[ n\\

<V NRC Description ofissue -

LA14 l-CTS 4.5.4.2.1 (Note this is the principal reference for this comment.)

CTS 4.5.4.1 and associated Note

  • CTS 3.5.4.1 CTS 3/4.5.4.1 Action CTS 4.5.3.2 11S SR 3.4.12.I Bases for ITS 3.4.12 CTS 4.5.4.2.1 requires at least one Si pump shall be demonstrated available when required every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ITS SR 3.4.12.1 verifies no Si pump is capable ofinjecting into the RCS. These two SRs do not appear to be equivalent. but this is implied by the CTS markup, page 3/4 5-10. Also, the discussion in DOC LA14 only :upports removing details about restricting sources of high pressure water injection into the RCS. This change, however, removes details related to the Operability of required SI pump and associated flow path from the RWST to the RCS. Further, the discussion in DOC LA14 does not specifically address (or list) CTS 4.5.4.2.1, so there is a question about whether it applies to the detail removal as indimted in the CTS markup. A new CTS DOC seems to be reqtaired to justify the removing the details of CTS 4.5.4.2.1 to the Bases.

Comment: Revise the submittal with the indicated technicaljustification. In addition, state where the information, as indicated by the markup of CTS 4.5.4.2.1. is contained in the ITS Bases.

Comed Response to issue JFD 3.4-LA14 will be revised to add a paragraph which states, " CTS LCO 3.5.4.2 establishes controls which ensure that I

diverse means ofintroducing makeup water from the RWST to the RCS are available in the event that a loss of inventory or loss of forced circulation occurs which results in a loss of decay heat removal. The LCO requires a Safety injection (SI) 1

- pump and flow path or an adequate RCS vent to allow gravity feed from the RWST to be available when in Mode 5 and 6

. [N with the pressurizer level less than or equal to 5 percent. These requirements were added in response to Generic Letter (GL) 88-17. " Loss of Decay Heat Removal." This Specification does not satisfy the Technical Specification Screening Criteria j

(see ITS Section 3.5 DOC RI). Howevet, CTS SR 4.5.4.2.1 also provides Low Temperature (cold) Overpressure Protection (LTOP) from inadvertent Si actuatior as indicated in the SER for ByrorvBraidwood Amendment 38'25. Section 2.2 dated i

August 31,1990. This portion of the requirements is retained in ITS SR 3.4.12.1. The detail of demonstrating the availability of the Si pump is relocated to the TRM. The relocation of this information maintains the consistency with NUREG 1431. Any change to this requirement is made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

l l

l l

l f

Ix 36 l:

R:sponse to NRC RAI For ITS Section 3.4 09-oct os 7

y

. - ~ -

NRC RAI Number NRC issued Date RAI Status 3.4.12-13 3'/9'98 Closed j g l

NRC Description of Issue l

DOC LA25 CTS 3/4.4.9.3 Action e CTS 3/4.4.9.3 Action e, requires a report to the NRC in the event the specified pressure relief valses are used to mitigate an RCS pressure transient, pursuamt to CTS 6.9.2. This Action is not retained in ITS 3.4.12. but is mosed to the TRM. The justification in DOC LA25 states it is acceptable to relocate this requirement to the TRM because the Special Report is not i

approved by the NRC. Staff disagrees. The only acceptable basis for this relocation it whether there exists any redundancy in regulato.y raquirements which control the preparation and submittal of the esent reports to the NRC. Comment: Reuse the submittal to proside additional technicaljustification for moving this reporting requirement to the TRM. If not addressed in response to another similar comment, list the dispostion of all such CTS reporting requirements, and show that the submitted justifications are consistent with the aceptable basis noted above. (i.e., this may be a global comment.)

Comed Response to issue Comed will revise DOC LA25 to state, " CTS 3.4.9.3.e provides a requirement to submit a Special Report in accordance with CTS Specification 6.9.2 in the event that the PORVs, the RHR suction relief valves, or the RCS vents are used to mitigate an RCS pressure transient. This requirement is to be relocated to the TRM. Relocating this requirement to the TRM is consistent with other required reports in the CTS. As discussed in Section 5.0 DOC A12. CTS Epecification 6.9.2 has been revised to delete the reference to the submittal location for the Special Reports. The requirements related to report submittal are contained in 10 CFR 50.36,10 CFR 50.72, and 10 CFR 50.73. Since conformance to 10 CFR 50 is a condition of the license, specific identification of this requirement in the TS would be duplicative and is not necessary. In addition, the Special Reporting requirements are deleted from the STS since they do not meet 10 CFR 50.36(c)(2)(ii) criteria for retention in the TS. As such, the relocated requirement is not required to be in the TS to provide adequate protection of the public health and safety. The relocation of this requirement maintains the consistency with NUREG-1431. Any changes to this requirement will be made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS A

Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.

Y

'~

NRC RAI Number NRC issued Date RAI Status 3.4.12-14 3/9'98 Closed NRC Description of issue Not used Comed Response to issue No response required.

NRC RAI Number NRC issued Date RAI Status 3.4.12-15 3/9/98 Closed NRC Description of issue Not used Comed Response to issue No response required.

\\

l V t

37

R:spanse to NRC RAI For ITS S:ction 3.4 09-oci-98 NRC RAI Number NRC issued Date RAI Status 3.4.12 16 3'9'98 Closed

(f~s\\

i l

NRC Description of issue f (/.

' Not used Comed Response to issue No response required.

NRC RAI Number NRC issued Date RAI Status 3.4.12 17 3/9'98 Closed NRC Description ofissue Bases JFD Pi Bases for ITS SR 3.4.12.7, STS markup page B 3.4 71 The second paragraph of the Bases for STS SR 3.4.12.8 has not been adopted in the Bases for correspondmg ITS SR 3.4.12.7. This omission is not explicitlyjustified.

Comment: Revise the submittal to adopt the omitted paragraph.

Comed Response to issue Comed will revise the submittal to adopt the omitted paragraph. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

_7 NRC RAI Number NRC issued Date RAI Status 3.4.13-01 3/9/98 Closed

' NRC Description ofIssue Q-Not used Comed Response to issue No response required.

l im i '

)

'%J i

38

=

= - - - - -

Respsuse to NRC RAI For ITS Section 3.4 09 ocim

=... :.;. ; --- - --

1 NRC RAI Number NRC lssued Date RAI Status p

3.4.13-02 3'9'98 Closed j

NRC Description of Issue DOC LA24 CTS 4.4.6.2.1.a. b. and e CTSs J 1611.a. b, and e require monitoring the containment annosphere radiation monitor the reactor cavity sump discharge, and the containment floor drain sump discharge and inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. and the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. DOC LA24 states these surveillances are relocated to the TRM because they are not necessary to ensure RCS operational leakage is maintained within limits. This is not a sufficient technical j

justification. Comment: Revise DOC LA24 with additional technicaljustification for moving these SRs to the TRM.

Describe how the ITS will ensure RCS operational leakage is maintained within limits.

Comed Response to issue Comed will revise DOC LA24 to state," CTS SR 4.4.6.2.1.a. SR 4.4.6.2.1.b. and SR 4.4.6.2.1.e proside requirements for monitoring the containment atmosphere radioactivity, reactor cavity sump discharge, the containment floor drain sump discharge, and inventory, and the reactor head flange leakoff. These requirements are being relocated to the Technical Requirements Manual (TRM). These requirements, along with other ITS requirements, provide monitoring functions for indicating RCS Operational Leakage. These specific requirements do not meet the 10 CFR 50.36(cK2)(ii) criteria for retention in the STS and therefore the ITS. However, their function provides an additional and independent operational indicator for RCS leakage and needs to be retained in a Licensee Controlled Document. The requirements ofITS LCO 3.4.13 provide adequate assurance that RCS Operational Leakage is maintained within the required limits. The relocated information is not necessary to be in ITS to ensure RCS Operational Leakage is within limits. As such. the relocated information is not required to be in the ITS to provide adequate protection of the public health and safety. The relocation of these requirements maintains the consistency with NUREG 1431. Any change to these requirements will be made in accordance with 10 CFR 50.59." This change will be provided in our comprehensive ITS Section 3.4 closecut submittal revision upon NRC's concurrence with the Comed responses to the ITS Section 3.4 RAl.

[

NRC RAI Number NRC issued Date RAI Status 3.4.13-03 3/9'98 Closed NRC Description ofissue Bases JFD PI Bases for STS 3.4.13 Action B, STS markup page B 3.4-76 The first paragraph. second sentence of the Bases for Required Actions B.1 and B.2 is not adopted. The following is not retained: "It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE." Bases JFD Pl does not explain why this statement is not applicable to Byron & Braidwood. Comment: Revise the submittal to adopt the omitted sentence, w hich is generally applicable to Westinghouse 4-loop design.

Comed Response to issue Comed will revise the subminal to adopt the omitted sentence. This change will bt provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Rtsponses to the ITS Section 3.4 RAl.

4 39

r_.

r -

m--

R:spanse to N~RC RAI For ITS Section 3.4 nocim NRC RAI Number NRC issued Date RAI Status 3.4.13-04 1 9'98 Closed n

NRC Description ofissue Bases JFD P43 Bases for SR 3.4.13.1, STS markup page B 3.4 77 The fourth paragraph of the Bases discussion of STS SR 3.4.13.1 is not adopted. This text clearly explains that the leakage monitoring requirements of CTS 3/4.4.6.2 are now located in ITS 3.4.15 which is important information rather than just a cross reference in the Bases. This Bases text (and Comment number 3.4.13-02 above) denotes the importance of these monitors for the detection of reactor coolant system pressure boundary leakage and unidentified leakage The omitted Bases text applies. Comment: Revise the Bases to adopt the omitted paragraph.

Comed Response to issue Comed will revise the Bases to adopt the omitted paragraph with one exception. The word " automatic" is being deleted since there is no automatic system associated with containment sump level. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

--=~.===.=:_=-.

z NRC RAI Number NRC Issued Date RAI Status 3.4.14-01 3/9/98 Closed NRC Description of issue JFD P41 ITS LCO 3.4.14 STS LCO 3.4.14 CTS 4.4.6.2.2

/%

lV)

ITS LCO 3.4.14 states "Each RCS PlV shall be OPERABLE." STS LCO 3.4.14 states " Leakage from each RCS PlV shall be within limits." JFD P41 states the revision is to reflect both the leakage requirements and the interlock functions requirements. This deviation from the STS is generic and is notjustifiable on a plant-specific basis.

Comment: Revise ITS LCO 3.4.14 to conform to STS LCO 3.4.14 win.,n is consistent with CTS 4.4.6.2.2.

Comed Response to Issue Comed will revise ITS LCO 3.4.14 to conform to STS LCO 3.4.14. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

- NRC RAI Number NRC issued Date RAI Status 3.4.14-02 3/9/98 Closed NRC Description of issue-JFD P46 ITS 3.4.14 Actions Note 2 ITS 3.4.14 Actions Note 2 differs from the STS note as indicated: " Enter applicable Conditions and Required Actions for systems if made inoperable by an inoperable PlV " Acceptance of this editorial deviation would require approval of a generic change to the STS addressing all applicable locations in the STS rather than sporadic changes here and there as implied by JFD P46. Besides, the STS presentation is clearer than the proposed deviation. Comment: Revise the Actions note to conform to the STS wording.

Comed Response to Issue The Note will be revised to adopt the STS wording. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. Note: This change is applicable to ITS LCOs 3.3.5, 3.3.6, 3.4.14, 3.6.2, 3.6.3, 3.7.7, 3.7.8, 3.8. I, 3.8.2, and 3.8.7. (See R A is 3.6.2-02, 4 g (v) 3.7.7-04,3.7.8-06, and 3.8.122.)

i 40 i

T.:.

l- ~ * : ~."..'.L-

. - -. ~. -

R:sponSe to NRC RAI For ITS S:ction 3A 09-o ct 9n l

NRC RAl Number' NRC INu~e' Date ~

~

d RAl Status l

1 I

3.4.14 03 3/9'98 Closed l (n) l V NRC Description ofIssue JFD Bl JFD B2 ITS 3.4.14 Action A Note j

STS 3.4.14 first attemative Required Action A.2 (bracketed) i h

l ITS 3.4.14 Action A Note has adopted the bracketed phrase "[or the high pressure portion of the system]" in the STS Action A note. However the ITS does not adopt bracketed STS 3.4.14 first alternatise Required Action A.2. pertaining to valses in the high pressure portion of the system. This is an inconsistent usage of the STS. If Comed does not used the first alternate, then this bracketed phrase in the note cannot be adopted. Comment: Revise the submittal to correct this STS technical usage l

error.

Comed Response to issue l

ITS 3.4.14 Required Action A Note has adopted the bracketed phrase "[or the high pressure portion of the system]" of the NUREG. Comed will revise the submittal to adopt the bracketed first alternative specified in Required Action A.2 to make j

j the ITS Note and the Required Actions consistent. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

... -. -. =

_=

_ -. = _

NRC RAI Number NRC issued Date RAI Status 3.4.14-04 3/9/98 Closed 1

NRC Description ofIssue JFD PI ITS 3.4.14 Required Actions A.1 and B.I ITS 3.4.14 Required Action A.I differs from the STS by adding a "de-energized power operated" valve to the list of valve alternatives. And ITS 3.4.14 Required Action B.I differs from corresponding STS 3.4.14 Required Action C.I so only a "de-energized" valve is used instead of a closed manual or de activated automatic valve. These are not editorial deviations but are technical deviations that are not justified by JFD Pl. Comment: Revise the submittal to adopt the STS wording or add a JFD with an appropriate plant-specife justification.

Comed Response to issue Revised Response: Refer to LCO JFD 3.4-48. This change is provided in our comprehensive ITS Section 3.4 c;oseout submittal Revision K.

Original Response: Comed will add an LCO JFD to justify this change. The JFD will state, "The references to " manual."

" remote-manual," " power-operated." " check," and " automatic" is not consistent within the STS. Byron /Braidwood plant specific terminology distinguishes between the classification of valves designated as " power operated" and " automatic."

Automatic valves refer to those valves that require a motive force to actuate, such as air or electric, and receive an automatic actuation signal. Automatic air operated valves and automatic electric operated valves fall into this category. Power operated valves, on the other hand, require a motive force to actuate, such as air or electric, but do not receive an automatic actuation signal. Air power operated valves and electric power operated valves fall into this category. Therefore, including the reference to " power operated" isolation valves reduces the potential for misinterpreting the requirements of the Required Action, while maintaining the assumptions of the accident analysis, and is consistent with plant specific terminology. The words " closed manual or der.ctivated automatic" have been deleted from NUREG Required Action (RA) C.1 due to those classifications of valves not being applicable to the penetrations with the RHR System suction isolation valves. With the RHR System suction isolation valve interlock function inoperable, ITS RA B.I requires that the affected RHR suction penetration be isolated by at least one de-energized power operated valve, i.e., an RHR suction isolation valve." This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed l

Responses to the ITS Section 3.4 RAl. (See RAI 3.6.3-07.)

t

.( J i

41

-.= = = =. = = =

= -,

R:sp:ns: to NRC RAI For ITS SIctinn 3A 09-oct 98 NRC RAI Number NRC issuid Date RAI Status

~

~

~

3.4.14-05 3/9/98 Closed

,m by-NRC Description of Issue i

. Not used I

Comed Response to issue No response required.

z.-

=,==:...

~

= =..

NRC RAI Number NRC issued Date RAI Status 3.4.14-06 3/9'98 Closed NRC Description ofissue JFD Pl CTS 4.4.6.2.2.b ITS SR 3.4.14.1 The Frequency Note Stating " Prior to entering Mode 2.. " has been editorially changed in ITS SR 3.4.14.1 when the CTS /STS wording for this statement is identical. Comment: Please revise the submittal. The STS text is applicable, clear.

and should be adopted.

Comed Response to issue No change. While Comed agrees that the NUREG text is clest as written, it is not standard ITS format to use "words" in place of equalities and inequalities in ITS. A phrase such as "7 days or more" is not used anywhere else in the NUREG and therefore, Comed continues to pursue this change for consistency throughout ITS.

=,.=..

NRC RAI Number

. NRC Issued Date RAI Status 3.4.14-07 3/9/98 Closed A(*)

NRC Description ofIssue JFD Pi CTS 3.4.6.2.f footnote

" equivalent" RCS pressure for testing PI'/s. CTS 3.4.6.2.f footnote *, which pertains to defining the equivalent pressure for PlV testing, is moved to the TRM. as explained by DOC LA10, because these details are not needed in the ITS. Note, however, that the last paragraph of the Bases for STS LCO 3.4.14 already contains the information specified by the CTS footnote. Comment: The addition of the modifier " equivalent" is an unnecessary generic change and is not accepted. - Revise the submittal to adopt the STS wording. Revise DOC LA10 to explain that the allowance to use an equivalent pressure is moved to the Bases in addition to the TRM. Suggest augmenting the Bases for ITS SR 3.4.14.1 to explicitly discuss the testing at lower pressures; i.e., at equivalent pressures - scaling the leakage measured at a reduced pressure to the equivalent leakage at the speciflied test pressure for comparison to the specified leakage limit.

Comed Response to issue DOC 3.4-LA10 will be revised to state," CTS LCO 3.4.6.2 Footnote

  • provides details of Pressure Isolation Valve (PlV) test performance for various unit conditions. These details are to be relocated to the ITS Baras. The requirements ofITS SR 3.4.14.1, which include leakage limits stated in terms of equivalent leakage rates with a specified pressure range, are adequate to ensure RCS PlV leakage is within required limits. As a result, the relocated details are not necessary for ensuring RCS PlV leakage is within required limits and do not need to be included in the TS to provided adequate protection of the public health and safety. The relocation of these details maintains the consistency with NUREG-1431. Any change to r-these details will be made in accordance with the Bases Control Program described in ITS Section 5.5 " In addition, the l-modifier " equivalent" will be withdrawn from ITS SR 3.4.14.1, and the ITS Bases will be revised to include the details q

associated with the CTS footnote. This change will be provided in our comprehensive ITS Section 3.4 closecut submittal

' revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

42

l l

Respnnse to NRC RAI For ITS Section 3A oo-Oei98

- =:.

NRC RAI Number NRC lssued Date RAI Status l

3.4.14 08 3'9'98 Closed

)

NRC Description ofissue JFD P26 ITS SR 3.4.14.1 ITS SR 3.4.14.1 omits the STS' requirement to perform PlV leakage testing at a Frequency in accordance with the Insen ice Test Program. The ITS requiress the test to be performed at 18 month mtervals but not per the IST Program. JFD P2o and Bases JFD P1 for SR 3.4.14.2 do not adequatelyjustify this deviation. Comment: Revise ITS SR 3.4.14.1. and associated Bases, to adopt the STS Frequency of"in accordance with the Insenice Test Program."

l Comed Response to issue Revised Response: Per discussions with the NRC Reviewer. Comed has adopted the NUREG Frequency for SR 3.4.14.1-This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.

l l-Original Response: Comed will revise ITS SR 3.4.14.1 Frequency to state. "In accordance with the Inservice Testing Program." The PlVs are tested in accordance with the Strc. ion's IST Program which was developed in accordance with ASME Section XI requirements. In addition, Comed will delete the 18 month Frequency currently in ITS since the Inservice Testing Program Frequency is also 18 months. It is not standard NUREG format to include specific times with Frequencies which are in accordance with Programs, such as "In accordance with the Inservice Testing Program." There is no benefit in stating the same time Frequency for the same SR twice. Comed will revise the ITS Bases for SR 3.4.14.1 to include the STS wording referencing the Inservice Testing Program. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

l

=

NRC RAI Number NRC issued Date RAI Status 3.4.14-09 3/9/98 Closed

=/N NRC Description of Issue JFD P47 CTS 4.4.6.2.2.b ITS SR 3.4.14.1 Frequency The wording of the third Frequency ofITS SR 3.4.14.1 differs from the STS. Instead of"Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following.,it says "Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after.." Comment: These editorial changes are unnecessary and notjustificable on an editorial or plant-specific basis. The STS wording is clear. Adopt the STS version of the Frequency.

Comed Response to Issue Comed will adopt the STS version of the Frequency. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09,3.4.16-05, and 3.4.18-03.)

NRC RAI Number NRC lssued Date RAI Status 3.4.14-10 3/9/98 Closed NRC Description ofissue Not used Comed Response to issue No response required.

U t

i 43

l Resp:nse to NRC RAI Fcr ITS S:ction 3A co-oei-98 NRC RAI Number NRC issued Date RAI Status f3 3.4.14 11 3.'9 98 Closed i(,/

' NRC Description of issue

?!)tused Comed Response to issue No response required.

. -. -.. - _. = _. =.=.

NRC RAI Number NRC issued Date RAI Status 3.4.14 12 3.'9'98 Closed j

NRC Description ofissue Bases JFD Pl Bases for ITS 3.4.14 Action Notes. STS markup page B 3.4-81 in the first paragraph, the fourth sentence the ITS differs from the STS as follows: " Note 2 requires an evaluation of affected systems Emergency Core Cooling System subsystems if a PlV is inoperable. The ITS wording appears to be less restnctive than the STS wording because some of these PIVs could also be considered to be in the CVCS or RCS Systems. Thus, this may not bejust an editorial change, and may also be generic. Cornment: Revise the Bases to adopt the STS wording.

Comed Response to issue i

Comed will revise the Bases to adopt the STS wording. This ci ange will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

.___.,. =.;,

= NRC RAI Number NRC issued Date RAI Status 3.4.14-13 3/9/98 Closed 4

NRC Description of issue '

%)

Not used Comed Response to issue No response required.

l 44

==-

Respanse to NRC RAI For ITS Section 3A oo-oct-98 NRC RAI Number NRC issued Date RAI Status m

3.4.15-01 3,9.'98 Closed 1

NRC Description of Issue DOC Ll7 l

DOC L19 JFD P27 JFD BP27 CTS 3.4.6.1.a and c CTS 3.4.6.1 Action c '

I ITS 3.4.15 and Action B CTS 3.4.6.1.a. b. and c define three separate RCS leakage system monitors as required to be Operable. Reg Guide 1.45 requires this number of diverse monitors and a minimum of two shall always be Operable. STS 3.4.15 contains provisions to ensure that two diverse monitors are Operable. ITS 3.4.15 and Action B have changed the CTS requirements to combme the

{

sepa ate gaseous and particulate monitoring functions into one monitor. The result is that when the one monitor is lost then F

both functions are lost. Also. the time permitted for this inoperable condition has been extended from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 30 days i

i with only the one sump monitor Operable during this period. For a 30 day period, when one of three are inoperable (if Condition B was changed to a gaseous or particulate monitor is inoperable) performing SR 3.4.13,1 is acceptable compensatory action. When two of the three (both gaseous and particulate functions) monitors are inoperable for a 30 day period, SR 3.4.13.1 or grab samples as the next monitoring system is not acceptable because the monitoring response times are greatly extended. This ITS Action B is contrary to the intent of Reg Guide 1.45. Comment: Please provide additional discussion and technicaljustification for this less restrictive change.

j Comed Response to issue i

Revised Response: Per discussions with the NRC Reviewer, no change required.

Original Response: Comed will rewrite ITS 3.4.15 to incorporate a Condition when one gaseous or particulate containment

)

l atmosphere radioactivity monitoring function is lost, and when both the gaseous and particulate containment atmosphere n/

radioactivity monitoring functions are lost. This change will be provided in our comprehensise ITS Section 3.4 closecut

{

submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

i NRC RAI Number NRC lssued Date

. RAI Status 3.4.15-02 3/9/98 Closed NRC Description of issue Not used Comed Response to issue

)

No response required.

(

(

u t

l 45 l

,. =

=

= =

l R sponse to NRC RAI For ITS S:ction 3.4 09-oci.98 NRC RAI Numb r RIlssbDa RIl Status

~'

l

~

3.4.15 3/9'98 Closed n

Q)

NRC D'escription of Issue l

DOC LA9 CTS 3/4.4.6.1 Action a Bases for ITS 3.4.15 Action B STS markup page B 3.4 89 l

j.

CTS 3.4.6.1 Action a requires analysis of the containment atmosphere grab samples for gaseous and particulate j

l radioactivity. DOC LA9 says the specific requirement to analyze the grab samples for both particulate and gaseous actn ity is a detail which is moved to the ITS Bases. The Bases for ITS 3.4.15 Action B. however. only mentions taking grab samples. but does not describe the CTS requirement for analysis. Comment: Even though the proposed discussion in the Bases for ITS 3.4.15 Action B is consistent with the STS, it must be revised so that the statement in DOC LA9 is accurate.

Comed Response to issue The first paragraph of the Actions Section of the Bases for ITS LCO 3.4.15 for Actions B.1 and B.2 will be revised to state.

"Either grab samp!es of the containment atmosphere must be taken and analyzed for gaseous and particulate radioactivity or water inventory balances, in accordance. " This change will be provided in our comprehensive ITS Section 3.4 closecut j

submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

NRC RAI Number NRC issued Date RAI Status 3.4.I6-01 3/9/98 Closed

)

NRC Description ofIssue Not used Comed Response to issue No response required.

(o)

NRC RAI Number NRC issued Date RAI Status 3.4.16-02 3/9/98 Closed NRC Description ofIssue Not used i

Comed Response to issue No response required.

NRC RAI Number NRC issued Dcte RAI Status 3.4.16-03 3/938 Closed NRC Description of issue Not used Comed Response to Issue No response required.

l i

/

f t: L l

46

~ R$sph~nsh to NRC RAI For ITS S ction 3.4 09-oci 98 NRC RAI Number NRC issued Date RAI Status I

3.4.16-04 3 9'98 Closed

-m

\\

V NRC Description ofIssue JFD P29 CTS Table 4.4-4 Measurement Type 3, Footnote

  • states the timing for the beginning of Frequency for when the E-bar determination is to be taken. STS SR 3.4.1.6.3 states this interval in both the Note and the SR 3.4.16.3. ITS SR 3.4.16.3 only states this timing in the Note. The change is not a plant specific change based upon a current CTS requirement.

Comment: Revise the submittal to adopt the omitted text of STS SR 3.4.16.3.

Comed Response to issue Comed will revise the submittal to adopt the omitted text of STS SR 3.4.16.3. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

NRC RAI Number NRC issued Date RAI Status 3.4.16-05 3/9/98 Closed NRC Description ofissue JFD P47 Bases JFD Pl CTS Table 4.4-4, Measurement Type 4b STS SR 3.4.16.2 Frequency and associated Bases ITS SR 3.4.16.2 Frequency and associated Bases In ITS SR 3.4.16.2, the word "once" is added to the STS Frequency which specifies a Frequency of"within" a particular time frame. For this Frequency,"within" is "between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a Thermal Power change of 15% RTP within a I hour period." It is clear that the STS (and CTS) Frequency means once for each such power change. Also, the STS SR Frequency is worded the same as the wording of the Frequency for CTS Table 4.4-4 Measurement Type 4b. Comment: This generic editorial deviation is unnecessary. Revise the Frequency consistent with the STS and CTS. Also withdraw the two apparent generic editorial deviations from the Bases for STS SR 3.4.16.2. In particular, the replacement of" inaccurate" with "less conservative" in the Bases is actually a technical change and is notjustified.

Comed Response to issue Comed will revise the Frequency consistent with the STS, and will withdraw the changes to the Bases for STS SR 3.4.16.2.

This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-09,3.4.14-09, and 3.4.18 03.)

l Q) '

47 I

L l

l

Resp:nse to NRC RAI For ITS Section 3.4 09-Oct 98 NRC RAI Number NRC lssued Date RAI Status 5

i 3.4.16-06 3998 Closed V

NRC Description ofIssue CTS 3.4.8 Table 4.4-4 Measurement Types 2 and 4b ITS 3.4.16.2 Note if the unit is in Mode 1,2 or 3. CTS 3.4.8 Table 4.4-4 Measurement Type 4b requires an isotopic analy sis of a reactor coolant sample for lodine including I 131,1 133, and 1 135 on a Frequency of"between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a Thermal Power change of 15% RTP within a i hour penod." The CTS markup indicates that ITS 3.4.16.2. verification of reactor coolant Dose Equivalent 1-131 specific activity, corresponds to this isotopic analysis. ITS SR 3.4.16.2 contains a note. consistent 1

with the STS, that only requires this test at the CTS Frequency if the unit is in Mode 1, which is less restrictive than the CTS applicability requirement. The submittal contains no technicaljustification for this change in applicability. Notice that the i CTS markup also indicates that ITS SR 3.4.16.2 corresponds to CTS Table 4.4-4 Measurement Type 2, isotopic analysis for Dose Equivalent 1 131 concentration, which is only required to be performed in Mode 1, Comment: Add an L-type DOC with technicaljustification for this less restrictive change to the CTS. Explain why ITS SR 3.4.16.2 satisfies the requirements of both Measurement Types 2 and 4b, as implied by the CTS markup.'

Comed Response to Issue Revised Response: Refer to CTS DOC 3.4-L39. This change is provided in our comprehensive 1TS Section 3.4 closeout submittal Revision K.

- Original Response: CorrsEd will revise the submittal to include DOC 3.4-LA30 stating, " CTS Table 4.4-4 Item 2 requires DOSE EQUIVALENT (DE) 1 131 concentration to be determined to be less than or equal to 0.35 pCi/gm for Unit I (1.0 pCi gm for Unit 2) once per 14 days while in Mode 1, item 4 requires an isotopic analysis for lodine including 1-131,1-133, and 1 135 once between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period while in Modes 1,2, and 3 with no limit imposed. NUREG SR 3.4.16.2 requires DE I 131 to be determined once per 14 days and once between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of greater than or

.(~

equal to 15% RTP within a i hour period while in Mode 1. NUREG SR 3.4.16.2 places a limit ofless than or equal to 1.0

(

pCilgm for DE I.131. The NUREG, and therefore ITS, do not require the Isotopic Analysis for 1 131,1-133, or 1 135 to be performed. The purpose for the analysis ofI-131,1 133, and 1 135 with a power change of greater than or equal to 15% is to

- trend possible fuel cladding leakage or failure following fast power changes when fuel failure is more apt to occur.

Relocating this requirement to the TRM still maintains its SR function for trending any fuel leakage. However, this requirement is not necessary to ensure DE l-131 is maintained. As such, the relocated requirement is not required to be maintained in the ITS, per 10 CFR 50.36(c)(2)(ii), and is not required to provide adequate protection to the public health and safety. Any changes to this requirement will be made in accordance with 10 CFR 50.59." In addition, the Frequency of "Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of greater than or equal to 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period" will be deleted from NUREG SR 3.4.6.2 Surveillance Requirement and the Surveillance Requirements Section of the Bases for ITS LCO 3.4.16. This change will be provided in our comprehensive ITS Section 3.4 c!oseout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAI.

l 4

J r

48 l

= -.

.- - - -.. =.

Response to NRC RAI For ITS Sectica 3.4 09-Oct-98 kAlStatus NRC RAI umber C5 e at n

3.4.16-07 i'9'98 Closed I.v)

NRC Description ofissue Bases JFD Pl Bases discussion Applicable Safety Analyses. STS markup page B 3.4 93 In the first paragraph, last sentence, the STS text pertaining to the safety ant. lysis assumption for secondary specine reactivity was not adopted. The ITS Bases only retains a redernece to ITS LCO 3.7J 7. This is a technical change (and not an editorial change) which requires an explanation or adoption of the STS text. Comment: Revise the Bases to adopt the STS text.

Comed Response to issue Comed will revise the Bases to adopt the STS text. This change will be provided in our comprehensive ITS Section 3 4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

NRC RAI Number NRC lssued Date RAI Status 3.4.16-08 3/9/98 Closed NRC Description of issue Bases JFD P3 Bases discussion Applicable Safety Analyses, STS markup page B 3.4-95 The e:ghth paragraph is not adopted based on editorial enhancement. The omitted text, however, is applicable to a standard plant and should be adoptet In addition, this is a generic technical deviation from the STS. Comment: Revise the Bases to

. adopt the omitted STS text.

Comed Response to issue

-[ 7 Comed will revise the Bases to adopt the omitted STS text. This change will be provided in our comprehensive ITS Section

(,gl 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

NRC RAI Number NRC lssued Date RAI Status 3.4.I7-01 3/9/98 Closed NRC Description ofIssue Bases JFD P3 Bases discussion of Background, STS markup page D 3.4A9 The Bases Background text identified as items a. b and e in the second paragraph is not adopted. This omission is characterized by Bases JFD P3 as a plant specific editorial enhancement. This editorial deviation fro n the STS Bases is generic and could apply to all Westinghouse plants with RCS loop isolation valves. Comment: Revise the Bases to adopt the omitted STS text. See similar comment 3.4.18-04.

Comed Response to issue Revised Response: Minor changes were made to the Bases for ITS LCO 3.4.17 due to changes associated with ITS 3.4.18 LCO and Bases. This change is provided in our comprehensive ITS Section 3.4 closecut submittal Revision K.

Original Response: The paragraphs omitted from the Background Section of the Bases for ITS LCO 3.4.17 pertaining to ITS LCO 3.4.18 for opening the RCS loop isolation valves will be retained with appropriate changes made to reflect corresponding changes made to ITS LCO 3.4.18. This change will be provided in our comprehensive ITS Section 3.4

. closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI s 3.4. I 8-04.)

.Q V

49 I

= =..

Response to NRC RAI For ITS S:ction 3A 09-oct-98 1-NRC RAI Number NRC issued Date RAI Status l

3.4.17-02 3/9'98 Closed

.,.m iV)

NRC Description ofissue l

Bases JFD P44 I

Bases for ITS LCO 3.4.17 STS Markup page B 3.4-100 -

l.

Bases insert B 3.4 100A JFD P44 states the paragraph was not adopted because the discussion relates to ITS 3.4.18. Staff thinks it is appropriate to state what happens in related LCOs to fully explain the context of the LCO requirements. Thus the omitted STS test should be adopted as applicable. Not doing so would be an unjustified generic deviation from the STS. Note that Bases insert B 3.4100A is acceptable and can be included with suitable editorial changes to accommodate the STS text. Comment: Resise the Bases to adopt the omitted STS text.

Comed Response to issue Revised Response: Minor changes were made to the Bases for ITS LCO 3.4.17 due to changes associated with ITS 3.4.18 LCO and Bases. This change is provided in our comprehensive ITS Section 3.4 closecut submmal Revision K.

Original Response: Comed will revise the ITS Bases to adopt the omitted STS text, but will also retain Bases insert B3.4-100A as a second paragraph in the LCO Section of the Bases for ITS LCO 3.4.17 This change will be provided in our comprehensive ITS Section 3.4 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl.

n.-

NRC RAI Number NRC issued Date RAI Status 3.4.17-03 3/9/98 Closed NRC Description ofissue Not used n

)

Comed Response to Issue No response required.

50

Respsnse to NRC RAI For ITS Section 3A no-Oct 98

.m

~

NRC RAI Number NRC issued Date RAI Status n

3.4.18-01 3 '9 +98 Closed Q) -

NRC Description of issue r

DOC A28 DOC L18 JFD P31 Bases JFD P36 Bases JFD P!

ITS 3.4.18 CTS 3'4.4.1.5.2 ITS 3.4.18 and associated Bases differ significantly from the STS in that the ITS state requirements for conditions needed to unisolate an isolated loop - rather than conditions for maintaining a loop isolated. In addition, the ITS proposes to permit unisolating a loop with the boron concentration in the loop less than the remainder of the RCS, provided that it is greater than the required SDM boron concentration. Note: These changes are not plant specific requirements and are not part of the current licensing basis. This deviation is miscategorized as plant-specific under the NEl 96-06 guidelines of Section 2. '

j Deviations from the Applicable STS. This is a generic deviation from the STS. DOCS A28 and L18 are prepared to j

implement the P31 deviation in the CTS. Staff can not review these CTS changes until a generic change to the STS 1

consistent with the deviations addressed by JFD P31 is approved by the staff. Therefore, ITS 3.4.18 and all associated deviations from the STS Bases can not be reviewed at this time. Note: There are also editorial changes categorized as PI and BPI when thay are changes incorporating the technical change P31. Comment: Revise ITS 3.4.18 to be consistent with j

STS 3.4.18 and CTS 3/4.4.1.5.2.

1 Comed Response to issue Revised Response: Per discussions with the NRC Reviewer on 9/3/98, Comed has adopted the NUREG format for ITS LCO 3.4.187 (Note: ITS 3.4.18 changes associated with Beyond Scope change #7 were accepted by the Staff at meetings on j

5/7/98 and 7/8/98, and via telecon on 9/17/98.) This change is provided in our comprehensive ITS Section 3.4 closeout i

submittal Revision K.

d Original Response: As discussed with the NRC Reviewer during the April 2,1998 meeting in Rockville. this change is not a generic change since the only other Westinghouse plants equipped with loop stop valves are Zion and Millstone. Zion is not implementing ITS and Millstone will be pursing an ITS conversion within six months following their restart. Therefore, per conversations with the NRC Reviewer, since Byron and Braidwood are the only operating plants for which this specification applies, Comed will pursue this change as plant specific. NUREG LCO 3.4.18, "RCS isolated Loop Startup," conflicted with the nomenclature of CTS 3.4.1.5.2 " Loop Isolation Valves - Shutdown" by referring to conditions to maintain the loops isolated rather than identifying the requirements needed to unisolate the RCS loop. Along with Comed's response to the LCO 3.4.18 RAls, Comed believes that DOC 3.4-A28 adequately addresses plant specific changes associated with LCO JFD 3.4 P31.

In reference to DOC 3.4-L18, this change was approved in the Zion Safety Evaluation Report for implementation of the improved Technical Specifications as a less restrictive change from Current Licensing Basis (CLB) after the isolated loop boron concentration was greater than or equal to the required cold shutdown boron concentration of the unisolated portion of

' the RCS. This change was approved by the Staff May 30,1975 for Zion amendment number 9 (DPR-39) for Unit I, and amendment number 6 (DPR-48) for Unit 2. The issuance of the above amendments also allowed the plant the flexibility to not meet the requirements for the cold leg stop valve temperature limitation ofless than or equal to 10 degrees F if the boron concentration was met. Comed believes that requiring the boron concentration in the loop to be unisolated to be higher than the boron concentration required for the entire RCS is unnecessarily restrictive. Proposed ITS LCOs 3.1.1 and 3.9.1 provide adequate requirements to assure reactivity control in Modes 5 and 6, respectively. The justification srpplied to the

- NRC for the previous amendments for Comed's Zion Station supports the less restrictive change for the unique Westinghouse design for four loop plants equipped with loop stop isolation valves. Comed continues to pursue this change on a plant specific basis.

2 O

51

Response to hRC RAI For ITS Section 3A R

09 oei m NRC RAI Number NRC issued Date RAI Status 3.4.18 02 3'9'98 Closed t_.()..

. NRC Description ofIssue DOC L9 ITS LCO 3.4.18.b -

ITS 3.4.18 Required Action B.1

CTS 3'4.4.1.5.2 Action CTS 3/4.4.1.5.2 Action prohibits opening either the hot leg or cold leg stop valves whenever the temperature requirement of

. CTS 3.4.1.5.2.b is not met. ITS 3.4.18 Required Action B.I requires the immediate closure of only the cold leg isolation valve whenever the temperature requirement is not met. consistent with the STS. This change would be acceptable 3mder the STS guidance; however, ITS 3.4.18 differs significantly from the STS, as described in comment 3.4,18 01, Provided that

. comment is resolved as requested, the CTS change addressed by DOC L9 will be accepted. Otherwise, the CTS.

requirements must be retained. Comment: Respond according to the resolution of comment 3.4.18-01.

Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.

Original Response: With the conditions of CTS 3.4.1.5.2 not met, the actio'n is to not open either the hot leg or the cold leg

. stop valves. ITS LCO 3.4.18a requires that only the boron concentration be met to open the hot leg loop stop valve, and that the boron concentration and the temperature be met to open the cold leg loop stop valve. The hot leg loop stop valve has no opening interlock on temperature limits, only that the cold leg loop stop valve be closed. With the cold leg stop valve closed, there can be no driving force (delta p) to allow mixing of the fluids in the isolated loop and the operating portion of the RCS.

' Interlocks are provided on the cold leg stop valve to prevent opening the cold leg stop valve until the hot leg stop valve is open and the temperature requirement is satisfied. An administrative control is placed on the hot and cold leg stop valves to prevent opening the valves until the boron concentration requirement is satisfied. Comed believes ITS LCO 3.4.18 Required l C Action B.1 correctly addresses the safety analysis concern of a positive reactivity addition due to the addition of cold water 3

from the isolated loop and is consistent with CTS. Comed continues to pursue this change.

\\

l 1

1 t

[.

l LO 52 h -, i y e

_y,,

7,,,,

._m

, ~. -

,-n.

,a

~ -..

-==

-==

y Rcsponsa to NRC RAI For ITS Section 3.4 09-oct.98 NRC RAI humber NRC issued Date RAI Status

~

3.4.18 03 3 9'98 Closed b/

NRC Description ofissue l'

JFD P47 l

ITS SR 3.4.18.1 and SR 3.4.18.2 l

Bases JFD P1 l

Bases for SRs 3.4.18.1 and 2, STS Bases markup page 5 3.4105 1

a. 'ITS SR 3.4.18.1 and SR 3.4.18.2 have the word "once" insetted before the Frequency it terval because JFD P47 states this provides "...a particular time frame...and... is necessary to comply with the SR" and ITS SR 3.0.2. This change does not l

achieve the stated technical objective because the SR may have to be performed several times in order to actually be withm l-the time interval " prior" to the opening of the cold leg isolation valve. The adding of"once" to an interval stated as occurring "after" any action, starts a clock which cannot be changed. The adding of"once" to an interval as occurrmg

" prior" to any action does not start a clock, until the action has actually occurred. This proposed change introduces an ambiguity not present in the STS which can cause the SR Frequency to be exceeded. Comment: Adopt the STS Frequencies for ITS SRs 3.4.18.1 and 3.4.18.2.

l-

b. Deviations from the STS Bases related to JFD P47 are characterized as editorial under Bases JFD PI, w hen in fact. they a a technical changes. Thus a technicaljustification is required. Comment: Withdraw the Bases deviations and adopt the STS which is clear and accurate as written.

Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closeout submittal Revision K.

Original Response: Comed will revise the Frequency consistent with the STS, and will withdraw the changes to the Bases for STS SRs 3.4.18.1 and 3.4.18.2. This change will be provided in our comprehensive ITS Section 3.4 closcout submittal

/~'N revision upon NRC's concu:rence with the Comed Responses to the ITS Section 3.4 RAl. (See RAls 3.1-01,3.1.6-04,3.6.3-()

09, 3.4. I4-09, and 3.4.16-05.)

NRC RAI Number NRC lssued Date RAI Status 3.4.I8-04 3/9/98 Closed NRC Description ofissue Bases JFD P3 l

Bases Background discussion of ITS 3.4.18. STS markup page B 3.4-103 The Bases Background text identified as paragraphs a. b and c has not been adopted. This omission is stated as a plant specific editorial enhancement; whereas, the omitted text is applicable to all Westinghouse plants with RCS loop isolation valves. The submittal contains no technicaljustification for this change. Comment: Adopt the omitted STS text.

Se e similar comment 3.4.17-01.

Comed Response to issue Revised Response: See RAI 3.4.18-01 Revised Response. This change is provided in our comprehensive ITS Section 3.4 closcout submittal Revision K.

Original Response: The paragraphs omitted from the Background Section of the Bases for ITS LCO 3.4.18 for opening the l

RCS loop isolation valves will be retained with appropriate changes made to reflect corresponding changes made to ITS LCO 3.4.18. This change will be provided in our comprehensive ITS Section 3.4 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.4 RAl. (See RAI 3.4.17-01.)

l f~'N L

l 53 I

=. =,

Response to NRC RAI For ITS Section 3.4 09-oct-98 NRC RAI Number NRC issued Date RAI Status 3.4 01 3 9'98 Open - NRC Action Required k

NRC Description of issue See table below Proposed changes based on STS generic change proposals that are still pending or that have been rejected. as indicated in the table, should be withdrawn. For each applicable line item, either adopt the STS or maintain the CTS requirementsf See separate correspondence regarding line items for beyond scope changes (reasons 4 and 5) that should have been addressed separately by the licensing project manager and NRR technical staff as appropriate. Line items considered closed are indicated by shading.

  • Reasons for exempting change from review:

1, Cover letter 1213-96, Attachment #3 Existing and Future Licensing Amendments to be incorporated into ITS.

2.' Cover letter 12-13-96 Attachment #4 Pending and Proposed ISTS Change Travelers

3. Comed letter 2-24-97, Attachment #I, Generic Changes versus CTS DOCS 4 Cover letter 12-13-96, Attachment #5 Beyond Scope Change (changes that are different than both CTS and ITS).
5. Cover letter 12-13 96 Attachment #6 Beyond Scope Bracketed Changes 6 Comed letter 2-24 97, Attachment #2, Plant Specific Change Justifications Which are Now in the Generic STS Change Process
7. Other Reason as identified in comments to this table and/or with the prior approval of the NRC Technical Monitor as referenced, Byron /Braidwood Units I and 2 s

"Beyond Contractor Review Scope (BCRS)" Table Section 3.4. Reactor Coolant System TableLine No.

,(

ITS Reference DOC JFD ' Reasons for Exemption of Review.

Comment (if required) i 234567 1 5.5.9

{

5.6.9 X -

- - - - Comed Amendment proposal dated 8-19 Note, ITS

' Section 5.0, DOC A24 adds the SG 3.0 volt criteria to CTS 4.4.5 for the SG Tube Surveillance Program.

2 3.4.16 - - - X -

- - - TSTF-3 RI, Not lncorporated 3 3.4.2 L36 Cl BC1

X^X - _ -.JTSTF-26 approved 9/16/96 4 3.4.2 M9 C2 BC2 - X: X - - - - TSTF-27 Rl; superceded by Rev.2 which is pending 5 3.4.16 - C3 BC3 - X - - - - - TSTF 28 approved 9/16/96 6 Bases for 3.4.13 - BC4 - X - -

- - TSTF-54, Comed states replaces " identified" with " unidentified" Should adopt Revision I which was approved 4/10/97 7 3.4.15 ' - - - X - -

TSTF-60. Not incorporated - Comed states contradicts Condition D for entering LCO 3.0.3. Approv d 9/17/96. Comed should adopt.

83.4 O

[3.4.13]

Cll

-X. - - - -

TSTF-61, approved 9/17/96; Comed should adopt.

.Q 9 3.4.5 3.4.9 L3

$4 1

.. = -. ~ = = = = = - - -

v =

z-w -.=

R:sponse to NRC RAI Fcr ITS S:ction 3A 09-Oct.,:.--- =.

--u====.=.=.

.- ~

i L23-

-b L26' CIO P37

(.

- [P36] BC101 - XIX:-: - X TSTF-87 R1, Comed specifies RA is " Initiate action to place" rather than " Place.. on Immediate frequency" [Per C. Harbuck P36 is BCRS from typo in JFD C10 ) revision 2 approved 10'3/97: Comed should adopt Revision 2

10. 3.4.9 A13: C5 BC5

~XL X '- E T -:TSTF-93, 11 3.4.9... X". _':..

TSTF 94, Not incorporated Comed provides brackets for words that were I

incorporated into CTS. Comed should adopt Rev. I which was approved 9'30 97.

12 'T 3.4.1 LAIS C6 BC6' 'X: X-~-T-

-3 ~ TSTF-105 was rejected.

13: 3.4.191-7 P30 BP35' -:XT !-: :-:X TSTF-108, Not incorporated -Comed states LCO 3.4.19 is for NTOL i

plants. Per C Harbuck this is not BCRS.

14' 3.4.ll:,L8 Cl2 BCl33-:X:X:-1 TSTF-ll3 R1, still pending 15 '. 3.4.7 ~ -:BC1 i BP3 ~ - X ~ -~ -T '. '-:TSTF-ll4, approved 12/31/96 16 : 3.~4.13 i

3.4.15 'L21 L22 L24~~C8' P23 BC8 BP23 -: X.X; V ' ~ TSTF-il6. superceded by Rev i which is pending 17. Bases 3.4.11' -'.'BCl41-: X:. ~.. -:-:TSTF-151 (WOG-61), Owners Groups asked to modify as suggested by TSB - waiting for response 18 3.4.5

[3.4.6]

[3.4'.7) '

-[3.4.8) A31.Cl4 BC18' -: X. ~X - '.T -J ' TSTF-153 (WOG-63) approved 4/11/97 V

19 3.4.1 A22 C7 BC7'.-:.X X - -J-' - WOG-21

)

20' 3.4

.- [3.4.12] Ll6 C9

. Pil P21 BC9 BPil BP19 BP21

[Pl7][P19] - X X ' - ' X WOG-51 R1, C9 states generic change is modified by plant specific changes Pf land P21 [P19 is tied to Pil] and [Pl7 is tied to C9]

21 3.4.

. [3.4.11] L27 Cl3 BCl3

.X.X -: - - - WOG-60 L 22 3.4

, [3.4.9) - BC l7

. X '..' - - - WOG-68

. 23 3.4

[3.4.2]

[3.4.16]. C15 - X

- - - - WOG 81 24 Bases for Section 3.4

. [All speci-fications]' - ' BC16' :'.X -' - - - - Editorial-1 25 SR 3.4.1.4 Note ~ M 15 P3 - - ~ ~ X -

26 3.4.3 L28 P44 ---X---

27 3.4.18 LIB

[A28] P31

[BP36] - - -' X '

~X" items in bracket are added because both are tied to the P31 change.

28 SR 3.4.18.2 Ll4 P4 - - - X - ~ - -

. 291 SRs 3.4.5.2 3.4.6.2

< h

  • 3.4.7.2 L5 [B3][Pl] -

, --'. X - X ' Items in bracket are adde'd because both are tied to the L5 change.

'%/

~ 30 3.4

[3.4.12].. P38

.. - - ' X ~

WOG-087 i

55 l

l L

L-

.. _ _ z_ m._ _

Rsspense to NRC RAI For ITS Sectisn 3.4 09-oct-9s m.-__u 3 1 3.4

([].

[3.4. l].^

P3. - -

- - X ' ' WOG-099 i

32 3.4'

' \\_/

[3,4.12] -;P21

.-;X -:WOG-100 l

33 '3.4 l

- [3.4.11): ~.PI4: ~..: :-:X:.: WOG-10' 34_ 3.4.

[3.4.16]~' ~ Pl P45 2-: ~.-:-:-!X:.: Editorial-12

' Comed Response to issue Revised Response: Two issues associated with the table remain open.

1. Regarding items #25 and #31 (RAI BYS 5.0): Per discussions with the NRC Reviewer on 9'3'98. Comed has written a letter to the NRC justifying the 7 days in the Note for ITS SR 3.4.1.4. Concurrently, NRC Reviewer Tony Attard reviewing same changes in TSTF 282. Resolution still pending.
2. Regarding item #28 (RAI BYS 8.0): Per discussions with the NRC Reviewer on 9/3/98, Comed has written a letter to the NRC justifying the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> sampling frequency for ITS SR 3.4.18.2. Resolution still pending.

Original Response: See table for Comed Response to RAI 3.4_01._ _._.. _ _ _ _..

Bottom of Report

)

l Lv l

56

ATTACHMENT 2

,Q ITS SECTION 3.4 ITS AFFECTED PAGE LIST

.l l

O O

.. ~ _._ _. _._ _......._..

l ATTACHMENT 2

/ 'T ITS SECTION 3.4 hs/

ITS AFFECTED PAGE LIST SECTION / TAB ITS AFFECTED

'RAI PAGE BYRON ITS /

3.4.1-1 3.4-01 #19 p

~BRAIDWOOD ITS 3.4.1-2

-3.4'1-02 3.4.2-1 3.4-01 #23 3.4.5-1 3.4.5-02 3.4.5-4 3.4.5-03 3.4.6-1 3.4.6-02 3.4.6-2 3.4.5-03 3.4.6-3 3.4.7-1 3.4.7-02 3.4.7-03 3.4.7-06 3.4.7-09 3.4.7-2 3.4.7-01 3.4.7-02 3.4.7-3 3.4.7-08 3,4.8-1 3.4.8-02 l

3.4.9-1 3.4.9-02 n

I.

1 l

.... ~. _. _

t

)

ATTACHMENT 2 f ' \\s-]-

/~

ITS SECTION 3.4

.ITS AFFECTED PAGE LIST' SECTION / TAB ITS AFFECTED RAI PAGE 3.4.10-1 3.4.10-05 l

3.4 10-2' 3.4.10-04 3.4.11-1 3.4.11-04 3.4.11-2 3.4.11-01 r

.3.4.11-04 3.4.11-3 3.4.11 3.4.11-04.

3.4-01 #21

,'~l

(' /

3.4.11-4 3.4.11-04 3.4.12-1 3.4.12-01 3.4.12-09 3.4-01 #23 3.4.12-2 3.4.12-01 3.4.12-08 L

3.4.12-4 3.4.12-01 3.4~.12-5 3.4.13-2 3.4-01#16

- 3. 4'.14-1 3.4.14-01 3.4.14-02 LO 2

l ':

o

ATTACHMENT 2 ITS'SECTION 3.4 l

ITS AFFECTED PAGE LIST l

SECTION /. TAB ITS AFFECTED RAI PAGE 3.4.14-2

.3.4.14-03 3.4.14-3 3.4.14-07 3.4.14-08 3.4.14-09 3.4.14-4 3.4.14-09 3.4.15-1 3 4-01 #16 3.4.15 3.4-01 #16

,-s 3.4.16-1 3.4-01 #23

(_)s.

3.4.16-3 3.4.16-04 3.4.16-05 3.4.18-1 3.4.18-01 3.4.18-2 3.4.18-03 B 3.4.1-2 3.4.1-05 3.4.1-06 B 3.4.1-3 3.4-01 #19 B 3.4.1-4 3.4.1-07 B 3.4.1-6 3.4.1-02 3.4-01 #12 i' ()

3 i

' ATTACHMENT 2

  1. ~l ITS SECTION 3.4 k-/

ITS AFFECTED PAGE LIST

-SECTION / TAB ITS AFFECTED RAI PAGE

- B 3.4.2-3 3.4.2-02 B 3.4.3-8 3.4.3-02 B 3.4.4-3 3.4.4-01 B 3.4 5-3'

~3.4.5-02 i

B 3.4.5-4 3.4.5-04 l

B 3.4.5-7 3.4.5-03

-i L( )

B 3.4.5-8

'3.4.5-05 B 3.4.6-2 3.4.6-02

)

B 3.4.6-5~

3.4.5-03 B.3.4.7-2 3.4.7-02 3.4.7-10 B 3.4.7-3 3.4.7-03 B 3.4.7-4 3.4.7-01 B 3.4;7-5

'3.4.7-01 3.4.7-03 3.4.7-08 L

I' l:

4 l

y y

. +.

y my.,

~

.. _ _ _ _ _ - -. _ _ _. = _. - -.. _._._. _.., _.__ _._. _

-c

ATTACHMENT.E' l'(

ITS SECTION 3.4 l-ITS AFFECTED PAGE LIST

'.SECTION / TAB-ITS AFFECTED RAI PAGE-B 3.4.7-6 i:

B 3.4.8-2, 3.4.8-02 3.4.8-07 k

3.4.8-09 l

[

B 3.a.9-2.

3.4.9-01 B 3.4.9-3 3.4.9-02 B 3.4.9-5 3.'4.9-01

)

3.4.9-03 I

l [..

B 3.4.9-6 3.4.1-10

~

s).

B-3.4.11-1 3.4.11.

i B 3.4.11-2 3.4.11-04 B 3-4.11 ^

3.4.11-04 g

l B 3.4.11-4 3.4.11-04 l

I B 3.4.11-5 3.4.11-04 3.4-1 #21 l

B 3.4.11-6 3.4.11-02 3.4.11-04 f

I-i+

5 t

t e

I ATTACHNENT2 (l

ITS SECTION 3.4

's ITS AFFECTED PAGE LIST SECTION / TAB-ITS AFFECTED RAI PAGE-B 3.4.11-7 3.4.11-01' 3.4.11-04 B 3_.4.11-8 3.4.11-04 3.4'1 #21 B 3.4.11-9 3.4.11-04 B 3.4.12-4 B 3.4.12-9 3.4.12-09 3.4.12-01 B 3.4.12-11 3.4.12-01 3.4.12-08 B 3.4.12-15 3.4.12-01 3.4.12-07 i

B 3.4.12-16 3.4.12-01 3.4.12-07 B 3.4.12-17 3.

_?-07 B 3.4.13-2 B 3.4.'13-3 i

B 3.4.13-6 3'.4.13-03 1

(}~

6

..t ATTACHMENT 2

?( J)

ITS SECTION 3.4

A ITS AFFECTED PAGE LIST SECTION / TAB ITS AFFECTED RAI-PAGE B 3.4.13-7

~3.4.13 B 3.4.13-8 B 3.4.14-4

.3.4.14-12 B 3.4.14-5 3.4.14-03

)

B 3.4.14-6 3.4.14-08 B 3.4.14-7 3.4.14-07

\\

(

B 3.4.14-8 3.4.14 08 8 3.4.15-3 B 3.4.15-4 3.4-01 #16 l

l B 3.4.15-5 3.4-01 #1e i

3.4.15-03 B 3.4.16-1 3.4.16-07 B 3.4.16-3 3.4.16-08 8 3.4.16-6 3.4.16-05 B 3.4.17-1 3.4.17-01

(}

7 v

AHACHMENT 2'

,md' '

ITS SECTION 3.4 i

ITS AFFECTED PAGE LIST l

SECTION-/ TAB ITS AFFECTED RAI PAGE l

l B 3.4.17-2 3.4.17-01

.B 3.4.17-3 3.4.17-01 3.4.17-02 i

B 3.4.18-1 3.4-18-04 B 3.4.18-2

.3.4.18-01 i

l B 3.4.18-3 3.4.18-01 3.4.18-03 H

.)

'(

8 A

l'l' l

~

ATTACHMENT 3 ITS SECTION 3.4 CTS AMENDED PAGE LIST 9

O d

i O

LATTACHMENT 3.

(

ITS SECTION 3.'4-A

-CTS AMENDED PAGE LIST.

SECTION/ TAB AFFECTED CTS PAGE/ AMENDMENT.#

3.4' BYRON CTS 3/4 4-2 #96 3/4 4-4'#96 j

3/4 4-5 #96 s

3/4 4-14.#101 1

3/4 4-15 #101 t

3/4 4-16 #101 3/4 4-17 #101-3/4 4L17b #101 3/4 4-17d #101 3/4.4-27 #101 3/4 4-28 #101 3/4.4-29 #101 3/4 4-29a #101-

,3/4.4-311#101 3/4 4-32 #98

-3/4 4-33 #98

)

3/4 4-34 #98

(^' \\,

3/4 4-35 #98

- k/

.3/4 4-36 #98 3/4 4-37 #98 ll I

q L,

i

(.

1 L):

4 I

.i'a

l :-

1 ATTACHMENT 3-i:-93 Li(

ITS SECTION 3.4 CTS AMENDED PAGE-LIST ln L

'.SECTION/ TAB -

.AFFECTED CTS PAGE/ AMENDMENT #

3.4'BRWD CTS.

3/4 4-2 #87 3/4~4-4 #87.

.3/4-4-5 #87 3/4 4-14 #92 3/4 4-15 #92 L'

3/4 4-16'#92-

'3/4 4-17 #92-L

-3/4 4-17a #92

^3/4 4-17b #92

^

3/4 4-17c #92-h 3/4 4-17d #92

-/

l 3/4 4-27 #92-l

'3/4 4-28 #92 3/4 4-29 #92 3/4 4-29a #92 l.

3/4 4-31 #92 3/4 4-32 #89 3/4 4-33 #89

! : /~_l

'3/4 4-34-#89

\\s/

4-3/4,4-35 #89

~

l 3/4 4-36 #89

'3/4 4;37 #89 i

i l-i l

I' Il-b L /

2

.; d t'

.J

. - -, ~, _

, - - -. - ~

e.A A

4 4-5 m

.a m$,,e A-2J4,.

4,muJd A-5.-

%du

4. 4me.a 4 d den M.

,#.a4 maama pAi.d..m, p

w-,3_.2 4_

4_4.,

e,.4 Iw seMp.,, Lana.g ATTACHMENT 4 ITS SECTION 3.4 SER TABLES i

' O 4

1 s

s

)

Lo

.pV b,, '

(f Table A - Administrative Changes to CTS Discussion Description.

ITS CTS ~

of Change of Change Requirement :

Requirement ITS Section 3.4, Reactor Coolant Systems 3.4 A1 Editorial rewording, reformatting, and renumbering changes were made to conform with 3.4 3/41,3/42,3/4.3,

- conventions used in Westinghouse Standard Technical Specifications NUREG-1431(STS).

3/44,3/4.5, 3/4.10 3.4 A2 Obsolete, cycle-specific limits regarding Reactor Coolant System (RCS) total flow rate, steam LCO 3.4.1.c, LCO 3.2.3 a, generator water level, and reactor coolant Dose Equivalent 1-131 was deleted.

SR 3.4.5 2, 4.4 1.2 2, SR 3.4.6.2, 4.4.1.3 2 LCO 3.4.7.b.

LCO 3 4141 b.

SR 3.4.7.2, LCO 3.4 8 a, t

SR 3 4.16.2, Figure 3 4-2, Figure 3.4.16-1 Table 4.4-4 Note ""

3.4 A3 Exception to the provisions of CTS 4.0.4 was removed for the associated RCS flow rate SR 3.0.4 4.2.3 1 surveillances. Wording and format of the surveillance and STS SR 3.0.4 make such exceptions unnecessary.

3.4 A4 Action to restore RCS operating loop temperature to within limit was deleted since the option to 3.4.2 Action A 3.1.1.4 Actions restore out of limit conditions always applies and does not need to be stated.

3.4 A5 Footnote reference to Special Test Exception (STE) Specification 3.10.3 was deleted in _

3 4.2 Applicability 3,1,1.4 i

conformance with STS which reformats the presentation of these STE requirements in the ITS Applicability Specification to which they apply.

(By)- Byrora specirc (Bw)- Braidwood specific L

Byron and Braidwood A_T BL3 4 1

_s

(

Table A - Administrative Changes to CTS Discussion Description ITS CTS of Change of Change Requirement Requirement 3.4 A6 Footnote reference to STE Specification 3.10.4 was deleted in conformance with STS which 3.4 4 Applicability 3.4.1.1 reformats the presentation of these STE requirements in the ITS Specification to which they Apphcability apply.

3.4 A7 Footnote reference to STE Specification 3.10.4 was deleted in conformance with STS which 3.4.5 Applicability 3.4.1.2 reformats the presentation of these STE requirements in the ITS Specification to which they Applicabshly apply.

3.4 A8 Since the condition "when no reactor coolant or Residual Heat Removal (RHR) loop in 3.4.6 Actions 3 4.1.3 Action b operation" implies both required loops are inoperable, the applicable Actions were applied to A and C each condition for clarity. The Action to suspend all operations involving a reduction in boron concentration of the RCS was applied te the condition when no required reactor coolant or RHR loop is in operation as well as when both required loops are inoperable.

3.4 A9 The LCO was revised to include the requirerr.?qt for the pressurizer heaters to have a LCO 3.4.9 LCO 3 4.3 redundant emergency power supply capability to be consistent with the surveillance requirement to demonstrate the cross-tie to the emergency safety feature (ESF) power supply.

3.4 A10 An explicit allowance for separate condition entry for each pressurizer power operated relief 3 4.11 Actions 3.4 4 Actions valve (PORV) and each block vaive was included to clarify current practice for tracking Note 1 a!!owable outage times for each inoperab!2 component.

3.4 A11 Actions to restore pressurizer PORV(s) or block valves were deleted since the option to restore LCO 3 0 2 3 4 4 Actions a b, inoperable components currently exists and does not need to be stated.

c, and d (By)- Byron specific (Bw)- Braidwood specif.c Byron and Braidwood A_ T BL3 4 2

.p im L)

Lj U

Table A - Administrative Changes to CTS Discussion Description.

ITS CTS of Change of Change Requirement Requirement 3.4 A12 Whenever a loop isolation valve is discovered open, compliance with the LCO cannot be 3 4.17 Action B 3.4.1.5.1 Actions.

reestablished in the Modes of applicability. These requirements are clarified by substituting the phrase " maintain the valves closed" for " suspend startup of the isolated loop" and by adding a note that shutdown of the unit to Mode 5 must be completed.

3.4 A13 Frequency for verifying the capacity of each group of pressurizer heaters was changed from SR 3 4.9.2 4.4.3.2 "each refueling outage" to the equivalent "18 months," consistent with the length of a fuel cycle.

3.4 A14 The phrase " water level not within limit" was used to clarify the intent with the pressurizer 3.4.9 Action A 3 4 3 Action b "otherwise inoperable."

3.4 A15 LCO and Action requirements for steam generator (SG) Operability were incorporated in other LCO 3 4.4, 3/4 4 5 STS Specifications. The specific surveillance requirements were incorporated in the Steam LCO 3.4.5, Generator Tube Surveillance Program and replaced by a surveillance to verify steam generator LCO 3 4.6, tube integrity in accordance with this Program.

LCO 3 4.13 SR 3.4.13 2,5.5 9 3.4 A16 The requirement to enter LCO 3.0.3 was explicitly stated as an Action for the condition of all 3.4.15 Action D 3.0 3 i

required RCS Leakage Detection System monitors being inoperable to clarify current requirements.

l 3.4 A17 Obsolete, cycle-specific surveillance extension allowance for the 18 month Channel Calibration SR 3 4.15'3 4 4.6 1 of the Containment Sump Monitor was deleted.

I

('By)- Byron spearic s

(Bw)- Braidwood spearic Byron and Braidwood A_ T BL3 4 3

r

. 7-,

4 Table A - Administrative Changes to CTS Discussion Description ITS CTS of Change of Change Requirement Requirement 3.4 A18 The exception to Specification 4.0.4 allowing entry into Modes 3 or 4 without performing SR 3.4.14.1 Note 4.4.6.2.2 leakage testing of the RCS pressure isolation valves (PlV) was reworded as a note stating the surveillance is only required to be performed in Modes 1 and 2.

3.4 A19 Explicit allowance was included for separate condition entry for each flow path with leakage 3.4.14 Actions -

3.4 6.2 Actions from one or more RCS PlVs not within its leakage limit. Also, direction was included to enter Notes 1 and 2 the applicable LCOs for systems made inoperable by an inoperable PlV to clarify current requirements.

3.4 A20 Not used.

3.4 A21 Requirements to protect the RCS from overpressurization by safety injection (SI) or charging LCO 3.4.12.b, SR 4.5 3 2 l

pump operation during shutoown Modes were reworded regarding the pumps' capability of SR 3.4.12.1, injecting into the RCS rather than the pump's inoperability except for certain specified SR 3.4.12.2 evolutions.

3.4 A22 Not used.

3 4 A23 The LCO for RCS loops in Modes 1 and 2 was revised to clarify that allloops be Operable as LCO 3.4.4 LCO 3 4.1.1 well as in operation since other Specifications require reactor coolant pumps and steam generators to be Operable.

3.4 A24 Frequency for verifying the capacity of each group of pressurizer heaters was changed from SR 3.4.1.4 4.2.3 5 "each refueling outage

  • to the equivalent "18 months," consistent with the length of a fuel cycle.

(By)- Byron specife (Bw) - Br.:idwood spectre Byron and Braidwood A._T BL3 4 i

4

}

l J

G.,

4 i

't Table A - Administrative Changes to CTS -

Discussion Description ITS.

CTS-i of Change of Chaetge Requirement Requirement 3.4 A25 Specifications were revised to indicate the RHR loops " required" to be in operation to clarify and SR 3.4.6.1, reference the LCO allowance for the pumps to be removed from operation for Imted periods.

LCO 3.4.7 Note 2,.

4.4.1.3.3, LCO 3.4.1.4.1,

. 3.4.7 Actions,-

3.4.1.4.1 Actions.

. SR 3.4.7.1, 4.4.1.4.1.2,

[

SR 3 4.8.1 4.4.1.4.2, 3.4 A26 The phrase "with power removed

  • was deleted from the allowance that PORV block valves SR 3 4.11.1 4.4.4 2 l

need not be tested if they are closed in accordance with specified Action requirements since Note 1 opening the block valve by any means is not allowed while in this cOnditkni.

I 3.4 A27 CTS was revised to reflect changes reauested in a License Amendment Request dated May 29, 3.4.11 Actions' 3.4 4 Actions

}

1998.

t 3.4 A28 Not used.

f t

3.4 A29 Actions regarding PORV inoperability due to automatic actuatKm circuitry failure were 3.4.11 Actions

..3.4.4 Actions.

t reformatted for clarification to be conditional upon the capability of the valve being manually and B and E b and c automatically closed.

(proposed) 3.4 A30 Actions pertaining to inoperable PORVs were reformatted for clarification to be conditional upon 3.4.11 Actions A, 3 4.4 Actions a, the capability of the valve being manually and automatically closed rather than upon excessive B, and E b, and c seat leakage.

?

4 (By) - Byron specific (Bw)- Braidwood specific I

t Byron and Braidwood A_i BL3 4 l

5 i

L f

M

'O 1

3 (O?

Table A -' Administrative Changes to CTS :

- Discussion Description ITS '

CTS l of Change; of Change.

Requirement

- Requirement j

i 3.4 - A31 -

' The allowance that reactor coolant or RHR pumps may be deenergized under certam LCO 3.4.5 Note, LCO 3.4.1.2 Note, conditions was reworded for clarification to allow the pumps to be " removed from operation.'

. LCO 3.4.6 Note 1

LCO 3 4.1.3 Note.

LCO 3.4.7 Note 1 LCO 3.41.41

+

LCO 3.4.8 Note 1 Note, LCO J

~ '

3.4.1 A.2 Note

.L 3.4 A32

' The surveillance to demonstrate the Operability of the

  • cross-tie' for the pressurizer heaters to

. SR 3.4.9.3 4.4.3.3 the ESF power supply was reworded for clanfication to demonstrate the heaters * " capability to be powered by* the ESF power supply.

3.4 A33 Explicit statement that inservice inspection and testing activities shall be in addition to other

- Specification

-4'4.4.1, i

specified SRs was deleted as an unnecessary steration of current requirements.

3.4.11 14.4.9.32.c Surveillance Requirements, SR 3 4.12.5 i

i 3.4 A34 Requirements were reformatted to more clearly specify the appropnate Actions to take when a 3 4.7 Actions 3.4.1.4.1 Action a j

required RHR loop or one or more required steam generators are ' operable in Mode 5 with B and C m

RCS loops filled.

[

k i

i 1

(By)- Byron spec:fic

{

(Bw)- Bradwood specire Byron and Braidwood A_ IBL3.4 -

-6

)

i

Table R - Relocated CTS Discussion Relocated

. Description of

'New Control -

of Change CTS-Relocated CTS Location Process CTS Section 3/4.4, Reactor Coolant System 3.4 R1 3/4.4.2.1 Safety Valves - Shutdown TRM.

$50.59 3.4 R2 3/4.4.7 Chemistry TRM'

$50.59 3.4 R3 3/4.4.9.2 Pressurizer Pressure / Temperature Limits TRM'

'650.59

.3 3.4 R4 3/4.4.10 Structural Integrity (except requirements for reactor coolant pump flywheel)

TRM-

$50.59 3.4 RS 3/4.4.11 RCS Vents TRM

$53.59 r

i L

r l

(By)- Byron speciric (Bw)- Braidwood specific Byron and Braidwood 1

R_IBL3 4

e, 73 Table M - More Restric:.We Changes to CTS Discussion Description ITS CTS of Change of Change Requirement Requirement ITS Section 3.4, Reactor Coolant Systems 3.4 M1 Surveillances were added to require verification of correct breaker alignment and indicated SR 3.4.7.3, N/A power available to the required Residual Heat Removal (RHR) pump that is not in operation SR 3.4.8.2 should it need to be placed in operation.

3.4 M2 The restrictions under which an RHR pump may be de-energized were revised to include a LCO 3.4.8 Note 1.c LCO 3.4.1,4 2 Note prohibition of any draining operations that would further reduce the Reactor Coolant System (RCS) water volume.

3.4 M3 The allowances for removing all required RCS pumps from operation were revised to limit the LCO 3 4 5 Note.

LCO 3 412 amount of time the RCS is without forced cooling to s 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

LCO 3 4 6 Note 1 LCO 3 4.1.3, LCO 3 4.7 Note 1 LCO 3 41.4.1 3.4 M4 With the RHR System suction isolation valve interlock function inoperable, the CTS Emergency 3.4.14 Action B 3.5.2 Action a Core Cooling System Specification requires restoration of the RHR subsystem to Operable within 7 days. An Action specific to the interlock function was added to require isolating the RHR flow path within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to protect RHR components from overpressurization.

3.4 M5 An Action to shutdown the unit to a Mode in which the LCO does not apply when two or more 3.4.10 Action B 3.0.3 pressurizer valves are inoperable was included rather then defer to LCO 3.0.3 for this requirement. The result is a completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> less to have the unit in Mode 4.

3.4 M6 The completion time for restoring an inoperable pressurizer power operated relief valve (PORV) 3.4.11 Action B 3.4.4 Action b was reduced to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> consistent with other similar component restoration times.

3.4 M7 The Specification for Low Pressure Overpressure Protection (LTOP) was revised to add LCOs, 3.4.12 3/4 4.9.3 Actions, and Surveillance Requirements for conditions in which the RCS could be overpressurized from unisolated accumulators, safety injection (SI) or charging pumps, or from any other reason LTOP becomes inoperable.

(By)- Byron spec fic (Bw)- Braidwood speofic Byron and Braidwood 1

M_TBL3 4

O

%/

v Table M - More Restrictive Changes to CTS s

Discussion

'Weription ITS -

'CiS~

of Change change

. Requirement Requirement 3.4 M8 With a SI pump (s) discovered Operabia in the applicable Modes and conditions, the Action to 3.4.12 Action B 3 5.4.1 Actions restore the Si pump (s) to inoperable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> was changed to immediately initiate action to verify no pumps are capable of injecting into the RCS.

3.4 M9 The frequency for verification of RCS average temperature was changed to every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while SR 3.4.2.1

'4.1.1.4 b in the applicable Modes and conditions rather than every 30 minutes only when RCS average temperature is s 557'F with the T

-T,,, deviation alarm not reset.

y 3.4 M10 A completion time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> was imposed on the Action to determine that the RCS remains 3.4.3 Action A 3 4.9.1 Action acceptable for continued operation after the RCS temperature or pressure limit has been.

exceeded in Modes 1,2,3 or 4.

3.4 M11 The Action to restore RCS temperature and/or pressure to within limit within 30 minutes was 3.4.3 Action C 3.4.9.1 Actions changed for Modes other than 1,2,3, or 4 to require immediate action to restore the parameter (s) to within limit and to determine that the RCS is acceptable for continued operation before entering A4 ode 4.

t 3.4 M12 Special Test Exception to allow reactor criticality under no flow conditions was deleted. The N/A 3/4.4.10.4 Specification is no longer needed since this testing was only necessary for initial unit startup with a new core.

3.4 M13 Specifications for RHR operation in Mode 5 conditions do not specify Actions for both loops of 3.4.7 Action D, 3.4.141 Actions,

,f RHR inoperable. Actions were added to immediately suspend all operations involving a 3_4.8 Action C 3.4.1.4.2 Actions

[

reduction of RCS boron concentration and to immediately initiate restoration of one RHR loop to j

Operable status.

t 3.4 M14 If unable to restore RCS total flow rate to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in Mode 1, the Action to 3.4.1 Action B 3.2.3 Action a 2 reduce Thermal Power was replaced with the Action to place the unit in a Mode in which the LCO does not apply.

+

l (By)- Byron specife (Bw)- Braidwood specife Byron and Braidwood 2

M_iBL3 4 m l

. (--

,,-~.

(

)-

(

.- (v -l Table M - More Restrictive Changes to CTS

_a Discussion Description ITS CTS.

of Change of Change Requirement Requirement -

3.4 M 15 A time period of 7 days after reaching 90% Rated Thermal Power was stipulated for determining SR 3.4.1.4 Note 4.2.3.5 RCS total flow rate by precision heat balance measurement rather than prior to completion of Physics Tests.

3.4. M16 A time period of 31 days was imposed for sampling and radioanalysis for RCS P. after a SR 3.4.16.3 Note Table 4 4-4. Note

  • minimum of 2 effective full power days and 20 days of Mode 1 operation.

3.4 M17 Not used.

3.4 M18 To provide additional assurance that low temperature overpressurization events are prevented, 3.4.12 Applicability 3.4.5.1 Applicability the Applicabihty was revised so that no Si pumps may be capable of injecting into the RCS, regardless of the pressurizer level.

3.4 M19 The surveillance frequency "in accordance with the Inservice Testing Program" for verifying the SR 3.4.14.1 '

4.4.6.2.2 s.

leakage from each RCS pressure isolation valve is within limits was added for consistency with STS.

4

)

(By)- Byron specife (Bw) - Braidwood specirc Byron and Braidwood 3

M_1 BL3.4

[

-m

(...

_y Q

Table LA - Details Relocated from CTS Discussion CTS Description of New Control of Change Reference Relocated Details Location Process Type ITS Section 3.4, Reactor Coolant Systems 3.4 LA1 4.4.1.1 Information describing the characteristics of operating reactor coolant loops.

Bases ITS 5.5.14 2

3.4 LA2 LCO 3.4.1.2 Design details listing the components associated with each reactor coolant loop for Bases ITS 5.5.14 1

Operability.

3.4 LA3 4.4.1.2.3, Information describing the characteristics of operating reactor coolant or Residual Bases ITS 5.5.14 2

4.4.1.3.3, Heat Removal (RHR) loops.

4.4.1.4.1.2, 4.4.1.4.2 3.4 LA4 LCO 3.4.1.3 Design details listing each RHR loop and the components associated with each Bases ITS 5.5.14 1

reactor coolant loop for Operability.

3.4 LA5 Not used.

3.4 LAS 4.4.31,4.4.3.2 Details describing the testing methods used to demonstrate pressurizer heater Bases ITS 5 5.14 3

Operability.

3.4 LA7 Table 4.4-4 Details describing the method used to analyze reactor coolant samples for gross Bases ITS 5 5.14 3

Note **

radioactivity.

3.4 LA8 Not used.

3.4 LA9 3.4.6.1 Action a Parameters for which containment atmosphere must be analyzed when Bases ITS 5.5.14 3

containment radiation monitors are inoperable.

Relocated Detail Types 1

Details of System Design 3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation (By) - Byron specific (Bw)- Braidwood specific Byron and Braidwood 1

LA_ i BL 3 4

__.__. - = _ = _ -

_ _ - _ _ _. _ _- _ _ = _ - - _ - - _

- ~

.I y

l N

Table LA - Details Relocated from CTS.

?

f Discussion CTS-Description of New Control of Change.

Reference Relocated Details

. Location Process

. Type

' 3.4 LA10 LCO 3.4.6.2.f.

Details fct adjusting allowable pressurizer isolation valve (PlV) leakage when -

Bases ITS 5.5.14 3

tested at Reactor Coolant System (RCS) pressures other than that specified.

J 3.4 LA11 Table 3.4-1 Listing of RCS PlVs valve identification numbers and functions.

Bases ITS 5.5.14 -

1

{

3.4 ' LA12 Not used 3.4 LA13 Not used.

e 3.4 LA14 4.5.3.2, Details describing the method used to demonstrate that the safety injection (SI)

Bases 11 S 5.5.14 3:

3/4.5.4.1 and charging pumps are incapable of injectog into the RCS during Low i

Temperature Overpressure Protection (LTOP) conditions.

4.5.4.2.1 Details describing the method used to demonstrate that the Si pumps are TRM

$50.59

'3 5

incapable of injecting into the RCS during LTOP conditions.

l

[

3.4 LA15 4.4.9.3.2 Valve identification numbers used for demonstrating Operability of RHR suction Bases ITS 5.514 3

relief valves when used for LTOP.

l

}

t 3.4 LA16 Not used.

3.4 LA17 LCO 3.2.3 Requirement for maintaining four RCS loops in operation.

Bases ITS 5 5.14 2

f 3.4 LA18 4.2.3.5 Method for determining RCS total flow rate.

TRM 50 59 3'

3.4 LA19 4.2.3.4 Surveillance requirement to perform an 18 month Channel Calibration of the RCS TRM 550.59 3

total flow rate indicators.

i 4

- Relocated Detad Types 1

Detads of System Design 3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation j

(By)- Byron specific

.r (Bw)- Braidwood specific h

Byron and Braidwood 2

LA_TOL 3 4 l

1

^ Tatde LA - Details Retocated from CTS

^

Discussion CTS-

Description of New=

' Control of Change Reference.

Relocated Details' Location

Process

. Type.

3.4 LA20-hot used.

.3.4 : LA21 LCO 3.4.6.2.c -

Excepting isolated steam generators from RCS leakage limits.

Bases ITS 5.5.14 3

3.4 LA22.

3.4.91 Actons Requirement that an engmeering evaluation be performed to determme the effects Bases ITS 5.514 -

"3 of a temperature or pressure excursion on the structuralintegrity of the RCS.

3.4 LA23 -

4.4.6,1.c Requirement to penodically verify the oil separator porton of the containment floor

-TRM

. $50.59 3

drain collection sump has been filled.

3.4 LA24 4.4.6.2.1.a.

Surveillance requirements for demonstrating RCS leakage is within snecified "

..T R M

$50.59

'3-4.4.6.2.1.b, limits.

4.4.6.2 1.e 3.4 LA25 3.4.9.3 Action e Requirement to submit a Special Report to the Commission in the event that 'edher TRM-

$50.59 the pressurizer power operated relief valves, the RHR sucton relief valves, or the RCS vents are used to mitigate an RCS pressure trensient.

3.4 LA26 4.4.6.2.2.c.

Requirement to demonstrate each RCS PlV Operable by verifying leakage to be TRM_

$50.59 -

.3 witnin its limit prior to retuming the valve to service following maintenance, repair, or replacement.

3.4 LA27 Table 3.3-6, RCS leakage detection instrumentation id3ntification numbers for the containment

' Bases ITS 5.5.14 1

Table 4.3-3 gaseous and particulate radioactivity monitors.

Relocated Detail Types 1

Details of System Design 3,. Procedural Detads for Meetmg TS Requwements 2 Description of System Operation (By)- Byron specific (Bw) - Braidwood specife Byron and Braidwood 3

i A_TBL3 4 4

~

~Q)'

)

\\ )

Table LA - Details Relocated from CTS Discussion CTS Description of New Control of Change Reference Relocated Details Location Process Type 3.4 LA28 LCO 3.4.6.1 b.

Details of the RCS leakage detection systems regarding the methods used to

-Bases

. ITS 5.514 1, 2 4.4.6.1.b monitor leakage into the containment floor drain sump and the reactor cavity sump.

3.4 LA29 SR 4.1.1.4.b Requirement to verify the RCS average temperature is at least 550*F once per 30 TRM

$50.59 3

minutes when the reactor is critical and RCS temperature is less than 557*F with the T.,-T,,, Deviation Alarm not reset.

.I Relocated Detail Types 1

Detads of System Design 3 Procedural Detads for Meeting TS Requirements 2 Description of System Operation (By)- Byron specirc (Bw) - Braidwood specife Byron and Braidwood 4

LA_IBL3 4

=. _..

~.. -...... -..

.~..:..--.~.

-J

N..Y Table L - Less Restrictive Changes to CTS Discussion Description ITS CTS Change of Change of Change Requirement Requirement Category ITS Section 3.4, Reacter Coolant Systems 3.4 L1 Requirements to verify through incore flux mapping and RCS total flow rate 3.2.2, 3.2.3 Actions 111 Vill comparison that the combination of Reactor Coolant System (RCS) total flow rate and 3 4.1 b and c. 4.2.3.2, Nuclear Enthalpy Rise Hot Channel Factor (F2n) are within limits were eliminated 4.2.3.3 consistent with STS. Individual limits for RCS total flow rate and Fynwere retained in separate Specifications.

3.4 L2 The explicit requirement to determine RCS temperature to be a 550*F within 15 '

SR 3.4.2.1, 4.1.1.4.a Vi minutes prior to achieving reactor criticality was removed since SR 3.0.4 requires the SR 3.0.4 performance of this surveillance prior to entering these cc..Jitions specified in the Applicability.

3.4 L3 Requirements were revised to base the number of operating RCS loops on the rod 3 4.5 LCO and 3 41.2 LCO and I, til withdrawal capability of the Rod Control System rather than on the position of the Actions A, B and.

Actions b and c Reactor Trip System breakers (RTBs) since methods other than opening the RTBs are C

available for preventing an inadvertent rod withdrawal.

3.4 L4 The completion tirne for reducing Thermal Power when RCS total flow rate is outside 3.4.1 Action B 3 2.3 Action a.2 IV its limit was relaxed from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to allow for an orderly transition to a Mode in which the limit is not applicable.

3.4 LS Not used.

l Less Restrictive Change Categones i

Retaxation of t_CO requirements V

Relaxation of SR acceptance enteria il Relaxation of Appicability VI Relaxation of Survedlance Frequency 111 Relaxation of Action requirernents Vil Deletion of requirements redundant to regulation IV Relaxation of completion tune Vill Deletion of Surveinance requirements (By)- Byron spectre (Bw)- Braidwood specirc Byron and Braidwood 1

L_i BL3 4

m,

t m.

- - g; w

y

}.

s_

-l s

.J' c

i Table L - Less Restrictive Changes to CTS -

Discussion Description ITS 1

. CTS Change.

of Change of Change' Requirement Requirement :

Category 3.4 a L6_.

'An allowance was included for separate condition entry for each RCS loop isolation 3.4.17 Actions 3.0.3 :

. til valve discovered either closed or with power available to its operator. Also, CTS Note and Action imphcitly requires that, when one or more loop isolabon valves have power avadable, A

i the unit be placed in a Mode in which the LCO does not apply. Required Achons were relaxed to allow 30 minutes to restore cofii,A=n.= with the LCO by removing power from the valve operators.

l 3.4 L7 The completion time for restoring an RCS pressure isolation valve (PlV) to within its 3'.4.14 Action A-3.4 6.2 Action c IV leakage limit was relaxed from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to indefinitely provided the compensatory.

[

Actions are taken to isolate the high pressure porten of the affected system from the i

Iow pressure porten with a specified isolation valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and with a second specified isolation valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.-

[

3.4 L8 Not used.

i 3.4 L9 The CTS req airement to maintain both hot and cold legs isolation valves closed until 3.4.18 Action B 3.4.1.5.2 Actions lil the isolated loop's cold leg temperature is within limits was reforrmhed and rela-

'5

[

require closure of only the cold leg isolation valve since this adequately prevem cold water reactivity event.

i 3.4 L10 An allowance was added so that the surveillance to perform a Channel Operational -

SR 3.4.12.7 4.4 9.3.1.a VI Test on each pressurizer power operated relief valve (PORV) actuaten chaNel need

[

not be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering the Modes (4) of appk in,ility from Mode 3.

i 5

i Less Restrictive Change Categores i

1 Relaxation of LCO requirements V

Relaxation of SR acceptance enteria i

il Relaxation of Applicatnisty VI Relaxation of Survenance Frequency til Relaxation of Action requirements VII Deletion of requirements redundant to regulation k

j IV Relaration of completion time Vitt Deletion of Surveillance requirements

{

i (By) - Byron specific

[

(Bw) - Braidwood specific i

i l

Byron and Braidwood 2

L_TBL3 4. l l

. t 1m 2

m.

m m.

m

.m

d D(~

}

,a

\\

Table L - Less Restrictive Changes to CTS Discussion.

Description

~ ITS -

CTS Change of Change of Change Requirement -

Requirement

Category 3.4 L11 The completion time for reducing power to < 5% RTP when any Departure from -

3.4.1 Action B -

3.2.5 Actions IV Nucleate Boiling (DNB) parameter limit is exceeded was relaxed from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to allow for an orderly power reduction to M ade 2.

3.4 L12 CTS 3.0.3 requires that, with only one RCS loop in operation and the RTBs in the 3.4.5 Action C 3.4.1.2 Actions.

til closed position (Rod Control System capable of rod withdrawal) and if the Action to b and c, open the RTBs is not completed within the required time, the unit be placed in a Mode 3.0.3 (4) in which the LCO does not apply. _ Required Actions were relaxed to allow continued operation in Mode 3 provided three compensatory Actions are taken immedetely.

3.4 L13 Not used.

3.4 L14 The frequency for determining the boron concentration of an isolated loop to be SR 3.4.18.2 4.4.1.5.2.2 VI greater than the boron concentration of the operating loops prior to opening the valves c

of the isolated loop was re! axed from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to allow adequate time to sample and confirm the analysis results.

3.4 L15 An exception was included to relax the surveillance requirement that RCS PlV leakage SR 3.4.14.1 -

4.4.6.2.2 VI be venfied whenever the valves are actuated. A note allows PlVs actuated during Note 2 surveillance testing need not be tested more than once if a repetitive testing loop cannot be avoided ess Restrictive Change Categories I

Relaxation of LCO requirements V

Relaxation of SR acceptance enteria ll Relaxation of App:,c.t,J4 VI Relaxatton of Surveillance Frequency j

lli Relaxaten of Action requirements Vil Deletion of requirements redundant to regulation IV Relaxation of completon time Vill Deletion of Surveillance requirements i

(By)- Byron specirac (Bw)- Braidwood specific 4

Byron and Braidwood 3

L_TBL3 4 i

n L)

J.

~G Table L - Less Restrictive Chang- + e C iS -

Discussion Description ITS.

CTS '-

Change.

of Change of Change Requirement Requirement Category 3.4 L16 An exception was included to relax the requirement that a maximum of one centrifugal 3.4.12 Action A LCO 3.5.3.a 1V charging pump may be capable of injection. A note was included in the LCO to allow Note -

two pumps capable of injecting into the RCS for s 15 minutes during pump swap ooerations.

3.4 L17 '

Because of the availability of diverse methods of RCS leakage detection, the LCO 3 4.15 Table 3.3-6 1V requirement that both containment atmosphere gaseous and particulate radiation

- SR 3.4.15.1, items 3 and 4, monitors be Operable was relaxed so that only one of the containment atmosphere SR 3.4.15.2 LCO 3.4 6.1, radioactivity monitors is required Operable.

SR 3.4.15 4 4 4 6.1.a 3.4 - L18 The minimum boron concentration to which an isolated loop must be charged prior to LCO 3.4.18 a, LCO 3.4.15.2.a.

I, V unisolating it was changed ftom the concentration of the operating loops to that 3R 3.4.18.2 4.4.1.5.2.2 required by shutdown margin (SDM) calculation. This change allows an isolated loop to be unisolated even if the boron concentration of the isolated loop is less than the operating loops as provided the isolated loop concentration meets the applicable SDM requirements.

3.4 L19 With both the containment atmosphere gaseous and particulate radiation monitors 3.4.15 Action B 3.4.6.1 Actions til, IV inoperable. CTS requires the restoration of one of the monitors within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In c 1 and c.2 addition, both an RCS inventory balance and grab samples of containr.ient ntmosphere are periodically required as compensatory Actions. These Actions were relaxed to require restoration of one of the monitors within 30 days and performance of either of the compensatory Actions.

Less Restrictive Change Categones i

Relaxation of LCO requirements V

Relaxation of SR acceptance criteria il Relaxation of Apphcability VI Relaxation of Surveillance Frequency til Relaxation of Acticn requirements VII Deletion of requirernents redundant to regulation IV Relaxation of completion time Vill Deletion of Surveillance requirements (By) - Byron speceric (Bw)- Braidwood speciric Byron and Braidwood L_1 BL3.4 4

f' N

/O V

D)

Table L - Less Restrictive Changes to CTS I

Discussion Description ITS

. CTS Change of Change of Change Requirement Requirement.

Category 3.4 L20 Exceptions were included to relax the requirement that all the monitors of the RCS '

3.4.15 Actions 3.0.4 II, til Leakage Detection System must be Operable prior to entering or changing Modes of A and B applicability. These changas allow Mode changes if either the containment sump monitor or either of the containment atmosphere radioactivity monitors are inoperable provided that the required compensatory Actions are performed daily.

3.4 L21 With the containment sump flow monitor inoperable, the requirement to restore the 3.4.15 Required 3.4.6.1 Action b

' Vi monitor to Operable status within 7. days was relaxed to allow 30 days for restoration Action A.2 provided the compensatory Action to perform a water inventory balance is performed l

daily.

3.4 L22 The interval for performing an RCS water inventory balance was relaxed from once 3.4.15 Required 3.4.6.1 Action IV per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> considering the availability of diverse methods of Actions A.1 and c.3 detecting RCS leakage.

B.1.2 3.4 L23 CTS 3.0.3 requires that, with two required RCS loops inoperable, the unit be placed in 3.4.5 Action F 3.0.3 Ill a Mode (4) in which the LCO does not apply. An explicit condition was included to allow continued operation in Mode 3 provided three compensatory Actions are taken immediately.

3.4 L24 The surveillance to perform an RCS water inventory balance once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> was SR 3.4.131, 4 4 6.2.1.d.

.VI modified to allow its initial performance 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state 3.4.15 Required 3 4 6.1 Action operation rather than requiring the surveillance to be met prior to entering this power Actions A.1 and c.3 condition. Actions requiring the periodic performance of this surveillance were also B.1.2 provided with this allowance for their initial performance.

Less Restnctive Change Categories f

I Relaxation of LCO requirements V

Relaxation of SR acceptance criteria 11 Relaxation of Applicabihty VI Relaxation of Surveillance Frequency i

Ill Relaxation of Action requirements Vil Deletion of requirements redundant to regulation IV Relaxation of completion time Vill Deletion of Surveillance requirements (By) - Byron spectre (Bw)- Braidwood specife Byron and Braidwood 5

L_~IBL3 4 i

r

-m m

+.

r.

(j _

f~.

O V

Table L - Less Restrictive Changes to CTS Discussion Description ITS CTS Change of Change of Change Requirement Requirement Category 3.4 L25 CTS imposes a maximum leakage rate of 1.0 gpm (notwithstanding the provisions for SR 3.4.14.1 LCO 3.4.6.2.f.

V RHR suction motor operated valves in Table 3.4-1) from any RCS PlV. A more Table 3.4-1 meaningfullimitation based on valve size was used to prevent unwarranted repair on Notes larger valves.

3.4 L26 With the pressurizer otherwise inoperable (water level not within limit), the Action 3.4.9 Action A 3 4 3 Action b 111 requirements were revised to place the unit in Mode 3 with all rods fully inserted and i

the Rod Control System incapable of rod withdrawal rather than Mode 3 with the RTBs open since methods other than opening the RTBs are available for preventing an inadvertent rod withdrawal.

3.4 L27 The 18 month surveillance to operate the PORVs through a complete cycle of travel SR 3.4.11.2 4 4.4.1.c VI was revised to eliminate the explicit requirement to perform the ter' in Mode 3 or 4 and Note requires, instead, the surveillance to be " current' upon entering Modes 1 and 2. STS SR 3.0.4 and Generic Letter 90-06 continue to require its performance in Mode 3 or 4.

3.4 L28 The default Action to reduce the RCS temperature and pressure to < 200'F and 3.4.3 Action B 3 4.9.1 Actions ill

< 500 psig, respectively, when any RCS temperature or pressure limit is not restored within 30 minutes was relaxed to place the unit in Mode 5. The temperature in this Mode is equivalent but pressure may exceed 500 psig.

3.4 L29 Not used.

[

Less Restrictive Change Categories 1

Relaxation of LCO requirements V

Relaxation of SR acceptance criteria 11 Relaxation of Applicability VI Relaxation of Surveillance Frequency 111 Relaxation of Action requirements Vil Deletion of requirements redundant to regulation IV Relaxation of completion time Vill Deletion of Surveillance requirements (By) - Byron snecific (Bw) - Braidwood speoric Byron and Braidwood 6

L_T BL3.4

_m

..-.. ~..

r

O; O

Table L - Less Restrictive Changes to CTS

- i

~ Discussion Description ITS '

. CTS

. Change

- of Change of Change

. Requirement Rg-i...;nt '

Category 3.4 L30 The applicability has been revised to delete the requirements to comply'with the LCO 3.4.16 3/4.4.8,

11. Ill and Actions and to penodically verify the RCS specific activity within limits during Table 4.4 '

Mode 3 with RCS temperature < 500*F and Modes 4 and 5 due to the unlikely possibility of a steam generator tube rupture during these Modes Similarly, the sampling and analysis requirements when the specific activity of the reactor coolant l

exceeds 100/E Ci/ gram were deleted since exceeding this limit now requires promptly placing the unit in a Mode in which the specific activity limits do not apply.

~

3.4 L31 Not used:

3.4 L32 An exception was included to relax the requirement that the Dose Equivalent 1-131 3.4.16 Action A 3.0.4 II,111 specific activity must be within limits prior to entering or changing Modes of applicability. This change allows entry into the applicable Modes while relying on the required Actions even though the Actions may eventually require exiting the manhc=Na Modes if the limits are not restored within specified times.

3.4 L33 Not used.

3.4. L34 The frequency interval for verifying the reactor coolant gross specific activity is within SR 3.4.16.1 4.4 8 VI limits was relaxed from 72 hoters to 7 days because this interval is adequate to trend Table 4.4-4 I

this parameter.

Item 1

{

I f

t t

Less Restnctive Change Categones I

Relaxation of LCO requirernents V

Relaxation of SR acceptance enteria il Relaxation of Applicability VI Relaxation of Surveillance Frequency 111 Relaxation of Actum requirements Vil Deletion of requirements redundant to regulation

[

IV Relaxation of completion time Vill Deleton of Surveillance requirements (By) - Byron specific I

(Bw) - Braidwood specific i

Byron and Braidwood 7

L T BL3 4 i

t i

t v

V-C U

Table L - Less Restrictive Changes to CTS Discussion Description ITS OTS._

Change of Change of Change Requirement Requirement Category 3.4 L35 The exception to CTS Specification 4.0.3 was eliminated for the surveillance to SR 3.4.1.4, 4.2.3.5 VI determine the RCS total flow rate by precision heat balance after each fuel loading.

SR 3.0.3 This change relaxes the frequency to allow the missed surveillance to be performed in the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay period.

3.4 L36 Whenever an RCS operating loop temperature is not within limit, the Action to place 3.4.2 Action A 3.1.14 Actions

, lil, IV the unit in Mode 3 was relaxed to place the unit in Mode 2 with k,, < 1.0 to be consistent with the Applicability. Also the time specified for completing this Action was relaxed from 15 minutes to 30 minutes to allow for an orderly unit shutdown.

3.4 L37 An exception was taken to the LCO requirement that at least one Residual Heat LCO 3.4.7 LCO 3 41.41 i

Removal (RHR) loop shall be in operation in Mode 5 with loops filled. The exception Note 4 allows all RHR loops to be removed from operation during the transition from Mode 5 to Mode 4 when at least one RCS loop is in operation. This change provides equivalent RCS circulation for mitigation of a boron dilution event and an orderly heatup transition to the next Mode.

3.4 L38 The requirements for pressurizer safety valves was relaxed to allow entry into the LCO 3.4.10 Note LCO 3 4.2 2 I, VI Mode of applicability without the lift settings having been verified within limits in order to set them at nominal operating temperature and pressure. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> following entry into Mode 3 is allowed for this adjustment provided the valves have had a preliminary cold setting.

i Less Restrir%e Change Categories 1

Relaxation of LCO requirernents V

Relaxation of SR acceptance criteria 11 Retaxation of Appicability VI Relaxation of Surveillance f requency Ill Relaxation of Acton requirernents VII Deleton of requirements redundant to regulation IV Relaxation of completion tune Vill Deleton of Surveillance requirements (By)- Byron specifec (Bw) - Braufwood specific Byron and Braidwood 8

L_1BL3 4

j-~)Q d

q:

- s,f

(_

Table L - Less Restrictive Changes to CTS ~

Discussion -

Description

' ITS CTS-Change of Change of Change Requirement Requirement

. Category 3.4 L39 The Modes in which sampling and analysis of reactor coolant for isotopic lodine is SR 3.4.16.2 Table 4.44 VI' required to be performed following power level changes > 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Items 2 and 4.b period was relaxed from Modes 1,2, and 3 to Mode 1 where fuel failure is more apt to occur and where RTP changes of this magnitude are of concem.

i C

f I

e L

[

l

~

e b

Less Restrictive Change Categories

[

t Relaxation of LCO requirements V

Relaxation of SR acceptance crites.a l

11 Relaxation of Apphcabitity VI Relaxation of Surveillance Frequency ill Relaxatsn of Action requirements V11 Deletion of requirements redundant to regulatoon IV Relaxation of completion time

- Vill Deletion of Surveillance requwements

[

f (By)- Byron speofc (Bw)- Braidwood specific

-}

Byron and Braidwood 9

I _1 BL3 4 l

L

ENCLOSURE 1 l

ITS REVISION K ITS SECTION 3.4 i

O l0

3.4 Q

BYRON ITS i

J 4

I l

i i

io e

J J

4 I

1 4

d O

Retrieved from "https://kanterella.com/w/index.php?title=ML20154M507&oldid=4136336"