ML20236W578

Forwards Rev G as Final Package Closeout of Improved Tech Specs (ITS) Sections 3.1 & 3.2,originally Submitted on 961231.Revs Are Being Provided in Same ten-section Format as Initial ITS Submittal

ML20236W578
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Site:	Byron, Braidwood
Issue date:	07/31/1998
From:	Tulon T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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_ - - - _ _ _ - _ - _ _ _ - _ - _ _ _ _ - _ _

Commonwealth idium Company liraidwood Generating station Route *). Ikn H4 Tramille, IL 60 40%%19 18144M 2801 July 31,1998 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 - 0001

Subject:

Revision G to the Improved Technical Specifications (ITS) Submittal -

ITS Sections 3.1 and 3.2 Closcout 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 1 and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Numbers: 50-456 and 50-457 7]

G

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 Revision G to the Referenced ITS submittal. ITS Revision G contains Commonwealth Edison's (Comed's) final Package Closecut for ITS Sections 3.1 and 3.2. However,in ITS Section 3.1, Comed is awaiting the Staffs resolution of TSTF-234 in order to close RAI 3.1.7+01. In ITS Section 3.2, Comed is awaiting the WOG ITS Subcommittee's resolution of WOG-117 (RAI 3.2.1-02) and the StalTs resolution of TSTF-241 in order to close RAI 3.2.4-01 and RAI 3.2.4-02 respectively.

Enclosure 1 contains ITS Revision G. Attachment 1 contains Comed's final RAI Responses to Sections 3.1 and 3.2. Any revised response is noted along with the original response. As requested by the Staff, Attachment 2 contains nn affected page list identifying submittal pages that have changed as a result ofincorporating RAI responses.

}{

Attachment 3 contains an affected page list summarizing all submittal pages that have changed in ITS Revision G.

3 D ~

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p 9000060079 990731 l PDR ADOCK 05000454' i P pm l

1 unwom Commny ,

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l F

Document Control Desk p July 30,1998 l NJ- Page 2 1

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

1 submittal:

{

l. ByronITS

2. Braidwood(Brwd)lTS l 3. Byron CTS Markups j 4. Brwd CTS Markups l 5. CTS Discussion of Changes (DOCS)

6. LCO Markups L

7. LCO Justification for Differences (JFDs) l 8. Bases Markups l 9. Bases JFDs

10. No Significant Hazards Consideration (NSilC) i L Please address any comments or questions regarding this matter to our Nuclear Licensing L Department. I L

! h Sincerely, l

f Timothy J. Tulon Site Vice President

!- Braidwood Nuclear Generating Station

Enclosure:

ITS Revision G i:

L Attachments: Attachment 1 -ITS Sections 3.1 and 3.2 RAI Revised Responses l- Attachment 2 -ITS Sections 3.1 and 3.2 RAI Affected Page List Attachment 3 -ITS Sections 3.1 and 3.2 Section Closcout Affected Page List cc: NRC Regional Administrator - Region ill Senior Resident Inspector - Braidwood Senior Resident Inspector - Byron Office of Nuclear Faci'ity Safety - IDNS O ~~~ ~

bec: Byron Project Manager- NRR Braidwood Project Manager -NIUt O W. Beckaer - NRR -

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ATTACHMENT I O

ITS SECTION 3.1 RAI REVISED RESPONSES O

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l Rzspons to NRC RAI For ITS Section 3.1 09-Jui 98 NRC R fNumber NRC Issued Date RAI Status i

3.1-01 8/5/97 Closed i

\ NRC Description of Issue j 3.1-O l ' .J FD-P19 SR 3.1.6.1, the verification of the estimated critical control bank position l The word "Once" has been added to the frequency which specifies an interval "Within" a particular time frame ("Within 4 I hours prior to criticality"). Comment: This is a legitimate use of the word "Once" in an SR frequency, and it is a generic change. This should be brought to the Tech Spec Task Force for future action. I l Comed Response to issue

' 4/1/98 Revised Response: Comed will withdraw this change. This change is provided in our comprehensive ITS Section 3.1 closcout submittal revision.

l Original Response: Comed will submit a traveler at the next Westinghouse Owner's Group (WOG) ITS meeting scheduled for November 19 and 20,1997 to propose tL Byron and Braidwood plant specific change to the WOG. In the interim, Comed continues to pursue this change. (See RAls 3.1.6-04,3.6.3-09,3.4.14-09,3.4.16-05, and 3.4.18-03.)

NRC RAI Number NRC issued Date RAI Status

[

3.1.1-01 8/5/97 Closed l NRC Description of Issue l

L 3.1.1-01 C Bases discussion ofITS SR 3.1.1.1, page B 3.1-6 I

l( The sentence " The SDM is specified in the COLR." has been added to the Bases.

l(_

Comment: Revise this insert to read "The SDM limits are specified in the COLR."

l Comed Response to issue ITS and NUREG were revised to reword the Bases insert (Ref. Bases JFD 3.1 P2 on page B 3.1-6) to read "The SDM limits are specified in the COLR."

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NRC RAI Number NRC issued Date RAI Status 3.1.2-01 8/5/97 Closed l

l NRC Description ofIssue

! 3.1.2-01 F JFD-P4 l ..JFD-BP9. .

l ITS SR 3.1.2.1 and SR 3.1.2.2 STS SR 3.1.3.1 in lieu of adopting STS SR 3.1.3.1, verification of core reactivity - with two frequencies, the ITS specifies two SRs, SR 3.1.2.1 and SR 3.1.2.2. Comment: This is an editorial change. Submit a TSTF change request.

Comed Response to issue Comed will submit a traveler at the next Westinghouse Owner's Group (WOG) ITS meeting scheduled for November 19 and 20,1997 to propose the Byron and Braidwood plant specific change to the WOG. In the interim, Comed continues to pursue this change.

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- = = = = = = = = = = = = = = = - -

Response to NRC RAI For ITS Section 3.1 09-Jui-98 l NRC RAI Number: NRC Issued Date RAI Status 3.1.3-01 8/5/97 Closed NRC l>escription of issue 3.1.3-01:: JFD-BP6

_ . Base discussion for ITS SR 3.1.3.2, page B 3.1-23 The discussion about the 300 ppm surveillance limit for the MTC has not been adopted. The reason given for this difference is that the discussion is at a level of detail not actually in the SR. This material is relevant to understanding the development of the 300 ppm MTC Surveillance limit. Comment: This is not justifiable plant specific or editorial difference frorn the STS. Revise the submittal to adopt the STS discussion.

Comed Response to issue ITS and NUREG were revised to include in the Surveillance Requirements Section of the Bases for ITS LCO 3.1.3 "Because the RTP MTC value will gradually become more negative with further core depletion and boron concentration reduction, a 300 ppm SR va:ue of MTC should necessarily be less negative than the EOL LCO limit. The 300 ppm SR value is sufficiently less negative than the EOL LCO limit vake to ensure that the LCO limit will be met when the 300 ppm Surveillance criierion is met." As a result, Bases JFD 3.1-P6 was changed to "Not used."

NRC RAI Number NRC Issued Date RAI Status 3.1.4-01 8/5/97 Closed NRC Description of Issue 3.1.4-01 : ' DOC-A6 JFD-P7 ITS 3.1.4, Required Action B CTS 3.1.3.1.b.1 STS 3.1.5, Required Action B.I The CTS and STS contain the required action to restore rod alignment. The ITS detes this action, since complying with the LCO is always an option. Approved.

Comment: Provide a TSTF change request for this change.

Comed Response to issue Comed will submit a traveler at the next Westinghouse Owner's Group (WOG) ITS meeting scheduled for November 19 and 20,1997 to propose the Byron and Braidwood plant specific change to the WOG. In the interim, Comed continues to pursue this change. (See RAI 3.2.2-01.)_

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R:spsnsa to NRC RAI For iTS Section 3d~ 09-Jui-98 NRC RAI Number NRC lssued Date RAI Status 3.1.4-02 8/5/97 Closed NRC Description ofIssue I

3.1.4-02 C DOC-LA9 - l E01FD-C10 i ZlTS SR 3.1.4.1  !

! CCTS SR 4.1.3.1.1 l l . CSTS SR 3.1.5.1 l

l The CTS and STS have an increased SR frequency to verify rod alignment when the rod position deviation monitor is

) inoperable. This change has been submitted in TSTF traveller 110. TSTF-110 final disposition is pending, and has been l recommended for rejection.

Comment: Retain increased SR frequency when the rod position deviation monitor is inoperable.

Comed Response to Issue 4/1/98 Revised Response: Comed will incorporate approved TSTF 110 Revision 2. This change is provided in our comprehensive ITS Section 3.1 closecut submittal revision.

l Original Response: No change. TSTF-Il0 Revision I relocates conditional Surveillance Requirements (SRs) for functions with inoperable alarms from the Technical Specifications (TSs) to plant procedures or programs. The TSTFjustifies this by stating that the alanns do not directly relate to the LCO limits. Inoperable abrms do not affect the operability of the TS ,

function. This justification was used and accepted by the Staff during the development of the BWR NUREGs to allow

{

relocation of the alarm functions from the BWR Technical Specifications to plant procedures. Thisjustification was accepted by the Staff prior to the issuance of Revision 0 of the NUREGs. Typically these alarms are monitoring parameters which must be verified met on a specified Frequency (e.g.,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />). The basis for this Frequency is justified due to the i operability of the alarm function. Whenever this alarm function becomes inoperable, a more frequent SR Fregnency interval l[ is performed on the parameter (e.g.,4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). This Frequency continues until the alarm function is restored to operable status. Relocating this detail to plant procedures or programs would not impact the safety significance of the TS requirement since the parameter being monitored is presumed to be operable whenever the alarm becomes inoperable. The inoperable alarm function does not impact operability of the monitored parameter. In addition, other ITS SR Frequencies are rtated in the ITS Bases to be based on associated alarms or indications which are assumed to be operable or available. (e.g., The Actions Section of the Bases for ITS LCO 3.2.4 for Required Action A.2 states "A 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is sufficient because any additional change in QPTR should be relatively slow. Further, this Completica Time is consistent with the Frequency required for the Surveillance with an inoperable alarm or instrumentation." The Surveillance Requirements Section of the Bases for ITS LCO 3.8.1 discussing SR 3.8.1.4 states "The 31 day Frequency is adequate to assure that a j sufficient supply of fuel oil is available since low level alarms are provided and facility operators would be aware of any -

large uses of fuel oil during this period." The Surveillance Requirements Section of the Bases for ITS LCO 3.9.5 discussing SR 3.9.5.1 states "The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient, considering the flow, temperature, pump control, and alarm indications available to the operator in the control room for monitoring the RHR System." The Surveillance Requirements l Section of the Bases for ITS LCO 3.9.6 discussing SR 3.9.6.1 states "The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient, considerir; l

the flow, temperature, pump control, and alarm indications available to the operator for monitoring the RHR System.") I These alarms / indications are not specified in the TSs but typically require additional actions within plant procedures to account for the alarm / indication not being available. Typically alarm response procedures provide guidance for any necessary actions whenever alarms are inoperable. Placing this detail in these procedures ensures that the operator has sufficient guidance to respond to the inoperable alarm function and to perform the necessary conditional SRs. (See RAls 3.1.6-05 and 3.2.3-04) Comed continues to pursue this change.

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Response to NRC RAI For ITS Section 3.1 09-Jui-98 NRC RAI Number NRC Issued Date RAI Status G 3.1.5-01 8/5/97 Closed NRC Description of Issue i

3.1.5-01 CJFD-P12 "DJ FD-l'14 aCITS 3.1.5, Applicability 0 D Bases for ITS 3.1.5, Applicability - page B 3.1-36 ^

STS 3.1.6 Applicability Note The S.TS Applicability Note states, "This LCO is not applicable while performing SR 3.1.5.2." This note is adopted in corresponding ITS 3.1.5, with changes, but is placed with the LCO statement to prevent a possible misinterpret:ation of SR 3.0.4. The ITS note states " Shutdown banks may be outside the limit when required for performance of SR 3.1.4.2."

Comment: These are notjustinable plant specific or editorial differences from the STS. The STS presentation is clear.

Revise the submittal to adopt the STS presentation.

Comed Response to Issue ITS and NUREG have been revised to adopt the NUREG wording for the Note. As a result, LCO JFD 3.1-P13 was changed to "Not used." However, the relocation of the Note from the Applicability to the LCO has not changed. Comed continues to ,

pursue this change. 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 entire 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 O TSTF: 3.6.3. (See RAls 3.1.6-01,3.4.1-04,3.4.10-03, and 3.4.12-01 item b.)

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NRC RAI Number NRC Issued Date RAI Status 3.1.5-02 8/5/97 Closed NRC Description of Issue 3.1.5-02 J JFD-Cl2 ITS 3.1.5 Applicability )

(recurring editorial changes) l The ITS incorporates editorial changes to the presentation of the Applicability paragraph (semi-colons and the word "and" l have been addeh. Comment: Revise the submittal to adopt the STS presentation.

Comed Response to issue l WOG-81 was withdrawn from the ITS submittal. ITS and NUREG were revised to adopt the ISTS presentation in the t-Applicability section ofITS LCOs 3.1.1,3.1.3,3.1.5, and 3.1.6. As a result, LCO JFD 3.1-Cl2 was changed to "Not used."

(See RAls 3.4-01,3.5-01,3.7.10-03,3.7.11-02,3.7.13-06,3.9.4-06,3.8.2-02, and 3.9.7-05.)

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l ResponS: to NRC RAI Fcr ITS S:cti:n 3.1 09 ,Iui-98

== ::= :. , - =:- .. = .- -- = = === l NRC RAI Number NRC Issued Date RAI Status i G , 3.1.6-01 8/5/97 Closed NRC Description ofIssue l

3.1.6-01 JFD-P12 D CJFD-Pl4 i

D:P

• 3.1.6, Applicabihty l

l TBases discussion for ITS 3.1.6, Applicability - page B 3.1-42

{

l. STS 3.1.7, Applicability Note The STS Applicability Note states, "This LCO is not applicable while performing SR 3.1.5.2." This note is adopted in corresponding ITS 3.1.6, with changes, but is placed with the LCO statement to prevent a possible misinterpretation of SR 3.0.4. The ITS note states, " Shutdown banks may be outside the hmit when required for performance of SR 3.1.4.2."

f Comment: These are not justifiable plant specific or editor.J differences from the STS. The STS presentation is clear.

Revise the submittal to adopt the STS presentation.

Comed Response to issue l

ITS and NUREG have been revised to adopt the NUREG wording for the Note. As a result, LCO'JFD 3.1-Pl4 was changed to "Not used." However, the relocation of the Note from the Applicability to the LCO has not changed. Comed continues to pursue this change. 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 l the entire LCO and not to exceptions to the Applicability. Having a Note that modifies the Applicability requirements could l 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 No'e was added by a

'I q 1 TSTF: 3.6.3. (See RAI 3.1.5-01,3.4.1-04,3.4.10-03, and 3.4.12-01 item b.)

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NRC RAI Number NRC Issued Date RAI Status 3.1.6-02 8/5/97 Closed l NRC Description of issue 3.1.6-02 CTS 4.1.3.6 ITS SR 3.1.6.1 SR 3.1.6.1 provides the Surveillance Requirement and the associated Frequency for the verification of the estimated critical control bank position. Corresponding CTS 4.1.3.6 does not show this material. Comment: This material does not appear in the markup of CTS 3/4.1.3.6. Revise the submittal to show the addition of this Surveillance Requirement to the CTS.

Comed Response to issue CTS markup pages 3/41-1 for CTS SR 4.1.1.1.1.b and 4.1.1.1.1.c were revised to include the material originally deleted by i CTS DOC 3.1-RI. CTS SR 4.1.1.1.1.b was annotated with "SR 3.1.6.2" in the margin and CTS SR 4.1.1.1.1.c was l annotated with *SR 3.1.6.1" in the margin. In addition, CTS markup pages 3/4121 and insert 3.12]C were revised to add l SR 3.1.6.1 to CTS Insert 3.121C. CTS DOC 3.1-A23 was created to document this change and reads " CTS SR 4.1.1.1.1.b requires that the SDM shall be determined to be within the limits specified in the COLR when in MODE 1 or 2 with keff greater than or equal to 1 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that control bank insertion is within the iimits of Specification 3.1.3.6. This requirement has been retained in ITS as S.R 3.1.6.2. In addition, CTS SR 4.1.1.1.1.c requires that the SDM shall be determined to be within the limits specified in the COLR when in MODE 2 with keff tess than I within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6. This requirement has been retained in ITS as SR 3.1.6.1. Since the SRs have been changed in format O

and presentation only, and the original intent was not changed. this is considered to be an administrative change and is consistent with NUREG-1431."

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Response to NRC RAI For ITS Section 3.1 09-Jui-98

!  : r == =::== = == ==== - = u_; u ._ .

l.

NRC RAI Number NRC issued Date RAI Status l /^ 3.1.6-03 8/5/97 Closed 6

NRC Description ofIssue l 3.1.6-03 BP34 i ZBases for ITS 3.1.6, Background - page B 3,1 39 Figure B 3.1.71, Control Bank Insertion vs. Percent RTP, has not been adopted. Thejustification for this difference is that the figure in the Bases duplicates the figure contained in the COLR, and to prevent misapplication and misinterpretation of the figure in the COLR. Comment: Figure in STS is for illustrative purposes. Consider using figure identical to figure in COLR.

Comed Response to issue l

No change. The convention adopted in the Byron and Braidwood ITS submittal was to delete " illustration only" figures in l the Bases to climinate the possibility of an Operator inadvertently using a Bases figure in place of an actual figure. (See l ElAls 2.0-03 and 3.2.3-03.) Comed continues to pursue this change.

NRC RAI Number NRC Issued Date RAI Status 3.1.6-04 8/5/97 Closed NRC Description of issue 3.1.6-04 OJFD-P19 J. ITS SR 3.1.6.1 ZSTS SR 3.1.7.1 The word "Once" has been added to the frequr. icy which specifies an interval "Within" a particular tim: frame ("Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to criticality"). Comment: This is a ler,itimate use of the word "Once" in an SR frequency, and it is a generic change. This should be brought to the Tech Spec ' Ink Force for future action.

Comed Response to Issue 4/1/98 Revised Response: In a meeting between Comed and the NRC on 4/1/98, this comment was withdrawn.

l Comed will submit a traveler at the next Westinghouse Owner's Group (WOG) ITS meeting scheduled for November 19 and 20,1997 to propose the Byron and Braidwood plant specific change to the WOG. In the interim, Comed continues to pursue

, this change. (See RAls 3.1-01,3.6.3-09,3.4.14-09,3.4.16-05, and 3.4.18-03.)

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Response to NRC RAI For ITS S ction 3.1 09-J ui-98 NRC RAI Number _ ~ _NRC _ _ _Issued

. _ . .Date _ _ -. _ . _ _ _ _ RAI Status

,- 3.1.6-05 8/5/97 Closed

. NRC Description ofissue

! 3.1.6-05:JFD-C10

itTS SR 3.1.6.2 t

CTS SR 4.1.3.6 ZSTS SR 3.1.7.2 The CTS and STS have an increased SR frequency to verify rod alignment when the rod position deviation inonitor is

!- inoperable. This change has been submitted in TSTE traveller 110. TSTF.! 10 final disposition is pending, and has been i recommended for rejection.

l. Comment: Retain increased SR frequency when the rod position deviation monitor is inoperable.

Comed Response to issue 4 /1/98 Revised Response: Comed will incorporate approved TSTF-110 Revision 2. This change is provided in our cunprehensive ITS Section 3.1 closeout submittal revision.

Original Response: No change. TSTF-110 Revision 1 relocates conditional Surveillance Requirements (SRs) for functions with inoperable alarms from the Technical Specifications (TSs) to plant procedures or programs. The TSTFjustifies this by stating that the alarms do not directly relate to the LCO limits. Inoperable alarms do not affect the operability of the TS function. This justification was used and accepted by the Staff during the development of the BWR NUREGs to allow relocation of the alarm functions from the BWR Technical Specifications to plant procedures. Thisjustification was accepted by the StafTprior to the issuance of Revision 0 of the NUREGs. Typically these alarms are monitoring parameters which must be verified met on a specified Frequency (e.g.,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />). The basis for this Frequency isjustified due to the operability of the alarm functicn. Whenever this alarm function becomes inoperable, a more frequent SR Frequency interval is performed on the parameter (e.g.,4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). This Frequency continues until the alarm function is restored to operable status. Relocating this detail to plant procedures or programs would not impact the safety significance of the TS requirement

( since the parameter being monitored is presumed to be operable whenever the alarm becomes inoperable. The inoperable alarm function does not impact operability of the monitored parameter. In addition, other ITS SR Frequencies are stated in the ITS Bases to be based on associated alarms or indications which are assumed to be operable or available. (e.g., The Actions Section of the Bases for ITS LCO 3.2.4 for Required Action A.2 states "A 12 hout Completion Time is sufficient -

because any additional change in QPTR should be relatively slow. Further, this Complen 1ime is consistent with the Frequency required for the Surveillance with an inoperable alarm or instrumentation." *1 he Sur veillance Requirements Section of the Bases for ITS LCO 3.8.1 discussing SR 3.8.1.4 states "The 31 day Frequency is adequate to assure that a sufficient supply of fuel oil ls available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period." The Surveillance Requirements Section of the Bases for ITS LCO 3.9.5 discussing SR 3.9.5.1 states "The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient, considering the flow, temperature, pump control, and alarm indications available to the operator in the control room for monitoring the RHR System." The Surveillance Requirements Section of the Bases for ITS LCO 3.9.6 discussing SR 3.9.6.1 states "The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient, considering the flow, temperature, pump control, and alarm indications available to the operator for monitoring the RHR System.")

These alarms / indications are not specified in the TSs but typically require additional actions within plant procedures to account for the alarm / indication not being available. Typically alarm response procedures provide guidance for any necessary actions whenever alarms are inoperable. Placing this detail in these procedures ensures that the operator has sufficient guidance to respond to the inoperable alarm function and to perform the necessary conditional SRs. (See RAls 3.1.4-02 and 3.2.3-04) Comed continues to pursue this change.

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i l R:spsnse to NRC RAI For ITS Szetion 3.1 09-J ui-98 NRC RAI Number NRC Issued Date RAI Status f

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3.1.6-06 8/5/97 Closed NRC Description ofIssue 3.1.6-06:JFD-PI

C CITS SR 3.1.6.3 i

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l ITS SR 3.1.6.3 has been editorially rewritten.

Comment: These are notjustifiable plant specific or editorial differences from the STS. The STS presentation is clear.

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l Revise the submittal to adopt the STS presentation. * '

Cun!'.d Response to Issue 1

No change. The change was for consistency in parallel construction within the LCO, the Required Actions, and the other two l SRs. The LCO states "{Each control bank) shall be within the { insertion, sequence, and overlap) limits specified in the COLR." The Required Actions and the SR3 were constructed similarly (i.e.," Verify (...) is within the {...) limits specified in the COLR."). Required Actions A.l.1 and B.l.1 state " Verify (SDM) is within the limits specified in the COLR." SR I 3.1.6.1 states " Verify (estimated critical control bank position) is within the limits specified in the COLR." SR 3.1.6.2 states " Verify (each contro) bank} is within the { insertion} limits specified in the COLR." Likewise, SR 3.1.6.3 states

" Verify {each control bann not fully withdrawn from the core} is within the (sequence and overlap} limits specified in the COLR." This change has been previously approved by the NRC as documented in the Ginna and Vogtle Safety Evaluation {

t Reports. Comed continues to pursue this change.

NRC RAI Number NRC Issued Date RAI Status 3.1.7-01 8/5/97 Open - NRC Action Required I p NRC Description ofIssue s

3.1.7-01: DOC-L11 I

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' CJFD-Cl3 IJFD-PIO

~1TS 3.1.7

' CTS 3.1.3.2 STS 3.1.8

. CTS 3.1.3.2 contains provisions for one Digital Rod Position Indication (DRPI) per bank inoperable. The STS relaxes this requirement by allowing one DRPI per group inoperable. The ITS attempts to takes this a ster further and allow all DRPl to be inoperable for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; by rewording the ACTIONS NOTE, and replacing CONDITION B. DOCS L4 and Lil do not adequately or accurately address these changes. Justification for these charges is based upon WOG-73,.which has not been approved through the TSTF process. These changes are not consistent with NUREG 1431 as stated. Comment:

Revise the submittal to adopt the STS wording. Revise the CTS markup to show the entire proposed change.

Comed Response to Issue 4/l/98 Revised Response: This item is open pending NRC resolution of TSTF-234.

Original Response: No change. The NRC, Owner's Group Chairpersons, and utility management are scheduling a meeting to discuss generic issues (i.e., TSTFs) that involve changes to the Improved Technical Specifications (ITS). The mam focus of this meeting is to discuss a schedule for reviewing the TSTFs, who is reviewing the TSTFs, and what direction is to be provided to utilities which have submitted ITS and have taken credit for the TSTFs that have not yet been approved.

Therefore, the status of this RAI is pending resolution of these issues.

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Resp:ns to NRC RAI For ITS Section 3.1 09-J ui-98 NRC RAI Number NRC Issued Date RAI Status I

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l 3.1.7-02 8/5/97 Closed j

NRC Description ofissue 1 1

3.1.7-02; Bases discussion for ITS 3.1.7 Background, page B 3.1-47 Bases Insert B 3.1-47A states that the Bank Demand Position Indication System is "not very reliable..." No additional quantification has been provided. In contrast with this, Bases insert B 3.1-47B provides substantially more information about the Digital Rod Position Indication System. Comment: Revise the submittal to provide additional information about the reliability of the Bank Demand Position Indication System.

Comed Response to Issue No change. Clarifying information about the reliability of the Bank Demand Position Indication System is found in the l Backgrour.d Section of the Bases for ITS LCO 3.1.7. In the Bases Markups section, page B 3.1-47, second paragraph, last I sentence, it states "For example, if a rod does not move one step for each demand pulse, the step counter will still count the l pulse and incorrectly reflect the position of the rod." Comed continues to pursue this change.

NRC RAI Number NRC Issued Date RAI Status 3.1.8-01 8/5/97 Closed NRC Description of Issue I 3.1.8-01 E Bases discussion for ITS 3.1.8 Background, page B 3.1-63 An insert has been proposed that discusses the beginning oflife (BOL) and end oflife (EOL) moderator temperature coefficient (MTC) tests that are performed and the associated Surveillance Requirements that they fulfill. Comment: The

.Q Q EOL MTC test is not performed in Mode 2, it is performed at power. The physics test exceptions provided by ITS 3.1.8 do not relate to the EOL MTC test. Revise the submittal and delete the reference to the EOL MTC test from the insert.

Comed Response to issue ITS and NUREG were revised to delete the reference to the EOL MTC test from the insert and to delete the reference to SR 3.1.3.2 from the insert . The insert now reads "The Moderator Temperature Coefficient (MTC) at Beginning Of Life (BOL) is' determined from the measured ITC. This test satisfies the requirement of SR 3.1.3.1."

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