ML20237E988
| ML20237E988 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 08/11/1998 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20237E991 | List: |
| References | |
| NUDOCS 9809010380 | |
| Download: ML20237E988 (40) | |
Text
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C(nnmonwealth Edimn Company Ilraidwood Generating Station Route al,Iksx 84 liracesille, II. 60107 %19 Tel 815-45&2801 o
CamEd August 11,1998 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555 - 0001
Subject:
Revision I to the Improved Technical Specifications (ITS) Submittal - ITS Section 3.9 Closeout 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
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 I to the Referenced ITS submittal. ITS Revision I contains Commonwealth Edison's (Comed's) final Package Closeout for ITS Section 3.9. However, in ITS Section 3.9, Comed is awaiting the Staff's resolution of TSTF-21 Revision 1 in order to close RAI 3.9-02.
Enclosure I contains ITS Revision I. Attachment I contains Comed's final RAI Responses to Section 3.9. Any revised response is noted along with the original
/I response. As requested by the Staff, Attachment 2 contains an afTected page list identifying submittal pages that have changed as a result ofincorporating RAI responses. contains an affected page list summarizing all submittal pages that have changed in ITS Revision I. Attachment 4 contains the SER Tables for ITS Section 3.9.
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August 12,1998
. These Revisions are being provided in the same ten-section format as the initial ITS submittal:
- 1. Byron ITS
- 2. Braidwood(Brwd)lTS
- 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 Licensing
- Department.
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.(O Sincerely, FL/
Timothy J. Tulon Site Vice President.
Braidwood Nuclear Generating Station
Enclosure:
-ITS Revision I
" Attachments: Attachment 1 - ITS Section 3.9 RAI Revised Responses
. Attachment 2 -ITS Section 3.9 RAI Affected Page List - ITS Section 3.9 Section Closeout Affected Page List
. Attachment 4 -ITS Section 3.9 SER Tables cc:
NRC Regional Administrator - Region III L
Senior Resident Inspector - Braidwood 3
Senior Resident Inspector-Byron j
Office of Nuclear Facility Safety -IDNS j
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ATTACHMENT 1 ITS SECTION 3.9 l
RAI REVISED RESPONSES O
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Response to NRC RAI For ITS Srction 3.9 Os-Aug-98
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NRC RAI Number NRC issued Date RAI Status
. r~si-3.9 12/5/97 Closed d;-
NRC Description of Issue
-3.9-01 DOC LA6 CTS 3/4.9.3, Decay Time Dyron/Braidwood characterized this change as less restrictive generic, LA. This specification is relocated based on application of the 10 CFR 50.36. Comment: Revise the LA.6 DOC to a Relocated DOC.
Comed Response to Issue
. No change. 'LA' designators are used for relocating details of specifications or specifications that are not addressed by the l
generic WOG Split Report. LA6 states,"This requirement is to be relocated to the TRM." Although CTS LCO 3.9.3, L
" Decay Time," satisfies Criterion 2 of the Technical Specification Selection Criteria in 10 CFR 50.36(c)(2)(ii), it is not i
- classified as an 'R' designator because it is not identified in the Generic WOG Split Report as being relocated. This presentation is standard throughout the Byron /Braidwood submittal. Comed continues to pursue this change.
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Rtspons to NRC RAI For ITS S:ction 3.9 os-Aug 98 NRC RAI Number NRC lssued Date RAI Status 3.9-02 12/5/97 Open NRC Action Required NRC Description ofIssue 3.9-02'.See table below Proposed changes based on STS generic changes that are still pending or that have been rejected, as indicated in the table, should be withdrawn. Either adopt the STS or maintain the CTS requirements.
" Byron /Braidwood Units I and 2 r"Beyond Contractor Review Scope (BCRS)" Table
'Section 3.9, Refueling Operations
. Updated: November 25,1997 '
' DOC [
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Reasons for Exemption of Review <
' Comment (if required)
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3.9.7: 'C3 BCin : iXD-J%-U-E:-nTSTF 20 g)
I1/24/97 status: pending
- i 3.9.6J L11 C CI P4
'BC2 BP24Li-RXU '; r.'-C "-0TSTF 21 proposed R1
' 11/24/97 status: TSTF-21 approved on 5/19/97, but Rev i is not to stafT for review.
3.9.5 3.9.6 E LA 10 E C27:-7. X n-D-7-3 J TSTF-22 11/24/97 status: Reject [] if CTS contains flow rates B3.9.3 : ' BC5
' BP4! :-DXn- ;, i-i.-o-uTSTF 23 R1 11/24/97 status: rejected 11/19/97 by TSTF, Rev3 is pending issuance for statTreview, Rev2 is being reviewed by the staff.
3.9.3 D C C5 BC4E-CXO C-C-0-R-GTSTF-96 11.24.97 status: approved 10/28/97
~ 3.90 E C4 0-F!XD-C-C-0-0-O WOG-81 11/24/97 status: WOG # not under review.
. B3.9:M BC30-SXC-M-G-C-C-CEditorial-1 11/24/97 status: Approved 10/18/95 3,9.4 E M8E P3 0-U-a-0X0 -1 3.9.lir P10-1 -E-n-J-nXG-n Editorial-l l 11/24/97 status: Approved 4/l1/97 li'!! 900 0 f R ! D
~p, P= plant specific; C= based on TSTF or WOG item; B= Bases Reasons for exempting change from review:
l LCCover letter 12-13-96, Attachment #3 Existing and Future Licensing Amendments to be incorporated into ITS.
L 2.gCover letter 12-13-96, Attac_hment #4 Pending and Prop _osed ISTS Change Travelers _. __
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i Response to NRC RAI For ITS Section 3.9 05-A ug-98 3 Comed letter 2-24-97, Attachment #1. Generic Changes versus CTS DOCS 7
- 4. ' Cover letter 12-!3-96, 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 with the written prior approval of the NRC Technical Monitor as referenced.
Comed Response to issue 4/1/98 Revised Response: This item is open pending NRC resolution of TSTF-21.
Original Response: Regarding TSTF-20. TSTF-96. Editorial-1, and Editorial-11: No change based on NRC approval of these changes. Regarding WOG-81: Withdrawn. See RAls 3.7.10-03, RAI 3.7.11-02,3.7.13-06,3.9.4-06, and 3.9.7-05.
Regarding TSTF-22: Withdrawn. See RAls 3.9.5-05 and 3.9.6-04. Regarding TSTF-23; See RAI 3.9.3-01. Regarding TSTF-21: No change, LCO 3.9.6 requires two RHR loops to be OPERABLE and one RHR loop to be in operation. The LCO Section of the Bases for ITS LCO 3.9.6 states that the flow path starts in one of the RCS hot legs and is returned to the RCS cold legs. With the RHR System aligned to. or during transitioning to or from, the Refueling Water Storage Tank (RWST) to support filling or draining the refueling cavity, or to support required testing, the LCO would be considered not met in order to acknowledge these operational conditions. TSTF-21, Revision 1 (NRC approved), made a change to the Bases for LCO 3.9.6 to allow both RHR pumps to be aligned to the RWST to support filling or draining the refueling cavity, or to support required testing. Comed disagrees with this change which allows an exception to the LCO to be included in the Bases with no corresponding LCO change. Instead, Comed added a Note to the LCO that permits the required RHR loop t be removed from operation and considered OPERABLE when aligned to, or during transitioning to or from, the RWST to support tilling or draining the refueling cavity, or to support required testing, if capable of being realigned to the RCS.
Comed contends that without this change, the LCO would be considered not met when the RHR System is aligned to the RWST, and Condition A would have to be entered. The Required Action requires immediately initiating action to restore the RilR loops to OPERABLE status, thereby prohibiting the use of the RilR System to fill or drain the cavity or perform p
required testing. Comed continues to pursue the change as addressed by LCO JFDs 3.9-Cl and 3,9 P4 and Bases JFDs 3.9-C2 and 3.9-P24.
NRC RAI Number NRC issued Date RAI Status 3.9.1-01 12/5/97 Closed NRC Description of issue 3.9.1-Ol ' Bases discussion for ITS 3.9.1 Applicable Safety Analyses, page B 3.9-2 in the second paragraph of the Applicable Safety Analyses, it has been proposed to delete the term " margin of safety" and replace it with the defined term " Shutdown Margin" The Shutdown Margin definition addresses stuck rod worth which is not relevant during refueling operations. Comment: This is not a justifiable plant specific or editorial difference. Revise the submittal to conform to the STS, Comed Response to issue
- Comed will conform to the STS. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal
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1 revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAI.
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Resp nse to NRC RAI For ITS S:ction 3.9 05-Aug-98
- NRC RAI Number NRC Issued Date '
RAI Status
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3.9.1-02 12/5/97 Closed (V
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NRC Description ofIssue l
j 3.9.1-02EBases discussion for ITS 3.9.1 Actions, page B 3.9-3 The first sentence of the first paragraph of the Actions section of the STS has not been adopted in the ITS. This sentence
. states," Continuation of Core Alterations or positive reactivity additions (including actions to reduce boron concentration) is contingent upon maintaining the unit in compliance with the LCO." Comment: This is not justifiable plant specific or i
editorial difference. Revise the submittal to conform to the STS.
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Comed Response to Issu The sentence in the Actions Section of the Bases for NUREG LCO 3.9.1, " Continuation of CORE ALTERATIONS or I
posi:ive reactivity additions (including actions to reduce boron concentration) is contingent upon maintaining the unit in con'pliance with the LCO" will be retained. This change will be provided in our comprehensive iTS Section 3.9 closeout subcnittal revision upon NRC oncurrence with the Comed Responses to the ITS Section 3.9 RAI.
l NRC RAI Number NRC issued Date RAI Status f
3.9.1-03 12/5/97 Closed N RC Description of Issue l
~ 3.9.1-03; : Bases discussion for ITS 3.9.1 Actions. page B 3.9-3 1
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In the middle of the first paragraph of the Actions section of the STS the term "all operations involving" has not been l
. adopted in the ITS. Instead, an insert has been proposed that states, "an inadvertent criticality may occur due to an incorrect i
fuel loading. To minimize the potential of an inadvertent criticality resulting from a loading error." This appears to overlook
- g the possibility of an inadvertent criticality as a result of a reduced boron concentration. Comment
- This is not justifiable
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plant specific or editorial difference. Revise the submittal to conform to the STS.
Comed Response to Issue 4/1/98 Revised Response: Comed will conform to the STS by adopting "all operations involving" in the Actions Section of the Bases for ITS LCO 3.9.1. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAI.
Original Response: No change. Comed disagrees. The possibility of an inadvertent criticality as a result of a reduced baron concentration is still addressed in that same sentence by ". and positive reactivity additions must be suspended immediately " Replacing "all operations involving CORE ALTERATIONS" with " CORE ALTERATIONS" does not address a reduction in boron concentration in either case. Comed continues to pursue this change.
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NRC RAI Number NRC Issued Date RAI Status i
3.9.1-04 12/5/97 Closed NRC Description ofIssue 3.9.1-04r ; Bases discussion for ITS 3.9.1 Actions. page B 3.9-3 An insert has been added to the end of the second paragraph of the. Actions section. The intention of the insert is to exclude l
" normal heatup/cooldown of the coolant volume for the purpose of system temperature control" from Required Action A.2 to l
suspend positive reactivity additions. Comment: This is not a justifiable plant specific or editorial difference. Revise the 1
i submittal to conform to the STS. This issue should be brought to the Tech Spec Task Force for future action.
I Comed Response to Issue The change associated with Bases JFD 3.9-P14 has been presented to the WOG for generic chance consideration and a g
traveler is being created for the other Owner's Groups' review and approval. Comed continues to pursue this change plant I
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specifically until generic resolution has been achieved.
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l Response to NRC RAI For ITS S:ction 3.9 05-A ug-98
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NRC RAI Number NRC Issued Date RAI Status 3.9.1-05 12/5/97 Closed
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j NRC Description ofIssue 3.9,1-05r Bases discussion for ITS SR 3.9.1.1, page B 3.9-4 i
In the STS, the last sentence of the first paragraph states, "The boron concentration of the coolant in each volume is determined periodically by chemical analysis." The ITS has not adopted the term "in each volume". Comment: This is not a justifiable plant specific or editorial difTerence. Revise the submittal to conform to the STS.
Comed Response to Issue No change. Since the LCO is applicable only to the filled portions of the RCS, the refueling canal, and the refueling cavity that are hydraulically coupled to the reactor core, the boron concentration limit is applicable only for the reactor core or those areas in direct communication with the reactor core (see Bases JFD 3.9-P7). Therefore, in the Surveillance Requirements Section of the Bases for NUREG LCO 3.9.1, the phrase, "in each volume" is technically incorrect if the RCS, the refueling canal, and the refueling cavity were not hydraulically coupled. Comed believes this change is necessary for properly representing the requirements of the LCO and SR 3.9.1.1, and continues to pursue this change.
NRC RAI Number NRC Issued Date RAI Status 3.9.1-06 12/5/97 Closed NRC Description of Issue 3.9.1-06EDOC A9
. CTS 3.9.1 l
The ITS adds the refueling cavity to the list of specified volumes that require the boron concentration limits of TS to be met.
Comment: Based on the discussion provided in A9 the change is not justifiable as an administrative change. Provide additionaljustification to support the administrative change category.
Comed Response to issue DOC 3.9-A9 will be revised to state, " CTS LCO 3.9.1 requires maintaining boron concentration of all filled portions of the RCS and refueling canal. Clearly, it is the intent ofCTS to include the refueling cavity when referencing the RCS in the LCO and Surveillance Requirements Sections. Therefore, ITS LCO 3.9.1 clarifies the " filled portions of the RCS" region by specifically denoting the " refueling cavity" area. This change is perceived as the intent of the CTS wording, is considered l-editorial in nature and does not involve a technical change (either actual or interpretational) to the TS. This change is consistent with NUREG 1431." This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
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NRC RAI Number NRC Issued Date RAI Status 3.9.1-07 12/5/97 Closed NRC Description of Issue 3.9.1-07CDOC LAl CTS 3.9.1
- The CTS markup shows the application of the LAl DOC to LCO 3.9.1.b(2) which is note " that is deleted by DOC A3.
7 Comment: Revise the CTS markup to correct the applications of LAI and A3.
Comed Response to issue l
Comed disagrees. In the CTS Markups, the 'LAl' designator penains to CTS LCO 3.9.1.b.2, excluding the footnote symbol l
("). The 'A3' designator addresses the footnote symbol in the LCO and footnote ". Comed continues to pursue this change.
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Rhspobse t[NRC rah For ITS Section 3.9 05-A ug-98 I
NRC RAI Number NRC lssued D' ate RAI Status 3,9.1-08 12/5/97 Closed NRC Description of Issue 3,9.1-08DJFD Pl TCTS LCO 3.9.1 The PI DOC adds the article "the" to SR 3.9.1.1. Comment: Revise ITS SR 3.9.1.1 to adopt the STS. (This and other sentence structure changes could be made throughout the STS and the industry declined to adopt and "English" language
' format in favor of specifications that contained the required information with a " human factored" format.
Comed Response to issue No change. This change has been approved on 4/l1/97 as Editorial-11. (See RAI 3.9-02.)
i NRC RAI Number NRC Issued Date RAI Status 3.9.2-01 12/5/97 Closed NRC Description ofIssue 3.9.2-01 ' ITS 3.9.2 Actions Note ITS 3.9.2 contains an Actions Note which states, " Separate Condition entry is allowed for each unborated water source isolation valve." Comment: The submittal has neither discussed norjustified using this note. Revise the submittal to provide the justiGcation for this note.
Comed Response to Issue i
O No change. Comed disagrees. The CTS Markup for CTS SR 4.9,1.3 addresses the addition of the ITS LCO 3.9.2 Actions l
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Note with 'A10' and 'Ml'.designators (page 3/4 9-1). Comed continues to pursue this change.
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NRC RAI Number NRC issued Date RAI Status 3.9.2-02 12/5/97 Closed NRC Description of Issue 3.9.2-02'. Bases discussion for ITS 3.9.2 LCO, page B 3.9-5 The proposed insert for this section reads,"This LCO includes valves from the RWST whenever concentration of the RWST fails below specified limits. Acceptable isolation in the closed position of unborated water source isolation valves is provided by mechanical stops, removal of air, or removal of electrical power." The revision that follows is a proposed alternate. "This LCO includes valves associated with the RWST whenever the boron concentration of the RWST falls below specified limits. The unborated water source isolation valves are acceptably secured in the closed position by utilizing mechanical stops, removing air, or removing electrical power as appropriate." Comment: Revise the submittal to incorporate the recommended insert material.
Comed Response to Issue 4/1/98 Revised Response: Comed will conform to the STS by deleting proposed Bases INSERT B 3.9-5B in the LCO Section of the Bases for ITS LCO 3.9.2. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
Original Response: No change. In comparing Comed's proposed Bases statement and the reviewer's proposed statement the only changes are wording preferences which are strictly editorial. Since there is no technical or operational benefits gained in using the proposed wording. Comed elects to maintain our current wording, and continues to pursue this change.
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Response to NRC RAI For ITS S:ction 3.9 05-Aug-98 NRC RAI Number NRC issued Date 5kAlStatus j
3.9.2 12/5/97 Closed NRC Description of Issue 3.9.2-031' Bases discussion for ITS SR 3.9.2.1, page B 3.9-7 In the STS the first three sentences of the Bases discussion for SR 3.9.2.1 provide general background about the surveillance. This material has not been adopted in the Bases discussion for corresponding ITS 3.9.2. Comment: This is not a justifiable plant specific or editorial difference. Revise the submittal to conform to the STS.
Comed Response to Issue Comed will revise the submittal to adopt the first three sentences in the Surveillance Requirements Section of the Bases for SR 3.9.2.1. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
NRC RAI Number NRC issued Date RAI Status 3.9.3-01 12/5/97 Closed NRC Description of Issue i
3.9.3-01 = DOC L10
. CTS 3/4.9.2 CTS 3/4.9.2 establishes the requirements for the nuclear instrumentation in Mode 6. The LCO requires in pan audible indication.in the con:ainment and the control room. It has been proposed to delete this requirement because there is no l
design requirement for the audible alarm and the ITS requirement to isolate all unborated water sources in Mode 6 (ITS 3.9.2) provides adequate assurance that a reactivity event will not occur. Comment: Insufficientjustification has been n
provided to support this proposed change. Revise the submittal to move this requirement to the ITS Bases, consistent with (L.-)
Comed Response to issue
~ 4/1/98 Revised Response: No change. Deleting the audible alarm requirement from the Background Section of the Bases for LCO 3.9.3 is consistent with NRC Approved TSTF-23, Revision 1. For plants such as Byron and Braidwood, which isolate all boron dilution paths per LCO 3.9.2, the source range OPERABILITY requirements include only the visual monitoring function. Braidwood and Byron UFSAR Section 15.4 provides the following discussion for boron dilution l
during MODE 6: "An uncontrolled boron dilution transient cannot occur during this mode of operation. Inadvertent dilution l
is prevented by administrative controls which isolate the RCS from the potential source of unborated water. CVCS valves, specified in CTS 3.9.1 (ITS 3.9.2.1) will be verified closed and secured in position by mechanical stnps or by removal of air l
or electrical power. These valves block all flow paths that could allow unborated makeup water to reach the RCS. Any l
inakeup which is required during refueling will be borated water supplied from the RWST by the low head injection pumps." This method of valve isolation is acceptable by the NRC as presented in other ITSs involving isolation of valves.
Based on the above justification, audible alarms are not required. Comed continues to pursue this change.
Original Response: No change. Deleting the audible alarm requirement from the Background Section of the Bases for LCO l-3.9.3 is consistent with TSTF-23, Revision I and Revision 2 (both under NRC consideration). For plants such as Byron and i_
Braidwood, which isolate all boron dilution paths per LCO 3.9.2, the source range OPERABILITY requirements include j'
only the visual monitoring function. Braidwood and Byron UFSAR Section 15.4 provides the following discussion for boron l;
dilution during MODE 6: "An uncontrolled boron dilution transient cannot occur during this mode of operation. Inadvertent l
dilution is prevented by administrative controls which isolate the RCS from the potential source of unborated water. CVCS L
valves, specified in CTS 3.9.1 (ITS 3.9.2.1) will be verified closed and secured in position by mechanical stops or by removal of air or electrical power. These valves block all flow paths that could allow unborated makeup water to reach the RCS. Any makeup which is required during refueling will be borated water supplied from the RWST by the low head
. injection pumps." This method of valve isolation is acceptable by the NRC as presented in other ITSs involving isolation of
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. valves. Based on the abovejustification, audible alarms are not required. Comed continues to pursue this change.
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Rcsponse to NRC RAI For ITS Section 3,9 05-Aug-98 NRC RAI Number 14RC issued Date RAI Status
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3.9.3 12/5/97 Closed i + q" '
NRC Description of issue 3.9.3-02 Bases discussion for ITS SR 3.9.3.2, page B 3.9-10 l
l The STS Bases states that the reason that the Channel Calibration is performed with an 18 month frequency is that this
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surveillance needs to be performed under the conditions that apply during a plant outage. This information has not been adopted in the ITS. Comment: This is not ajusti6able plant specific or editorial difference. Revise the submittal to conferm to the STS.
Comed Response to issue L
CoriEd will conform to the STS. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal rev:sion upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
N RC RAI Number NRC Issued Date RAI Status 3.9.4-01 12/5/97 Closed NRC Description of issue 3.9.4-01 DOC A6 JFD P2 CTS 3.9.4.a ITS LCO 3.9.4 Note CTS LCO 3.9.4.a allows removal of the equipment hatch pursuant to the successful performance of the Surveillance Requirement to verify the Operability of the fuel handling building exhaust plenums. This has been reformatted in the form of an LCO note' for corresponding ITS 3.9.4. This note states that item a of the LCO is only required when the Fuel
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' Handling Building Exhaust Filter Plenum Ventilation System is not in compliance with ITS LCO 3.'/.13. However, the t
Applicability for ITS 3,9.4 and ITS 3.7.13 are not the same. The note should be revised to state that item a of the LCO is only required when the Fuel Handling Building Exhaust Filter Plenum Ventilation System is not Operable. Comment:
Revise the submittal to specify system Operability status rather than compliance with LCO 3.7.13.
Comed Response to issue 4/l/98 Revised Response: Comed will revise ITS LCO 3.9.4 to state, ". One door in the personnel air lock closed and the equipment hatch held in place by greater than or equal to 4 bolts." This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
. Original Response: No change. The proposed wording for the LCO 3.9.4 Note stating, ". System is not Operable" merely represents a wording preference over Comed's proposed wording stating. ". System is not in compliance with LCO 3.7.13,
." Comed continues to pursue this change.
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f?SPonse to NRC RAI For ITS Stetion 3.9 05-A ug-98
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s NRC RAI Number _, NRC Issued Date RAI Status
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3.9.4-02.
. 12/5/97 Closed
- NRC Description of Issue 3.9.4-02 JFD Pl7,
~ Bases discussion for ITS SR 3.9.4.2, page B 3.9-15 in the STS the last part of the paragraph describes other Surveillance Requirements in other LCOs that demonstrate the e Operability of the containment purge valves and their associated actuation instrumentation. This information has not been adopted in the ITS. Comment: This is not justifiable plant specific or editorial difference. Revise the submittal to conform to the STS.
Comed Response to issue Comed will conform to the STS. This change will be provided in our comprehensive iTS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAI.
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Response to NRC RAI For ITS Scetion 3.9 63-A ug-98 NRC RAI Number NRC !ssued Date RAI Status
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j 3.9.4-03 12!5/97 Closed V
NRC Description ofissue 3.9.4-03 DOC L2 CTS 4.9.4.1 CTS 4.9.9 DOC L2 states the CTS has been revised to relax the surveillance frequency from 7 days to 18 months. Comment: DOC L.2 justines the proposed changes to CTS 4.9.9 test frequencies; however, DOC L.2 does not provide appropriate discussion for CTS 4.9.4.1 changes identified as L2 and the CTS 4.9.4.1 markup does not reflect the proposed ITS. Revise the CTS markup and provide DOC discussion to address each proposed CTS change.
Comed Response to issue 4/1/9C Revised Response: CTS DOC 3.9-L2 was revised as follows. " CTS SR 4.9.4.1 and SR 4.9.9 :equire the containment purge isolation valves to be demonstrated OPERABLE every 7 days by verifying that con:ainment isolation occurs on an actuation signal. ITS SR 3.9.4.2 requires the containment purge isolation valves to be demonstrated OPERABLE every 18 months by verifying that containment isolation occurs on an actuation signal. CTS SR 4.9.4.1.b has been revised to relax the Surveillance Frequency from 7 days to 18 months. This is acceptable since the instrumentation is highly reliable and since the containment purge isolation system requires the performance of additional SRs to ensure operability of the system and the containment isolation function. The 18 month Frequency maintains consistency with other similar ESFAS instrumentation and valve testing requirements. The SRs for the actuating instrumentation are contained in LCO 3.3.6.
These requirements include a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Channel Check, a 92 day Channel Operational Test, and an 18 month Channel Calibration and TADOT (for the Manual Initiation function only). In addition to the instrumentation requirements of LCO 3.3.6, each containment purge isolation valve requires the verification of the isolation time in accordance with the IST program (SR 3.9.4.3) in addition, CTS SR 4;9.4.1.a requires verification that the penetrations are in their " closed / isolated" conditions at least once every 7 days. ITS SR 3.9.4.1 requires the containment penetrations to be in their " required status"
[7 every 7 days. The ITS demonstrates that each containment penetration required to be isolated is indeed isolated and those (j
purge valves that are open are not blocked from closing. This change is consistent with NUREG-1431." In addition, CTS DOC 3.9-L8 was revised as follows, " CTS SR 4.9.4.1 and SR 4.9.9 requires verification that the containment purge valves actuate to the isolation position on an ESF test signal. ITS SR 3.9.4.2 requires verification that the containment purge valves actuate to the isolation position on an actual or simulated actuation signal. The CTS has been revised to allow either an actual or simulated actuation signal for demonstrating performance of the SR. This is acceptable since use of an actual signal instead of a simulated signal will not affect the performance of the associated components. There is no reason why an actual signal would preclude satisfactory verification or performance of an actuation logic test or channel operational test.
Operability can be adequately demonstrated in either case since the associated components can not discriminate between actual or simulated signals. This is perceived as the intent of the CTS wording, and therefore, could be considered an administrative change. However, since this allowance is being specifically denoted in the SR, this change is discussed and justified as a less restrictive change. The intent of this change is to provide clarity and completeness in avoiding any misinterpretation. This change is consistent with NUREG-1431." This change will be provided in our comprehensive ITS Section 3.9 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
Original Response: CTS DOC 3.9-L2 will be revised as follows. " CTS SR 4.9.4.1 and SR 4.9.9 require the containment purge isolation valves to be demonstrated OPERABLE every 7 days by verifying that containment isolation occurs on an actuation signal. ITS SR 3.9.4.2 requires the containment purge isolation valves to be demonstrated OPERABLE every 18 months by verifying that containment isolation occurs on an actuation signal. CTS SR 4.9.4.1.b has been revised to relax the Surveillance Frequency from 7 days to 18 months. This is acceptable since the containment purge isolation system requires the performance of additional SRs to ensure operability of the system and the containment isolation function. The 18 month Frequency maintains consistency with other similar ESFAS instrumentation and valve testing requirements. The SRs for the actuating instrumentation are contained in LCO 3.3.6. These requirements include a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Channel Check, a 92 day Channel Operational Test, and an 18 month Channel Calibration and TADOT (for the Manual Initiation function only). In addition to the instrumentation requirements of LCO 3.3.6, each containment purge isolation valve requires the verification of the isolation time in accordance with the IST program (SR 3.9.4.3). In addition, CTS Sit 1.9.4.1.a requires verifying that O[d the penetrations are in their closed / isolated condition, while ITS SR 3.9.4.1 demonstrates that the open purge valves are not blocked from closing and each valve operator has motive power by verifying each required penetration is in the required state. These changes are consistent with NUREG-1431." This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC'r concurrence with the Comed Responset to the ITS Section 3.9 RAl.
10
Response to NRC RAI For ITS Section 3.9 05-Aug-98
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NRC RAI Number NRC lssued Date RAI Status 3.9.4-04 12/5/97 Open - NRC Action Required NRC Description of Issue J.9.4-04 DOC M8 JFD P3 ITS SR 4.9.4.3 DOC M8 justifies adding purge valve isolation time testing in accordance with IST frequencies. Comment: The proposed SR represents a generic change to the STS. Typically, valve isolation testing is performed as part of the system operability requirements. Explain why this proposed SR does not duplicate the testing requirements ofITS SR 3.C3.5.
Comed Response to issue No change. ITS SR is applicable in MODES l-4. ITS SR 3.9.4.3 is applicable during CORE ALTERATIONS and during f
movement ofirradiated fuel assemblies within containment. Therefore, they are not duplicate testing requirements. Comed r utinues to pursue this change.
NRC RAI Number NRC Issued Date RAI Status 3.9.4-05 12/5/97 Closed NRC Description of Issue 3.9.4-05 DOC Ai1
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ITS LCO 3.9.4 DOC A 1 I states that the requirements of CTS 3.9.9. " Containment Purge isolation System" are retained in the presentation c
ofITS LCO 3.9.4.c which requires an operable Containment Purge isolation System. Comment: The proposed ITS LCO j
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3.9,4.c requires the " Containment Ventilation (emphasis added) System to be operable. Provide a DOC for the deletion of
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Containment Purge Isolation System operability requirements during core alterations or movement ofirradiated fuel in containment.
l Comed Response to issue No change. Containment " Purge isolation" System and Containment " Ventilation" System are one and the same. They are/can be used interchangeably. Comed continues to pursue this change.
NRC RAI Number NRC lssued Date RAI Status I
3.9.4-06 12/5/97 Closed NRC Description ofissue
-3.9.4-06 ' JFD C4 1
ITS 3.9.4 Applicability j
JFD C4 proposes to revise the STS format for constructing applicable conditions. Comment: This is a generic change that
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requires a statT-approyed TSTF chant,e. Revise the submittal to adopt the STS.
. Comed Response to Issue WOG-81.will be withdrawn from the ITS submittal. ITS and NUREG will be revised to adopt the ISTS presentation in the Applicability section ofITS LCOs 3.9.4 and 3.9.7. As a result. LCO JFD 3.9-C4 will be deleted. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's con:urrence with the Comed Responses to the !TS Section 3.9 RAI. (See RAls 3.7.10-03,3.7.1102,3.7.13-06,3.8.2-02, and 3.9.7-05.)
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Rcsponse to NRC RAI For ITS Section 3.9 05-Aug-98 NRC RAI Number NRC lssued Date RAI St.itus
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3.9.5-01 IT5/97 Closed U
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NRC Description of Issue l
3.9.5 01 DOC L4
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CTS 3/4.9.8.1 footnote
- The footnote modifies the LCO by allowing the RilR loop to be removed from operation during the performance of Core i
Alterations in the vicinity of the reactor vessel hot legs. It has been proposed to delete the term "during the performance of i
Core Alterations in the sicinity of the reactor vessel hot legs" from the footnote. Comment: Insufficient justification has been provided for this proposed change. Revise the submittal and provide additionaljustification.
CoraEd Response to issue 41148 Revised Response: CTS DOC 3.9-L4 was revised as follows. " Comed has conformed to the STS LCO 3.9.5 Note wh ch allows the required RilR loop to be removed from operation for I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided no operations are permitted that would cause reduction of the RC? boron concentration. This Note allows other retueling operation activities i
such as core mapping, valve testing, installation and removal of temporary lighting, temporary submarines or any other activity not involving any operations that would cause a boren reduction in the RCS or a reactivity change. The CTS also pioudes a footnote stating that the RiiR loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during tl e
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performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs. In conserting to ITS. and in compliance with the STS, the words, "during the performance of CORE ALTERATIONS in the vicinity of the vessel hot is gs" were removed. The ITS definition of CORE ALTERATION states," CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the sessel head removed and fuel in the sessel." The ITS definition differs from the CTS definition in that equipment in the vicinity of the hot leg (such as lighting.
temporary submarines, etc.) is no longer required to be classified as CORE ALTERATIONS in ITS. Without the revised Note, certain operations which were allowed under the CTS Note would no longer be allowed in ITS. The footnote in ITS LCO 3.9.5 is consistent with the ITS definition and the deletion of the words, "during the performance of CORE j
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ALTERATIONS in the vicinity of the vessel hot leg" is appropriate." This change will be provided in our comprehensive ITS Section 3.9 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAI.
Original Response: No change. Comed has conformed to the STS LCO 3.9.5 Note which allows the required RilR loop to be removed from operation for I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided no operations are permitted that would cause reduction of the RCS boron concentration. This Note allows other refueling operation activities such as core mapping, valve testing, installation and removal of temporary lighting, temporary submarines or any other activity not involving any operations that would cause a boron reduction in the RCS or a reactivity change. The CTS also provides a footnote stating that the RHR loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs. In converting to ITS, and in compliance with the STS, the words, "during the performance of CORE ALTERATIONS in the vicinity of the vessel hot legs" were removed. The ITS definition of CORE ALTERATION states, " CORE ALTERATION shall be the movement of any fuel, sources or reactivity control components.
within the reactor vessel with the sessel head removed and fuel in the vessel." The ITS definition differs from the CTS definition in that equipment in the vicinity of the hot leg (such as lighting, temporary submarines. etc.) is no longer required to be classified as CORE ALTERATIONS in ITS. Without the revised Note, certain operations which were allowed under the CTS Note would no longer be allowed in ITS. The footnote in ITS LCO 3.9.5 is consistent with the ITS definition and the deletion of the words, "during the performance of CORE ALTERATIONS in the vicinity of the vessel hot leg" is appropriate. Comed continues to pursue this change. (See RAI 3.9.5-04.)
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Response to NRC RAI For ITS Section 3.9 05-Aug-98 NRC RAI Number ~
NRC Issued Date RAI Status 3.9.5-02 12/5/97 Closed
, C NRC Description of Issue 3.9.5-02: Bases discussion for ITS 3.9.5 LCO, page B 3.9-18 i
The LCO section describes why one RiiR loop must be Operable and in operation. The STS identifies removal of decay heat, mixing of the borated coolant to minimize the possibility of criticality, and indication of reactor coolant temperature.
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The ITS has omitted mention of the indication of reactor coolant temperature. Comment: This is not a justifiable plant I
specific or editorial change. Revise the submittal to conform to the STS.
Comed Response to issue 4/1/98 Revised Response: Comed h.,s retained items a, b, and c in the LCO Section of the Bases for ITS LCO 3.9.5. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the.
Comed Responses to the ITS Section 3.9 RAl.
I Original Response: Comed will conform to the STS. This change will be provided in our comprehensive ITS Section 3,9 l
closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl. (See RAI 3.9.6-02.)
NRC RAI Number NRC issued Date RAI Status 3.9.5-03 12/5/97 Closed NRC Description of issue 3.9.5-03: : DOC M3 CTS 3/4.9.8.1 Action
~ /).
The CTS Action is modified in the ITS to require "immediate" action to perform required remedial measures. Comment:.
b.
The DOC does not address that time limits are imposed by adoption of the STS content. Provide a revised DOC.
Comed Response to issue No change. Comed disagrees. Ti.e addition of"immediately" is addressed in DOC 3.9-M3. The only time limit associated with ITS LCO 3.9.5 is the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time of Required Action A.4, which is consistent with CTS and therefore is not changed. Comed continues to pursue this change. (See RAI 3.9.6-03.)
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NRC RAI Number NRC Issued Date RAI Status 3.9.5-04 12/5/97 Closed NRC Description of issue 3.9.5-04: ' DOC M9 CTS 3/4.9.8.1 Note
- The ITS provides allowances for removing a loop from operation. The CTS change ensures boron dilution does not occur with no loops in operation for the one-out-eight hour period permitted by the TS. Comment: Insufficient justification has been provided to state the safety basis for this provision. Revise the submittal and provide additional justification.
' Comed Response to issue See Comed Response to RAI 3.9.5-01.
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Response to,NRC RAI For ITS Section 3.9 05-A u g-98 NRC RAI Number NRC issued Date RAI Status 3.9.5-05 12/5/97 Closed NRC Description of issue 3.9.5-05 DOC LA10 CTS 4.9.8.1 The proposed CTS chrnge relocates details regarding flow and temperature equiremems during testmg to licensee controlled documents. This is generic change TSTF-22. TSTF-22 was rejected by the staff. Comment: Withdraw the CTS change and resubmit revised ITS.
Comed Response to issue 4/1/98 Revised Response: Comed will revise the ITS submittal to include the flow rate value in ITS SR 3.9.5. and ITS SR 3.9.6.1. However, the CTS requirement for the RCS temperature to be less than or equal to 140 of will be relocated to a Licensee Controlled Document. The temperature requirement does not meet the 10CFR50.36(c)(2)(ii) criteria and is not included in NUREG-1431. Relocating the temperature requirement (DOC 3.9-LA 10) to a Licensee Controlled Document provides assurance that the requirement is maintained and any potential changes to the specific temperature requirement will require a 50.59 evaluation. DOC 3.9-LA10 will be revised to relocate only the RCS temperature requirement to the TRM.
This change will be provided in our comprehensive ITS Section 3.9 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAI. (See RAI 3.9.6-04.)
Original Response: Comed will revise the ITS submittal to include the flow rate value in ITS SR 3.9.5.1 and ITS SR 3.9.6.1. (Note: Approved TSTF-21, Revision 1, allows deleting the flow rate requirement in NUREG SR 3.9.6.1.)
However, the CTS requirement for the RCS temperature to be less than or equal to 140 oF will be relocated to a Licensee Controlled Document. The temperature requirement does not meet the 10CFR50.36(c)(2)(ii) criteria and is not included in NUREG-1431. Relocating the temperature requirement (DOC 3.9-LA10) to a Licensee Controlled Document provides assurance that the requirement is maintained and any potential changes to the specific temperature requirement will require a 50.59 evaluation. DOC 3.9-LA10 will be revised to relocate only the RCS temperature requirement to the TRM. This change will be provided in our comprehensive ITS Section 3.9 closecut submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl. (See RAI 3.9.6-04.)
NRC RAI Number NRC issued Date RAI Status 3.9.6-01 12/5/97 Closed NRC Description of Issue 3.9.6-01 JFD PS ITS 3.9.6 Condition A and Required Action A.!
Bases discussion for ITS 3.9.6 Required Action A.1, page B 3.9-22 Condition A for STS 3.9.6 states. "Less than the required number of RHR loops Operable." Corresponding Condition A for ITS 3.9.6 states. "One or more RHR loops inoperable." STS Required Action A.] refers to restoring the required RHR loops. ITS Required Action A.] would omit the word ' required" Comment: These are notjustifiable plant specific or editorial differences. Revise the submittal to conform to the STS. These are generic changes. These changes should be brought to the Tech Spec Task Force for future action.
Comed Response to issue No change. Comed disagrees. The NUREG rules of usage reserves the word required for when the LCO allows " options" to fulfill the TS requirement (e.g., NUREG LCO 3.4.12 LTOP), or when the LCO requires less than the total number to be OPERABLE. In this case the LCO requires that two RHR loops be OPERABLE, and since there are only two RHR loops in the Byron /Braidwood design, adding the word " required" would be inappropriate. Comed continues to pursue this change.
14
R:sponSe to NRC RAI For ITS Sectich 3.9 05-Aug-98
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NRC RAI Number NRC Issued Date RAI Status O
3.9.6-02
~ 12/5/97 Closed NRC Description of issue 3.9.6-02. Bases discussion for ITS 3.9.6 LCO, page B 3.9-22 The LCO section describes why one RilR loop must be in operation. The STS states that mixing minimizes the possibility of criticality and that RilR must be in operation in order to provide indication of reactor caolant temperature. This material has not been adopted in the ITS. Comment: This is not a justifiable plant specific or editorial difference. Revise the submittal to conform to the STS.
Comed Response to issue 4/1/98 Revised Response: Comed has retained items a, b, and c in the LCO Section of the Bases for ITS LCO 3.9.6. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
Original Response: Comed will conform to the STS. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl. '(See RAI 3.9.5-
. 02.)
NRC RAI Number NRC lssued Date RAI Status 3.9.6-03 12/5/97 Closed NRC Description of Issue 3.9.6-03" DOC M3 CTS 3/4.9.8.2 Action DOC M7 The CTS Action is modified in the ITS to require "immediate" action to perform required remedial measures. Comment:
The DOC does not address that time limits are imposed by adoption of the STS content. Provide a revised DOC.
Comed Response to issue 2/6/98 Corrected Response: No change. Comed disagrees. The addition of"immediately" is addressed in DOC 3.9-M4.
The only time limit associated with ITS LCO 3.9.6 is the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time of Required Action B.3, which is consistent with CTS and therefore is not changed. Comed continues to pursue this change. (See RAI 3.9.5-03.)
' NRC RAI Number NRC Issued Date RAI Status 3.9.6-04 12/5/97 Closed NRC Description of Issue 3.9.6-04~ DOC LA10
- CTS SR 4.9.8.2 The proposed CTS change relocates details regarding flow and temperature requirements during testing to licensee controlled documents. This is generic change TSTF-22. TSTF-22 was rejected by the staff. Comment: Withdraw the CTS change and resubmit revised ITS.
Comed Response to Issue See Comed Response to RAI 3.9.5-05.'
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Response to NRC RAI For ITS Section 3.9 05-A u g-98 NRC RAI Number NRC Issued Date RAI Status 3.9.7-01 12/5/97 Closed NRC Description of Issue 3.9.7-01 CTS 4.9.10 STS SR 3.9.7.1 The CTS markup for this Surveillance Requirement refers to determining the water level during the movement ofirradiated fuel assemblies. Corresponding STS SR 3.9.7.1 does not contain this applicability reference. Comment: The CTS markup is in e ror. Revise the CTS markup to conform to the STS.
Comed Response to Issue No < hange. Comed disagrees. The CTS markup for CTS SR 4.9.10 is merely clarifying that this surveillance is only regt. ired to be performed consistent with the revised CTS Applicability, (i.e., During movement of" irradiated" fuel assemblies.. ) as justified in DOC 3.9-LAI 1. Comed is not proposing that this Applicability reference be included in the ITS SR. This change is consistent with the Applicability of NUREG LCO 3.9.7. Comed continues to pursue this change.
NRC RAI Number NRC Issued Date RAI Status 3.9.7-02 12/5/97 Closed NRC Description of Issue 3.9.7-02 Bases discussiod for ITS 3.9.7 Applicable Safety Analysis. page B 3.9-25 The discussion in the STS refers to Regulatory Positions C.I.c and C.I.g of Regulatory Guide 1.25 which adopts a 23 foot minimum level requirement for refueling. Comment: This is not justifiable editorial difference. Revise the submittal to either conform to the STS or provide plant specific Bases for the LCO limit of 23 feet of water above the reactor vessel flange.
Comed Response to Issue Comed will revise the Applicable Safety Analysis Section of the Bases for ITS LCO 3.9.7 to include reference to Regulatory Guide 1.25, C.I.c and C.l.g. This change will be provided in our comprehensive ITS Section 3.9 closeout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAl.
NRC RAI Number NRC Issued Date RAI Status 3.9.7-03 12/5/97 Closed NRC Description of Issue 3.9.7-03 DOC L5 ITS LCO 3.9.7 The CTS changes identified as L5 include administrative changes because CTS limits on movement of control rods is included in the ITS definition of CORE ALTERATIONS. Comment: Provide a separate identification and discussion of each administrative change.
Comed Response to issue 2/6/98 Corrected Response: No change. Comed believes that DOC 3.9-L5 adequatelyjustifies the less restrictive change, and does not contain any administrative changes. Comed continues to pursue this change.
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Response to NRC RAI For ITS Section 3.9 05-Aug-98
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NRC RAI Number NRC issued Date.
RAI Status TO 3.9.7-04 12/5/97 Closed
-.\\j NRC Description of Issue 3.9.7-04 7 DOC LS -
ITS LCO 3.9.7 The CTS changes identified as L5 include less restrictive changes not discussed because CTS establish water level limits when fuel assemblies or control rods are moved with irradiated fuel seated in the reactor vessel. Comment: Provide a separate ' identification and discussion of each less restrictive change.
Comed Response to issue No change. Comed disagrees. The whole purpose of DOC L5 and the relocation of" irradiated" fuel assemblies is discussed in LA11. Comed continues to pursue this change.
NRC RAI Number -
NRC issued Date RAI Status
.3.9.7 05 12/5/97 Closed
' NRC Description of issue 3.9.7-05 ^JFD C4 ITS 3.9.7 Applicability JFD C4 proposes to revise the STS format for constructing applicable conditions. Comment: This is a generic change that requires a staff-approved TSTF change. Revise the submittal to adopt the STS.
Comed Response to issue
- WOG-81 will be withdrawn from the ITS submittal. ITS and NUREG will be revised to adopt the ISTS presentation in the O()T A' applicability section ofITS LCOs 3.9.4 and 3.9.7. As a result. LCO JFD 3.9-C4 will be deleted. This change will be provided in our comprehensive ITS Section 3.9 closcout submittal revision upon NRC's concurrence with the Comed Responses to the ITS Section 3.9 RAI. (See RAls 3.7.10-03,3.7.11-02,3.7,13-06,3.8.2-02. and 3.9.4-06.)
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