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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212B9961999-09-15015 September 1999 Proposed Tech Specs Page 3.3-52,deleting Condition G as Well as or G from Condition H,Per TS Change Request TSCR-003 ML20210B9411999-07-16016 July 1999 Proposed Tech Specs Revising SLMCPR to Support Operation with GE-12 Fuel with 10x10 Pin Array ML20206P2321999-05-10010 May 1999 Proposed Tech Specs Section 3.7.4,providing Specific Conditions & Required Actions for Control Bldg Barrier Degradation (as Opposed to Ventilation Train Degradation) ML20206P7401999-05-10010 May 1999 Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 with 10x10 Pin Array ML20206J3011999-04-30030 April 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 3.4.3.1 to Implement More Appropriate Safety Valve & Safety Relief Valve Setpoint Tolerances ML20205P8031999-04-12012 April 1999 Proposed Tech Specs Re Relaxation of Excess Flow Check Valve Surveillance Testing ML20202E5931999-01-22022 January 1999 Proposed Tech Specs SR 3.8.1.7 Re Rev to DG Surveillance Requirement ML20204A7541999-01-22022 January 1999 Proposed Tech Specs Re Spent Fuel Racks Storage Update ML20206S2421999-01-21021 January 1999 Proposed Tech Specs Surveillance Requirement 3.8.1.7 for EDGs ML20154P6621998-10-15015 October 1998 Proposed Tech Specs 3.6.1.3,revising Condition E to Add Time Limit for Plant Operation If Penetration Flow Path Isolated by Single Purge Valve with Resilient Seal & Adding TS for Cb/Sbgt IAS NG-98-0720, Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements1998-04-17017 April 1998 Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements ML20217B8271998-04-15015 April 1998 Proposed Tech Specs Re RTS-300,revising Reactor Vessel pressure-temp Curve Update ML20203M5021998-02-26026 February 1998 Proposed Tech Specs Re Improved Conversion of Plant ML20199K9871998-02-0303 February 1998 Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing Operability Requirements ML20199K9601998-02-0303 February 1998 Proposed Tech Specs Re Standby Liquid Control Operability Requirements ML20198P8871998-01-0909 January 1998 Proposed Tech Specs Section 3.7.B LCO for PCIVs Revised to Allow 72 Hours to Isolate Failed Valve Associated W/Closed Sys ML20203G5331997-11-21021 November 1997 Proposed Tech Specs Marked Up Pages for Improved TS for Rev a Showing Changes for Rev B ML20211J2331997-10-0303 October 1997 Proposed Tech Specs,Supplementing thermal-hydraulic Analysis Included as License Rept in 930326 to Murley NG-97-1010, Proposed Tech Specs Change for Instrument Setpoints1997-06-10010 June 1997 Proposed Tech Specs Change for Instrument Setpoints NG-97-0847, Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions1997-05-0909 May 1997 Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions ML20141D3621997-05-0909 May 1997 Proposed Tech Specs Revising Definitions of LSSS & Instrument/Channel Calibration to Ref New Program Being Added to TS for Control of Instrument Setpoints ML20115E0301996-07-0505 July 1996 Proposed TS Table 3.6.B.2-1,raising Reactor Water Conductivity Limit to Support Implementation of Noble Metal Chemical Addition at Plant as Method to Enhance Effectiveness of HWC in Mitigating IGSCC ML20101Q7191996-04-0909 April 1996 Proposed Tech Specs Re Recirculation Pump Trip Min Operable Channels ML20097A1871996-01-30030 January 1996 Proposed Tech Specs Revising Certain CR Scram Insertion Time Testing Limits ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20099L8491995-12-22022 December 1995 Proposed Tech Spec 3.7, Plant Containment Sys ML20095H2371995-12-15015 December 1995 Proposed Tech Specs,Incorporating EDG Conditional Surveillance & Editorial Clarifications ML20095A9011995-11-30030 November 1995 Proposed Tech Specs to Implement Option I-D Reactor Stability Solution ML20094M4131995-11-15015 November 1995 Proposed Tech Specs Re RPT Operability & Surveillance Requirements ML20087F5831995-08-0707 August 1995 Proposed Tech Specs Sections 6.5.2.8 & 6.5.3 Re Changes to Audit Program ML20086R8061995-07-21021 July 1995 Proposed Tech Specs,Eliminating Inappropriate Condition Surveillance in Sections 4.5 & 4.8,clarifying Requirements Governing Spent & New Fuel Storage in Section 5.5 ML20087H7021995-04-28028 April 1995 Proposed Tech Specs Bases Page 3.5-20,adding Clarification for Single Core Spray Pump Requirement ML20082S0201995-04-21021 April 1995 Proposed Tech Specs Reflecting Deletion of TS 6.5.3.1.2 Due to Audit Frequency Requirements Being Removed from TS ML20082D1171995-03-28028 March 1995 Proposed TS Table 3.2-A, Isolation Actuation Instrumentation ML20081C9891995-03-10010 March 1995 Proposed Tech Specs,Removing Redundant LCOs & SRs for Containment Hydrogen & Oxygen Monitors ML20080Q0851995-03-0101 March 1995 Proposed Tech Specs Modifying Pump & Valve Surveillance Criteria for LPCI & Core Spray Subsystems,Rhr Svc Water, Hpci,Esw & River Water Supply Systems from Once Every Three Months to Frequency Specified by DAEC ASME Section XI IST ML20080Q8731995-03-0101 March 1995 Proposed Tech Specs Reflecting Rev to TS Table of Contents, Incorporating New Section ML20078R9171995-02-13013 February 1995 Proposed TS Section 6.5.2.8 & 6.5..3.1,reflecting Deletion of Audit Frequency Requirements ML20080H5651995-02-13013 February 1995 Proposed Tech Specs Re Bases for Shutdown Cooling Piping Safety Limit ML20077A9191994-11-10010 November 1994 Proposed Tech Specs Re Offgas Radiation Monitors ML20149G9241994-10-28028 October 1994 Proposed Tech Specs,Deleting Plan for Integrated Scheduling of Plant Mods ML20076K9591994-10-20020 October 1994 Revised Proposed TS to TS Changes RTS-246 & RTS-246A ML20072F1651994-08-15015 August 1994 Proposed Tech Specs Increasing Allowable Main Steam Isolation Valve & Deleting TS Requirements Applicable to MSIV LCS ML20071Q6211994-07-29029 July 1994 Proposed Tech Specs Revising Isi/Ist Program Requirements ML20070H3321994-07-12012 July 1994 Proposed Tech Specs Surveillance Frequencies for Rod Block Instrument Sys ML20070E0411994-06-30030 June 1994 Proposed Tech Specs,Clarifying Requirements for Audit of Conformance to Tss,Deleting Requirement for Safety Committee Oversight of Audits & Allowing Designation of Signature Authority ML20070E0621994-06-30030 June 1994 Proposed Tech Specs Re Addition of Control Bldg Chiller Operability & Surveillance Requirements ML20070E0251994-06-30030 June 1994 Proposed Tech Specs Re Revision of ESW Flow Requirement 4.8.e.1 ML20069G9181994-05-27027 May 1994 Proposed TS Section 3.7, Containment Sys ML20069A9961994-05-0606 May 1994 Proposed TS SRs Section 4.6.G, Primary Sys Boundary Structural Integrity, Deleting SR Which Refers to ISI Program Interval,Allowing DAEC Current ISI Program Interval to Be Extended Per Ruling in Fr 57FR34666 1999-09-15
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B9961999-09-15015 September 1999 Proposed Tech Specs Page 3.3-52,deleting Condition G as Well as or G from Condition H,Per TS Change Request TSCR-003 ML20210B9411999-07-16016 July 1999 Proposed Tech Specs Revising SLMCPR to Support Operation with GE-12 Fuel with 10x10 Pin Array ML20206P2321999-05-10010 May 1999 Proposed Tech Specs Section 3.7.4,providing Specific Conditions & Required Actions for Control Bldg Barrier Degradation (as Opposed to Ventilation Train Degradation) ML20206P7401999-05-10010 May 1999 Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 with 10x10 Pin Array ML20206J3011999-04-30030 April 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 3.4.3.1 to Implement More Appropriate Safety Valve & Safety Relief Valve Setpoint Tolerances ML20205P8031999-04-12012 April 1999 Proposed Tech Specs Re Relaxation of Excess Flow Check Valve Surveillance Testing ML20202E5931999-01-22022 January 1999 Proposed Tech Specs SR 3.8.1.7 Re Rev to DG Surveillance Requirement ML20204A7541999-01-22022 January 1999 Proposed Tech Specs Re Spent Fuel Racks Storage Update ML20206S2421999-01-21021 January 1999 Proposed Tech Specs Surveillance Requirement 3.8.1.7 for EDGs ML20207E9931999-01-0707 January 1999 Rev 15 to Pump & Valve IST Program for Daec ML20205P8091998-11-30030 November 1998 Excess Flow Check Valve Testing Relaxation ML20154P6621998-10-15015 October 1998 Proposed Tech Specs 3.6.1.3,revising Condition E to Add Time Limit for Plant Operation If Penetration Flow Path Isolated by Single Purge Valve with Resilient Seal & Adding TS for Cb/Sbgt IAS ML20236T8621998-06-15015 June 1998 Third Ten Yr Interval ISI Summary Rept Refueling Outage 15 from 961116-980522 for DAEC Palo,Ia NG-98-0720, Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements1998-04-17017 April 1998 Proposed Improved Tech Specs Page 5.0-21 for Reporting Requirements ML20217B8271998-04-15015 April 1998 Proposed Tech Specs Re RTS-300,revising Reactor Vessel pressure-temp Curve Update ML20203M5021998-02-26026 February 1998 Proposed Tech Specs Re Improved Conversion of Plant ML20199K9871998-02-0303 February 1998 Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing Operability Requirements ML20199K9601998-02-0303 February 1998 Proposed Tech Specs Re Standby Liquid Control Operability Requirements ML20198P8871998-01-0909 January 1998 Proposed Tech Specs Section 3.7.B LCO for PCIVs Revised to Allow 72 Hours to Isolate Failed Valve Associated W/Closed Sys ML20203G5331997-11-21021 November 1997 Proposed Tech Specs Marked Up Pages for Improved TS for Rev a Showing Changes for Rev B ML20211J2331997-10-0303 October 1997 Proposed Tech Specs,Supplementing thermal-hydraulic Analysis Included as License Rept in 930326 to Murley NG-97-1010, Proposed Tech Specs Change for Instrument Setpoints1997-06-10010 June 1997 Proposed Tech Specs Change for Instrument Setpoints ML20141D3621997-05-0909 May 1997 Proposed Tech Specs Revising Definitions of LSSS & Instrument/Channel Calibration to Ref New Program Being Added to TS for Control of Instrument Setpoints NG-97-0847, Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions1997-05-0909 May 1997 Proposed Tech Specs Revising Definition of LCO to Address Situation When Sys & Components Are Removed from Svc or Otherwise Made Inoperable During Secondary Modes of Operation,W/O Requiring Entry Into LCO Actions ML20138D9791996-12-0505 December 1996 Rev 9 to Offsite Dose Assessment Manual for Gaseous & Liquid Effluents ML20115E0301996-07-0505 July 1996 Proposed TS Table 3.6.B.2-1,raising Reactor Water Conductivity Limit to Support Implementation of Noble Metal Chemical Addition at Plant as Method to Enhance Effectiveness of HWC in Mitigating IGSCC ML20101Q7191996-04-0909 April 1996 Proposed Tech Specs Re Recirculation Pump Trip Min Operable Channels ML20108B6271996-03-15015 March 1996 Rev 0 to Third Ten-Yr Insp Interval ISI Plan for DAEC Palo, Ia ML20097A1871996-01-30030 January 1996 Proposed Tech Specs Revising Certain CR Scram Insertion Time Testing Limits ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20099L8491995-12-22022 December 1995 Proposed Tech Spec 3.7, Plant Containment Sys ML20095H2371995-12-15015 December 1995 Proposed Tech Specs,Incorporating EDG Conditional Surveillance & Editorial Clarifications ML20095A9011995-11-30030 November 1995 Proposed Tech Specs to Implement Option I-D Reactor Stability Solution ML20094M4131995-11-15015 November 1995 Proposed Tech Specs Re RPT Operability & Surveillance Requirements ML20129H0041995-10-13013 October 1995 Weld Ref Sys ML20087F5831995-08-0707 August 1995 Proposed Tech Specs Sections 6.5.2.8 & 6.5.3 Re Changes to Audit Program ML20086R8061995-07-21021 July 1995 Proposed Tech Specs,Eliminating Inappropriate Condition Surveillance in Sections 4.5 & 4.8,clarifying Requirements Governing Spent & New Fuel Storage in Section 5.5 ML20087H7021995-04-28028 April 1995 Proposed Tech Specs Bases Page 3.5-20,adding Clarification for Single Core Spray Pump Requirement ML20082S0201995-04-21021 April 1995 Proposed Tech Specs Reflecting Deletion of TS 6.5.3.1.2 Due to Audit Frequency Requirements Being Removed from TS ML20082D1171995-03-28028 March 1995 Proposed TS Table 3.2-A, Isolation Actuation Instrumentation ML20081C9891995-03-10010 March 1995 Proposed Tech Specs,Removing Redundant LCOs & SRs for Containment Hydrogen & Oxygen Monitors ML20080Q8731995-03-0101 March 1995 Proposed Tech Specs Reflecting Rev to TS Table of Contents, Incorporating New Section ML20080Q0851995-03-0101 March 1995 Proposed Tech Specs Modifying Pump & Valve Surveillance Criteria for LPCI & Core Spray Subsystems,Rhr Svc Water, Hpci,Esw & River Water Supply Systems from Once Every Three Months to Frequency Specified by DAEC ASME Section XI IST ML20080H5651995-02-13013 February 1995 Proposed Tech Specs Re Bases for Shutdown Cooling Piping Safety Limit ML20078R9171995-02-13013 February 1995 Proposed TS Section 6.5.2.8 & 6.5..3.1,reflecting Deletion of Audit Frequency Requirements ML20078L1201995-01-26026 January 1995 Rev 13 to Pump & Valve IST Program for Daec ML20077A9191994-11-10010 November 1994 Proposed Tech Specs Re Offgas Radiation Monitors ML20149G9241994-10-28028 October 1994 Proposed Tech Specs,Deleting Plan for Integrated Scheduling of Plant Mods ML20076K9591994-10-20020 October 1994 Revised Proposed TS to TS Changes RTS-246 & RTS-246A ML20072F1651994-08-15015 August 1994 Proposed Tech Specs Increasing Allowable Main Steam Isolation Valve & Deleting TS Requirements Applicable to MSIV LCS 1999-09-15
[Table view] |
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RTS-292 Attachment 2 to I
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NG-97-0847 Page1ofI l
PROPOSED CIIANGE RTS-292 TO THE DUANE ARNOLD ENERGY CENTER'
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l TECHNICAL SPECIFICATIONS l ;
The holders oflicense DPR-49 for the Duane Arnold Energy Center propose to amend Appendix !
A (Technical Specificttions) to said license by deleting certain current pages and replacing them j with the attached, new pages. The List of Affected Pages is given below.
LIST OF AFFECTED PAGES 1 1.0 - 1 ,
SUMMARY
OF CHANGES:
The following list of proposed ciunges is in the order that the changes appear in the Technical Specifications.
J Egge Descriotion of Changes 1.0 - 1 Add a paragraph to the Definition of Limiting Conditions for l Operatien (LCO) that provides the criteria for not entering the I actions of an LCO when a system, component, etc. h removed i from service in support of secondary modes of operation, such as surveil:ance testing.
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f 9705200061 970509 PDR ADOCK 05000331 P PDR w c_-____-__-_--_____________-___________________-__-______________-___-___________-_. .
DAEC-1, 1.0 CEFINITIONS ..
. The succeeding frecuently used te-ns are exclicitly cefined so that a uniforn
' interpretation of the soecifications may be achieveo.
- 1. SAFETV LIMIT l The safety limits are limits below which the reasonable maintenance of the cladding
- and primary systems are assured. Exceeding such a limit recuires unit shutdown anc ,
review by the Nuclear Regulatory Cemdssion before resumation of unit operation.
Operation beyond such a limit may not in itself result in serious consecuences but .:
it indicates an operational deficiency sebject to regulatory review. .
- 2. LIMITING SAFETY SYSTEM SETTING (LSSS)
The limiting safety system settings are settings on instrtsnentation which initiate
~
i the automatic protective action at a level such that the safety limits will not be exceeded.. These settinos take into consideration the instrumentation tolerances ,
'and the instruments are reouired to be periodically calibrated as specified in >
these Technical Specifications. The limiting safety system setting plus the . l tolerance of the instrisnent as given in the system design control document gives
-the , limiting trip point for operation. This additional margin has been established ,
so that with proper'. operation of the instrumentation the safety limits will never be exceeded. The' ineouality sign which may be given merely signifies the preferred direction of operational trip setting.
- 3. LIMITING CONDITIONS FOR OPERATION (LCO)
. ~ The limiting conditions specify the minimum acceptable levels of system performance
, necessary to assure safe startuo and coeration of the facility. When these conditions are met, the plant can be operated safely and aonormal situations can be ,
safely controlled.
, Bhen_a system, subsystem, train, component or device is determined to be inocerable sol ~ely because its emergency power' source is inoperable, or solely because its ,
normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the recuirements of its applicable Limiting Condition for Ooeration,
, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s) and :
devices (s) are OPERABLE, or likewise satisfy the reoutrements of this
,. W W th h* W D l aNftWfD' WI h NC. '
i 1.0-1 Amendment No. 114 i
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' INSERT TO TS PAGES FOR RTS-292
.j (Insert A) ;
When a system, subsystem, train, component, or device is removed from service (or f otherwise made inoperable) during secondary modes of operation (i.e., conditions or i states other than the primary safety function, such as surveillance testing. Note: l maintenance activities are not secondary modes of operation.), it may be considered ,
i OPERABLE for the purposes of satisfying the requirements ofits applicable Limiting Condition for. Operation, provided: (1) such secondary modes of operation are controlled by plant procedures; (2) is administratively limited in duration (or is controlled by an Allowed Outage Time note within these Technical Specifications); and, (3) all ofits ;
redundant systems, subsystems, trains, components, or devices are OPERABLE or ;
likewise satisfy the requirements of this specification.
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. RTS-292 Attachment 3 to NG-97-0847 Page1of2 SAFETY ASSESSMENT By letter dated May 9,1997, IES Utilities Inc. submitted a request for revision of the Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC). The proposed TS amendment would revise the definition of Limiting Conditions for Operation (LCO) to address the situation when systems, components, etc. are removed from service or otherwise made inoperable during secondary modes of operation, without requiring entry into the LCO actiora. This is the current operating practice at the DAEC and is supported by the plant design and licensing basis. Within the definition of LCO, such secondary modes are also being defined consistent with the DAEC design and licensing basis. As compensatory measures during such secondary modes of operation, criteria are established within the defm' ition of LCO that ensure the plant is operated consistent with the original design basis assumptions. The criteria establish the administmtive controls that ensure that the plant is under the control of the operators, k, use pre-approved plant procedures, limit the amount of time in such secondary modes, and ensure that a loss-of-function is not inadvertently created. (Note: for some systems, surveillance testing will create a loss-of-function. Consequently, the criteria are applied to both systems, trains, etc., in this situation.) If these criteria are not met, then the LCO will be entered and those actions will be taken in the specified time period.
In addition to the most-recent meeting on March 20,1997, this DAEC practice has been the subject of previous communications with the Staff (Ref. September 22,1994 Meeting and IES letters NG-94-4017, dated November 30,1994 and NG-95-0815, dated March 10,1995) on the Generic Letter 89-10 Program for motor-operated valves.
Assessment:
The fundamental design and licensing basis for the DAEC is that LCO actions are only intended to be entered when equipment is removed from service for maintenance (either corrective or preventative), not when taken out of service for testing or other allowed secondary modes of operation (Ref. General Electric reports APED-5736: Guideline for Determining Safe Test Intervals and Renairlimes for Engineered Safeguards , and NEDO-10739: hiethods for Calculating Safe Test Intervals and Allowable Renair Times for Engineered Safeguard Systems). This was determined to be acceptable because the time in such secondary modes of operation (k the safe test interval) is very short in duration, especially when compared to the allowable repair time for maintenance (k, LCO time); and, that redundant systems, trains, etc. would not be removed from service simultaneously. Operation in secondary modes of operation (such as, system / component testing, torus cooling mode (test line-up) of Residual Heat Removal system, and use of liigh Pressure Coolant Injection system or Reactor Core isolation Cooling system in test line-up for reactor pressure control during transients)is assumed in the safety analysis ;
report (Ref. UFSAR Section 6.3.4.2.1 and 7.3.4.2). Because maintenance activities are l not considered to be secondary modes of operation in the above evaluations, they are l purposefully excluded fmm this TS definition. i l
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. RTS-292 ' Attachment 3 to
, NG-97-0847 +
Page 2 of 2
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The proposed change merely adds criteria to the TS that are consistent with the
- . assumptions contained within these evaluations; no actual changes in the way plant 4
equipment is operated or tested is being proposed. The uniform application of the new TS ,
i
- - criteria will further ensure that the plant remains within the original design and licensing basis assumptions for equipment removed from service during secondary modes of operation. In particular, in the special case where testing also removes the redundant system, train, component, etc., from service, these criteria ensure that both affected ,
systems, trains,'etc., are properly controlled. This is acceptable because the time in such l
!- secondary modes of operation is very short in duration, such that the impact on overall availability / reliability is insignificant.
{
! Consequently, based upon the above evaluation, we find that the proposed changes in the !
! TS definition for LCO to not require entry into the LCO actions for secondary modes of
- j. operation, provided the associated criteria are met, to be acceptable. !
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. RTS-292 Attachment 4 to
- . NG-97-0847 Page1of1 ENVIRONMENTAL CONSIDERATION 10 CFR Part 51.22(c)(9) identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perform an environmental assessment. A proposed amendment to an operating license for a facility requires no enviromnental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and, (3) result in an increase in individual or cumulative i occupational radiation exposure. IES Utilities Inc. has reviewed this request and detennined that the proposed amendment meets the eligibility criteria for categorical -
exclusion set forth in 10 CFR Part 51.22(c)(9). Pursuant to 10 CFR Part 51.22(b), no ,
environniental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR Part 51.22(c)(9) for the following reasons:
1
- 1. As demonstrated in Attachment 1 to this letter, the proposed Amendment does not involve a significant hazards consideration.
- 2. The proposed Amendment revises the definition of Limiting Conditions for Operation (LCO) to address the situation when systems, components, etc. are removed from service or otherwise made inoperable during secondary modes of operation, without requiring entry into the LCO actions. This is the current operating practice at the DAEC and is supported by the plant design and licensing 4 I
basis. The proposed chenge merely adds criteria to the TS that are consistent with the assumptions contained within the design basis; no actual changes in the way plant equipment is operated or tested are being proposed. Consequently, there l will be no increase in either the types or amounts of effluents that may be released )
offsite as a result of this proposed change.
)
- 3. The proposed Amendment revises the definition of Limiting Conditions for Operation (LCO) to address the situation when systems, components, etc. are removed from service or otherwise made inoperable during secondary modes of operation, without requiring entry into the LCO actions. This is the current operating practice at the DAEC and is supported by the plant design and licensing basis. The proposed change merely adds criteria to the TS that are consistent with !
the assumptions contained within the design basis; no actual changes in the way plant equipment is operated or tested are being proposed. Consequently, there will be no increase in either individual or cumulative occupational exposure as a result of this proposed change.