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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 ML20206P7401999-05-10010 May 1999 Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 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) 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 ML20204A7541999-01-22022 January 1999 Proposed Tech Specs Re Spent Fuel Racks Storage Update ML20202E5931999-01-22022 January 1999 Proposed Tech Specs SR 3.8.1.7 Re Rev to DG Surveillance Requirement 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 ML20199K9601998-02-0303 February 1998 Proposed Tech Specs Re Standby Liquid Control Operability Requirements ML20199K9871998-02-0303 February 1998 Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing 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 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 ML20070E0621994-06-30030 June 1994 Proposed Tech Specs Re Addition of Control Bldg Chiller Operability & Surveillance Requirements 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 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 ML20206P7401999-05-10010 May 1999 Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 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) 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 ML20204A7541999-01-22022 January 1999 Proposed Tech Specs Re Spent Fuel Racks Storage Update ML20202E5931999-01-22022 January 1999 Proposed Tech Specs SR 3.8.1.7 Re Rev to DG Surveillance Requirement 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 ML20199K9601998-02-0303 February 1998 Proposed Tech Specs Re Standby Liquid Control Operability Requirements ML20199K9871998-02-0303 February 1998 Proposed Tech Specs Re Vessel Hydrostatic Pressure & Leak Testing 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 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] |
Text
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RTS-290 Attachment 2 to
,. .. NG-96-1297 Page1of1 ERO. POSED CHANGE (RTS-290)TO THE DUANE ARNOLD ENERGY CENTER l TECHNICAL SPECIFICATIONS l
The holders oflicense DPR-49 for the Duane Arnold Energy Center propose to amend Appendix A (Technical Specifications) to said license by deleting certain current pages and replacing them with the attached, new pages. The List of Affected Pages is given below.
1 LIST OF AFFECTED PAGES l 3.6-4 3.6-6 3.6-21 l
SUMMARY
OF CHANGES:
The following list of proposed changes is in the order that the changes appear in the Technical Specifications (TS).
1 Eage Descrintion of Changes 3.6-4 Add monitoring frequency to Sections 4.6.B.2.c and 4.6.B.2.d for chloride and acidity (pH) during Noble Metal Chemical Addition (NMCA).
3.6-6 Add two asterisks to the conductivity limit for the STARTUP/ HOT I
SHUTDOWN Modes in Table 3.6.B.2-1.
3.6-6 Add the higher limit (10.0 pmhos/cm) and explanation for the NMCA process below the Table.
l 3.6-21 Add the bases for the NMCA process.
l l
9607160068 960705 l PDR ADOCK 05000331 1 P PDR
DAEC-1 L'NITING I CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
- 2) With the conductivity c. Obtain and analyze a sample exceeding 10.0 ymho/cm at of the reactor coolant for 25'c or chloride chlorides at least once concentration exceeding ev W 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever44.h ;
500 ppb, be in at least HOT 44 condactivity is greater than SHUTDOWN within the next the limit specified in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD Table 3. 6. B. 2-1, dt MS M 44 SHUTDOWN within the M4hi. C44c4 AdA"*. )
following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Obtain and analyze a sample--
of the reactor coolant for pH at_least_once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever .sd h ,
t44, conductivity is greater than the limit specified in i Table 3.6. B.2-1, OA, M
- 3) Continuously record the 4.144. Mitdt cheni. A %. I
- conductivity of the reactor a coolant. With no e. With no continuous recording continuous recording conductivity monitor conductivity monitor OPERABLE, obtain an in-line OPERABLE, install a conductivity measurement at temporary in-line least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when conductivity monitor within in RUN, STARTUP, or HOT 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least SHUTDOWN MODES and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> HOT SHUTDOWN within the at all other times.
next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. f. Perform a CHANNEL CHECK of the continuous conductivity monitor at least once per 7
- b. In STARTUP and HOT SHUTDOWN: days.
4
- 1) With the conductivity, i chloride concentration or pH exceeding the limit specified in Table 3.6.B.2-1 for more than 48 continuous hours, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. In COLD SHUTDOWN and REFUEL:
- 1) With the conductivity or pH exceeding the limit specified in Table 3.6.B.2-1, restore the conductivity and pH to within the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
l 2) With chloride concentration exceeding the limit
- specified in Table 3.6.B.2-1, restore
., the chloride concentration to within the limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
RTS 290 AMENDMENT NO. 203 3.6-4 7ah5,l9%
Correction letter, dated 8/4/93
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DAEC-1 dependent corrosion rates and provide time for the RWCU System to.re-establish *l the purity of the reactor ecolant. During some periods of operation, conductivity or chloride cencontration may exceed 5.0 pmo/cm or 200 ppb j respectively because of the initial evolution of gases, the initial addition I of dissolved metals, or the breaking out of chlorides entrapped in the system.
The total time during which the conductivity or chloride concentration may exceed the specified limit must be limited to 2 weeks / year or less to prevent stress corrosion cracking.
At DAEC, conductivity is continuously monitored at the Reactor Water Cleanup System, between the hot well and the domineralizer beds, and at the outlet of the domineralizar beds. Any of these monitors are considered to fulfill the requirement of continuously monitoring the Reactor Coolant System. In the event that the conductivity cannot be continuously monitored, a temporary in-line monitor iu to be installed.
The iodine radioactivity will be monitored by reactor water sample analysis.
The total iodine activity would not be expected to change over a period of 1 week In addition, the trend of the offgas stack release rate, which is l continuously monitored, is an indication of the trend of the iodine activity in the reactor coolant. Since the concentration of radioactivity in the reactor coolant is not continuously measured, coolant sampling would be ineffective as a means to rapidly detect gross fuel element failures.
However, the capability to detect gross fuel element failures is inherent'in the radiation monitors in the offgas system and on the main steam lines.
The conductivity of the reactor coolant is continuously monitored.
Conductivity instrumentation will be checked every 3 days by instream l measurements with an independent conductivity monitor to assure accurate readings. If corsductivity is within its normal range, chlorides and other impurities will also be within their normal ranges. The reactor coolant samples will also be used to determine the chlorides. Therefore, the sampling frequency is considered adequate to detect long-term changes in the chlor.ide ion content. Isotopic analyses to determine major contributors to activity can be performed by a gamma scan, f Noh M CA'"4 AddOb ( d " CA) b A 'A'442*P6L % #
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h to 48a T f a c 4g4 - RT5 J80 AMENDMENT NO. 7J,203 3.6-21 -gg 5, M
l RTS-290 Attachment 3 to i
NG-96-1297 Page1of1 ENVIRONMENTAL CONSIDERATION i i
i 10 CFR Section 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 l proposed amendment to an operating license for a facility requires no environmental 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 th. amounts of any effluents that may be released offsite; and (3) result in a i significant increase in individual or cumulative occupational radiation exposure. IES Utilities l Inc. has reviewed this request and determined that the proposed amendment meets the eligibility I criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR Section 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination l
follows:
lhuiis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Attachment I to this letter, the proposed TS amendment does not )
involve a significant hazards consideration.
- 2. The proposed TS amendment will only permit a higher value of the reactor water conductivity limit during the application period of Noble Metal Chemical Addition (NMCA). During and after the application, excess ions will be removed from the reactor water by the Reactor Water Cleanup (RWCU) system and the conductivity will be l restored to the limit specified in Section 3.6.B. The deposited layer of noble metals is beneficial for mitigating Intergranular Stress Corrosion Cracking (IGSCC) in reactor l vessel internal components. Therefbre, the proposed TS amendment will not result in a significant change in the types or a significant increase in the amounts of any effluents that may be released ofTsite.
- 3. As is discussed above, NMCA process is developed as a method to mitigate IGSCC in reactor vessel intemal components in conjunction with the liydrogen Water Chemistry (IIWC). Use of NMCA allows lower injection rates of HWC which in turn reduces plant radiation exposure over the life of the plant. Therefore, the proposed TS amendment will not result in an increase in either individual or cumulative occupational radiation exposure.
(
l RTS-290 Attachment 4 to
,. NG-96-1297 Page1of1 SAFETY ASSESSMENT
- 1. Introduction By letter dated July 5,1996, IES Utilities Inc. requested changes to the Duane Arnold Energy Center (DAEC) Technical Specifications (TS). The proposed TS amendment will permit a higher value of the reactor water conductivity limit during the application period of Noble Metal ,
Chemical Addition (NMCA). l The NMCA project at the DAEC is part of ongoing efforts to maintain the integrity of reactor vessel internal components and to limit increases in plant radiation exposure over the life of the plant. NMCA has been developed by General Electric Nuclear Energy (GENE) and an overview of NMCA has been discussed between the NRC and IES Utilities Inc. and GENE during a public meeting held on May 6,1996.
- 2. Assessment NMCA process will deposit a very thin, discontinuous layer of the noble metals on all wetted surfaces during the application period. The treated surfaces will behave catalytically and promote oxidant-hydrogen recombination to reduce corrosion potentials. Hence, a treated surface combined with a low Hydrogen Water Chemistry (HWC) injection rate will reduce the propensity for Intergranular Stress Corrosion Cracking (IGSCC). Lower injection rate of HWC reduces plant radiation exposure over the life of the plant.
During the application period of NMCA, it is expected that the reactor water conductivity will increase and exceed the conductivity limit of 2.0 micromhos per centimeter ( mhos/cm) I specified in the DAEC TS. The expected increase in conductivity is due to the effect of noble metals on conductivity and is appropriate during the application. The deposited layer of noble metals is beneficial for mitigating IGSCC in reactor vessel internal components.
During and after the application, the Reactor Water Cleanup (RWCU) system will continue to operate to remove excess ions and restore the reactor water conductivity to the limit specified in J Section 3.6.B. !
I Based upon the above assessment, we conclude that this proposed TS change is acceptable. l l
l i
j