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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 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 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 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
. _..
AC Sources - Operating 3.8.1 l
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify the fuel oil transfer system 31 days operates to transfer fuel oil from storage
. tank-to the day tank.
SR 3.8.1.7
NOTE--------------------
1 All DG starts may be preceded by an engine prelube period.
)
Verify each DG starts from standby 184 days condition and achievesl inA 10 segefids.
.r ol e 2 37 and/ 4574V and ffequency v
L2
.5Hz ds60/JHz.}
SR 3.8.1.8
NOTE-------------------
(
This Surveillance shall not be performed in MODE 1 or 2.
However, credit may be l
taken for unplanned events that satisfy this SR.
Verify automatic slow transfer 24 months I
of AC power supply from the Startup Transformer to the Standby Transformer.
(continued) h 6 to reconds volhge 3 3'P/W an A q,
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9902030086 990122 l
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AC Sources-Operating B 3.8.1 B,ASES,
SURVEILLANCE SR 3.81.2 and SR 3. ELL 2 (continued)
REQUIREMENTS i
After completion of the SR the fuel racks to the DG are disabled to allow purging of any residual fuel oil from the cylinders. This also renders the DG inoperable.
The two hours allowed by the Note minimizes the amount of time a DG is inoperable while providing enough time to perform the required Conditional Surveillance and avoids entering the shutdown actions of Condition E or F unnecessarily For the purposes of this testing, the DGs are manually started from standby conditions.
Standby conditions for a DG mean that the diesel engine coolant and oil are being continuously circulated and temperature is being maintained consistent with manufacturer recommendations.
In order to reduce stress and wear on diesel engines during testing, the manufacturer of the DGs installed at the DAEC h o.cMeve4 sYadf recommends a modified start in which the starting speed of f sh% vob e,33')yy the DG is limited, warmup is limited to this lower speed.
and the DGs are gradually accelerated to synchronous speed "d MSN M prior to loading. These start procedures are the intent of 6epewy >,b ELS Ha Note 2 (SR 3.8.1.2).
4d 6 GO,5 NQ SR 3.8.1.7 requires that, at a 184 day Frequency, the DG starts from standby conditions and achieves reauirgd voltag and frequency (i.e. -soltace 2 3744 V(ang s 4F/6 V)and frequency a 59.5 Hz(ani s 60/5 Hb) withiri 10 seconds;in the e
10 second start requirement sugorts the assumptions r
design basb LOCA analysis of JFSAR. Section 6.3 (Ref.12) and DAEC SAFER /GESTR LOCA Analysis. NEDC-31310P (Ref. 15).
The 10 second start requirement is not a]plicable to SR 3.8.1.2 (see Note 3 of SR 3.8.1.2), w1en a modified start procedure as described above is used.
If a modified start is not used, the 10 second start requirement of SR 3.8.1.7 applies.9 The normal 31 day Frequency for SR 3.8.1.2 is consistent with Safety Guide 9.
The 184 day Frequency for SR 3.8.1.7 is a reduction in cold testing consistent with Generic Letter 84-15 (Ref. 7).
These Frequencies provide adequate assurance of DG OPERABILITY, while minimizing degradation resulting from testing.
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DAEC B 3.8-16 Amendment 223
TSCR-022 to NG-99-01 I2 l
Page1ofI SAFETY ASSESSMENT By letter dated January 22,1999, IES Utilities Inc. submitted a request for revision of the Technical Specifications for the Duane Arnold Energy Center (DAEC). The proposed change is consistent with NRC-approved Revision 2 to Traveler TSTF-163 for the Improved Standard Technical Specifications for General Electric BWR/4 plants (NUREG-1433).
i Evaluation:
I This proposed change revises surveillance requirement SR 3.8.1.7 to better match plant
- conditions during testing. This surveillance test is performed with the DG unloaded, so that the DG initially over-shoots its target nominal voltage and frequency during testing.
In an actual event, the DG would be almost immediately loaded once minimum voltage and frequency requirements are met, thereby limiting the over-shoot. The revision changes the SR 3.8.1.7 criteria to clarify which voltage and frequency limits are applicable during the transient and steady state portions of the DG start.
The revised test criteria are a better match for the tested condition (unloaded). The Loss of Offsite Power - Loss of Coolant Accident (LOOP-LOCA) test will still be performed to demonstrate DG operability in conditions which are more representative of accident conditions (loaded in the actual time sequence for loading).
i This change does not affect the DG's ability to supply the minimum voltage and frequency required within 10 seconds or the steady state voltage and frequency required by the UFSAR analysis. The DGs will continue to perform their intended safety function, l
in accordance with the DAEC accident analysis.
Therefore, we have concluded that the proposed revision to the DAEC Technical Specifications is acceptable, i
l~
l 1
l l
l.
I i
k 4
l TSCR-022 to NG-99-0112 I
PageiofI ENVIRONMENTAL CONSIDERATION 10 CFR Section 51.22(c)(9) identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perfonn an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed I
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 a significant increase in individual or cumulative occupational radiation exposure. IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR Section 51.22(b),
i no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:
Basis l
The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR l
Section 51.22(c)(9) for the following reasons:
i 1.
As demonstrated in Attachment I to this letter, the proposed amendment does not involve a significant hazards consideration.
I 2.
There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed change is consistent with NRC-approved Revision 2 to Traveler TSTF-163 for the Improved Standard j
Technical Specifications for General Electric BWR/4 plants (NUREG-1433). This l
change affects DG testing criteria only and will not affect either the amount or l
type of effluents normally released from the plant.
3.
There is no significant increase in individual or cumulative occupational radiation exposure. The proposed change is consistent with NRC-approved Revision 2 to l
Traveler TSTF-163 for the Improved Standard Technical Specifications for General Electric BWR/4 plants (NUREG-1433). This change affects DG testing criteria only and will not significantly affect either individual or cumulative occupational radiation exposure.
1 l