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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
.
DAEC-1 c.
Mont hly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the NRC to arrive no later than the 15th of each month following the calendar month covered by the report.
d.
Other Reports Table 6.11-1 lists some of the routine reports required by 10 CFR Parts 20, 40, 50 and 70, including those listed in Specification 6.11.1.
hha5} Safety /ReliefValveChallenge e.
A repor_t__docu gntiyg sa_fety_/r_eli_ef v dv_e_challen Wo se,pubmitted_ -
sh I' wi thin @,;(syp _ ?[ _Jem_ary
.._._ _ _- f, m erd h 5....,... _..... _..,. - _ - _
yearv a++er eu.h e.E FuC uMC ourA 1 :::P N [lkk M Radioactive Material Release Report f.
l The(Gem 4[nnualRadioactiveMate
~ [ckl%Kar_ yeaQ
., W. x Re1 e
t covering the operation l
_o f _ t he qni_t _ uring_the pr_evi_on * =cnths c. crntm shall be submitted
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b de h *% _l9 N U U [Yi i} N f 10j1 N S_
Foi / M.!_of_e_a_ch_,y_ea_rh The report 0
shall i
~
- Anclude a summary of the quantit'tes of radioactive liquid and gaseous r
i effluents and solid waste released from the unit. The material provided i
shall be (1) consistent with the objectives outlined in the ODAM and PCP l
and (2) in conformance with 14 CFR 50.36a and Section IV.B.1 of Appendix I l
to 10 CFR Fart 50.
i I
i g.
Annual Radiological Environmental Report Olg/
l The Annual Radiological Environmental Report covering the operation of the l
unit during the previous calendar year shall be submitted"before May 1 of l
each year.
The report shall include summaries, interpretations, and l
analysis of trends of the results of the Radiological Environmental i
Monitoring Program for the reporting period. The material provided shall l
be consistent with the objectives outlined in (1) the ODAM and (2) l Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
l h.
I-131 Dose Equivalent Exceeding 50% of Ecuilibrium Value A report of the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 4.6.B.1.h shall be submitted on an annual basis within 60 days after January 1.
The following information shall be included:
(1)
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sartple in which the limit was exceeded; (2)
Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and radioiodine concentrations; (3)
Cleanup system operating status starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4)
Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and Amendment No. 184 6.11-3 09/92 !
9308090341 930728 PDR ADOCK 05000331 p
P PDR 6
DAEC-1 P
TABLE 6.11-1 REPORTING SUMMAFtY - ROUTINE REPORTS Recuirement ReDort Timing of Submittal (kkkkkhSafety/
15 i bb : b f;hh TSI Relief Valve January 1.
^^^^^^^^^^^^
Challenge TS Annual Exposure Within 60 days after January 1.
520.407 Personnel Exposure Within first quarter of and Monitoring each calendar year.
520.408 Personnel Exposure Within 30 days after the on Termination of exposure of the individual Employment or Work has been determined or 90 days after date of-termination of employment or work assigraent, whichever is earlier.
e 540.64(a)
Transfer of Source Promptly upon transfer.
Material 540.64(a)
Receipt of Source Within 10 days after Material material is received.
540.64(b)
Source Material within 30 days after Inventory September 30 of each year.
i 1
Mthb (, mewths afh urh I
AGFREL NC ou RAGE.
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Technic nl ')pecifications 1
Amendinent No. 184 6.11-6 09/9
-]
1 m
,o-i
DAEC-1 TABLE 6.11-1 (Cont)
RIPORTING
SUMMARY
- ROUTINE REPORTS Requirement Report Timing of Submittal
..z...
550.59(b)
Changes, Tests,
!!it h;r 00 d;y: cft:r and Experiments J a nu ai--j !.
(
570.53 Special Nuclear Within 30 days after March Material Status 31 and September 30 of each year.
570.54 Transfer of Special Promptly upon transfer Nuclear Material 570.54 Receipt of Special Within 10 days after Nuclear Material material is received Appendix G Fracture Toughness On an individual-case basis to 10 CFR at least 3 years prior to Part 50 the date when the predicted fracture toughness levels will no longer satisfy section V.B. of Appendix G to 10 CFR Part 50.
Appendix H Reactor Vessel Completion of tests after to 10 CFR Material Surveillance each capsule withdrawal.
Part 50 Appendix I
' Innual adioactive ;'ithin 00 dr.y; cf t:r to 10 CFR Materia elease J anu ; --- 1 :nd July 1.
Part 50 Report 0 o g
,, ig 17, Appendix I Annual Radiological On or before May 1.
to 10 CFR Environmental Report Part 50 Appendix J Reactor Containment Approximately 3 months to 10 CFR Building Integrated following conduct of test.
Part 50 Leak Rate Test
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I Amendment No. 184 6.11-7 09/92 V
e es DAEC-1 6.14 OFFSITE DOSE ASSESSMENT MANUAL (ODAM) l 6.14.1 Changes to the ODAM i
l a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.14.
This l
documentation shall contain:
I l
1)
Sufficient information to support the change together I
with the appropriate analyses or evaluations justifying I
the change (s) and I
l 2)
A determination that the change will maintain the level l
of radioactive effluent control required by 10 CFR I
20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I I
to 10 CFR Part 50 and not adversely impact the accuracy I
or reliability of effluent doce or netpoint calculations.
I b.
Shall become effective after review and acceptance by the Operations Committee and approval by the Plant Super _i_ntendent,
Nuclear.
g gg c.
Shall be submitted to the Commission in the form of a complete, legible co the entire ODAM as a of or concurrent with the
- nnual Radioactive..uer, Release in whic Pa^nf :fhange to the
^i Report for the period o the report l
ODAM was made. Each change shall be identified by markings in I
the margin of the affected pages, clearly indicating the area i
of the page that was enanged, and shall indicate the date the l
change was implemented.
I I
I I
I I
I I
1 h
Amendment No. 184 6.14-1 09/92