Similar Documents at Byron |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209B7411999-06-30030 June 1999 Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries ML20204H9781999-03-23023 March 1999 Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations ML20204H4291999-03-22022 March 1999 Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20198N2041998-12-29029 December 1998 Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements ML20198N3471998-12-29029 December 1998 Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values ML20198A0811998-12-14014 December 1998 Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys 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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209B7411999-06-30030 June 1999 Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20204H9781999-03-23023 March 1999 Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations ML20204H4291999-03-22022 March 1999 Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20202G9361999-01-30030 January 1999 Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex ML20198N3471998-12-29029 December 1998 Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values ML20198N2041998-12-29029 December 1998 Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements ML20198A0811998-12-14014 December 1998 Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys ML20196G6611998-11-30030 November 1998 Proposed Rev to Improved Tech Specs Section 3.1 ML20155J2051998-11-0505 November 1998 Proposed TS Converting to Its,Rev R ML20155J0041998-10-30030 October 1998 Proposed Tech Specs Section 5.6.2, Fuel Storage Drainage, to Identify Sf Pool Level Sufficient to Ensure SRP Acceptance Criteria ML20154S5011998-10-18018 October 1998 Proposed Rev N to Improved TS Section 3.7 ML20154M5281998-10-15015 October 1998 Revisions K,O & P of 961213 ITS Submittal ML20154A8881998-10-0202 October 1998 Proposed Rev L to Improved Tech Specs Section 3.8 Closeout ML20153G4331998-09-25025 September 1998 Revs J & M to Tech Specs Sections 3.6 & 5.0,converting to Improved Tech Specs (Its),Final Closeout Package ML20236W5851998-07-31031 July 1998 Proposed Rev G to Sections 3.1 & 3.2 of Improved Tech Specs ML20237B6391998-07-30030 July 1998 Proposed Rev H to Section 3.5 of Improved Tech Specs ML20237E9971998-07-21021 July 1998 Rev I to Proposed Improved Tss,Section 3.9 Re Final Closeout ML20237B7021998-07-0909 July 1998 Proposed Improved TS (ITS) Section 3.3 Issued as Result of Removing Generic Change Traveler TSTF-135,Rev E from ITS Submittal ML20236H6531998-07-0202 July 1998 Rev F to 961213 Improved TS Submittal,Containing Final Package Closeout for Improved TS Sections 1.0,2.0 & 3.0 ML20248M1491998-06-0101 June 1998 Proposed Tech Specs Bases Page B 3.8-58b,converting to Improved Tech Specs ML20248K7361998-05-31031 May 1998 Commonwealth Edison Bnps Unit 1 Cycle 9 Startup Rept ML20248C5511998-05-29029 May 1998 Proposed Tech Specs Bases Section 3/4.4.4, Relief Valves, Specifically Crediting Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS at Power Accident ML20217Q8521998-05-0101 May 1998 Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments ML20216D9431998-04-0909 April 1998 Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66 ML20217E1891998-03-24024 March 1998 Proposed Tech Specs Surveillance Sections & Bases Allowing Util to Defer 10CFR50,App J,Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20217B2681998-02-14014 February 1998 Proposed Rev D to ITS ML20199J7581997-12-31031 December 1997 Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 ML20198C3181997-12-30030 December 1997 Proposed Tech Specs 3.7.1.3 Re Condensate Storage Tank ML20203M5921997-12-17017 December 1997 Proposed Tech Specs,Rev C Changes Improved TSs 3.0,3.3,3.7, 3.8 & 5.0 as Result of Removing Generic Change Traveler TSTF-115 from Improved TS Submittal ML20203D0361997-12-0909 December 1997 Proposed Tech Specs Pages Correcting Errors Discovered in Current TS W/Regards to Total RCS Volume & Correction to Increase in RCS Volume Associated W/Unit 1 Replacement SGs Accounting for Hot Conditions ML20199A4751997-11-0707 November 1997 Proposed Tech Specs Pages Revising TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.c & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20216H8241997-10-31031 October 1997 Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F ML20198M2621997-10-31031 October 1997 Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12 ML20217K4461997-10-21021 October 1997 Proposed Tech Specs Re Boron Credit in SFP ML20202F4561997-10-10010 October 1997 Proposed Tech Specs,Deleting Lower Flow Rate Requirement Associated W/Nonaccessible Area Exhaust Filter Plenum & Fuel Handling Bldg Ventilation Sys ML20211D9421997-09-24024 September 1997 Proposed Tech Specs Revising Allowable Time Interval for Performing Turbine Throttle Valve & Turbine Valve SRs Requirements from Monthly to Quarterly ML20216G8541997-09-0808 September 1997 Proposed Tech Specs Change to TS 4.5.2.b & Associated Bases Bringing Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20217H6071997-08-0707 August 1997 Proposed Tech Specs Pages,Revising Bases for Proposed Improved TS SR 3.8.6.1 & 3.8.6.3,to Indicate That Correction for Level Is Not Required When Battery Charging Current Is Less than 2 Amps for Gould & Less than 3 Amps for C&D ML20148P7721997-06-30030 June 1997 Proposed Tech Specs,Revising TS 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Permanently Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3081997-06-24024 June 1997 Proposed Tech Specs,Changing TS for ECCS Venting ML20141B7781997-06-17017 June 1997 Proposed Tech Specs Revising TS Sections 3/4.6.1.6,4.6.1.2, 6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a, Which Requires Utils to Update Existing Containment Vessel Structural Integrity Programs ML20148J3231997-06-0909 June 1997 Proposed TS Reflecting Latest Rev of Waste Gas Decay Tank Rupture Accident Dose Calculation ML20140D0081997-05-31031 May 1997 Proposed Tech Specs,Revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8991997-05-24024 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K3381997-05-23023 May 1997 Proposed Tech Specs Requesting Enforcement Discretion from Compliance W/Ts 4.5.2.b.1 Requirements of Venting of Emergency Core Cooling Sys Pump Casings & Discharge Piping High Points Outside of Containment ML20141K0011997-05-21021 May 1997 Proposed Tech Specs Relocating Reactor Vessel Surveillance Program Capsule Withdrawal Schedules IAW GL 91-01 ML20148B6151997-05-0606 May 1997 Proposed Tech Specs,Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0501997-04-25025 April 1997 Proposed Tech Specs Revising Primary Containment & Reactor Coolant Sys Volume Associated W/Unit 1 Steam Generator Replacement ML20137S5341997-04-0707 April 1997 Proposed Tech Specs 3/4.8.2 Re D.C. Sources 1999-06-30
[Table view] |
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s PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION
- 3. 7.1. 2 At least two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
- a. One motor-driven auxiliary feedwater pump capable of being powered from an ESF Bus, and
- b. One direct-driven diesel auxiliary feedwater pump capable of being powered from a direct-drive diesel engine and an OPERABLE Diesel Fuel Supply System consisting of a day tank containing a minimum HWi=5f of 195E1420 gallons 3 of fuel.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
- a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. With both auxiliary feedwater pumps ' inoperable, be in at least HOT
, STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following l 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE: -
- a. At least once per 31 days on a STAGGERED TEST BASIS by:
l 1) Verifying that the pump develops a differential pressure of l greater than or equal to 1825 psid at a flow of greater than or equal to 85 gpa on the recirculation flow when tested pursuant to Specification 4.0.5;
$f)[kD P
BYRON - UNITS 1 & 2 3/4 7-4
INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.
APPLICABILITY: At all times.
ACTION:
- a. With one or more of the above required seismic monitoring instruments inoperable'for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.3.1 The seismic monitoring instrumentation shall be determined OPERABLE:
- a. At least once per 31 days by verifying operable status indications of the seismic monitoring instrumentation.
- b. At least once per 92 days by verifying that:
- 1) The triaxial acceleration sensors and the time-history accelero-graphs properly process the equipment internal test signals.
- 2) The response spectrum analyzer properly executes its diagnostic routine.
- c. At least once per 184 days by verifying that the triaxial acceleration sensors and the time-history accelerographs properly record the equipment internal test signals. The test may be performed in lieu of the test required by Specification 4.3.3.3.1.b.1), and
- d. At.least once per 18 monthsx-during-shutdog by: l
- 1) Verifying the electronic calibration of the time-history j accelerographs.
l 2) Installing fresh magnetic recording plates in the triaxial peak l accelerographs.
4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the et,uipment listed in Table 3.3-7 shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 14 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.
BYRON - UNITS 1 & 2 3/4 3-44
ATTACHMENT 2 Summary of Chances Two changes have been identified in the Byron Station Technical Specifications due to differences between Unit 1 and Unit 2, or are administrative in nature as indicated below:
- 1) Page 3/4 3-44, Surveillance Requirements 4.3.3.3.ld Delete the words ", during shutdown," and'the comma preceeding and following the words, so the sentence reads: "At least once per 18 months by:
- 2) Page 3/4 7-4, Auxiliary Feedwater System, Limiting Condition for Operation 3.7.1.2.b.
Delete the words " level of 71%" and insert "of" in its place. Also, remove the parenthesis surrounding 420 gallons, so the sentence reads: "One direct-driven diesel engine and an OPERABLE Diesel Fuel Supply System consisting of a day tank containing a minimum of 420 gallons of fuel.
ATTACHMENT 3 Evaluation of Significant Hazards Consideration A. Seismic Instrumentation (pace 3/4 3-44)
Description of Amendment Request The requested change deletes "during shutdown" for the surveillance requirement. This procedure can be done in any mode and does not require shutdown conditions. As currently worded, both Byron Units 1 and 2 and Braidwood Units 1 and 2 would need to be shutdown for the performance of this surveillance.
The reason this constraint was originally imposed was due to ALARA considerations. Although the seismic monitors are located inside containment, the tests are performed outside containment.
Therefore, ALARA is not a pertinent issue in determining when these surveillances are performed.
This proposed change is also applicable to Braidwood and, if approved, should be included in the draft Braidwood Technical Specifications.
Basis for Proposed No Significant Hazards Consideration Determination Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards considerations. In accordance with the criteria of 10CFR 50.92(c),
the proposed amendment does not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:
(a) the proposed amendment does not alter the manner in which the surveillances are performed. The change merely allows the option of doing the seismic instrumentation surveillances while the units are in operation. The seismic instrumentation does not perform a protective function; changing the mode of operation during which the surveillances are performed does not cause a significant increase in the probability or consequences of a previously evaluated accident.
(2) Create the possibility of a new or different kind of accident from an accident previously evaluated; because:
(a) the sole purpose of these instruments is to perform'a monitoring function. Therefore, changing the mode of operation during which these. tests are done does not create the possibility of a new or different kind of accident from an accident previously evaluated.
(b) This is an administrative change which would permit surveillances to be performed while ,
the units are operating.
(3) Involve a significant reduction in the margin of safety, because:
(a) there is no margin of safety associated with these seismic monitoring instruments.
Based on the preceeding assessment, Commonwealth Edison han determined that the proposed amendment involves no significant hazards consideration and request its approval in accordance with the provisions of 10CFR 50.91(a)(4).
B. ..uxiliary Feedwater System (pace 3/4 7-4)
Description of Amendment Request The requested change is to replace the words " minimum level of 71% (420 gallons) of fuel" for the diesel fuel supply system day i tank (specification 3.7.12), with " minimum of 420 gallons of fuel".
This change is sought to remove the 71% reference from the Technical Specifications.
^
The 71% figure is based on level indication which is a function of the diesel fuel supply system day tank dimensions. The dimensions of the Unit 1 and Unit 2 day tanks differ, hence, the 71%
reference is not valid for Unit 2. The minimum required level of 420 gallons is correct for both units and is not being altered.
This change is therefore considered an administrative change for clarification.
This proposed Technical Specification change is also applicable to Braidwood and, if approved, should be included in the
, draft Braidwood Technical Specifications.
Basis for No Sionificant Hazards Consideration Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards considerations. In accordance with the criteria of 10CFR 50.92(c),
the proposed amendment does not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:
(a) the proposed amendment does not alter the minimum required level of fuel in the diesel fuel supply system for the direct driven diesel auxiliary feedwater pump.
(b) The amendment merely deletes references to "71%" to eliminate confusion due to different instrument spans and physical tank capacity on Unit 1 and Unit 2.
(2) Create the possibility of a new or different kind of accident from any accident previously evaluated i because:
(a) the proposed amendment does not allow any new equipment or modes of operation which could initiate or effect the control of a transient or accident because the minimum required level of fuel for the DFSS day tank is not being altered.
4 (3) Involve a significant reduction in the margin of
- safety, because
I j (a) there are no changes being made to hardware, 1 or in the manner that the system is being j operated. Hence, the margin of safety is not being compromised or changed. This proposed licensing amendment should be considered an administrative change.
Based on the preceeding assessment, Commonwealth Edison has determined that this proposed amendment involves no significant hazards consideration and requests its approval in accordance with the provisions of 10CFR 50.91(a)(4).
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