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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210J1751999-07-30030 July 1999 Marked-up TS Pages for Proposed Changes Re Upper Temp Limit for UHS ML20209B7411999-06-30030 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 ML20198K5841998-12-23023 December 1998 Revised Tech Spec Pages 3/4 3-53,3/4 3-53a,6-27 & 6-27a,for Rv LI Sys 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 ML20196B4101998-11-25025 November 1998 Proposed Tech Specs Facilitating Replacement of 125 Vdc At&T Batteries with New 125 Vdc C&D Batteries While in Mode 1-4 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 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 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 ML20198L8811998-01-14014 January 1998 Proposed Tech Specs Pages,Revising TS Section 3/4.8.2 & Bases,To Allow Replacement of 125 Volt Dc At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries ML20198L8131998-01-14014 January 1998 Proposed Tech Specs Pages Revising TS 3.4.8, Specific Activity, Figure 3.4-1,Table 4.4-4 & TS Bases 3.4.8 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 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 ML20216F1351997-09-0202 September 1997 Proposed Tech Specs 3.4.8 Re Specific Activity 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 ML20141K8931997-05-23023 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b.1 for Unit 1 as It Relates to Requirement to Vent ECCS Pump Casings & Discharge Piping High Points Outside Containment 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 ML20148D6861997-05-23023 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b.1 for Unit 1 as It Relates to Requirement to Vent ECCS Pump Casings & Discharge Piping High Points Outside 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 1999-07-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210J1751999-07-30030 July 1999 Marked-up TS Pages for Proposed Changes Re Upper Temp Limit for UHS ML20209B7411999-06-30030 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 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 ML20198K5841998-12-23023 December 1998 Revised Tech Spec Pages 3/4 3-53,3/4 3-53a,6-27 & 6-27a,for Rv LI Sys 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 ML20196B4101998-11-25025 November 1998 Proposed Tech Specs Facilitating Replacement of 125 Vdc At&T Batteries with New 125 Vdc C&D Batteries While in Mode 1-4 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 ML20153C0351998-08-31031 August 1998 Revs to ODCM for Plant,Including Rev 2 to Chapters 10 & 11, Rev 4 to Chapter 12 and Rev 3 to App F ML20238F8221998-08-25025 August 1998 Rev 2 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan ML20236Y5481998-08-0303 August 1998 Rev 1 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan 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 ML20216C1011998-03-26026 March 1998 Revs to ODCM for Braidwood,Including Rev 1.9 to Chapter 10 & Rev 3 to Chapter 12 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 ML20217C3011998-01-31031 January 1998 Rev 0 to Inservice Testing Program Plan Pumps & Valves Braidwood Nuclear Generating Station,Units 1 & 2 ML20198L8131998-01-14014 January 1998 Proposed Tech Specs Pages Revising TS 3.4.8, Specific Activity, Figure 3.4-1,Table 4.4-4 & TS Bases 3.4.8 ML20198L8811998-01-14014 January 1998 Proposed Tech Specs Pages,Revising TS Section 3/4.8.2 & Bases,To Allow Replacement of 125 Volt Dc At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries ML20199J7581997-12-31031 December 1997 Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 ML20216H4321997-12-31031 December 1997 Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F 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 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 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 ML20217K4461997-10-21021 October 1997 Proposed Tech Specs Re Boron Credit in SFP ML20198P1601997-10-20020 October 1997 Rev 1.5 to Odcm,Chapter 12 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 ML20216H7011997-09-10010 September 1997 Revised Procedures,Including Rev 2 to Bwzp 2000-18, Post- Accident Sampling Sys (Primary Responsibility - Chemistry Director) & Rev 2 to Bwzp 2000-18A1, PASS Sample Collection Procedures 1999-07-30
[Table view] |
Text
- - - - _-_- _ -___ _ - _ _ _ _ _ - _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ - _ - _ - _ - _ _ - - _ _ _ _ _ - - _ ,
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s AIIACIMMI_A ERQEQSED CHANDES TO AEfj;NplK_4 IgcgICAL SPECIUChTIONS OF FACILLH OPERATING LICQlRES NPF-37 NPF-66. NPF-72 ansLEPM i
i SyLQn_$_(ation RIaldwood Station' 1'
Revised Page: 3/4 5-4 3/4 5-4 i !
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EMERGENCY CORE COOLING SYSTEMS
- 1 SURVEILLANCE REOUIREMENTS J
<tl 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
~
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves '
are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position MOV SI8806 Suction to the SI Open Pumps
'MOV SI8835 SI Pump Discharge Open*
To RCS Cold Legs . I-MOV SI8813- SI Pump Recirculation Open-
.To The RWST MOV SIB 809A RHR Pump Discharge to RCS Cold Legs Open* d MOV S18809B RHR Pump Discharge to Opn a .f RCS Cold Legs MOV SIB 840 RHR Pump Discharge to Closed RCS Hot Legs MOV SIB 802A SI Pump Discharge to Closed RCS Hot Legs MOV SIB 802B SI Pump Discharge to Closed RCS Hot Legs
- b. once per 31 days by: 1
- 1) -Verifying ECCS pump casings an CCS piping is full of water by venting the ;
"le dh t rge piping high points, and ;
- 2) Verifying that each valve (manual, pow in the flow path that is not locked, sealed, or oted, or automatic)
secured in position, is in its correct position. i c.. ,
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump be suctions during LOCA ebnditions. This visual inspection shall performed:
Rsfact dtS %56b ; * '
" Valves may be realigned for testing pursuant to Specification 4.4.6.2.2.
-P BYRON - UNITS 1 & 2 3/4 5-4 AMENDMENT NO.
' EMERGENCY-CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS
{
4.5.2 Each ECCS' subsystem shall be demonstrated OPERABLE: i
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that' the following valves !
are in th% indicated positions with power to the valve operators -
removed:
Valve Number Valve Function Valve Position.
MOV SI8806 Suction to the SI Oper. I Pumps MOV SIB 835 SI Pump Discharge Open* ;
To RCS Cold Legs !
r M0V SI8813 .SI Pump Recirculation Open To The RWST MOV S!8809A RHR Pump Discharge to Open* ,,
RCS Cold Legs MOV SI8809B RHR Pump Discharge to Open*
RCS Cold Legs i MOV SIB 840 RHR Pump Discharge to Closed ;
RCS Hot Legs j
MOV SI8802A SI Pump Discharge to Closed l RCS Hot Legs. '
MOV 5I88028 SI Pump Discharge to Closed RCS Hot Legs
- b. At ce per 31 days by:
- 1) Verifying tha CCS piping is full of water by venting the i ECCS pump casings and a le discharge piping high points, and -
- 2) Verifying that each valve (manual, po ated, or automatic) i in the flow path that is not locked, sealed, or ise ;
secured in position, is in its correct position. !
- c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be !
transported to the containme.nt sump and cause restriction of the j pump suctions during LOCA conditions. This visual inspection shall ~
be performed:
R 9 taa w M iuer+, o Mk 1
- Valves may be realigned for testing pursuant to Specification 4.4.6.2.2.
BRAIDWOOD - UNITS 1 & 2 3/4 5-4
p :, '
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L-N INSERT TO PAGE 3/4 5-4 1
- b. 1) By verifying thatt e
a) The discharge piping for the ECCS subsystem. required by f
Specification 3.5.3 is full of water, by venting the ECCS discharge piping hlgh points, prior to entering MODE.4 from MODE.5, if venting has not been performed in the-previous 31 days, and
~ e-b) The discharge piping for both ECCS subsystems is full of '
water, by venting the ECCS discharge piping high points, l:.
prior to entering MODE 3 from MODE 4, if venting has not been performed in the previous 31 days.
- 2) At least once per 31 days by: I a) Verifying that the ECCS suction plping is full of water by venting the ECCS pump casings, and b) Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct.
position.
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ATTACl! MENT D DESfElEIlON AND
SUMMARY
_Qf_.PfQfQSED CilANGES The present Technica1' Specification 4.5.2 regulres all ECCS piping to be verlfled full of water by venting every 31 days. This requirement requires entry into several High Radiation areas during power operation which provides a significant impact on plant operations. The vents located on the discharge portion of the ECCS piping are-located inside containment, thus involving substantial radiation exposure to individuals: performing the I: surveillance. The proposed change will assist in reducing this exposure #
consistent with ALARA guidelines, and at the same time, provide an j-_ equivalent means of performing the necessary surveillance.
The proposed amendment to Technical Specification Surveillance
{ ;- Requirement 4.5.2.b would- require that the ECCS discharge,, piping bo demonstrated operable by venting It prior to entry into Mode 4 for the operable single train, and prior to entry-into Mode 3 for both operable trains. . These surveillance requirements will be performed when venting has not been completed in the previous 31 days.
The surveillance for- the ECCS auction _ piping and the ECCS pumps will continue to be done on the once per 31 day frequency. Since this equipment is located outside contaimnent, radiation exposure is not as significant.
sc1:0028T 16 1
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ATTACm4ENT C SAFETY EVALUATION AND Et[YJJONMENTAL ASSESSMENT The revised ECCS pipe venting survellisnee requires venting of discharge piping prior to entering Mode 3 or 4, as required. This approach should ensure that no air pockets exist following plant evolutions that might result in the ECCS piping being drained or opened to atmosphere.
Af ter entering Mode 3 or 4, manipulations should not occur that wouldL result in gas volds being introduced. Since pump casing and suction piping will be.
vented monthly, the full condition of the ECCS will be routinely verified.
These venting procedures should ensure the ECCS piping is adequately filled prior to entering Mode 3 or 4 and subsequently maintained in that condition. Also, all ECCS piping up to the Reactor Coolant System is- s physically located at a lower elevation than the Refuel Water Storage Tank.
This be.Ing the case, all piping would be maintained at a pressure greater than atmospheric. This provides assurance that the piping will remain full at all times.
Commonwealth Edison has evaluated the proposed amendment against
'the' criteria-for and identification of licensing and regulatory actions requirj ug environment assessment in accordance with 10 CFR 51.21. It has been determined that the proposed change meets the criteria for a categorical exclusion as provided'for under 10 CFR 51.22(c)(g). This determination was based on-the fact that.this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50. The change involves no significant hazards, there is no significant change in the types or amounts of .of fsite ef fluents, and there is no significant increase in individual or cumulative occupational radiation exposure.
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I 1 s ATTACHtiENT_p UAW AT LVli_ Q[_31 CN 1 f 1 C ANI.j{ AgMQjl CQN U DJ Rh710K$
Commonwealth Edison has evaluated this proposed anendment and determined that it involves no significant hasards considerations.
According to 10 CTR 50.92(c), a proposed amendment to an operating license involves no significant hasards considerations if operation of the facility in accordance with the proposed amendment would nott
- 1. Involve a significant increase in the probability or consequences of an accidvnt previously evaluated
- 2. Create the possibility of a new or alfferent kind of accident from any accident previously evaluated or
[
- 3. Involve a significant reduction in a margin of safety.
A. Tht.P.IR22E23 chaDgt_dQ1R_nat_intQ1Yt A.E.lgnificant_Jngt.tast. An ..thm p.Tchab.i.1117..nt.Innstgnentts Af_an_attidaut PLeviqua1y..e3Ainated.
The probability of an accident occurring is independent of any testing requirements. No changes to the CCCS system are being made that would increase the probability for en accident, nor affect an initiating event of an accident. The revised testing provides assurance that the ECCS piping will remain in a full condition.
Venting will be performed after achieving cold shutdown, if venting has not been not performed in the previous 31 days. Venting will also be performed on piping after any maintenance activity that has the potential to drain the piping. This approach comblned with the fact that the piping by design remains above atmospheric pressure at al', times, provides assursnce that the piping will remain fir.ed, and the system will be capable of providing injection flow dthin all assumed time responses.
B. Tht ptQpoind.shangt JQt1_rs1_EtzAtt_.the w PSAsibill.tk.nLt_nex QI different k,lnd of accident from aDy ACIIAtal.previously 11&lukLtd.
No new equipment is being introduced that could create a new kind of accident. No changes are being made to existing equipment.
Presently, installed equipment will continue to be operated within the bounds of the UTSAR.
C. The..PLQPnard_ChAngt 3015 Dat iDER 1 ve a signiLicant.rtdvCtlan_in _m mBLgin of saltiy.
The revised venting surveillance requirements provide adequate assurance that the ECCS piping will be maintalued in a filled condition. By maintaining the ECCS piping filled, delivety M water to the core in the event of an accident will temain unchanged. The revised ECCS pipe venting surveillance will not reduce the capability of the ECCS to function as described in the Bases for 3.5.2 and the Byron /Braidwood UTSAR. As such, the proposed changes do not involve a significant reduction in a margin of safety.
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Therefore.,basodion the above evaluation, Commonwealth Ediron- -
i k, 'T believes that these changes'do not involve significant hasards- '
M.N, ;. consideration. ..
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