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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 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 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 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 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 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 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 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 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
. , _ _ _ _ _
4 4'
ATTACHMitNT A 4
i..
PROPOSED CHANG 5S_,_TO APPENDIX A, TECHNICAL SPECIFICATIONS OF FACILITY l
O9ERATING LICENSES WPF-37, NPF-66, NPF-72, and WPF-75 4
t k s a Byron Station Braidtood Station Revised ragg: 3/4 3-5C Revised Pages: 3/4 3-60 3/4 3-60 3/4 3-62 t
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f 425 OO $64
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TABLE 3.3-12 I ;l
-$< RADI0 ACTIVE LIQUID ,FFFLUENT MONITORING INSTRUMENTATION E
, MINIMUM CHANNELS
$ INSTRUMENT OPECABLE ACTION d
y 1. Radioactivity Monitors Providing . Alarm and '-
p Automatic Termination of Release i m _.
Liquid Radwaste Effluent Line (ORE-PR001) 1 31
- 2. Radioactivity Monitors Providing Alarm
, But Not Providing Automatic Termination of Release
- a. Essential Service Water R 1) Unit 1 l <;> a) RCFC 1A and IC Outlet (IRE-PR002) 1 32 b) RCFC IB and ID Outlet (IRE-PR003) 1 32 j 2) Unit 2 I a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32-l b) RCFC 28 and 2D Outlet (2RE-PR003) 1 32
- b. Station Blowdown Line'(ORE-PR010) 1 32
! I I 3. Flow Rate Measurement Devices f[
l i
- a. Liquid Radwaste Effluent Line (Loop-WX001) 1 33 i li b. UplJ RaJ waa+c. Efhen+ Loin Floso L. int. (f.por - LOX 630) 1 33 i
e C. 5t on 8 down Line (Loop-CWO32) 1 33
- \> ~ -]
mb
_ - , _ . _ _ ,_-_m.m.,-_..... -,,m, -
.,~,,.-,e., , , , , - - . , , . , , - . , , , , , , - , , , . . , , . , , , . . , , . . , , ~ . . - , , _ . . . , , , _ - , , . , m.o..,,,o. . , _ , . ,,_., ,.=. m. ._ ..-, ,, ....,,.m.
TABLE 4.3-8 E
g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL ANALOG CHANNEL CHANNEL E CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL O CHECK CHECK CALIBRATION EST TEST
- 1. Radioactivity Monitors Providing
" Alarm and Automatic Termination of Release D P 0:3)# Q(1) N.A.
Liquid Radwaste Effluent Line (ORE-PR001)
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
$ a. Essential Service *. tater
. 1) Unit I M Q(2) N.A.
a) RCFC 1A and 1C Outlet (IRE-PR002)
D R(3)f Q(2) N.A.
D M R(3) b) RCFC 18 and ID Outlet (IRE-PR003)
- 2) Unit 2 D M R(3)# Q(2) N.A.
a) RCFC 2A and 2C Outlet (2RE-PR002) D M R(3)# Q(2) N.A.
b) RCFC 28 and 2D Outlet (2RE PR003)
M R(3)# Q(2) N.A.
D j{ b. Station Blowdown Line (ORE-PRO 10) h 3. Flow Rate Measurement Devices
- a. Liquid Radwaste Efflu Line (Lo p-WX001) D(4) N.A. R[ N.A. Q
- si -
- p. n. R g. g, Q (b. Lly<ed Rn wssts. EHlutn+ Low Floso tjeg.(9.uyuq) Q(s4) N.A. R N.A. Q G c.)I. Station Blowdown Line (Loop-CWO32) O(4) ---
__g
y m TABLE 3.3-12 5$
g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 6
o MINIMUM CHANNEAS c- INSTRUMENT OPERABLE
" ACTION d 1. Radioactivity Monitors Providing Alarm and y Automatic Termiaation of Release Liquid Radwaste Effluent Line (ORE-PR001) 1 31
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release o a. Essential Service Water b
w 1) Unit 1 A
o a) RCFC 1A and IC Outlet (IRE-PR002) 1 32 b) RCFC 18 and ID Outlet (IRE-PR003) 1 32
- 2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) 1 32 b) RCFC 28 and 20 Outlet (2RE-PR003) 1 32
- b. Station Blowdown Line (ORE-PR010) 1 32
- 3. Flow Rate Measurement Devices
= -- _m. ---
- a. Li 1
- b. t..' pas d Adu < quid Radwaste Effluent Line .p- (Loop-WX001)%
WK 636) E+fluen4 Lota Flow L;nt. 33Ct.
c, )f. Station Blowdown Line (Loop-CWO32) 1 33 1 33 J
_ ~ ^ __ - J
' ~
TABLE 4.3-8 h RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS "o
!5 DIGITAL ANALOG 8 CHANNEL JHANNEL i
CHANNEL S0JRCE CHANNEL OPERATIONAL OPERATIONAL c INSTRUMENT CHECK CHECK CALIBRATION . TEST TEST 3
d 1. Radioactivity Monitors Providing Alarm and Automatic Termination
- p. of Release to Liquid Radwaste Ef fluent Line (0RE-PR001) D P R(3)# Q(1) N.A.
- 2. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
- a. Essential Service (later w 1) Uni' 1 1 N.A.
w a) RCFC 1A and IC Outlet (1RE-PR002) D M R(3)# Q(2) b) RCFC IB and 10 Outlet (1RE-PR003) D M R(3)# Q(2) N.A.
- 2) Unit 2 a) RCFC 2A and 2C Outlet (2RE-PR002) O M R(3)# Q(2) N.A.
b) RCFC 28 and 2D Outlet (2RE-PR003) D M R(3)# Q(2) N.A.
R(3)# Q(2) N.A.
h b. Station Blowdown Line (0RE-PR010) D M p
5l 3. Flow Rate Measurement Devices c! _ --
~
O
~
- a. Liquid Radwaste Effluent Line M (Loop-WX001) . D(4) N.A. R# N.A. Q
- b. Li9uad Rad we5+e e.E4 tue n t Lew Flow t *(cey.wygjo) o(q) p.n. g g,g. q C . /. Station 310wdown Line (Loop-CWO32) D(4) N.A. R N.A. Q
'A
p
.b ,
ATTACHMENT B DESCRIPTION AND m7MMARY OF PROPOSED CHANGES.
The proposed changes involve Technical Specification Tables 3.3-12 and 4.3-8 for the Byron and Braidwood Stations. The proposed changes result from a modification to the Liquid Radwaste Effluent Line. This modification installs a 3" diameter bypass line around flow element WX001, that includes a new flow element (WX630) and accompanying flow control / isolation valves in the added line. The purpose of this bypass is to allow accurate measurements of lower effluent discharge flow rates than is currently possible with the originally installed flow metering system. The existing radiation monitor, (ORE-pR001) will continue to provide the high radiation isolation signal for both the existing ar.d the bypass isolation valves. The Technical Specification changes propose to add the new flow element to Tables 3.3-12 and 4.3-8.
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ATTACHMENT C EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIONS Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards considerations.
According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards considerations if operation of the facility in accordance with the proposed amendment would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3) Involve a significant reduction in a margin of safety.
The physical changes to the plant involve, the installation of a 3" diameter bypass around t'.ie existing 6" diameter liquid radwaste effluent discharge line flow rate element and flow control / isolation valves. The bypass includes a new flow rate element and flow control /isolttion valves, and is fabricated of the same quality group materials as the original. The purpose of the new bypass is to provide the capability to measure lower flow rates (0 to 150 gpm) than is possible with the existing system (180 to 550 gpm). The existing radiation monitor will not be bypassed, and will have the capability to provide an isolation signal to the isolation valves in both loops. Controlled key (only one key issued at a time) locks on the valve operator switches will assure that only one loop may be used at a time.
The new bypass will perform the same function as the existing liquid radiant effluent discharge lines. The addition of the new flow rate element to the Technical Specifications will ensure system operability and controlled keylocks will assure that only one loop may be used at a time.
Therefore, this added bypass does not increase the probability of an accident previously evaluated.
The consequences of previously evaluated accidents would not be
- significantly increased because the operability of the required radwaste system train will not be decreased.
l The operability of the flow rate elements will continue to be verified by performing the related Technical Specification required surveillances. Because the added bypass loop performs the same function and is constructed of the same quality group materials as the existing loop, the l possibility of a new or different kind of accident from any accident previously evaluated is not created.
The added bypass flow element performs the same function as the original monitor, but at a lower flow rate. The same radiation monitor provides isolation signal on high radiation levels to both the original and I the new bypass line isolation valves. Therefore, there is not a significant l reduction in the margin of safety.
Based on the precceding evaluation, Commonwealth Edison believes that the proposed amendment involves no significant hazards considerations.
4056K