Proposed Tech Spec Pages 2-8,3/4 3-39,3/4 4-28,3/4 6-23,6-4 & 6-13 Re Instrumentation,Rcs,Containment Isolation Valves, Unit Organization & Administrative ControlsML20206A044 |
Person / Time |
---|
Site: |
Braidwood ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
---|
Issue date: |
04/02/1987 |
---|
From: |
COMMONWEALTH EDISON CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20205T726 |
List: |
---|
References |
---|
RTR-NUREG-1223 NUDOCS 8704070398 |
Download: ML20206A044 (6) |
|
|
---|
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 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 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 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 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 ML20196G0501997-04-25025 April 1997 Proposed Tech Specs Revising Primary Containment & Reactor Coolant Sys Volume Associated W/Unit 1 Steam Generator Replacement ML20137P0081997-03-24024 March 1997 Proposed Tech Specs Removing Values of cycle-specific Core Operating Limits from TS & Relocating Values to Operating Limits Rept ML20135E6851997-02-28028 February 1997 Proposed Tech Specs,Replacing Original W D4 SG at Byron & Braidwood W/B&W International SGs ML20138N6841997-02-24024 February 1997 Proposed Tech Specs Changing TS from Current TS to Improved TS Consistent w/NUREG-1431,Rev 1, STS - W Plants, Dtd Apr 1995 ML20134N8481997-02-18018 February 1997 Proposed Tech Specs Table 2.2-1 & Table 3.3-4 Re Sys Instrumentation Trip Setpoints,Ts 3.4.1.2 Re Reactor Coolant Sys & TS 4.4.1.2.1 Re Surveillance Requirements ML20134E8661997-01-30030 January 1997 Proposed Tech Specs Revising TS 1.0, Definitions, 3/4.6.1, Primary Containment & Associated Bases & 5.4.2, Reactor Coolant Sys Volume, for Bs & Bs to Support SG Replacement ML20134A1551997-01-21021 January 1997 Proposed Tech Specs 3/4.7.1.1 to Clarify That Values Calculated from New Equation for Reactor Trip Setpoint Reductions Were Adjusted 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 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 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 ML20216C1011998-03-26026 March 1998 Revs to ODCM for Braidwood,Including Rev 1.9 to Chapter 10 & Rev 3 to Chapter 12 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 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 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 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 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 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 1999-07-30
[Table view] |
Text
--.
~
TABLE 2.2-1 (Continued)
"!E h
y TABLE NOTATIONS (Continued) ~
8 NOTE 1: (Continued)
Ic
= Time constant utilized in the measured T avg lag compensator, to = 0 s, T' 5 588.4 F (Nominal T avg t RATED THERMAL POWER),
2' K3 = 0.00134, ro P = Pressurizer pressure, psig, P' = 2235 psig (Nominal RCS operating pressure),
L o Plact S transform operator, s 2, and f t(AI) is a function of the indicated difference between top and bottom detectors of the T power-range neutron ion chambers; with gains to be selected based on measured instrument oo response during plant STARTUP tests such that:
(i) for qt - Ob between -m% and +10%, f (AI) = 0, where qt and qb are percent 3
RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + 9b is total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent that the magnitude of qt 9bexceeds +10%, the AT Trip Setpoint shall be automatically reduced by 2.0% of its value at RATED THERMAL POWER.
NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.9% of aT span. ,
8704070398 870402 PDR ADOCK 05000456 P PDR
1 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1* The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.
APPLICABILITY: As shown in Table 3.3-6.
ACTION:
- a. With a radiation monitoring channel Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
- b. With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.
! c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
j 1
- SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3.
4 i ni +i n '
- Control Room isolation not required prior t 4a44e4 criticality on Cycle 1. I J
BRAIDWOOD - UNITS 1 & 2 3/4 3- I j
REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION ACTION (Continued)
MODES 1, 2, 3, 4, and 5:
With the specific activity of the reactor coolant greater than 1 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram of gross radioactivity, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days with a copy to the Director, Nuclear Reactor Regulation. Attention: Chief, h O p t_ - A "crfor = c Branch, and Chief, Accident Evaluation Branc @ U.S. Nuclear Regulatory Commission, Washington, D.C. , 20555. This report shall contain the results of the specific activity analyses together with the following information:
I
- a. 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 sample in which the limit was exceeded:
- b. Results of: (1) the last isotopic analysis for radiciodine performed prior to exceeding the limit, (2) analysis while limit was exceeded, and (3) one analysis after the radiciodine was reduced to less than the limit, including for each isotopic analysis, the date and time of sampling and the radioiodine concentration; I
- c. Clean up flow 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 sample in which the limit was exceeded,
- d. History of degassing operation , if any,, 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, and
- e. The time duration when the specific activity of the primary coolant exceeded 1 microcurie per gram DOSE EQUIVALENT I-131.
@ea.c.kc S y s+ em s SURVEILLANCE REOUIREMENTS l l
1 4.4.8 The specific activity of the reactor coolant shall be determined to be '
within the limits by performance of the sampling and analysis program of Table 4.4-4.
I BRAIDWOOD - UNITS 1 & 2 3/4 4-28 i
i
~, . _ , _ . . , - . _ ,-, - _ . - - . _ - . . , - - ~,,
TABLE 3.6-1 (Continued)
CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NO. FUNCTION ISOLATION TIME (SEC)
- 9. Manual (Continued) 99 FW0150*,# Feedwater N.A.
100 FWO15A*,# Feedwater N.A.
101 FW0158*,# Feedwater_ N.A.
102 FWO15C*,# Feedwater N.A.
- 10. Check 28 CV8113 RCP Seal Water Return N.A.
37 CV8348* RCS Loop Fill N.A.
6 W0007A Chilled Water N.A.
4 10 W0007B Chilled Water N.A.
1 21 CC9534 RCP Mtr Brng Return N.A.
24 CC9518 RCP Thermal Barrier Return N.A.
25 CC9486 RCP Cooling Wtr Supply N.A.
1 C5008A Containment Spray N.A.
16 CS008B Containment Spray N.A.
39 IA091 Instrument Air N.A.
30 WM191 Make-Up Demin N.A.
52 PR032 Process Radiation N.A.
AL PR002G Process Radiation N.A.
AL PR002H Process Radiation N.A.
l 12 PS231A Hydrogen Monitor N.A.
- 1. 31 PS231B Hydrogen Monitor N.A.
l 27 RY8047 PRT Nitrogen N.A.
44 RY8046 PRT Make-Up N.A.
26 SI8815* Safety Injection N.A.
50 SI8818A* Safety Injection N.A.
50 SI88180* Safety Injection N.A.
51 SI8818B* Safety Injection N.A.
51 SI8818C* Safety Injection N.A.
59 905A* Safety Injection N.A. j 59 " I C. -- Safety Injection N.A.
60 SI8819A* Safety Injection N.A.
60 SI8819B* Safety Injection N.A.
s I % 9 0 5'O BRAIDWOOD - UNITS 1 & 2 3/4 6-23 p - -mr-m--g r 7-- y v ,,,--.,y e
CD Z
3>
ew O 1 e
- E. svarem emanante l o
o I 1 I I I r----------'-1 US 0 g usat gly assussata.E [ Phota a. f lise gE AvlCE S nR3 Geek ,5 1 Sta+t uvitiedt & t raf f n 64W191Nt4 F44 NI gggg g gggg ggg gy mes33eg g gggy(g gg, gg g gg ggg ,
t--------J z g l y [ } .I ass:GlaN g[Utg aggnf I
m ass s aiahr eUPE E INTite( NT asassiant SUPG AINSEt4M NT SuPf a gaittp,I 4NT - assamarat ASS IS T ANT SUPE R INT E taK NT MagssigNaea g toisen Plateeteas gaPraat a*E3 SG SuPl e v i trat TECM SE AvtCE S g
I I I Q* l l om,P l l l
[ ousan l openas see I a t not as 3 ,,c,,,,c , ,,,,,,,
N I l orar,s ll sine e ug, og ,,
l teesu s as l sunavism cie.saut sungvium *un"8ma I <= nan l 1.un...,... .. l l I I
, , a. - - .N.,,. .u .. -
,egi.;
a
- i . i i ,,,,,,,,,i t
g mso s sun nv e sums li l
,,.,.,n,c,i,.,,
l l g I ems an auna.w.
i I l "#" l nasica
"'" nasue N '"
l TEE. l l " "'" I C"'" I in sane 3 nC nNic 3nr ."
"8 '.'w*i c' ctscia scian * * * * * 'l l 1 eunavisun l I l
I 1
I I I l !
I l l seinen l l a..y.s.g ,,,,,,,,,, i l "'"ey,*",,,l
- m. l a n.,e.
...... . I 1 nm.... . . I l na.,s.. .m....l a naa**'
a , ; , I onenaione
=
a l sais t l
,o e-l i
,on ,an . I I l i l l l g l
! ! g l DPESaf0A0 [l j cF,3ct l De ChaNIC AL BDetf #t3G NT ELECTRICAL l l SUPE 4vigast l Dealmtf esataX pe CettfelC9 Ma lNTE 0WS 1 l ll [
,.N
,1 0RfmaN SOg L I ct= = l l 1 cim i r, i l ,m. 1== isintoal
~
tenutIndB l eungswas 9
p l atstStaNIS l 0 * .eester Opeestec*e Licen l esat aantus l so
-. ne so.i.e, me.es.e.,i e,e,ete,.se.
, et eis . .e e,ees. e.ies.e.e e 88ettee er cell Seatee Operater*e Leeeeee
- Mey be filled by e ScitE cusset I C00AOINafm ,
= = = = = ,eg.g,g e s,,g g,e esnet G ene n FIGURE 6.2-2 UNIT ORGANIZATION
l ADMINISTRATIVE CONTROLS ONSITE (Continued) j
- 3) Review of all proposed changes to the Technical Specifications;
- 4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;
- 5) Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Assistant Vice President and General Manager Nuclear Stations and to the Superintendent of the Offsite Review and Investigative Function;
- 6) Review of all REPORTABLE EVENTS;
- 7) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite Review nd Investigative Function; Review of the Station Securi y Plan and implementing procedures and submittal of recommended x -
n -- u- - . .ma c--- g u 7 =;hanges g St;t$; to the Assi"h pgc
- t ir: o-f C o r po ca +e- S e c.un t-
- 9) Review of the Emer an and station implementing procedures and submittal of recommended changes to the Assistant Vice President and General Manager Nuclear Stations;
- 10) Review of Unit operations to detect potential hazards to nuclear safety;
- 11) Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering. evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Assistant Vice President and General Manager Nuclear Stations and the Superintendent of the Offsite Review and Investigative Function; and
- 12) Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and the Radwaste Treatment Systems.
I
- c. Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant mainte- .
nance, operation, and administrative procedures relating to facility j operations and shall have the authority to request the action neces- l sary to ensure compliance with rules, regulations, and procedures when in.his opinion such action is necessary. The Station Manager shall follow such recommendations or select a course of action that <
1 BP,AIDWOOD - UNITS 1 & 2 6-13 l l
. _ . . - _ - - .