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 ProceduresML20216H701 |
Person / Time |
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Site: |
Braidwood |
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Issue date: |
09/10/1997 |
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From: |
COMMONWEALTH EDISON CO. |
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To: |
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References |
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PROC-970910, NUDOCS 9709170034 |
Download: ML20216H701 (10) |
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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood 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 ML20216C1011998-03-26026 March 1998 Revs to ODCM for Braidwood,Including Rev 1.9 to Chapter 10 & Rev 3 to Chapter 12 ML20217C3011998-01-31031 January 1998 Rev 0 to Inservice Testing Program Plan Pumps & Valves Braidwood 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 ML20198P1601997-10-20020 October 1997 Rev 1.5 to Odcm,Chapter 12 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 ML20137A4961996-12-31031 December 1996 Rev 2 to Odcm,Braidwood Annex,Chapter 12 & App F ML20116F3811996-06-30030 June 1996 Rev 1.9 to ODCM, Chapters 11,12 & App F ML20134N3051996-03-25025 March 1996 Rev 1 to 10CFR50.59 Se ML20095A9071995-10-31031 October 1995 Rev 1.8 to Odcm ML20129B7051995-09-22022 September 1995 Rev 0 to Byron/Braidwood Units 1 & 2 SG Eddy Current Analysis Guidelines ML20092B1051995-09-0202 September 1995 Rev 0 to SG Structural Insp Plan in Support of Braidwood 1 & Byron 1 3.0 Volt Ipc ML20091M8641995-08-25025 August 1995 Verification Analysis for Computer Program ML20082L5451995-04-18018 April 1995 Rev 3 to ISI Plan for Braidwood Nuclear Generating Station Units 1 & 2 1st Insp Interval ML20082C9481995-03-14014 March 1995 Rev 7 to IST Program Plan for Pumps & Valves ML20083N8701994-07-31031 July 1994 Rev 7 to Byron & Braidwood Stations Units 1 & 2 Eddy Current Analyis Guidelines ML20063F8961994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Braidwood Station ML20064N3281993-12-20020 December 1993 Rev 0 to Operating Parameter Uncertainties for Byron/ Braidwood Revised Thermal Design Procedure ML20056C7441993-06-30030 June 1993 Rev 0.M to ODCM Chapters 10,11 & 12 for Braidwood Station ML20046C7941993-06-25025 June 1993 Idns Map Monitoring Point Id for Braidwood Station, Tables H & I ML20062N7851993-03-0101 March 1993 Rev 4.1 to Procedure Bwhp 4006-008, Repairing, Determinating,Terminating,Splicing,Taping,Cable Jacket Repair & Application of Ray Chem Kit on Cable ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20101M2191992-06-25025 June 1992 Rev 5 to Inservice Testing Program Plan for Pumps Braidwood Station Units 1 & 2 ML20098D7431992-05-31031 May 1992 Rev 0.G to ODCM Chapter 11,pages 11.i,11-5,11-6,11-7 & 11-7, Figure 11-3 ML20092F2251992-02-0606 February 1992 Rev O.F to Chapter 11,Pages 11-i,11-7 & 11-17 of ODCM ML20092J4091992-02-0303 February 1992 Rev 25 to Block Index Procedure Bwzp 600-3A1,App a, Federal Agency Emergency Support Phone List ML20058E8761991-11-18018 November 1991 Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1 ML20082S8031991-09-0707 September 1991 Rev 55 to 1BWOA PRI-10, Loss of Residual Heat Cooling,Unit 1 ML20082S8001991-09-0707 September 1991 Rev 54 to 1BWOA PRI-10, Loss of Residual Heat Cooling,Unit 1 ML20082B2431991-07-0303 July 1991 Plant Procedure Manual Update Notification,Including Rev 20 to Block Index Procedure (Bip) Bwzp 600-1,Rev 22 to Bip Bwzp 600-1A3 & Rev 23 to Bips Bwzp 600-3 & Bwzp 600-3A1 Through Bwzp 600-3A8 ML20077G3631991-06-19019 June 1991 Rev 0.D to Odcm ML20091C8421991-04-30030 April 1991 Rev O.A to Odcm,Consisting of Pages Inadvertently Omitted from Previous Distribution ML20076D8331991-04-25025 April 1991 Rev 0.A to Odcm ML20066D9121990-12-0505 December 1990 Rev 2 to BWAP-1205-3TI, Odcm ML20246H6241989-08-28028 August 1989 Rev 0 to Special Procedure SPP-89-9, Control Room Boundary In-Leakage Test ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML20062N7961989-07-14014 July 1989 Rev 0 to Procedure Bwhp 4006-008A32,Attachment AF, Straight Splices of Power Cables 600 Volts or Less ML20062N7941989-07-14014 July 1989 Rev 0 to Procedure Bwhp 4006-008A31,Attachment Ae, Terminations of Power Cables 600 Volts or Less ML20062N7881989-07-14014 July 1989 Rev 0 to Procedure Bwhp 4006-008A29,Attachment AC, Straight Splice for Multiconductor Control & Instrument Cable ML20062N7921989-07-14014 July 1989 Rev 0 to Procedure Bwhp 4006-008A30,Attachment AD, Typical Pigtail Splices for Motor Connections of 600 Volts or Less, Control & Instrument Cable ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing ML20247M7801989-04-0404 April 1989 Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985 ML20247M8011989-02-0101 February 1989 Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1 1999-04-30
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - -
TIBC102 PASSPC:ti DCCUMENT/ DRAWING TRANSMITTAL h)
I
'From: BRAIDWOOD PROCEDURES GROUP . .
To SET f.206 DQCUMENT CONTROL DESK NRC PROC SET #206 Add: DOCUMENT CONTROL DESK Facility: BRW Dept.: Copy No.: US NRC Passport 10: BRWOO206 Work Request / Task: WASHINGTON DC 20555 DCD Type /No.:
33333333383333333333333333333333334333333333333333333333333333333333333 33333333333333333333333333333333333333333333333333333333333 Date/ Times 09/10/97.11:25- Transmittat Group ID: 0000013955 Transmittat Number: 000364304 Total items: 2 PROCEDURE UPDATE FOR 9/10/97 Page: 1 of 34 See Notes and Ccaments below. Function Number 3s=3333333 333333333.a3333 33 3.e33a.333 3333 3333=s33==s33333 m333 3==333 3333 333mes3333333333 3=a3333333 3333 333333m 33333. 333 ITEM FAC TYPE SUB VENDOR DRAWING / DOCUMENT NUMBER SHT .REV REVDATE CR MEDIA COPY NO. COPlES !SS C M 3333333333333333E3333333SEE23333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333 1 -BRW- PROC STN BWZP 2000 18 002 09/10/97 N H 206 01 0 2 BRW PROC STN BWZP 2000 18A1 002 09/10/97 N N 206 01 0 33333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333 Your teknowledgement is required. Please check the appropriate response and return form to sender.
ALL documents received.
Documents noted above not received (identify those not received).
I to longer require distribution of these docunents.
Holder retains preylous revision.
Dates Signature:
T C
jk CO I
.'1mtusv 'n
,)
9709170034 970910 - iI**glgi, n, i.t 13 MR -
PDR ADOCK 05000456 P PDR ,
BwZP 200018 Revision 2 Information Use h
POST ACCIDENT SAMPLING SYSTEM (PRIMARY RESPONSIBILITY CHEMISTRY DIRECTOR)
A. PURPOSE 3-This procedure defines the Post Accident Sampling System (PASS) capabilities which may be warranted in the determination of core damage.
B. REFERENCES
- 1. BwCP 7031, " Initial Requirements for Post Accident Sampl.'ng of Reactor Coolant, Radwaste and Air".
- 2. BwCP 703 2, " Post Accident Sampling of Diluted Reactor Coolant (Cold or Hot Leg)"
- 3. BwCP 703 3, " Post Accident Sampling of Diluted Reactor Coolant (RHR Heat Exchanger)"
- 4. BwCP 703 4, " Post Accident Sampling of Diluted Pressurizer Steam".
h 5. BwCP 703 5, " Post Accident Sampling of Diluted Pressurizer Liquid".
- 6. BwCP 703-6, " Post Accident Sampling of Diluted Containment Floor Sump"
- 7. BwCP 703 7, " Post Accident Sampling of Diluted HRSS Waste Drain Tank".
- 8. BwCP 703-8, " Post Accident Sampling of Diluted Liquid Radwaste"
- 9. BwCP 703 9, " Post Accident Sampling of Undiluted Reactor Coolant (Cold or Hot Leg)"
- 10. BwCP 703-10, " Post Accident Sampling of Undiluted Reactor Coolant (RHR Heat Exchanger)".
- 11. BwCP 70311, " Post Accident Sampling of Undiluted Pressurizer Steam"
- 12. BwCP 70312, " Post Accident Sampling of Undiluted Pressurizer Liquid"
- 13. BwCP 703-13, " Post Accident Sampling of Undiluted Containment Floor Sump" S 14. BwCP 70314, " Post Accident Sampling of Undiluted Steam Generator Blowdown".
APPROVED (9/8/97) 1 SEP 101997.
oE*EOv7w
BwZP 200018 Revision 2 Information Use O '.8 ' 's.1 n-ce voa 1s. "reet ^cciae t s -nii=8 er u#atietea unss w 1e or i-Tank".
- 16. BwCP 70316. " Post Accident Sampling of Undiluted Liquid Radwaste".
- 17. BwCP 70317, " Stripped Gas Sampling of Post Accident System". '
.I .18. BwCP 703 21, " Post Accident and Normal Sampling of Containment Air in the_ Manual Mode of Operation".
- 19. BwCP 70319, " Transporting Post Accident Samples".
- 20. BwCP 713 3, " Post Accident HRSS Operation for Gas Chromatograph Hydrogen Determination".
- 21. - BwCP 713 4, " Post Accident Boron Analysis Using Fluoroborate Selective Ion Electrode and Sulfuric Acid".
- 22. BwCP 713 5, " Radiological Precautions for Post Accident Sample Analysis".
- 23. BwCP 7231, " Preparation of Radiciodine Samples for Counting".
- 24. BwCP 723 2, " Dilution Criteria Post Accident Isotopic".
- 25. BwZP 2000 4, " Core Damage Assessment".
- 26. BwZP 200017, " Chemistry Director Implementing Procedure".
C. - PREREQUISITES None.
APPROVEDi SEP 101997 HHA!DWOOD (9/8/97) 2 5" 8 '" """
BwZP 200018 Revision 2 Information Use D. PRECAUTIONS
- 1. High radiation fields may be encountered in the post accident sampling room. Coordination with Radiation Protection will be necessary to assure adequate radiation protection is provided to the PASS sample team.
- 2. Area dose rates in the Chemistry labs and counting room in excess of 5 mrem /hr may prohibit use of equipment needed for analyses. Alternate locations for sample analyses may need to be determined.
E. LIMITATIONS AND ACTIONS The Chemistry Director should begin to set up the sampling system for post accident sampling conditions as soon as it is believed a reactor coolant sample or containment air sample may be needed.
F. ERf0CEDURE
- 1. When core damage is suspected, confer with the Technical Director to determine the appropriate sample points on the Post Accident Sampling System (PASS). Refer to the flow charts in Bw2P 2000-4, Appendix B for suggested PASS sampling points.
- 2. Instruct the OSC Director that PASS is required. Ensure the OSC Director and PASS Chemist know which samples are to be taken. Refer to Appendix A for the appropriate procedures used in sample collection. Ensure the PASS Chemist is aware of the procedures.
- 3. Ensure activities of the PASS samples are reported at the time of analysis and that decay correction factors back to the time of sampling and during counting have not been applied.
- 4. Forward a copy of the analysis results to the Technical Director for further use in Core Damage Assessment.
- 5. PASS samples should be stored in the designated sample storage containers. Each container holds four samples. These containers reduce the dose rate by a factor of 1000. Current storage container locations:
- a. Laboratory
- b. General Warehouse (SI #799973) tO APPROVED
%.)
SEP 101997, ttHAIDWooQ (9/8/97) 3 "8'"""
l
BwZP 200018 Revision 2 Information Use g F.
- 6. Prior to moving any storage containers, an area should be designated.
Depending on the severity of the accident, storage containers may need to be located in a posted area.
- 7. The Pooled Inventory Management (PIM) is able to provide assistance in obtaining and relocating the sample storage containers. The names and phone numbers can be found in the " Miscellaneous" section of the Emergency Response Facilities (ERF) Telephone Directory,
- 8. After a loss of offsite power, restoration of power to PASS is accomplished by
\
- a. Bus 143 tied into ESF Bus 141 and
- b. Bus 144 tied into ESF Bus 142.
.. 9. Samples which will be shipped to an offsite vendor for analysis will require transportation in a Type B Shipping Cask. The list of personnel who are currently authorized to withdraw the cask can be found in the tabbed
= " CECO Miscellaneous" section of the Emergency Response Facilities Telephone Directory (ERF).
h To withdraw the cask, a call must be made to one of the people on the list.
He will notify the Pooled Inventory Management (PIM) to obtain the shipping cask.
G. APPENDICES Bw2P 200018A1, PASS Sample Collection Procedures.
O APPROVED
. (Final)
.SEP 101997 '
(9/8/97) 4 BRAIDWooD ON SITE Rtvitw
Bw7,P 200018A1 Revision 2 Reference Use G
t 1,0CA condition Pass S,.nipi Counction Ivoccitures Initial PASS Setup 7 '
=~=_
, BwCP 703-I BwCP 713 5
! l ! l RCS Ilot leg l Prmsurizer tulu Containment Sump Containment Air
=
bT litCP 703-6 i---
or BwCP 703 21
- Bw CP 703-13 i
Bw CP 70317 HwCP 703 4 BwCP 703 3 Strippeil Gas Bw I 034 or Sampling
! Ilw CP 70312
- O B.CP 713 3 Gas I
Chromatograph 112 Determination i
BwCP 703-2 j or j ..
[1wCP 703 9 !i li i
Sample Trapportation
{ BwCP 70319 i
i l OIT Site Anal > sis lab Analysis Boron Isotopic i l fiwCP 713 4 j 11.CP 723 2 l i
i j 7 I I'i,uiil Gas Particulates i ! i Bw CP 703-20 BwCP 703 20 Bw CP 7231 Bw CP 703 ',9.
- 9
- For On Site Lab Analysis Only APPROVED SEP 101997, (9/8/97) 1 BRAIDWOOD ON SITE Rtvitw
^
BwZP 200018A1 Revision 2 Reference Use
- 2. STEAM LINE imE.\K trutial PASS Setup I
DwCP 703-1 DwCP 713 5 l J
l I i j RCS Ilot t#g Prmuruer Containment Air BwCP 703 21 l BwCP 703-17 j BwCP 703-4 Strippui Gas - DwCP 703 5 Sampimg or G HwCP 713 3 Bw CP 7031I Bw CP 70312 Gas Chromatograph l HwCP 703-2
---j or j BwCP 703 9 ;a ,
j t
i Sample Transportation Bw CP 70319 I
i
]
Off Site Anal.uis lab Analysis Bornn [so opic i
l BwCP 713 4 BwCl 723 2 I
lijtuiti Gas Particu'lates I !
l Bw CP 703-m ;! .
Bw CP 703-m !r! , ,,...
.. a ,,,,
.. ,:3 1 ,
BwCP 703-m I O
- For On. Site lab Analysis Only APPROVED (9/8/9-) 2 SEP 101997.
BRAIDWOOD eq sitt arview
4 BwZP 200018A1 Revision 2 Reference Use r . .
(
- 3. STEAM GENEllATOlt TUBE ItUPTUllE 1mtial PASS Setup
, 14wCP 70&l Bw CP 7115
\
i l I Steam Generator I RCS liot leg C""'" ""*"' ^i' Blowdow n I
BwCP 70114 Bwcp 703 21 1 J
liwCP 70117 Stripped Gas Sampling E
.CN Bw CP 7113 (j. Gas Chromatograph i I I I
l Bw CP 7012 or BwCP 7010 i__.
Sample Transportation L .- '
Uw CP 10310 f r----- -l i l OtT. Site Analysir 14.b Analys:s t
Du *ota tsutt,pic P
i t L_EwCP 713,4 f .
L'wCP 7212 {
s i
\ \
IJquid Gss Particuls'es '
l j ,
- F,or Dr. Site lab Analysis Only I bwCP T9.120 { Bw CP 70120 1 _
Rw CP.. ..11 1 swCP m3 20 !
r\ \
\w)
APPROVED (9/m97) a SEP 101984
~BHAm,10W
_OOD. .._
BwZP 200018A1 Revision 2 Reference Use
,O, -
O 4 SIGNIFICANT CONTAINhlENT SUhlP INVENTORY Olt CONTAINA1ENT llUllblNG R ADIATION A10NITOR ALARht initial Pa.m Setup i
I i, UwCP 7031 1 BwCP 713J.
Contamment Containment Sump Air liw CP 70An I or ( BwCP 70121 l
{ ;
hw CP 70313 I i I
i i I
Sample Transportation
~l
{llwCP 70319]
( -
l I
Off. Site Analysia leb Analysis
( l floron isotopie l I
' Hw CP 713-4 j BwCP 723 2
, _w l i l 1.iquitt Gas Particulat ss t
! l.
BwcP701.x l HwCP70mm j
- For On Site lab Analy.<is Only L l uwCP72sl !
l DwCP 7013) l t
J.
1 A
l
(
4,.
.' V APPROVED SEP 101997.
1 BdAIDWOOD I (b/0/9D 4 ON SITE REVIEW
e
- BwZP 200018A1 Revision 2 Reference Use 5 SAFF'IT IN, LECT 10N ACTUATED 011 INDICATION OF IIIGli ItAD LEVEL IN ItCS Initial PASS Setup
}
HwTP7031 fiwCP 713 5 g I
l RCS Ilot Leg Pressuruer
! , ]
l l
1 9
l HwCP 703-4 I
hw CP "03-17 Bw CP 703-5 Strippel Gas or Samphng BwCP 703 Il r ! ,
3 i
Bw CP 70312 ~
I t I s =
I IlwCP 713 3 I Gas Chromatogr ph
}I2 Determination l
! HwCP 703-2 L-4 {e---j or
( f1w CP 7059 l
Sample Transportation c
l" BwCP703-19 )
i Off. Site Analpis leb A pis
(
, Borun isot >pic r , ,
} Bw CP 713-4 a ! } BwCP 72?~ 2 ;
I i l
Liquid cas Particulates i I
- For On Site Lab AnalysisOnly Ii,cp 7amo ! litcp7oa.co l
[_ i ! Bw CP ..,.1-
.. 1 3
(s_) HwCP 703-20 (Final) APPROVED SEP 101997.
(9/8/07) 5 BRAIDWOOD ore arrt REVIEW
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