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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999
Rev 4 to Severe Weather Plan, Including Summary of Changes.With
ML20217A2421999-09-30030 September 1999
Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow
ML20211Q8071999-09-0808 September 1999
Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements
ML20211Q2361999-09-0808 September 1999
Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR
ML20211G2281999-08-24024 August 1999
Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List
ML20211C0371999-08-18018 August 1999
Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs
ML20210J0481999-07-28028 July 1999
STP Unit 1,Cycle 9 Startup Testing Summary Rept
ML20209G9351999-07-15015 July 1999
Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves
ML20209H2131999-07-13013 July 1999
Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification
ML20209H3371999-07-13013 July 1999
Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting
ML20209G4461999-07-13013 July 1999
Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations
ML20209C1511999-07-0101 July 1999
Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan
ML20209B5341999-06-24024 June 1999
Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR
ML20209H3151999-06-23023 June 1999
Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management
ML20195E4211999-06-0707 June 1999
Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR
ML20195E4701999-06-0707 June 1999
Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2
ML20209H3081999-06-0101 June 1999
Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program
ML20205S3511999-04-19019 April 1999
Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3
ML20205G8081999-03-30030 March 1999
Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431
ML20204J9681999-03-22022 March 1999
Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves
ML20204D1581999-03-15015 March 1999
Proposed Tech Specs 3/4.7.9 for Snubbers to TRM
ML20207D9651999-03-0202 March 1999
Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B
ML20207C4721999-02-24024 February 1999
Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance
ML20202G6871999-01-26026 January 1999
Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels
ML20199K5681999-01-20020 January 1999
Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing
ML20198A2181998-12-10010 December 1998
Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria
ML20198A1951998-12-0909 December 1998
Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon
ML20196B8121998-11-23023 November 1998
Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section
ML20155J9031998-11-0303 November 1998
Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools
ML20155D5441998-10-29029 October 1998
Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM
ML20155D5561998-10-29029 October 1998
Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM
ML20155D5801998-10-29029 October 1998
Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM
ML20154M1621998-10-12012 October 1998
Revised Tech Specs Bases Pages B3/4 8-14 Through -17
ML20154C0051998-09-30030 September 1998
Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria
ML20154C5071998-09-30030 September 1998
Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics
ML20154A4281998-09-28028 September 1998
Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys
ML20151T1621998-08-31031 August 1998
Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs
ML20238F0841998-08-28028 August 1998
Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code
ML20236T5141998-07-22022 July 1998
Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences
ML20236R1461998-07-15015 July 1998
Proposed Changes to Current Tech Specs Bases
ML20236L6311998-07-0707 July 1998
Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs
ML20236K3481998-07-0606 July 1998
Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual
ML20236M6381998-07-0606 July 1998
Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual
ML20236N0001998-07-0606 July 1998
Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR
ML20247F3321998-05-0707 May 1998
Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences
ML20217P1441998-04-0202 April 1998
Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria
ML20202H9771998-02-16016 February 1998
Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections
ML20198C3741997-12-31031 December 1997
Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow
ML20197A7211997-12-17017 December 1997
Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years
ML20199H2081997-11-20020 November 1997
Revised TS Bases Page B 3/4 4-15
1999-09-08
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999
Rev 4 to Severe Weather Plan, Including Summary of Changes.With
ML20209H3371999-07-13013 July 1999
Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting
ML20209H2131999-07-13013 July 1999
Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification
ML20209H3151999-06-23023 June 1999
Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management
ML20209H3081999-06-0101 June 1999
Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program
ML20212G0031997-10-21021 October 1997
Rev 2 to OPGP-04-ZA-0002, Condition Rept Engineering Evaluation Program
ML20209H3321997-07-31031 July 1997
Rev 2 to 0PGP01-ZA-0304, Probabilistic Safety Assessment Risk Ranking
ML20198E8411997-05-22022 May 1997
Rev 4 to 0PGP05-ZA-0002, 10CFR50.59 Evaluations
ML20217G8191997-02-15015 February 1997
Rev 16 to 0POP03-ZG-0009, Mid Loop Operation
ML20198E8511996-10-28028 October 1996
Rev 5 to 0PGP05-ZA-0002, 10CFR50.59 Evaluations
ML20134J9951996-09-11011 September 1996
South Tx 1 Fuel Assembly Insp Program
ML20148C9531996-07-15015 July 1996
Rev 0 to 0PGP04-ZA-0604, Probabilistic Safety Assessment Program
ML20217F0001996-04-0101 April 1996
Rev 0 to Usqe 96-0101, Control Room Envelope HVAC Emergency Makeup Flow Control Damper B2HEFCV9585 Temporary Mod
ML20097D4021996-02-0202 February 1996
Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting
ML20097D3751996-02-0202 February 1996
Rev 0 to 0PGP02-ZA-003, Comprehensive Risk Mgt
ML20097D3821996-01-0202 January 1996
Rev 0 to 0PGP02-ZA-XXXX, Probabilistic Safety Assessment Program
ML20097D3881995-10-30030 October 1995
Rev 0 to 0AAA00-AA-0000, Configuration Control of Probabilistic Safety Assessment
ML20149E0061995-10-20020 October 1995
Rev 1 to Procedure Usqe 92-0022, Proposed Change Evaluates Doses from Leakage of Sump Water Into Rwst
ML20149E0561995-10-20020 October 1995
Rev 2 to OPGP05-ZA-0002, 10CFR50.59 Evaluations, Form 2
ML20093E7361995-10-0202 October 1995
Rev 0,Suppl 1 to ISI Plan for First Insp Interval of South Tx Project Electric Generating Station Unit 1
ML20149E0321995-06-0404 June 1995
Rev 2 to Procedure OPGP05-ZA-0002, 10CFR50.59 Evaluations, Form 1
ML20080G9091994-12-31031 December 1994
1999 Business Plan
ML20217G8141994-11-22022 November 1994
Rev 2 to 0PGP03-ZA-0101, Shutdown Risk Assessment
ML20078Q2561994-11-0707 November 1994
Rev 6 to OPMP04-JC-0002, Polar Crane Insp
ML20078C5971994-10-26026 October 1994
Rev 4,Suppl 2 to STP Electric Generating Station Unit 2 Pump & Valve IST Plan
ML20078C5961994-10-26026 October 1994
Rev 6,Suppl 2 to STP Electric Generating Station Unit 1 Pump & Valve IST Plan
ML20078Q5651994-10-17017 October 1994
Rev 6 to OPGP03-ZX-0002, Condition Reporting Process
ML20078Q7291994-10-17017 October 1994
Rev 10 to OPGP03-ZA-0090, Work Process Program
ML20078Q8051994-10-17017 October 1994
Rev 2 to OPGP04-ZE-0310, Plant Mods
ML20078Q5081994-08-29029 August 1994
Rev 7 to OPMP02-ZG-0011, Alternative Valve Packing & Live- Load Valve Packing
ML20078Q5581994-06-24024 June 1994
Rev 5 to OPGP03-ZX-0002, Corrective Action Program
ML20078Q7801994-06-0101 June 1994
Rev 2 to OPEP07-ZE-0007, MOV Tracking & Trending Program
ML20078Q4021994-05-24024 May 1994
Rev 7 to OPOP01-ZA-0001, Plant Operations Dept Administrative Guidelines
ML20064N4561994-03-21021 March 1994
South Tx Project Electric Generating Station Operational Readiness Plan Unit 2
ML20078Q5521994-03-0808 March 1994
Rev 2 to OPOP02-AF-0001, Auxiliary Feedwater
ML20078Q2581994-02-14014 February 1994
Rev 5 to OPGP03-ZM-0021, Control of Configuration Changes
ML20078Q5671994-01-25025 January 1994
Rev 8 to OPGP03-ZA-0090, Work Process Program
ML20063K3251993-12-23023 December 1993
300 Ton Essential Chiller Bypass Mod Verification Test
ML20058C4771993-10-25025 October 1993
Rev 0 to STP Restart Action Plan
ML20083P6821993-10-19019 October 1993
Rev 1 to Dept Procedure 0POP05-EO-EC00, Loss of All AC Power
ML20078Q7851993-10-15015 October 1993
Rev 0 to, Equipment History Program
ML20058N7821993-10-14014 October 1993
STP 1994-98 Business Plan
ML20083P6831993-09-15015 September 1993
Rev 2 to Dept Procedure 0POP04-AE-0001, Loss of Any 13.8 Kv or 4.16 Kv Bus
ML20046A2161993-07-15015 July 1993
Field Change 93-1163 to Rev 0 to Procedure 0PGP05-ZV-0008, Siren Sys Activation,Testing & Documentation, Adding Caution to Conducting Manual Growl Test
ML20062L1461993-07-0606 July 1993
Rev 3 to Speakout Program Instruction SPI-02, Classification of Concerns
ML20045E9781993-06-29029 June 1993
Rev 4 to Pump & Valve IST Plan, for Stp,Unit 2
ML20045E9901993-06-29029 June 1993
Rev 6 to Pump & Valve IST Plan, for Stp,Unit 1
ML20078Q2751993-06-28028 June 1993
Rev 5 to ISEG-01, Independent Safety Engineering Group Organization & Responsibilities
ML20062L2301993-03-0202 March 1993
Rev 2 to Speakout Program Instruction SPI-08, Speakout Review Committee
ML20062L2101993-03-0202 March 1993
Rev 2 to Speakout Program Instruction SPI-07, Speakout Repts
1999-07-13
[Table view] |
Text
~
. FOR INFORMATION ONLY IIOUSTON LIGHTING AND POWER COMPANY SOUT!! TEXAS PROJECT ELECTRIC GENERATING STATION PLANT PROCEDURES MANUAL STATION PROCEDURE NON SAFETY-RELATED (Q)
Sampling and Analysis.for Release IPCP08-AP-0009 Assessment - Post Accident Rev. O Page 1 of 8 APPROVED: kM. %33-%
DATE APPROVED 9c4C9C DATE EFFECTIVE PLANT MANAGER Q '
1.0 Discussion
1.1 Purpose and Scope
1.1.1 The purpose of this procedure is to establish the steps necessary to quantify the activity released from the plant under accident conditions in a safe and ef ficient manner.
1.1.2 The type of activity releases considered in this procedure are:
1.1.2.1 Unit Vent 1.1.2.2 Condenser Vacuum Pump 1.1.2.3 Main Steam Line Power Operated Relief Valves (PORV) 1.1.3 The data obtained from the sample analysis will be provided to the RMS computer for dose assessment.
1.2 Definitions 1.2.1 POST ACCIDENT SAMPLING SYSTEM (PASS): A syctem composed of various components that provides the capability to obtain Reactor Coolant System and Containment Atmosphere samples and perform required analyses under Post Accident conditions within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> from the time a decision is made to sample.
8610160189 861009 PDR ADOCK 05000498 E PDR
.e 4
Sampling and Analysis for Release IPCP08-AP-0009 Assessment - Post Accident Rev. O Page 2 of 8 1.2.2 RADIATION MONITORING SYSTEM: The plant system that monitors, quantifies and reports the plant radioactive releases for dose assessment.
1.3 Principle 1.3.1 Samples are obtained from the system making the abnormal release so that a representative isotopic mix may be dete rmined. The isotopic mix is then used to estimate the offsite dose to the public. Determining the release rate during abnormal conditions may mean obtaining samples f rom secondary sources, such as the containment or reactor Coolant.
1.4 Limitations 1.4.1 Only samples from the accident release point need to be obtained.
1.4.2 The samples are listed in order of preference, as the first sample source listed would be the most representative of the actual release rate.
2.0 Prerequisities 2.1 The gamma analysis detection system shall have a current calibration.
3.0 Precautions 3.1 Sample collection, preparation, transport and analysis will be performed under applicable Radiation Work Permits.
3.2. Samples and sample areas may have high dose rates dae to accident conditions. The choice of the sample (s) taAen will be determined by the Health and Safety Services Division.
3.3 Follow the Laboratory Safety Practices of OPCP01-ZA-0017 (Post Accident Sampling and Analysis Program) to minimize personnel dose.
4.0 Procedure 4.1 Obtain a Radiation Work Permit in accordance with OPGP03-ZR-0002 (Radiation Work Permit).
ad D' s
F -
Sampling and Analysis lor Release IPCP08-AP-0009 Assessment - Post Accident Rev. 0 Page 3 of 8 4.2 Unit Vent Sampling 4.2.1 Obtain, as needed, one of the following samples in ac'cordance with the listed procedure. Record the sample point, time and date on the Post Accident Release Assessment Data Sheet (-1).
- a. Unit Vent, OPCP07-ZS-0016 (Collection of Particulate and Iodine Samples)
- b. Containment Atmosphere, OPCP07-ZS-0016 (Collection of Particulate and Iodine Samples)
- c. Containment Atmosphere - Post Accident, IPCP08-AP-0004 (Sampling and Analysis of the RCB Atmosphere - Post Accident) 4.2.2 Obtain, as needed, the following data and record on Post '
Accident Release Assessment Data Sheet (- 1 ) .
- a. Unit Vent Flow Rate - CFM (Unit Vent sample only)
- b. Containment Purge Rate - CFM (Containment Atmosphere samples only)
- c. Air Sample Flow Rate - (CFM)
- d. Sample collection time 4.3 Condenser Sampling 4.3.1 Obtain, as needed, one of the following samples in accordance with the listed procedure. Record the time and date on the Post Accident Release Assessment Data Sheet (-1).
- a. Condenser Vacuum Pump Discharge, OPCP07-ZS-0016 (Collection of Particulate and Iodine Samples).
- b. Main Steam Sample, IPCP07-ZS-0001 (Sampling at Secondary Sample Panel ZLP-132).
- c. Reactor Coolant Sample, (RCS) IPCP07-ZS-0001 (Sampling at Primary Sample Panel ZLP-131 Reactor Grade Sinks).
- d. Reactor Coolant Sample - Post Accident IPCP08-AP-0003
. (Sa,npling and Analysis of RCS, Ri!R, and RGB Sump - Post Accident).
C' e
Sampling and Analysis 'ar Release IPCP08-AP-0009 Assessment - Post Accident Rev. O Page 4 of 8 4.3.2 Obtain, as needed, the following data and record on the Post Accident Release Assessment Data Sheet (-1).
a Condenser Vacuum Pump Flcw Rate - CFM (Condenser Vacuum Pump sample only).
- b. Main Steam Flow - lbs/Hr (Main Steam Sample only).
- c. Primary to Secondary Leak Rate - gal / min (Reactor Coolant sample and Main Steam Samples).
- d. Air Sample Flow Rate (Condenser Vacuum Pump and Main Steam)
- e. Saiple Collection Time (Condenser Vacuum Pump and Main Steam) 4.4 Main Steam Line PORV 4.4.1 Obtain, as needed, one of the following samples in accordance with the listed procedure. Record the time and date on the Post Accident Release Assessment Data Sheet (-1).
- a. Main Steam Sample IPCP05-ZS-0016 (Sampling at Secondary Sample Panel ZLP-132) .
- b. Reactor Coolant Sample IPCP07-ZS-0001 (Sampling at Primary Sample Panel ZLP-131 Reactor Grade Sample Sink). 2
- c. Reactor Coolant Sample - Post Accident IPCP08-AP-0003 (Sampling and Analysis of the RCS, RHR, RCB Sump - Post Accident).
4.4.2 Obtain, as needed, the following data and record on the Post Accident Release Assessment Data Sheet (-1).
- a. Main Steam Flow - lbs/Hr (Main Steam Sample only).
- b. Primary to Secondary Leak Rate - gal / min (Reactor Coolant Sample and Main Steam Sample).
- c. Air Sample Flow Rate - (CFM)
- d. Sample Collection Time 4.5 Calculate the air sample volume following equation in section 5.1 or use the sample liquid mass for the sample analyzed.
Sampling and Analysis f or Release IPCP08-AP-0009 Assessment - Post Accident Rev. O Page 5 of 8 4.6 Analyze the sample for activity in accordance with the appropriate procedure.
4.6.1 IPCP08-AP-0005 (Determination of Radionuclide - Post Accident).
4.6.2 OPCP09-ZR-0004 (Determination of Radionuclide by Gamma Spectroscopy).
4.7 Calculate the sample activity (in uCi/ml or uCi/ gram) using the equation in section 5.2 for each radionuclide. .+
4.8 Release Rate Calculations 4.8.1 Calculate the release rate using the equation in section 5.3 for samples collected in steps 4.1.1.a, 4.1.1.b, 4.1.1.c, 4.2.1.a, and 4.3.1.a f or each nuclide.
4.8.2 Calculate the release rate using the equation in section 5.4 and 5.5 for samples collected in steps 4.2.1.c, 4.2.1.d, 4.3.1.b, and 4.3.1.c.
4.9 Record the results of step 4.8 on Data Sheet (-1).
4.10 Sign and date the Data Sheet (-1). Send the Data Sheet to the Lead Chemical Technician for review and signature.
4.11 Forward the release rate data to Health and Safety Services for dose calculations.
5.0 Calculations 5.1 Air Sample Volume Vol (cc) = SFR x T x 2.83E4 where:
SFR = Air Sample Flow Rate (CFM)
T = Sampling Time (min) 2.83E4 = Cubic centimeters per cubic foot 5.2 Sample Activity Nuclide Activity (uC1)
Activity (uCi/cc or g) = --------
. Sample mass or volume (cc or g)
I e p~.- . - - - - - -'-.-.,.e.. - . -
-- - -& +..c..h*% -
Sampling and Analysis for Release IPCP08-AP-0009 Assessment - Post Accident Rev. O Page 6 of 8 5.3 Nuclide Release Rate (Step 4.8.1)
Nuclide Release Rate (uCi/sec) = A x PSF x 2.83E4 x 0.0167 where:
A = Nuclide Activity (uCi/cc)
PSF = Process Steam Flow (CFM) 2.83E4 = Cubic centimeters per cubic foot-0.0167 = Minutes per second 5.4 Nuclide Release Rate (Step 4.8.1) - Noble Gases (A x LR x 3785)
Nuclide Release Rate (uCi/sec) =
60 where:
A = Nuclide Activity (uCi/cc)
LR = Priraary to Secondary Leak Rate (gal / min) 3785 - Cubic centimeters per gallon 60 = Seconds per minute 5.5 Nuclide Release Rate (Step 4.8.1) - Iodines (A x LR x 3785 x 0.01)
Nuclide Release Rate (uci/sec) =
60
- vhereY A = Nuclide Activity (uC1/cc)
LR = Primary to Secondary Leak Rate (gal / min) 3785 = Cubic Centimeters per gallon 60 = Seconds per minute 0.01 = Estimated Iodine Fractional Carryover of Iodine in Steam
I w
Sampling and Analysis for Release IPCP08-AP-0009 Assessment - Post Accident Rev. O Page 8 of 8 RELEASE ASSESSMENT DATA SHEET IPCP08-AP-0009-1 (Page 1 of 1)
Unit Condenser SG Vent _ Vacuum Pump PORV Sample Date Sample Time Process Flow Rate (CFM)
Primary to Secondary Leak Rate (gal / min)
Air Sample Flow Rate (CFM)
Sm1ple Collection Time (Min)
Nuclide Nuclide Activity Release Rate uCi/cc or gr uCi/sec Noble Gases Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Iodine I-131 1-132 1-133 I-134 1-135 Performed By : Date :
Reviewed By : Date :
This form, when completed, shall be retained for the . life of the plant. ,' .
- - - . - - , - - , - - - , - , . - , , ,_ . . - - . _ - - - - - - - - - - - , , . . _ . , - - -
