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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. 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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20106A6521992-02-29029 February 1992 Proposed Rev 3 to Ei Hatch Nuclear Plant Solid Radwaste PCP, Per GL 89-01 ML20106A6501992-02-0707 February 1992 Rev 7 to Ei Hatch Nuclear Plant ODCM, Reflecting Proposed Changes,Per GL 89-01 ML20056B3031990-08-0101 August 1990 Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval ML20149N1141988-01-0404 January 1988 Revised Second 10-Yr Interval Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20211H5491987-02-20020 February 1987 IGSCC-Susceptible Primary Pressure Boundary Stainless Steel Piping & Components Insp/Mitigation Program, 1987 Maint/Refueling Outage ML20245B8301986-12-10010 December 1986 Rev 0 to SO-OPS-05-1286, Spent Fuel Pool Transfer Canal Gates ML20245B8171986-12-0505 December 1986 Rev 0 to SO-OPS-02-1286, Processing of Water from Yard Drains ML20245B8201986-12-0505 December 1986 Rev 0 to SO-OPS-01-1286, Radwaste Discharges. Supporting Documentation Encl ML20203L9291986-08-0101 August 1986 Rev 0 to Training Procedure 72TR-TRN-002-0S, License Requalification Training Program ML20137V9031985-12-0505 December 1985 Rev 1 to Emergency Implementing Procedure 62RP-RAD-009-05, Airborne Radioactivity Concentration Determination ML20076J1871985-11-0808 November 1985 Rev 2 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp for Georgia Power Co ML20076J1911985-11-0404 November 1985 Rev 1 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20076J1961985-10-23023 October 1985 Rev 0 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20135F3161985-08-26026 August 1985 Rev 1 to Emergency Operating Procedures Implementation Plan for Emergency Response Capability Project ML20132E5471985-08-23023 August 1985 Rev 0 to Engineering Svc Procedure 42EN-ENG-011-OS, Scram/ Transient Reporting ML20209F2391985-07-0101 July 1985 Recirculation,Rhr & Reactor Water Cleanup Sys Piping Weld Joint Insp/Mitigation Program for 1985 Maint/ Refueling Outage ML20128A0561985-06-25025 June 1985 Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20126E8331985-06-11011 June 1985 Emergency Plan Implementing Procedures & Deleted Title Sheets,Including Procedures HNP-8007 Re Decontamination of Clothing & Hats & HNP-8004 Re Dosimetry Issuance & Tracking ML20116D4401985-04-23023 April 1985 Revised Emergency Procedures HNP-8109 Re Continuous Air Monitors Models AM-3D & AM-33-1,HNP-8122 Re Radiation Monitor Model RM-16 & HNP-8146 Re Rascal Portable Rate Meter-Scaler/Model PRS-1 Operation & Calibr ML20245B7911985-04-17017 April 1985 Rev 0 to 10AC-MGR-04-0, Deficiency Control Sys. Supporting Documentation Encl ML20107G1421985-02-15015 February 1985 Revised Emergency Implementing Procedures,Including Rev 3 to HNP-8161 Re Eberline Model PCM-1 Portable Monitor Operation & Calibr & Rev 2 to HNP-8036 Re Waste Classification & Manifest Reporting Resin Shipments ML20215F7371984-12-26026 December 1984 Rev 1 to Administrative Control Procedure 40AC-FPX01-0, Fire Protection Program. Portions of Procedures 34AB-OPS-056-1S & 34AB-OPS-056-2S Encl ML20101B0551984-12-17017 December 1984 Rev 5 to Emergency Plan Implementing Procedure HNP-8134, Whole Body Counter Sys ML20108E0921984-11-29029 November 1984 Rev 10 to Procedure Data Package HNP-1-3980-1, Kinemetrics SMA-3 ML20107H5701984-10-31031 October 1984 Detailed Control Room Design Review Program Plan ML20155C8961984-09-30030 September 1984 Rev 1 to Offsite Dose Calculation Manual ML20155C8841984-09-30030 September 1984 Rev 1 to Solid Radwaste Process Control Program ML20098G3401984-09-30030 September 1984 Offsite Dose Calculation Manual ML20098G3381984-09-30030 September 1984 Solid Radwaste Process Control Program ML20108E0741984-06-13013 June 1984 Rev 10 to Procedure HNP-1-3980-M, Seismic Instrumentation Functional Test & Calibr ML20084H4971984-05-0101 May 1984 Rev 0 to Procedures Generation Package for Emergency Operating Procedures,Including plant-specific Technical Guidelines for Units 1 & 2,plant-specific Writers Guide & Implementation Plan for Emergency Response Project ML20086U4131984-02-29029 February 1984 Vendor Equipment Technical Info Program, Per Generic Ltr 83-28,Section 2.2.2,final Draft ML20087N9101984-01-26026 January 1984 Public Version of Transmittal & Title Page to Deleted Emergency Plan Implementing Procedures,Including Procedure HNP-8031 Re Determination of Specific Activity of Spent Resin & Curie Contents of Liner & 840322 Memo ML20087M7911984-01-25025 January 1984 Public Version of Transmittal & Title Pages of Deleted Emergency Plan Implementing Procedures HNP-8019, Insp of Steel Radwaste Shipping Drums & HNP-8422, Handling & Loading of Chem-Nuclear Cask & 840322 Memo ML20087M9321984-01-20020 January 1984 Public Version of Rev 7 to Emergency Plan Implementing Procedure HNP-8101, Teletector Model 6112B/D Operation & Calibr & Jm Felton 840322 Release Memo ML20081B6731984-01-18018 January 1984 Public Version of Rev 0 to Emergency Plan Implementing Procedure HNP-8161, Eberline Model PCM-1 Portal Monitor & Rev 17 to HNP-8008, Radiation Work Permit & Jm Felton 830307 Release Memo ML20087P0191984-01-13013 January 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8038 Re Waste Classification & Manifest Reporting & HNP-8042 Re Radiological Work Practices & 840326 Memo ML20079H9011983-12-0707 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8035 Re Pulmonary Function Screening Program & HNP-8016 Re Shipment of Radioactive Matl ML20093D4881983-10-31031 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including HNP-4858, Naturally Occurring Phenomenon & HNP-8108, Pocket Dosimeter Use & Performance Test. W/831031 & 840709 Release Memo ML20108E0491983-10-28028 October 1983 Rev 4 to Procedure HNP-4858, Naturally Occurring Phenomenon ML20080L0651983-10-12012 October 1983 Rev 1 to Procedure HNP-4848, Determination of Extent of Core Damage Under Accident Conditions ML20081L9461983-10-12012 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4827 Re Offsite Radiological Environ Monitoring During Emergencies & HNP-4852 Re Offsite Dose Estimation 1998-04-30
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. GEORGIA POWER COMPANY l DOCUMENT TYPE: l PLANT E.I. HATCH I RADIATION PROTECTION l PAGE 1 0F 6 DOCUMENT TITLE: l DOCUMENT NUNBER: l REVISION NO:
m AIRBORNE RADIOACTIVITY CONCENTRATION DETERMINATION l 62RP-RAD-009-OS I 1 EXPIRATION DATE: l APPROVALS: ., / ,
l EFFECTIVE DATE:
l DEPT. MGR. ld42MA , DATE .shi!fi l'M/fN GEN. MGR. W 1444- DATE ft '
- //
[
1.0 OBJECTIVE To establish a method for taking air samples and determining the concentration of airborne radioactivity.
2.0 APPLICABILITY This procedure applies to HP/ Chemistry personnel who would take and/or count an airborne sample,
3.0 REFERENCES
3.1 Helgeson " Determination of Concentrations of Airborne Radioactivity," Health .
Physics, Vol. 9, 1963, pp. 931-942. TDC #0502.
3.2 60AC-HPX-006-05 Respiratory Protection Program 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS Personnel should be trained in the use of the selected air sampler and the use of the HP Well Counter.
4.2 MATERIAL AND EQUIPMENT 4.2.1 Selected air sampler 4.2.2 Appropriate filter media 4.3 SPECIAL REQUIREMENTS N/A - not' applicable to this procedure
~
fm FkkIhCK20 050003851205 2 O ""
Q4C f MGR-0002 Rev. 2
~
GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 2 0F 6 DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION N0: ~
AIRBORNE RADI0 ACTIVITY CONCENTRATION DETERMINATION I 62RP-RAD-009-0S l 1 5.0 PRECAUTIONS / LIMITATIONS 5.1 PRECAUTIONS . .
N/A - not applicable to this procedure 5.2 LIMITATIONS N/A - not applicable to this procedure 6.0 PREREQUISITES N/A - not applicable to this procedure f
7.0 PROCEDURE 7.1 GENERAL Although the plant is designed to operate within the limits set forth for airborne activity by 10 CFR 20, there is a possibility that some event may'cause a release of airborne radioactivity to the immediate local plant environment.
Such an occurance could be the result of routine operations or maintenance; for example, welding, grinding or opening a system to tlie atmosphere. In order to increase protection to plant personnel, routine air samples will be taken in O conjunction with area radiation surveys and when any operation or maintenance work is being performed on radioactive material on systems where loose radioactive material may be present.
7.2 DATA ANALYSIS
~~
Due to naturally occurring Radon and Thorium gases in the atmosphere and their particulate daughters being carried directly or indirectly on dusts, air samples normally show significant activity from these isotopes alone. Radon daughters, whose longest half-life is 30 minutes, may be considered as completely decayed four hours af ter completion of sampling. Thoron daughters, whose longest half-life is 10.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, will take approximately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to be considered completely decayed. It is seen, therefore, that for the measured count rate i
without regard to the delay time between stopping and counting the sample, will give highly variable results.
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MGR-0001 Rev. 1
i
PLANT E.I. HATCH l l PAGE 3 0F 6 DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:
AIRBORNE RADI0 ACTIVITY CONCENTRATION DETERMINATION I 62RP-RAD-009-OS l I- E I .
l l l Where an emergency exists, the concentration of l l activity of the contaminant is well above normal l l background trends and can be readily recognized. l 7.2.1 Long lived activity can be estimated by counting the sample four hours af ter sampling (count C1 ) and again 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter sampling (count C2 ). The -
estimated long lived activity count rate (C LLi n counts / min) may then be determined from the following formula:
CLL = C2 - 0.271 Ci 0.729 The use of this formula imposes a delay in obtaining data on the concentration of activity immediately. Therefore, for routine operations the filter samples will be counted immediately af ter collection and the air contamination estimated, assuming all counts on the filter are due to the contaminant.
O 7.2.2 When air samples are taken and the concentrations are used to set stay times for MPC hours for personnel, then if the results are greater than or equal to 2.0 X 10-9 uci/cc, the sample activity should be identified for specific radionuclides. A decay count may be conducted to determine if the sample half-life is k two hours. The sample may also be recounted at four and twenty four hours for further evaluation.
7.3 Install a 2" diameter glass fiber filter, by removing the outer ring and placing the filter paper over the cross-grid support. Where radioiodine or gases are suspected to be present, install a charcoal cartridge in addition to the glass fiber filter.
7.4 Replacef the outer ring by threading clockwise until seal is made between the outer ring, filter paper, and the "0" ring seal.
7.5 Carry the unit to the designated air sampling location and plug into a 115 VAC outlet. .For locations where 115 VAC is unavailable, a battery operated sampler may be used. .
O N6R-0001 Rev. I I
- PLANT E.I. HATCH I l PAGE 4 0F 6
{'
DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:
AIRBORNE RADI0 ACTIVITY CONCENTRATION DETERMINATION 1 62RP-RAD-009-OS I 1 i
1 i
i l NOTES l
. t l l Always try to obtain a breathing zone air sample l ,
4 l if possible. l l l Do not lay air samplers on the floor. l I
l Do not tie off air samplers with the power cord. l
- i l Use a rope to tie off the air sampler. l l Survey the air sampler and cord upon completion l ,
l of sampling. l .,
l Attach the " HASP" printout to Attachment 2 if l l needed. l l Air samples drawn with a charcoal shall be drawn l l at no greater rate than 3 CFM. l 7.6 Turn on the air sampler. .
i
- 7.7 Record the applicable information on an Air Sample Envelope (shown in '
! Attachment 1) or other suitable container.
q 7.8 Turn of f the air sampler af ter a minimum time of: i 15 minutes - Low volume air sampler (Eberline) j 15 minutes - Low volume air sampler (Radeco at 3 cfm) i 7.9 Remove filter and place in Air Sample Envelope or other suitable container. Take
} to laboratory for counting.
i
!' 7.10 Count the charcoal sample for a minimum of 2 minutes and the paper filter for a --
minimum of 5 minutes and note the total counts on the Portable Air Sample Log shown on Attachment 2.
7.11 Transfer all data from the air sample envelope to the Portable Air Sample Log.
Be specific about sample point location.
i 7.12 Calculate"the activity using the appropriate equation and data on Attachment 2.
7.13 If the results of the particulate filter exceeds 25% of the MPC for unidentified ,
air concentrations or 2.0 X 10-9 uC1/cc for all radioactivity, also if the results of the charcoal cartridge exceeds 25% of the MPC for unidentified air ,
concentration's or 2.0 X 10-9 uC1/cc for all radioactivity, the Health Physics Supervisor or his designated alternate should be notified immedir.tely. The particulate filter and charcoal cartridge will be counted tcgether using GeLi detectors to sum the total MPC values and to identify each radionuclide present.
7.14 The results may then be further evaluated as determined necessary by the Health ,
Physics Supervisor, or his designated alternate.
i' MGR-0001 Rev. 1 _ ,
~
. GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 5 0F 6 DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:
cs AIRBORNE RADI0 ACTIVITY CONCENTRATION DETERMINATION l 62RP-RAD-009-OS l 1
( ATTACHMENT 1 l ATTACHMENT PAGE:
1 TITLE: AIR SAMPLE ENVELOPE I 1 0F 1 AIR SAMPLE ENVELOPE -
AIR SAMPLE Sample Location: l UNIT NO l Date l l Sample Conditions:
Sample Taken By:
Sampler Type: l l High Volume l l Planchet l l Low Volume Collector: l l Filter Paper l l Stack l l Charcoal Sample Name l Collection Time: l Monitor Reading l l Date l Time l 1 l l l O Flow Rate l ON l 1 l V I I l 1 Remarks l OFF l l l O
MGR-0009 Rev. I
1
- GEORGIA POWER COMPANY l l PLANT E.I. HATCH l l PAGE 6 0F 6 DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:
/^T AIRBORNE RADI0 ACTIVITY CONCENTRATION DETERMINATION I 62RP-RAD-009-05 l 1
'd ATTACHMENT 2 l ATT/.CHMENT PAGE:
1 TITLE: AIR SAMPLE CALCULATION SHEET l 1 0F 1 UNIT # DATE / /
SAMPLE SAMPLE LOCAil0N TIME (CSTJ, (2) SAMPLE FLOW RATE VOLUME COLLECTED STAY TIME NO. ON OFF TIME (MIN) (CFM OR LPM) (FT OR L) BY HOURS
- 1. ELEY RWPJ -
- TIME TOTAL MIN BKG NET ACTIVITY CALC MPC MPC MPC MPC COUNTING OATA SCALER (CST) COUNT CTD CPM CPM [FF. uC1/cc BY RATIO INERT RATIO RATIO INIT IODINE GASSES PART. TOTAL GROSS BETA GROSS IODINE GROSS ALPHA SAMPLE SAMPLE LOCATION TIME (CST) (2) SAMPLE FLOW RATE VOLUME COLLECTED STAY TIME NO. ON OFF T!ME (MIN) (CFM OR LPM) (FT OR L) BY HOURS
- 2. ELEV RWP#
TIME TOTAL MIN BKG NET ACTIVITY CALC MPC MPC MPC MPC COUNTING DATA SCALER (CST) COUNT CTO CPM CPM EFF. uC1/cc BY RATIO INERT RATIO RATIO INIT IODINE GASSES PART. TOTAL GROSS BETA GROSS IDDINE GROSS ALPHA I SAMPLE SAMPLE LOCATION TIME (CST) (2) SAMPLE FLOW RATE VOLUME COLLECTED STAY TIME w/ NO. ON OFF TIME (MIN) (CFM OR LPM) (FT OR L) BY HOURS
- 3. ELEV RWP#
TIME TOTAL MIN BKG NET LCTIVITY CALC MPC MPC MPC MPC C0JNTING DATA SCALER (CST) COUNT CTO CPM CPM EFF. uC1/cc BY RATIO INERT RATIO RATIO INIT IODINE GASSES PART. TOTAL GROSS 8 ETA GROSS IODINE -
GROSS ' ALPHA SAMPLE ' SAMPLE LOCATION TIME (CST) (2) SAMPLE FLOW RATE VOLUME COLLECTED STAY TIME ~
NO. ON OFF TIME (MIN) (CFM OR LPM) (FT OR L) BY HOURS
- 4. ELEY RWPJ TIME TOTAL MIN BKG NET ACTIVITY CALC MPC MPC MPC MPC COUNTING DATA SCALER (CST) COUNT CTD CPM CPM EFF. uC1/cc BY RATIO INERT RATIO RATIO INIT IODINE GASSES PART. TOTAL GROSS BETA
. GROSS IODINE GROSS ALPHA CALCULATIONS FOR DERIVING ACTIVITY IN uC1/cc (2) MINIMUM SAMPLE TIME: LOW VOLUME PARTICULATE LOW VOLUME CHARCOAL (a) Eberline LV 15 minutes (NET CPM) (4.5 X 10-10) (NET CPM) (4.5 K 10-10)
(b) Radeco: 15 min. at 3 cfm (VOLUME IN LITERS) (EFF) (VOL. IN LITERS) (EFF) (.999)
A NOTE: Man, sample rate when using charcoal is 3 cfm.
3 cfm = 85 Lpm HPX-0213 Rev. O MGR-0009 Rev. I
- l. Georgin Power Comp:ny J. Post Offics 8:x 439 j , ,hl:y, Georgis 31513 Telephone 912 367-7781 912 537-9444 i
GeorgiaPbwer i Edwin I. Hatch Nuclear Plant i
December 5, 1985 LR-ADM-003-1285 PLANT E. I. HATCH Emergency Implementing Procedures Docket Nos. 50-321/50-366 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555 l
l Gentlemen:
Pursuant to Appendix E,Section V of 10 CFR 50, please find enclosed two l (2) copies of the latest revisions to the Plant E.I. Hatch Emergency Impic.menting Procedures. Three (3) copies of these procedures are also being l forwarded to the Region II office in Atlanta, Georgia.
l E. C. Sorrell Document Control Supervisor ECS/klm xc: U.S.N.R.C./ Region II w/3 l J.P. O'Reilly/GPCo w/0 file i'
mWr I g l
I' i