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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
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DAVIS-BESSE REVISION COVER SHEET January 5, 1984 l DATE TO: // >_ > N 1226 FROM: EMERGENCY PLANNING 4 PREPAREDNESS SUPV.
SUBJECT:
Davis-Besse EMERGENCY PLAN SUPPORTING PROCEDURES Manual Changes This letter transmits additions and revisions to the Davis-Besse EMERGENCY PLAN SUPPORTING PROCEDURES Manual. Control Copy M M .
Instructions for the material are as follows:
REMOVE AND RETURN INSERT Revision Index, Revision 197 Ravision Index, Revision 198 Admin. Memo. No. 41, Revision 29 Admin. Memo No. 41, Revision 30 I
Date Revision Entered Addressee Signature RETURN TO THE OFFICE MANAGER - STOP #3050 8401300333 840125 n.
PDR ADOCK 05000346 F PDR
i i
4 E
DAVIS-BESSE REVISION COVER SHEET January 11, 1984 l
DATE To: / 5A.) D-/ WS0 v
FROM: EMERGENCY PLANNING & PREPARDNESS SUPV.
SUBJECT:
Davis-Besse EMERGENCY PLAN SUPPORTING PROCEDURES Manual Changes
- This letter transmits additions and revisions to the Davis-Besse 8
EMERGENCY PLAN SUPPORTING PROCEDURES Manual. Control Copy M M .
Instructions for the material are as follows:
4 REMOVE AND RETURN INSERT Revision Index, Revision 198 Revision Index, Revision 199 l
AD 1827.04.2 AD 1827.04.3 I
i 3
1 l
i j
Date Revisica Entered i
Addressee Signature i
RETURN TO THE OFFICE MANAGER -
STOP #3050
THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN SUPPORTING PROCEDURES REVISION INDEX Page Revision Procedures Revision Temporary Modifications i 7 HP 1602.01 15 HP 1604.01 5 HP 1604.02 0 AD 1827.01 4 AD 1827.02 10 AD 1827.03 3 AD 1827.04 2 AD 1827.05 2 AD 1827.06 2 T-7248 AD 1827.07 3 T-7480 AD 1827.08 2 AD 1827.09 2 AD 1827.10 13 AD 1827.11 5 AD 1827.12 10 AD 1827.13 6
.f AD 1827.15 5
' AD 1827.16 2 AD 1827.17 T h~-
AD 1850.04 7 AD 1850.05 7 AD 1850.06 2 Administrative Memotandums Revision No. 37 ECS Pager and Telephone Numbers 31 No. 38 First Aid Team 12 No. 39 Fire Brigade 16 No. 41 Emergency Duty Officer (EDO) 30 No. 42 Radiation Monitoring Teams (RNT) 20 Revision 198 o- . January, 1984 l __
l
oATE INTRA-COMPANY MEMORANDUM Eo s214 2 Deca her 23. 1981 Rev. 10 Page 1 All Davis-Besse Station Personnel PROM Terry Murray TW %Ihq"
- SU3 JECT Emergency Duty Officer (EDO) and Other Emergency Duties ._
ADMINISTRATIVE MEMORANDUM NO. 41-30
- 1. Emergency Duty Officers (ED0's) 1.1 In accordance with the Davis-Besse Emergency Plan, the following named individuals are qualified and designated as Emergency Duty Officers:
C. T. Daft S. A. Hall R. R. Durdel D. A. Huffman J. A. Faris D. L. Rhodes J. L. Freels R. F. Peters B. L. Geddes J. H. Syrowski C. J. Greer J. L. Scott-Wasilk L. A. Grime S. G. Wideman 1.2 Emergency Duty Officers, in addition to the requirements in the Station Emergency Plan, are responsible for the administrative items as given in Section 5 of EI 1300.12 Administrative Controls.
1.3 The following persons have been trained and are qualified as Emargency Assistants, to assist the EDO in the Emergency Control Center (ECC), if necessary.
Gary Downing Rex Rutledge Richard Vollmar Joyce Lingenfelter Larry Konopka Rick Sharpe Debra Goetz Marie Frazer James Adams Dennis Gordon Charles Rupp Kelly Nash Jeff Lieczow
- 2. Other Emeraency Duties 2.1 The Station Superintendent or his designee is to be notified by the Shift Supervisor of any condition which requires an immediate report and/or notification t;o the NRC.
- 3. EDO Schedule A revised EDO schedule for the first quarter of 1984 is attached.
TDM:nif enc 1.
Admin. Memo No. 41-30 Rev. 30 - Dec. 23, 1983 Attachment Page 2 EDO 1st QUARTER SCHEDULE - 1984 Weekly Dates Individual Assigned Nov. 28 -
Dec. 05 Don Rhodes Dec. 05 -
Dec. 12 *Ron Durdel Dec. 12 -
Dec. 19 Jim Freels Dec. 19 -
Dec. 26 Bob Peters Dec. 26 -
Jan. 02 Jim Faris Jan. 02 -
Jan. 09 *Stu Hall Jan. 09 -
Jan. 16 Chuck Daft Jan. 16 -
Jan. 23 Larry Grime Jan. 23 -
Jan. 30 Jim Greer Jan. 30 -
Feb. 06
Feb. 13 Dave Huffman Feb. 13 -
Feb. 20 Bruce Geddes Feb. 20 -
Feb. 27 Jim Faris
'Feb. 27 -
Mar. 05
Mar. 12 Jim Syrowski -
Mar. 12 -
Mar. 19 Steve Wideman Mar. 19 -
Mar. 26 Bob Peters Mar. 26 -
Apr. 02 Ron Durdal
- Denotes that week in which the EDO must perform the Monthly Communications Link Test, in accordance with PT 5108.01. The Emergency Planning Group will be present to assist with the Communications Test each month.
RRD:nif 12/23/83 I
~
' THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN SUPPORTING PROCEDURES REVISION INDEX Page_ Revision Procedures Revision Temporary Modification i 7 HP 1602.01 15 HP 1604.01 5 HP 1604.02 0 AD 1827.01 4 AD 1827.02 10 AD 1827.03 3 AD 1827.04 3 AD 1827.05 2 AD 1827.06 2 T-7248 AD 1827.07 3 T-7480 AD 1827.08 2 AD 1827.09 2 AD 1827.10 13 AD 1827.11 5 AD 1827.12 10 AD 1827.13 6 J. - , AD 1827.15 5 AD 1827.16 2 AD 1827.17 F--
AD 1850.04 7 AD 1850.05 7 ~
AD 1850.06 2 Administrative Memorandums Revision No. 37 ECS Pager and Telephone Numbers 31 No. 38 First Aid Team 12 No. 39 Fire Brigade 16 No. 41 Emergency Duty Officer (EDO) 30 No. 42 Radiation Nbnitoring Teams (RMT) 20 Revision 19e '
. AD 1827.04 Davis-Msse Nuclear Power Station Unit No. 1 Administratise Procedure AD 1827.04 Overexposure / Internal Contamination hai i Record of Approval and Changes
' Prepared by C Dovel/W. Green 1/13/76 Date Submitted by A LL b 9 W _2/38/76 Date ction Head
~
Reco mended by V//-
'~
SRB Chairman Date QA Approved OM ^ O 2' '
M
~
Manage o 'liff-issurance Date Approved by _ [
' Station Superintendent Date Kevision SRB QA Sta. Supt.
No. Re ommendation Date -
roved Date Approved Date f p/f f //q/fo ;~ )_ 9 2-es-s> p p_ =_- 2//s-/5b g fMC : g }s3}$1. T h I' 3 pysy v.m c-24p ww wm *'"
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1 AD 1827.04.3
- 1. PURPOSE To describe the actions necessary to investigate, treat and report the overexposure of an individual at Davis-Besse Nuclear Power Station (DBNPS) due to radiation. Overexposure is defined as any internal or external radiation exposure where the whole body dose is in excess of permissable limits set forth in 10 CFR 20.
- 2. REFERENCES 2.1 10 CFR 20, " Standards for Protection Against Radiation" 2.2 Davis-Besse Station Radiation Protecticn Manual 3l 2.3 Deleted 2.4 FSAR Section 12 2.5 HP 1602.01, " External Personnel Radiation Monitoring" 2.6 HP 1605.06, "Whole Body Counting" 2.7 AD 1807.00, " Control of Conditions Adverse to Quality" 2.8 AD 1804.00, " Report Management - - - - - - - - - - - - - -
2.9 TEco NQAM ..
- 3. RESPONSIBILITIES 3.1 General 3 Each person who works at the DBNPS shall be responsible for complying with the requirements of HP 1602.01, " External Personnel Radiation Exposure Monitoring" for personnel radiation exposure.
Should any person suspect that he has been subjected to overexposure, he shall immediately notify a member of the Chemistry and Health Physics Section.
3.2 Chemist and Health Physicist 3.2.1 Conduct final overexposere investigation if indeed it is determined by Health Physics personnel that an overexposure did occur.
3.2.2 Coaplete " Report of Overexposure Investigation",
(Enclosure 1).
3.2.3 Submit applicable reports to the NRC as defined in 10 CFR 20.403, 20.405(a), and 20.405(b).
2 AD 1827.04.2 3.2.4 Initiate an Action Item Report if required in accordance with AD 1807.00, "Centrol of Conditions Adverse to Quality".
3.3 Chemistry and Health Physics Section Conduct the initial investigation of reports of overexposure to verify the incident and determine the need for further action and investigation as directed by the Chemist-Health Physicist.
- 4. PROCEDURE 4.1 External Exposure 4.1.1 An over-external exposure is defined when it is known ,
or suspected that an individual has been exposed in !
excess of the limits specified by 10 CFR 20.101, an immediate investigation will be conducted by Chemistry-Health Physics Section personnel and such reports or notifications as required by 10 CFR 20 will be submitted.
2 If an exposure comes within the definition of 10 CFR 20.403(a), the Station Superintendent will contact the company's radiation medical emergency consultant for their rectemendations.
4.1.2 Routine external radiation monitoring (which will be the indicator that an overexposure has occurred) is described in HP 1602.01, External Personnel Radiation Monitoring Program.
4.2 Internal Exposure 4.2.1 If an over-exposure resulting from internal contamination is known or suspected in excess of the limits specified by 10 CFR 20.103, an investigation will be conducted in accordance with HP 1605.06.
- 1. The services of the company's radiation medical emergency consultant may be utilized to determine the magnitude of any excessive exposure, its cause, and effective preventive measures.
2
- 2. If the amount of radioactive material in the body exceeds 10% MPOB, a dose assessment should be performed,
- 3. If there is a reasonable probability that any individual incurred an internal deposition of 2 one or more radionuclides exceeding 520 MPC-hours the Station Superintendent will contact the
3 AD 1827.04.2 company's radiation medical emergency consultant for their recommendations.
4.2.2 Routine internal monitoring of contamination, (which vill detect if an over-exposure resulting from internal contaminatica has occurred) will be performed as described below.
hhole Body Counting
- 1. Yearly whole body counts will be taken on selected station personnel.
- 2. Selection of the individuals for whole body counting shall include at least 25% of the personnel assigned to the station.
4
- 3. Criteria used for selecting individuals will be quarterly whole body exposure records and work history in airborne radioactivity areas.
- Tritium Monitoring
- 1. Urinalyses for tritium will be performed for i selected station personnel.
- 2. On a quarterly basis, a bioassay for tritium will be collected from individuals who have been working in areas where there could be a potential for inhaling tritium.
NOTE: During periods when the Refueling Canal is filled, urine samples for tritium should be collected from selected indi-
. viduals every two (2) weeks.
4.3 Records 4.3.1 If the limits specified in 10 CFR 20.403, .405, have been or are likely to be reached, the Region III Director of the NRC shall be notified.
4.3.2 The Chemist & Health Physicist shall be responsible for initiating the Report of Over-Exposure form.
l r
. _ . _ - _ _ _ _ - . - _ . -_ _ = . _ . .
0 4 AD 1827.04.0 REPORT OF OVEREXPOSURE (Over-exposure resulting from internal or external radiation exposure)
Name Date i
Soc. Sec. No. Job Title Date & Time of Possible Overexposure i
Location Exposure Occurred
, REP No.
4 Type of Work or Operation at Time of Exposure
.i How did Exposure Occur Why did Exposure Occur Was Employee Injured Yes No Describe Medical Treatment Required e
Damage to Equipment Type of Exposure Involved:
Whole Body Other Skin Radionuclides Hands & Forearms l Feet & Ankles Internal Survey of Exposure Location: By Title
. Gen. Bkgd. mR/hr Hot Spot (s) mR/hr i
Enclosure 1 Sheet 1 of 3 l
,, - . , . . _ _ ,- . _.y , ,
5 AD 1827.04.0 Air Activity pCi/cc Hot Spot (s) mR/hr Contamination: Surface dpe/100 cm 2 Dosimeters Readings mR-Ser#
mR-Ser#
Evaluation of TLD: Beta mR Gamma mR Beta & Gamma mR 1
Neutron Exposure Were Na.,al Swipes Taken Results Was Sputum Analyzed Results l
Was Whole Body Counter Utilized (Attach scan to this report) l l
Bioassay Program Begun l Final Disposition:
Did overexposure occur Yes No (If yes, initiate NCR)
Total Dose Assigned for Period to Whole Body (External) (Internal)
Skin Extremities Other Future Radiation Exposure Limitations Future Clinical Radiation Data Required From Title 10 CFR 20 " Standards for Protection Against Radiation";
20.403 and 20.405 - is an NRC notification and report to Regional Compliance Required Yes No Enclosure 1 Sheet 2 of 3
l 6 AD 1827.04.2
' Has 520 MPC-hours in a 13 week period been exceeded?
Yes No If the answer to either of the above questions is yes, contact the company's radiation medical emergency consultant, and complete report NP-02 as required in accordance with AD 1804.00, " Reports Management".
NRC Region III Telephone (Days, Nights, Sundays & Holidays) - 312-858-2660 Who made telephone call Time Date To whom call was made Capacity Date and Time of Telegram Confirmation To whom telegram sent Capacity Date and Time 30 day written report mailed To whom report sent Capacity Was report Mailed Registered Return Receipt?
(Attach copy of report, telegram statement, and phone conversation to this investigation.)
Signatures of Personnel Making Investigation:
Name Title Date Naue Title Date Name Iitle Date Chemistry & Health Physicist Signature Date Station Superintendent Signature Dace l
Enclosure 1 END Sheet 3 of 3 ;
l i