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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20198J5641998-01-0707 January 1998 Unit 2 Pressure & Temp Limits Rept ML20198J5531998-01-0707 January 1998 Unit 1 Pressure & Temp Limits Rept ML20198P6591997-12-31031 December 1997 .0 Volt IPC Full Cycle Operation Technical Basis Supplement to 'Braidwood Unit 1 Cycle 7 Interim Plugging Criteria Rept,Aug 1997.' ML20210P8611997-08-31031 August 1997 Cycle 7 Interim Plugging Criteria Rept ML20141K0371997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0431997-05-21021 May 1997 Pressure & Temp Limits Rept ML20148P8811997-05-16016 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble B Credit ML20141G6361997-05-15015 May 1997 Interim Plugging Criteria Return to Power Rept ML20138H0001997-04-28028 April 1997 Locked Tube Tts Circumferential Indication Root Cause Determination Evaluation ML20134M3131996-11-13013 November 1996 Revised SG Tube Rupture Analysis for Byron/Braidwood ML20134N3131996-10-31031 October 1996 Sys Design Description for Containment Spray ML20134N8011996-10-31031 October 1996 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20116H1461996-08-0101 August 1996 Cycle Length Assessment Rept Addendum ML20112B8521996-05-17017 May 1996 Cycle Length Assessment Rept Suppl ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20106G5891996-04-30030 April 1996 Training Dept Braidwood Simulator 1996 Certification Rept ML20100R7371996-02-29029 February 1996 Cycle 6 Interim Plugging Criteria 90 Day Rept ML20094K6101995-11-30030 November 1995 Interim Plugging Criteria Return to Power Rept ML20093G7171995-10-12012 October 1995 Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test ML20093G8821995-10-11011 October 1995 Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3 ML20092A9731995-09-0101 September 1995 Independent Verification of Byron/Braidwood D4 SG Tube Support Plate Differential Pressures During Mslb ML20091M8711995-08-25025 August 1995 Rept of Independent Assessment of Calculation of TSP Forces ML20084V2101995-06-0909 June 1995 Interim Plugging Criteria 90 Day Rept ML20078P1551995-02-0606 February 1995 Probability of Detection by Bobbin Insp ML20078R1161994-11-15015 November 1994 Non-proprieatry NFSR-0090, Response to Nuclear Regulatory Staff Request for Addl Info on VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20077N0131994-09-30030 September 1994 Rev 2 Evacuation Time Estimates within Plume Exposure Pathway Emergency Planning Zone for Braidwood Nuclear Generating Station ML20149H1591994-06-30030 June 1994 Spent Fuel Rack Criticality Analysis Considering Boraflex Gaps & Shrinkage ML20106G5961993-06-0202 June 1993 Simulator Malfunction Cause & Effects ML20128E8871992-11-30030 November 1992 Environmental Qualification of Okonite Tape Splice (T-95/No 35) Under Local Submergence for Power & Control Applications, Calculation Rept ML20127L0091992-09-0808 September 1992 Rev 0,to VIPRE/WRB-2 DNBR Thermal Limit for Westinghouse 17x17 Ofa & Vantage 5 Fuel ML20064N8021991-07-27027 July 1991 Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20101F5631991-07-0303 July 1991 Byron/Braidwood Unit 1 Rhr/Safety Injection Piping Water Hammer Acoustic Analysis ML20065D6601991-02-28028 February 1991 Heatup & Cooldown Limit Curves for Normal Operation Braidwood Unit 2 (Capsule U) L-90-469, Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation1990-10-31031 October 1990 Byron/Braidwood Units 1 & 2 Increased Main Steam Safety Valve Setpoint Tolerance Safety Evaluation ML20065D6501990-08-31031 August 1990 Heatup & Cooldown Limit Curves for Braidwood Unit 1 Reactor Veesel (Capsule U) ML20042E9131990-03-31031 March 1990 Nonproprietary Rev 1 to Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20247E4521989-07-13013 July 1989 Units 1 & 2 Suppl 1 to Response to NRC Concern 7 ML20247E4811989-07-11011 July 1989 Units 1 & 2 Suppl 1 to Sargent & Lundy Rept Dtd 890630, Response to NRC Concern 8,Environ Qualification of Class 1E Control Circuits Terminated at Marathon 1,600 Nuc Terminal Boxes ML20247E4671989-06-30030 June 1989 Units 1 & 2 Response to NRC Concern 8, Environ Qualification of Class 1E Control Circuits Terminated at Marathon 1,600 Nuc Terminal Boxes ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247E4451989-06-26026 June 1989 Units 1 & 2 Response to NRC Concern 7 ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20248C0051989-05-31031 May 1989 Engineering Study on Control Room Integrity Test Requirement 1999-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
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$ Federal Emergency Management Agency Washington, D.C. 20472 f
November 15, 1985 ICLICY STATEMENT ON RESPIRAIORY PROI1DCTION The Federal Emergency Managenent Agency (FEMA) has been ordered by the Braid-wood Station Atanic Safety and Licensing Board (ASLB) to file a written expla-nation on how the Agency interprets the phrase, " respiratory protection," as used in NUREG-0654/ FEMA-REP-1, Rev.1, section G.l.c. This policy statement contains fem's explanation of respiratory protection as used in this section.
Background
The use of " respiratory protection" .in G.1.c. is addressed within the context of disseminating information to the public on protective measures to be used during a radiological energency. Information on protective measures is provided to the public through various means such as prepared materials and ptblic meetirgs. The focas of the ALSB's discussion on respiratory protec-tion is on the content of Com1onwealth Edison's emergency information brochure for Braidwood. The specific issue raised is whether or not the brochure should contain an explicit reference to respiratory protection since it does not at the present time.
Issue Definition FEMA's answer to the Braidwood ASLB is provided through answers to these questions:
o In NUREG-0654/ FEMA-REP-1, Bev.1, is respiratory protection equated with sheltering and evacuation?
o What is the context of G.l.c. for providing public information on respiratory protection?
o Is the larguage in G.l.c. a reconmendation or a mandate that respira-tory protection be incitded in brochures?
Since the concerns raised by the ASLB are limited to providing information to the public, the policy provided in this statement does not pertain to the use of respiratory protection by emergency workers.
Interpretation of Language in G.I.c. on Respiratory Protection As stated, FEMA's policy on respiratory protection is provided below through answers to the posed questions.
- 1. In NUREG-0654/ FEMA-REP-1, is respiratory protection equated with sheltering and evacuation?
Ingically, both evacuation and particularly sheltering of fer mme degree of respiratory protection. Further, respiratory protection is closely related to sheltering and evacuation in that it may sucolenant either of these latter two 8512260044 e51219 PDR ADOCK 05000456 G PDR
r actions by serving a ccmnon function to all protective measures in preventing or minimizing the inhalation of certain types of airborne radioactive materials. It is noteworthy, however, that both evacuation and sheltering offer protection on a much broader range.
In a specific sense, respiratory protection is a type of protective measure distinct from either sheltering or evacuation. His is reflected in how the phrase is used in G.l.c. and E.7. In G.l.c., respiratory protection is listed as one of four distinct types of protective neasures, i.e., evacuation, shelterirg, radioprotective drugs and respiratory protection. In E.7. , an exanple (handkerchief over mouth) is provided.
Reference is also made at the end of evaluation criterion E.7. to guidance on respiratory protection published by the American Industrial Hygiene Asso-ciation (AIHA). An examination of the AIHA guidance shows that respiratory protection is discussed through the use of ccumon household and personal items (e.g., hankerchiefs and towels) to reduce the inhalation of airborne toxic materials including radioactive materials.
- 2. What is the context of G.l.c. for providing public information on respira-tory protection?
Were are two contexts in NURD3-0654/PEMA-REP-1, Rev.1 in which the provision of information to the public on respiratory protection is addressed. In G.l.c.,
the context is the anrual dissmination of information to the pi1>l1c such as information comonly provided through brochures. In E.7., the context is the provision of information durirg an mergency through the Emergency BroaJeast System (EBS). R us, it is clear that in G.l.c. the context for providing public information is the repetitive distribution of prepared materials on at least an annual basis as distinct from the content of EBS nessages provided at the time of an actual radiological emergency. m ile the specific type and form of disseminated materials is not specified in G.l.c., the most ccmton method for accanplishing su:h a dissnination is through mergency information brochures that are developed through a coordinated effort by licensees and State and local goverrments.
- 3. Is the language in G.l.c. a reconmendation or a mandate that respiratory protection measures be included in brochures?
De intent of the larguage in G.l.c. is to set forth the types of topic coverage considered essential for incorporation into public information materials. 21s is expressed in the phrase, "his information shall include
. . . ." Rus, it is necessary to include inforTretion on protective measures in these materials. With respect to addressirg specific types of protective neasures, the intent of the language in G.I.c. is structured to suggest various trotective measures or conponents of protective neasures that may be included in these materials. B is is expressed in the abbreviation, "e.g."
which means "for example." inis intent is further witnessed by the two references (" evacuation routes" and " relocation centers") to components of evacuation. Rese two references, like the other references within this level of G.l.c., are provided as illustrative topics that nay be used in discussiry protective measures.
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While infonnation on protective measures in general nust be included in brochures, it is not required that information specific to a form of respira-tory protection be included. However, if the information is included, it must be consistent with the governing emergency plan for the area. Protective actions information included in the brochure, like all the information in the brochure, is required to be a reflection of the public policy for protective actions. A jurisdiction might feel that a particular action is not acceptable.
Thus requiring information within the brochure on protective actions not interded for general use within jurisdictions might confuse rather than inform.
Consistent with the above, the inclusion of information on each of the indi-vidual types of protective measures is not mandated in G.l.c. Pbreover, the absence of language on respiratory protection in brochures will not constitute a basis per se for FEMA to irdicate a planning inadequacy. However, FEMA recemnends that the brochures reflect language on protective measures contained in the energency response plan.
Conclusion Wille not specifically mandated in NUREG-0654/ FEMA-REP-1, Rev.1, FEMA recon-mends that language on respiratory protection be incorporated in brochures.
As stated, the absence of language on respiratory protection in brochures will rnt constitute a basis per se for FEMA to indicate a plannirg inadequacy.
We are more concerned, in reviewing brodiures, that references to protective neasures be couched in a manner that help persons to be prepared to take specific types of protective actions but yet cautions than to listen to EBS messages in order to follow the specific protective actions recomended for the particular accident circumstances.
APPROVED J
Assistant Kssocia'te Director Office of Natural and Technological Hazards Program State and Iocal Prograns and Support Directorate