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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20138K0131997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970324-28 ML20138K0091997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20135E7161997-03-0303 March 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961118-22 ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 ML20134M2471997-02-14014 February 1997 Submits List of Plants Not Meeting Selection Criteria for Ti 2515/118 Insp on Basis of Factors Such as SWS Operating Experience,Contribution of SWS to Plant Risk Assessment, Licensee Programs in Response to GL-89-13 ML20135F6941996-11-27027 November 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of Atomic Safety & Licensing Board Terminating Proceedings in Docket Has Expired.W/Certificate of Svc.Served on 961127 ML20128L7761996-10-10010 October 1996 Notification of 961023 Meeting W/Wppss,Energy Facility Site Evaluation Council & State & Local Govt Agencies in Elma,Wa to Discuss Proposed Termination of CP & OL Application for Plant ML20236U9391995-12-20020 December 1995 Discusses Oi,Region IV Rept of Investigation,Dtd 940511, Case 5-93-023R,which Reported OI Investigative Efforts Re Alleged Employee Discrimination at Plant Units 1,2 & 3.Rept Was Sent to Us Attorney Office in Phoenix,Az in May 1994 ML20138F9871994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by IA-96-341, Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr1994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20198E3271992-10-20020 October 1992 Notification of Significant Licensee Meeting W/Util on 921027 to Discuss Transfer of Fire Watch Responsibilities to Security Dept & Ongoing Programs within Security Dept ML20126L8441992-09-14014 September 1992 Provides Status Rept Concerning Actions Re Det Performed at Plant ML20127C2461992-03-0202 March 1992 Forwards AEOD SALP Input for Facilities in Support of Ongoing SALP Reviews.Two of Six Important Operating Events Involved Deficiencies of Reactor Power Cutback Sys Which Relies on Proper Functioning of Steam Bypass to Condenser IA-92-218, Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility1990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B6281990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B5671990-12-12012 December 1990 Forwards NRR Input for SALP Rept,Per NRC Ofc Ltr 907,Rev 1 ,NRC Manual Chapter 0516 & 901120 Memo ML20058C2811990-10-26026 October 1990 Summary of 901018 Meeting W/Util Re Potential Restart of Units 1 &/Or 3 ML20059M2041990-09-27027 September 1990 Notification of Significant Licensee Meeting W/Util on 901003 to Discuss Licensee Response to Diagnostic Evaluation Team Findings & Overall Status of Programs. Addl NRC Attendees Should Be Made Known by 901002 ML20059L6531990-09-20020 September 1990 Notification of 900921 Meeting W/Util in Walnut Creek,Ca to Discuss Licensee Initiatives & Status in Area of QA ML20059D6361990-08-27027 August 1990 Notification of 900831 Enforcement Conference W/Util in Walnut Creek,Ca to Discuss Medical Qualifications & Exams of Licensed Operators ML20127B4571990-08-24024 August 1990 Comments on Response to Facility Diagnostic Evaluation Team Rept.Suggests That Region V Followup & Closely Monitor Development & Implementation of Specific Tasks Which Will Address Team Findings ML20058M3441990-08-0606 August 1990 Forwards List of Open Items in Sims for Plant.Documented Basis Exists for Closure of TMI Related Items at Plant ML20126L8271990-06-14014 June 1990 Provides Summary of Schedule & Status of Items Re Det of Plant Performed by Aeod,In Response to 900314 Memo ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20127B2171990-01-18018 January 1990 Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989 ML20127B1681989-11-0909 November 1989 Forwards NRR Input to SALP for Facilities.Category 2 Rating Assigned in Functional Areas of Plant Operations, Radiological Controls,Emergency Preparedness,Security & Safety Assessment/Quality Verification ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N7371989-08-29029 August 1989 Notification of Maint Team Insp Meeting on 890901 W/Util in Phoenix,Az to Discuss Status of Licensee Commitments from 890605 Mgt Meeting in Consideration of Unit 3 Restart ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20127B1401989-08-0707 August 1989 Forwards for Info & Consideration for Info Notice,Lers Describing Potter & Brumfield Relay Problems & Atmospheric Dump Valve Deficiencies.Info Provided as Part of AEOD Function to Identify Potential Adverse Events ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart 1999-08-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A8641999-10-0606 October 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990829-0903 ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20138K0091997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (as-given Operating Exam) for Tests Administered on 970324-28 ML20138K0131997-05-0606 May 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970324-28 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20135E7161997-03-0303 March 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961118-22 ML20134P2231997-02-20020 February 1997 Discusses Ti 2515/122 Evaluation or Rosemount Pressure Transmitter Performance & Licensee Enhanced Surveillance Programs multi-plant Action B-122 ML20134M2471997-02-14014 February 1997 Submits List of Plants Not Meeting Selection Criteria for Ti 2515/118 Insp on Basis of Factors Such as SWS Operating Experience,Contribution of SWS to Plant Risk Assessment, Licensee Programs in Response to GL-89-13 ML20135F6941996-11-27027 November 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of Atomic Safety & Licensing Board Terminating Proceedings in Docket Has Expired.W/Certificate of Svc.Served on 961127 ML20128L7761996-10-10010 October 1996 Notification of 961023 Meeting W/Wppss,Energy Facility Site Evaluation Council & State & Local Govt Agencies in Elma,Wa to Discuss Proposed Termination of CP & OL Application for Plant ML20236U9391995-12-20020 December 1995 Discusses Oi,Region IV Rept of Investigation,Dtd 940511, Case 5-93-023R,which Reported OI Investigative Efforts Re Alleged Employee Discrimination at Plant Units 1,2 & 3.Rept Was Sent to Us Attorney Office in Phoenix,Az in May 1994 ML20138F9871994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by IA-96-341, Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr1994-08-0303 August 1994 Discusses Allegation RV-94-A-0004,Songs Vendor Manuals. Licensee Reviewed Allegation,Concluded Unfounded & Notified NRC for Conclusion by 940228 Ltr ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20198E3271992-10-20020 October 1992 Notification of Significant Licensee Meeting W/Util on 921027 to Discuss Transfer of Fire Watch Responsibilities to Security Dept & Ongoing Programs within Security Dept ML20126L8441992-09-14014 September 1992 Provides Status Rept Concerning Actions Re Det Performed at Plant ML20127C2461992-03-0202 March 1992 Forwards AEOD SALP Input for Facilities in Support of Ongoing SALP Reviews.Two of Six Important Operating Events Involved Deficiencies of Reactor Power Cutback Sys Which Relies on Proper Functioning of Steam Bypass to Condenser ML20127B6281990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility IA-92-218, Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility1990-12-31031 December 1990 Forwards Updated Status Rept on Actions Re Diagnostic Evaluation Performed at Facility ML20127B5671990-12-12012 December 1990 Forwards NRR Input for SALP Rept,Per NRC Ofc Ltr 907,Rev 1 ,NRC Manual Chapter 0516 & 901120 Memo ML20058C2811990-10-26026 October 1990 Summary of 901018 Meeting W/Util Re Potential Restart of Units 1 &/Or 3 ML20059M2041990-09-27027 September 1990 Notification of Significant Licensee Meeting W/Util on 901003 to Discuss Licensee Response to Diagnostic Evaluation Team Findings & Overall Status of Programs. Addl NRC Attendees Should Be Made Known by 901002 ML20059L6531990-09-20020 September 1990 Notification of 900921 Meeting W/Util in Walnut Creek,Ca to Discuss Licensee Initiatives & Status in Area of QA ML20059D6361990-08-27027 August 1990 Notification of 900831 Enforcement Conference W/Util in Walnut Creek,Ca to Discuss Medical Qualifications & Exams of Licensed Operators ML20127B4571990-08-24024 August 1990 Comments on Response to Facility Diagnostic Evaluation Team Rept.Suggests That Region V Followup & Closely Monitor Development & Implementation of Specific Tasks Which Will Address Team Findings ML20058M3441990-08-0606 August 1990 Forwards List of Open Items in Sims for Plant.Documented Basis Exists for Closure of TMI Related Items at Plant ML20126L8271990-06-14014 June 1990 Provides Summary of Schedule & Status of Items Re Det of Plant Performed by Aeod,In Response to 900314 Memo ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20127B2171990-01-18018 January 1990 Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989 ML20127B1681989-11-0909 November 1989 Forwards NRR Input to SALP for Facilities.Category 2 Rating Assigned in Functional Areas of Plant Operations, Radiological Controls,Emergency Preparedness,Security & Safety Assessment/Quality Verification ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N7371989-08-29029 August 1989 Notification of Maint Team Insp Meeting on 890901 W/Util in Phoenix,Az to Discuss Status of Licensee Commitments from 890605 Mgt Meeting in Consideration of Unit 3 Restart ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20127B1401989-08-0707 August 1989 Forwards for Info & Consideration for Info Notice,Lers Describing Potter & Brumfield Relay Problems & Atmospheric Dump Valve Deficiencies.Info Provided as Part of AEOD Function to Identify Potential Adverse Events ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys 1999-08-27
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L JUN 211985 Memorandum For: LeMoine J. Cunningham, Chief, Section 2
. Operating Reactor Programs Branch, IE i
From: Frank A. Wenslawski, Chief Emergency Preparedness and Radiological Protection Branch, RV
Subject:
Proposed Emergency Preparedness (EP) Preoperational Procedures
-A May 8, 1985 memorandum from James G. Partlow, subject as above, transmitted a series of eight (8) draft EP PREOP for our comments. . Attached are our comments as requested by the May 8 memorandum.
Region-V strongly believes that the_EP inspection program should.be similar to the other IE' inspection programs. The' proposed creation of several procedures using the standard format to address the items to be covered during the
.preoperational inspection effort is a significant improvement over the previous _ single procedure (TI 2513/55). Based on our review of these draft
~
procedures, it appears that the' items to be inspected during the preoperational EP. inspection program can be adequately addressed by using Procedures 82103 through 82108. We also support an initial inspection visit as envisioned by Procedure 82101. These seven (7) procedures would appear to represent a preoperatio'n inspection' program that.is both adequate and similar
- to the health physics / radiation protection preoperational program which is its -
,' nearest _ counterpart..
I .We cannot support the inclusion of Procedure 82102 inithe preoperational EP
' inspection program. _ Procedure 82102 is a duplicate of material' covered by the l
other seven procedures.and, thus, is unnecessary.- In. addition it appears to set a basis for a team appraisal (inspection) which is a departure from the normal inspection programs. . The Region should determine whether it is better
! 'to' accomplish the established inspection program with an inspector (s) making b '
several visits or a team making one visit. Based on our experience it is less i- . efficient, and not that much more effective, to perform the preoperational EP i
inspection program using a team of inspectors (and contractors) for a single visit.
i /
44g p 8506250354 pp 850621 I i p ADOCK 05000508 '
i PDR L .
I
JUN 211985 In reviewing the various procedures we noted that each one had an extensive listing of references. These references include those generated during the period shortly after TMI-2 when the upgraded emergency preparedness program was still in the developmental stages. We suggest that the listing of s
references be reduced to those that currently address the items to be inspected.
. Region V has essentially completed the preoperational EP inspection program at all of our sites. We have a few items (i.e. EP training and the satellite TSC) at Palo Verde Units 2 and 3 still to be addressed. There is only a slight possibility that WNP-3 will be completed which would require a preoperational inspection. Thus, weido not see a need for these procedures for several years.
If you have any questions about our comments please contact Ray Fish (FTS 463-3761) of my staff.
Original skv4 FY F. A. WensbwsLi Frank A. Wenslawski, Chief Emergency Preparedness and Radiological Protection Branch
Attachment:
As stated cc w/ attachment:
R. Fish R. Bellamy, RI D. Collins, RII C. Paperiello, RIII R. Hall, RIV cc w/o attachment: '
J. Partlow, IE bec w/ attachment:
RSB/ Document Control Desk (RIDS) ,
Mr. Martin
"*"8hggsy1
- ff!kd* ,
6/Al/85 6/df/85' ;
1 1 ,
9
4 ~- ,
,s i
, ATTACHMENT Comments On Draft EP Preoperational Procedures Procedure 82101
+
' 1. Page 2, Item-03.01, line 5 Place a comma after "onsite" and remove the word "or".
- 2. Page 2. Item 03.01.
Add a sentence to address the'onsite and corporate organizations that' are p responsible for administering the EP program.
- 3. Page 3. Item 03.07, lines 1, 2 and 3 The first sentence is not clear and it is very difficult to try and guess what should be inspected (how many organizations?).
- 4. Page 3, Item 03.08, line 4 of.2nd paragraph
- Insert a sentence noting that the adequacy of the abnormal occurrence and emergency operating procedures (EOPs) is performed under IE Procedure 42452. With respect to these two types of procedures, EP should only be checking to make sure they reference the appropriate EP implementing procedure (c).
Procedure 82103 l
- 1. Page 1 Item 02.02.b, lines 1 and 2 Insert "or positions" af ter " personnel" and replace " assigned" with 4 " identified".
- 2. Page 2, Item 02.04.a This item should also cover subsequent changes to the emergency plan and j related implementing procedures.
t-
- 3. Page 2, Item 02.05 This new item should address the corporate and onsite organizations that are responsible for the emergency planning program and its
- . implementation. This item should also cover management support of the-EP program. It may.be appropriate to place this item higher in the listing.
, Guidance on this subject will also need to be inserted into the Inspection Guidance Section.
4 4
1 1
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n 2
-4.' Page 2. Item 03.01.a By title this Section addresses the onsite emergency organization.
However, the initial paragraph in "a.3" discusses the management and administration of the emergency preparedness program. Thus, the specific guidance in 03.01.a is not. limited to the onsite emergency organization.
The guidar.ce' not related specifically to the onsite emergency organization should be removed and placed where it is appropriate (see previous comment).
- 5. Page 2, Item 03.01.a. line 7 Modify sentence beginning on this line to read as follows: "By discussion with appropriate management and staff assure the utility resolves the differences between the actual organization and the Emergentf Plan and implementing procedures."
6.- Page 2 Item 03.01.a.3(a)
From line 2 remove the words "onsite, and". On line 3 replace the semicolon with a parentheses and close the parentheses at the end of the sentence. On lines 5 and 6 remove the word "particular."
- 7. Page 3, Item 03.01.a.3(g)
This item should be eliminated because'it is covered in Procedure 82105 (03.01.2, nege 2).
- 8. -Page 3 Item 03.01.a.3(h)
Rewrite to address the responsibility for not'ifications (initial and follow-up) being assigned.
- 9. Page 3, Items 03.01.a.3 (1)', (j), (k), (1). and (m)
Based on the title of'03.01.a. these items should be written so that the inspector makes sure someone (or position) has been assigned the
~
responsibility for the item.
I
- 10. Page~4,. Items 03.01.a.3-(n) and (o)
Both of theseibelong somewhere else (see comment no. 3 for this procedure).
- 11. Page 4, Item 03.01a.5 The last two sentences should be reworked to address responsibilities assigned to the Emergency Coordinator and the identification of those that can't be delegated.
i D
'3
.12. Page 4, Item 03.01.a.7 This' belongs with the new 02.05 (see comment no. 3 for this procedure.
- 13. Page 5, Item 03.02.a. 3rd sentence of 1st paragraph Remove this " Oral agreements" sentence and replace it with the following:
"When the support is required by law, the emergency plan / implementing procedures should specifically reference the law that requires the described support." This is suggested because oral agreements can be legally binding.
- 14. Page 5, Items 03.02.a.1 and 2 These should be expanded to address the situation where a written agreement will not be given (e.g. NRC and FEMA response). Also, the State and local governments emergency pains may be considered to be the agreement.
- 15. Page 5, Item 03.02.b, line 4 After the word " personnel" insert the words "or positions." Also, on the next line replace the word " assigned" with " identified."
- 16. Page 6, Item 03.03 As presently written, this item doesn't appear to address the situation where a contract with an outside contractor is issued for the audit required by 10 CFR 50.54(t). There should be an inquiry regarding which parts of QA Manual would apply under these circumstances.
- 17. Page 6, Item 03.03.e This new item should address the system used to assure that deficiencies, weaknesses and improvement items identified during drills and exercises are considered and the action (s) taken on such items is documented (loop closed).
- 18. Page 6 Item 03.05 A new section should be developed to address the comment made in the third and tenth comments for this procedure. This comment may also impact Item 03.04 of this procedure.
Procedure 82104
- 1. Page 1 Items 02.01.d As presently written this subject belongs in Procedure 82108, Protective Response. This item should address the habitability requirements for the TSC and, if applicable, the EOF.
(
z
- 2. Page 3. Item 03.01 EOF Recove the words "and 9(c)" from line nine because 9(c) concerns communications which is covered in Procedure 82105.
- 3. Page 4, Item 03.01.b On line eight insert the words "TSC, OSC or" immedictely before the first "E01". At the end of this same line replace the words "the EOF" with "these activation and implementation".
- 4. Page 5, Item 03.01.b.1 Insert " Objectives or" before the first word (specification).
- 5. Page 5, Item 03.01.c.1 On line 2 change Rev. 2 to Rev. 3 because new facilities will likely be held to Rev. 3. If some facilities might be held to Rev. 2, then both revisions will need to be mentioned. Also this statement should make note that meteorology (a RG 1.97 item) is covered by Procedure 80721.
- 6. Page 5, Item 03.01.c.4 On line 2 replace the word " records" with " documentation" because this better describes the listed items that follow.
- 7. Page 6, Item 03.01.c.5.(e)
Include a reference to Procedure 83526 which covers emergency kits.
- 8. Page 7, Item 03.01.d Rewrite this to conform to suggested change made in the first comment of this procedure.
- 9. Page 10, Item 03.03 Rewrite the second sentence as follows.
" Focus on the capacity to accomodate the number of people expected, direct radiation and airborne exposure control, accessibility of protective equipment and supplies and emergency lighting."
Procedure 82105
- 1. Page 3, Item 03.01.a.2 On the second line of the second paragraph remove the word "onsite" because in almost all cases the EOFs are not onsite.
5
- 2. Page 3, Item 03.01.b.2 On line 2 replace the word " documentation," with "means" because we don't want to limit ourselves to actual observation or seeing something in writing as the only way to confirm this item.
- 3. Page 4, Item 03.01.c Add a statement. that FEMA has the initial and continuing responsibility for evaluating the adequacy of the system.
- 4. Page 4, Item 03.01.d Add " brochures" to the last sentence.
- 5. Page 5, Item 03.02.a.1. (b)
On line 2 insert the word "onshift" before the word " operating". Also, remove the last four words because E0Ps will not be relevant to the notification process.
- 6. Page 5, Item 03.02.a.3 Add a reference to the notifications (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) required by 10 CFR 50.72.
- 7. Page 5, Item 03.02.a.4 Insert the words "and follow-up" between " initial" and " emergency".
- 8. Page 6, Item 03.02.d This item should be changed to reviewing the licensee's documentation or program for confirming that identified positions / persons can be reached (proper telephone number) and in a timely manner. The NRC's observing'of this process is accomplished when we inspect the EP exercises. If it is felt that this current requirement should remain, it should be limited to onsite or licensee personnel only. Making unannounced notification ,
checks to State and local government personnel will likely cause trouble because these governmental groups don't appreciate such use of these dedicated telephones.
Procedure 82106 l 1. Page 2, Item 03.01 l
j- On line four of the initial paragraph insert the word " support" after the word " emergency".
- 2. Page 2, Item 03.01.a On line four insert the words "for emergency preparedness training" after the word " responsibilities".
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- 3. Page 3, Item 03.01.c.2 On line 3 insert ", site access (security) during an emergency" between the words " site" and "and".
- 4. Page 3, Item 03.01.c.3 A sentence should be added noting that the licensee may not have the primary responsibility for trainng State and local agencies personnel.
The licensee may only be providing supplemental training.
- 5. Page 3, Item 03.01.c.6 A new item should be added to address the retraining program.
- 6. Page 4, Item 03.02.a.1 After the word " conducted" add the words "or specifically scheduled".
- 7. Page 4, Item 03.02.a.5 This wording should be reduced to the following.
" Applicant and non-applicant emergency response personnel who need access to the site during an emergency understand the security requirements when an emergency condition exists."
As presently written, the words " material access area" in line 10 should not have been included because they don't apply to a reactor facility.
- 8. Page 4, Item 03.02.b on line 4 insert the words "and verbal response." at the end of the first sentence. Also, the second sentence should be changed to the following.
" Discussion of the scope and nature of the walk-throughs with appropriate plant management before they are conducted is essential."
- 9. Page 5, Item 03.02.b.1(a)
At the end of the seventh line change the requirement to "10 CFR 50.47(b)(4)" because 50.47(b)(2) does not apply to the matter of emergency event classification and EALs.
- 10. Page 6 Item 03.03.a On the second line the requirement 50.47(a)(2) should be changed to 50.47 (b) (14) .
- 11. Page 6, Item 03.03.a.3 This item should be rewritten. In Region V the licensees' security plans do not provide for any waiver of access controls except in a real emergency situation. Therefore, this guidance on security should consist L
7 of checking with Regional Security Personnel to ascertain the security provisions related to drills and then confirming what is permitted during the drills.
- 12. Page 6, Item 03.03.a.4 Remove the words within the parentheses (lines 3-7) because Planning Standard and Criteria II N of NUREG-0654 does not describe any drill that would include evacuation. Evacuations are part of EP exercises that are covered by Procedure 82301.
- 13. Page 7, Item 03.03.a.5 Replace the wording with the following.
" Organizational interfaces, including coordination between onsite and offsite support organizations."
For the most part drills involve a single onsite organization and other onsite organization support is minimal.
- 14. Page 7, item 03.03.a.6 Add words in a parentheses showing this may be part of an EP exercise.
- 15. Page 7, Item 03.03.b-A sentence should be added noting that some drill requirements may be satisfied by the initial EP exercise' required by IV.F.1 of Appendix E (Part 50).
- 16. Page 7, Item 03.03.c On line one remove the:words " audit reports". Audit reports are covered by Procedure 82103.
Procedure 82107
- 1. Page 1. Item 02.01.d Add a sentence stating that the technical evaluation cf the adequacy of the Abnormal Occurrence and Emergency Operating Procedures is performed under Procedure 42452.
- 2. Page 2, Item 02.02.a On line 2, after the word " systems" insert "(including computer software)."
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- 3. Page 2. Item 03.ul.b On line three insert the words " critical function" immediately before the word " instrument". EP is not responsible for all of the RG 1.97 instrumentation, just the critical function measurements that are to be available in the TSC and EOF.
- 4. Page 3,' Item 03.02.a.l(a)
On line one replace the word " dose" with the word " accident" because what follows appears to be related to the latter and not the former.
- 5. Page 3, Item 03.02.a.1.a(3)
This. statement should also address computer software that may be kept on discs, tape or in the computer memory.
- 6. Page 4, Item 03.02.a.2 On line two remove the word " manual" because it makes the statement too restrictive. There are backup capabilities other than just manual that would satisfy the need.
- 7. Pages 3 and 4, Item 03.02.a This item is not well organized, particularly with respect to the guidance for satisfying 02.02.a. Discussions of items pertaining to accident assessment and dose assessment are intermingled and it is difficult to address each as a separate subject which they are.
- 8. Page 5, Item 03.02.c Add a sentence referring to the inspection effort performed in 82105-02.01.e.
Procedure 82108
- 1. Page 2. Item 03.01.a If Procedure XXXXX is really 82105, then the subject of initiating onsite protective actions is not addressed because 82105 only discusses the means of communicating and content of messages.
- 2. Page 2. Item 03.01.b l
-Include a statement that the procedure for authorizing exposures in 1 excess of Part 20-(particularly those permitted for saving life and j equipment) should address such items as volunteering for the exposure, '
using older persons if possible and discussing the effects of the expected exposure with the individual (s) prior to receiving the exposure.
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- 3. Page 2, Item 03.01.c Modify wording to also cover situations where the accountability procedure (s) may not be associated with the security organization.
- 4. Pages 2 and 3, Item 03.01.e The initial paragraph should state thet the NRC is responsible for the medical support for onsite personnel that is provided by offsite organizations (ambulance and hospital) . FEMA is responsible for medical provisions for care of the general public and offsite personnel.
- 5. Page 3. Item 03.01.e.4 Remove the first eight (8) words. The NRC is responsible for inspecting the offsite medical treatment facilities to the extnet that they are used to support the applicant / licensee. FEMA will not evaluate the offsite medical treatment facilities on the basis of the types of injuries that may be experienced onsite.
- 6. Page 3, Item 03.01.f On line seven replace the word "all" with " nonessential".
- 7. Page 4, Item 03.02 On the third line of the first paragraph, " Item IV.D" should be Item IV. B".
- 8. Page 4, Item 03.02.a Af ter the last word (instrumentation) of the paragraph add the words "and technical knowledge".
- 9. Page 4, Item 03.02.a.1 On the first line' replace "which exclude" with " excluding".
- 10. Page 4 Item 03.02.a.2.(a)
On line two remove the words "by containment vessel melt-through".
Containment failure is the important fact not how the containment failed. >
Also, on line four the word "is" should be replaced with "may be".
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