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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217M5311999-10-25025 October 1999 Notification of 991103 Meeting with Util in Rockville,Md to Discuss Licensee Analytical Approach in Design of Pipe Supports at Plant ML20217C9051999-10-12012 October 1999 Forwards SER Input Approving License Request for Amend to Plant,Units 1 & 2.Licensee Proposal to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217E1501999-10-0707 October 1999 Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20211K8611999-09-0101 September 1999 Informs That There Has Been Some Confusion Re Recently Issued ODCM Generic Section Rev Which Needs to Be Clarified. Clarifications Are Listed ML20210L6431999-08-0606 August 1999 Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen ML20210P1361999-08-0404 August 1999 Notification of 990817 Meeting with Util in Rockville, Maryland to Discuss Status of Licensing Actions Submitted by Comm Ed & Plan for Proposed Licensing Workshop ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20195G6941999-06-0808 June 1999 Rev 1,rescheduling Notification of 990625 Licensee Meeting 99-32 in King of Prussia,Pa with Util to Discuss Recent Plant Initiatives to Improve Corrective Action Program & Processes ML20195C5081999-06-0303 June 1999 Submits Summary of 990527 Telcon Between J Rajan of NRC & K Korcz of Niagara Mohawk Power Co Re Util Requesting NRC Approval of Proposed Mod to Upper Spring Assembly of Four Core Shroud Tie Rods ML20207F2701999-05-25025 May 1999 Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes ML20206R3691999-05-0707 May 1999 Notification of Significant Licensee Meeting 99-24 with Util Current Employee on 990513 to Discuss Apparent Violation of 10CFR55,noted in NRC Correspondence to Individual Ref OI Rept 1-1998-033 ML20154D8211998-10-0505 October 1998 Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs ML20151V1241998-09-0909 September 1998 Notification of 980924 Meeting W/Util & Public in Oswego,Ny to Review NMPC Request to Extend Current Core Shroud Vertical Weld Insp Interval & to Receive Comments/Questions Re NMPC Request to Extend Unit 1 Core Shroud Vertical Weld ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl IR 05000220/19980031998-08-20020 August 1998 Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution ML20237C9501998-08-20020 August 1998 Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23 ML20237D9821998-08-11011 August 1998 Notification of Licensee Meeting W/Util on 980915 to Discuss Status of LaSalle Unit 1 & Performance Improvement & Restart Plans for LaSalle Unit 2 ML20237D9751998-08-11011 August 1998 Notification of Cancelled Licensee Meeting W/Util to Discuss Effectiveness of Performance Improvement Initiatives & Progress Toward LaSalle Unit 1 Restart ML20237D9721998-08-11011 August 1998 Notification of Cancelled Licensee Meeting W/Util on 980903 to Discuss Effectiveness of Performance Improvement Initiatives & Progress Toward LaSalle Unit 1 Restart ML20236X5631998-07-31031 July 1998 Discusses NMP & Several Supporting Ltrs, Requesting That NRC Authorize Extension of Insp Interval for Cracks in Plant,Unit 1 Core Shroud Welds from 10,600 Hot Operating H to 14,500 Hot Operating H ML20217F4411998-03-19019 March 1998 Forwards Order Approving Application Re Acquisition of New York State Electric & Gas Corp by Holding Co Affecting License NPF-69,Nine Mile Point Nuclear Station,Unit 2 for Fr Publication ML20216H6971998-03-17017 March 1998 Notification of 980326 Meeting W/Commonwealth Edison Co in Lisle,Il to Discuss Comed Request to Consolidate near-site Emergency Operations Facility Into Single Central EOF ML20203A3041998-02-0606 February 1998 Notification of 980224 Meeting W/Niagara Mohawk Power Corp in Rockville,Md to Discuss Schedules for Current & Projected Licensing Actions & Licensing Activities for Project Mgt Purposes ML20199C0771998-01-23023 January 1998 Corrected Notification of 980128 Meeting W/Nmp in Rockville, Md,To Disduss NRC Position That Exceeding Relief Pressures Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs Should Have Been Reported in 1993 ML20198N7961998-01-13013 January 1998 Confirms Rev to Time of NRC Oversight Panel Meeting for LaSalle County Station.Meeting Will Be Conducted on 980126 in Lisle,Il to Discuss Status & Effectiveness of Restart Plan Plant Performance Improvement Actions ML20198J4911998-01-0606 January 1998 Notification of 980128 Meeting W/Nmp in Rockville,Md to Discuss NRC Position That Exceeding Relief Pressure Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs That Should Have Been Reported to NRC in 1993 ML20197A8901997-12-16016 December 1997 Forwards Plant Restart Action Plan,For Review & Approval. Restart Action Plan Status Will Be Updated on as Required Basis ML20202B2321997-12-0101 December 1997 Responds to 960313 Memo Requesting NRR Technical Assistance to Determine Adequacy of NMPC Revised Design Calculations for Reactor Bldg & Turbine Bldg Pressure Relief (or Blowout) Panels.Partially Withheld ML20217E8371997-10-0101 October 1997 Notification of 971009 Meeting W/Util in Rockville,Md to Discuss Mgt Aspects of Current & Pending Licensing Activities,Including Plans to Convert Unit 2 to Improved Std TSs Plans Re Unit 1 Core Shroud Insp & Associated Schedule ML20217D4261997-09-30030 September 1997 Informs of Scheduled Visits W/Nuclear Services at Gpu on Nov 14th & Visit at Commonwealth Edison on Dec 3rd & Would Like to Receive Any Info Available.Supporting Documentation Encl ML20202B1451997-09-24024 September 1997 Discusses Response to Nine Mile Point on Blow Out Panels ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7661997-09-0303 September 1997 Informs of Intent & Rationale for Extending Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20199J0971997-08-21021 August 1997 Emails Info Re Plant Blowout Panels ML20149F1531997-07-16016 July 1997 Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606 ML20199J1041997-07-0707 July 1997 Emails Util Ltr for concurrence,EA-96-079.Comments Requested ML20202B1721997-07-0707 July 1997 Requests Concurrence on by 970714.Partially Withheld ML20138C7071997-04-29029 April 1997 Forwards Summary for Two Public Meetings Held W/Nmp on 970414 to Discuss Core Shroud Issues at Plant,Unit 1.Copies of Subj Meeting Videotape Have Been Sent to PDR IA-97-178, Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission1997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission ML20217D5461997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission ML20140C4811997-04-11011 April 1997 Discusses Exams of Core Shroud Welds & Tie Rod Repair Assemblies Conducted During Current Refueling Outage at Plant,Unit 1 & Initiation of Adjustments to One of Core Tie Rods ML20147J2391997-04-0909 April 1997 Notification of Meeting on 970416 W/Util in Rockville,Md to Discuss Overall Response & Present Addl Details Re Performance Indicators Used to Monitor Performance Stations ML20137S3611997-04-0303 April 1997 Notification of Cancelled 970410 Meeting W/Util in Rockville Md,Rescheduled on 970414 in Oswego,Ny,To Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results That Revealed Cracks in Heat Affected Zones ML20137L4441997-04-0303 April 1997 Notification of 970410 Meeting W/Util in Rockville,Md to Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results Revealing Cracks in Heat Affected Zones of Horizontal & Vertical Welds ML20147H6501997-04-0101 April 1997 Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320 ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20147D7251997-02-0707 February 1997 Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20149M6901997-01-19019 January 1997 Notification of 970128 Meeting W/Commonwealth Edison Co to Discuss Licensee Proposed Program for Use of Mixed Oxide Fuel 1999-09-16
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217M5311999-10-25025 October 1999 Notification of 991103 Meeting with Util in Rockville,Md to Discuss Licensee Analytical Approach in Design of Pipe Supports at Plant ML20217C9051999-10-12012 October 1999 Forwards SER Input Approving License Request for Amend to Plant,Units 1 & 2.Licensee Proposal to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217E1501999-10-0707 October 1999 Notification of 991022 Meeting with NMPC to Discuss Nine Mile Point Performance as Documented in Mid-Cycle PPR of Nine Mile Point Nuclear Station ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20211K8611999-09-0101 September 1999 Informs That There Has Been Some Confusion Re Recently Issued ODCM Generic Section Rev Which Needs to Be Clarified. Clarifications Are Listed ML20210L6431999-08-0606 August 1999 Notification of 990901 Meeting with NMP in Rockville,Md to Discuss NMP Plans to File Application Re Transfer of Interest & Authorities Under Plant Licenses to Amergen ML20210P1361999-08-0404 August 1999 Notification of 990817 Meeting with Util in Rockville, Maryland to Discuss Status of Licensing Actions Submitted by Comm Ed & Plan for Proposed Licensing Workshop ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20195G6941999-06-0808 June 1999 Rev 1,rescheduling Notification of 990625 Licensee Meeting 99-32 in King of Prussia,Pa with Util to Discuss Recent Plant Initiatives to Improve Corrective Action Program & Processes ML20195C5081999-06-0303 June 1999 Submits Summary of 990527 Telcon Between J Rajan of NRC & K Korcz of Niagara Mohawk Power Co Re Util Requesting NRC Approval of Proposed Mod to Upper Spring Assembly of Four Core Shroud Tie Rods ML20207F2701999-05-25025 May 1999 Notification of 990608 Meeting with Licensee in King of Prussia,Pa to Discuss Licensee Recent Initiatives to Improve Corrective Action Program & Processes ML20206R3691999-05-0707 May 1999 Notification of Significant Licensee Meeting 99-24 with Util Current Employee on 990513 to Discuss Apparent Violation of 10CFR55,noted in NRC Correspondence to Individual Ref OI Rept 1-1998-033 ML20154D8211998-10-0505 October 1998 Forwards SE Accepting Licensee 980619 Submittal of Proposed Changes to PT Limits to Provide New Limits Valid to 28 EFPYs ML20151V1241998-09-0909 September 1998 Notification of 980924 Meeting W/Util & Public in Oswego,Ny to Review NMPC Request to Extend Current Core Shroud Vertical Weld Insp Interval & to Receive Comments/Questions Re NMPC Request to Extend Unit 1 Core Shroud Vertical Weld ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl IR 05000220/19980031998-08-20020 August 1998 Forwards Exam Rept 50-220/98-03OL Administered on 980119-23 W/As Given Written Exam,Designated for Distribution ML20237C9501998-08-20020 August 1998 Forwards Facility Submitted Outline & Initial Exam Submittal W/As Given Operating Exam for Tests Administered on 980119- 23 ML20237D9821998-08-11011 August 1998 Notification of Licensee Meeting W/Util on 980915 to Discuss Status of LaSalle Unit 1 & Performance Improvement & Restart Plans for LaSalle Unit 2 ML20237D9751998-08-11011 August 1998 Notification of Cancelled Licensee Meeting W/Util to Discuss Effectiveness of Performance Improvement Initiatives & Progress Toward LaSalle Unit 1 Restart ML20237D9721998-08-11011 August 1998 Notification of Cancelled Licensee Meeting W/Util on 980903 to Discuss Effectiveness of Performance Improvement Initiatives & Progress Toward LaSalle Unit 1 Restart ML20236X5631998-07-31031 July 1998 Discusses NMP & Several Supporting Ltrs, Requesting That NRC Authorize Extension of Insp Interval for Cracks in Plant,Unit 1 Core Shroud Welds from 10,600 Hot Operating H to 14,500 Hot Operating H ML20217F4411998-03-19019 March 1998 Forwards Order Approving Application Re Acquisition of New York State Electric & Gas Corp by Holding Co Affecting License NPF-69,Nine Mile Point Nuclear Station,Unit 2 for Fr Publication ML20216H6971998-03-17017 March 1998 Notification of 980326 Meeting W/Commonwealth Edison Co in Lisle,Il to Discuss Comed Request to Consolidate near-site Emergency Operations Facility Into Single Central EOF ML20203A3041998-02-0606 February 1998 Notification of 980224 Meeting W/Niagara Mohawk Power Corp in Rockville,Md to Discuss Schedules for Current & Projected Licensing Actions & Licensing Activities for Project Mgt Purposes ML20199C0771998-01-23023 January 1998 Corrected Notification of 980128 Meeting W/Nmp in Rockville, Md,To Disduss NRC Position That Exceeding Relief Pressures Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs Should Have Been Reported in 1993 ML20198N7961998-01-13013 January 1998 Confirms Rev to Time of NRC Oversight Panel Meeting for LaSalle County Station.Meeting Will Be Conducted on 980126 in Lisle,Il to Discuss Status & Effectiveness of Restart Plan Plant Performance Improvement Actions ML20198J4911998-01-0606 January 1998 Notification of 980128 Meeting W/Nmp in Rockville,Md to Discuss NRC Position That Exceeding Relief Pressure Stated in FSAR Design Bases for Blowout Panels of Reactor & Turbine Bldgs That Should Have Been Reported to NRC in 1993 ML20197A8901997-12-16016 December 1997 Forwards Plant Restart Action Plan,For Review & Approval. Restart Action Plan Status Will Be Updated on as Required Basis ML20202B2321997-12-0101 December 1997 Responds to 960313 Memo Requesting NRR Technical Assistance to Determine Adequacy of NMPC Revised Design Calculations for Reactor Bldg & Turbine Bldg Pressure Relief (or Blowout) Panels.Partially Withheld ML20217E8371997-10-0101 October 1997 Notification of 971009 Meeting W/Util in Rockville,Md to Discuss Mgt Aspects of Current & Pending Licensing Activities,Including Plans to Convert Unit 2 to Improved Std TSs Plans Re Unit 1 Core Shroud Insp & Associated Schedule ML20217D4261997-09-30030 September 1997 Informs of Scheduled Visits W/Nuclear Services at Gpu on Nov 14th & Visit at Commonwealth Edison on Dec 3rd & Would Like to Receive Any Info Available.Supporting Documentation Encl ML20202B1451997-09-24024 September 1997 Discusses Response to Nine Mile Point on Blow Out Panels ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7661997-09-0303 September 1997 Informs of Intent & Rationale for Extending Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20199J0971997-08-21021 August 1997 Emails Info Re Plant Blowout Panels ML20149F1531997-07-16016 July 1997 Forwards NRC Approved Operator Licensing Written Retake Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 970606 ML20199J1041997-07-0707 July 1997 Emails Util Ltr for concurrence,EA-96-079.Comments Requested ML20202B1721997-07-0707 July 1997 Requests Concurrence on by 970714.Partially Withheld ML20138C7071997-04-29029 April 1997 Forwards Summary for Two Public Meetings Held W/Nmp on 970414 to Discuss Core Shroud Issues at Plant,Unit 1.Copies of Subj Meeting Videotape Have Been Sent to PDR IA-97-178, Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission1997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission ML20217D5461997-04-18018 April 1997 Forwards Partially Withheld Background Briefing Package in Preparation for 970425 Meeting Between Comed & Commission ML20140C4811997-04-11011 April 1997 Discusses Exams of Core Shroud Welds & Tie Rod Repair Assemblies Conducted During Current Refueling Outage at Plant,Unit 1 & Initiation of Adjustments to One of Core Tie Rods ML20147J2391997-04-0909 April 1997 Notification of Meeting on 970416 W/Util in Rockville,Md to Discuss Overall Response & Present Addl Details Re Performance Indicators Used to Monitor Performance Stations ML20137S3611997-04-0303 April 1997 Notification of Cancelled 970410 Meeting W/Util in Rockville Md,Rescheduled on 970414 in Oswego,Ny,To Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results That Revealed Cracks in Heat Affected Zones ML20137L4441997-04-0303 April 1997 Notification of 970410 Meeting W/Util in Rockville,Md to Discuss Evaluations & Conclusions Re Core Shroud Integrity in View of Insp Results Revealing Cracks in Heat Affected Zones of Horizontal & Vertical Welds ML20147H6501997-04-0101 April 1997 Forwards Copies of Core Shroud Insp Results & Schedules That Licensee Has Telecopied to NRC Staff Since 970320 ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20147D7251997-02-0707 February 1997 Forwards from Mj Mccormick Requesting Data from NRC Sponsored Tests on Pressure Locking of motor-operated Gate Valves ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20149M6901997-01-19019 January 1997 Notification of 970128 Meeting W/Commonwealth Edison Co to Discuss Licensee Proposed Program for Use of Mixed Oxide Fuel 1999-09-16
[Table view] |
Text
- .. _ ._ .__ _ _ . _ _ _. . . _ _ _ __ _ . _ . . _ . _ _ _ _ . _
hvmber 4,1996
/
MEMORANDUM TO: Thomas T. Martin. Director l Division of Reactor Program Management i
FROM: Alfred E. Chaffee. Chief [ original sigrxx1 by]
Events Assessment and Generic Communications Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING :
OCTOBER 30, 1996 - BRIEFING 96-14 '
On October 30, 1996, we conducted an Operating Reactors Events Briefing (96-14) to inform senior managers from offices of the Commission. OE. AE00
.RES. NRR and regional offices of selected events that occurred since our last briefing on October 23. 1996. Attachment 1 lists the attendees. Attachment 2 presents the significant elements of the discussed events.
' Attachment 3 contains reactor scram statistics for the week ending October 27, 1996. One significant event was identified for input into the NRC Performance '
Indicator Program (Attachment 4).
The statements contained in the attached briefing slides represent the best information currently available to the NRC. Future followup could produce new I
-information that may alter the NRC's current view of the events discussed. I Attachments: As stated (4) cc w/atts:
See next page CONTACT: Kathy Gray. NRR (301) 415-1166 O
\ t0 >
DISTRIBUTION: (w/atts) l
-Central Files ;
PUBLIC LKilgore. SECY ,
PECB R/F g ;
\ '
DOCUMENT NAME: G:\KAG\0RTRANS
- f. To receive a copy of this document. Indicate in the boa: *C" = Copy without attachtnent/ enclosure "E" = Copy with attachment / enclosure *N* = No copy i M A.
l.
l OFFICE PECB ,_ lE #CB , lE @fy l C/PECB lN lNAME KGray:kag .Qqg /CWFter MQlennM AChaffee /)U g, p i lDATE 10/3 l /96' ' Q> 1)/ / 196 1(/ { 196 1)/ .( 196 / ,
omcuu. necono con g .,. p ) ,y,,4 060092 c'P" !
$-N/
l 9611060288 961104 PDR ORO NRRA PDR g fh I
I l
CC:
F.-Miraglia. NRR (0-12G18) -
R. Lobel. NRR (0-8H7) l F. Gillespie. NRR (0-12G18)
R. Zimmerman. NRR (0-12G18)
A. Thadani. NRR (0-12G18)
B. Sheron NRR (0-12G18)
S. Varga. NRR (0-14E4)
J. Zwolinski, NRR (0-14H3)
J. Roe NRR (0-13E4)
E. Adensam. NRR (0-13E4)
G. Lainas. NRR (0-7D26)
G. Holahan. NRR (0-8E2)
M. Virgilio. NRR (0-8E2)
D. O'Neal. NRR (0-10E4)
B. Boger NRR (0-9E4)
M. Markley. ACRS (T-2E26)
E. Jordan. AE0D (T-4D18)
C. Rossi. AE00 (T-4A9)
F. Congel. AE00 (T-4D28)
R. Barrett AEOD (T-4A43)
S. Rubin. AE00 (T-4D28)
M. Harper. AE0D (T-4A9)
W. Leschek. AEOD (T-4A9)
V. McCree. EDO (0-17G21)
J. Gilliland. PA (0-2G4)
D. Morrison. RES (T-10F12)
W. Hill. SECY (0-16G15)
H. Miller, Region I R. Cooper. Region I S. Ebneter. Region II E. Merschoff Region II S. Vias. Region II A. Beach Region III J. Caldwell. Acting. Region III L. Callan. Region IV J. Dyer. Region IV K. Perkins, Region IV/WCFO G. Fader. INP0 J. Zimmer. DOE l
i j
i
l..
l 1
l LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (96-14)
OCTOBER 30. 1996 i
l NAME OFFICE NAME OFFICE :
A. Chaffee NRR L. Rossbach NRR K. Gray NRR W. Burton NRR R. Dennig NRR E. Adensam NRR J. Carter NRR J. Kauffman OE i R. Lobel NRR R. Lloyd AEOD l C. Berlinger NRR A. Serkiz RES T. Martin NRR M. Marshall RES S. Lee NRR J.D. Wilcox NRR .,
TELEPHONE ATTENDANCE l (AT ROLL CALL) l l
Reaions Resident Insoectors 1 Region I B. Norris. SRI Nine Mile Point i Region II I Region III l l Region IV Misc.
l t
4 4
ATTACHMENT 1 l
1 1
l i
l l OPERATING REACTORS EVENTS BRIEFING 96-14 l
LOCATION: 0-10B11, WHITE FLINT WEDNESDAY, OCTOBER 30, 1996 11:00 A.M.
1 l
HULTIPLE SUPPRESSION POOL DEBRIS l
l l
l l
PRESENTED BY:
EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR Attach rnt 1 f
1
l 96-14
! SUPPRESSION P00L DEBRIS l OCTOBER 29, 1996 i
. PROBLEM j DEBRIS, CONSISTING OF SLUDGE AND MISCELLANE0US FOREIGN
! MATERIAL INCLUDING PLASTIC AND RUBBER SHEET MATERIALS
- FOUND IN SUPPRESSION P00L AND DOWNCOMERS.
i
< CAUSE
- A THOROUGH CLEANING OF THE SUPPRESSION P00L AND l INTERFACING EQUIPMENT HAD NOT YET BEEN MADE.
SAFETY-SIGNIFICANCE THE FOREIGN MATERIAL WAS OF A TYPE AND QUANTITY THAT OPERATION OF RECIRCULATION PUMPS TAKING SUCTION FROM THE SUPPRESSION P0OL COULD BE ADVERSELY IMPACTED.
DISCUSSION e DURING THE PAST APPR0XIMATELY 10 YEARS, DEBRIS OF AN UNANTICIPATED NATURE AND QUANTITY HAS BEEN FOUND IN A NUMBER OF LOCATIONS NOT PREVIOUSLY EXPLICITLY CONSIDERED IN SAFETY EVALUATIONS.
e A NUMBER OF GENERIC COMMUNICATIONS HAVE BEEN ISSUED:
SOME PROVIDED EXAMPLES UNIQUE TO EITHER BWRs OR PWRs A FEW WERE DIRECTED TO EITHER PWRS OR BWRs FOUR BULLETINS, INCLUDING SUPPLEMENTS, AND ONE GENERIC LETTER HAVE BEEN ISSUED CONTACT: J. CARTER, NRR/DRPM/PECB AIT: NO
REFERENCES:
10 CFR 50.72 #31172, #31159; SIGEVENT: N0 ,
MR 1-96-0093 l
96-14 e BULLETIN 95-02 ISSUED OCTOBER 17, 1995, REQUESTED BWR LICENSEES T0:
VERIFY OPERABILITY OF ALL PUMPS SCHEDULE A CLEANING 0F THE SUPPRESSION P00L REVIEW FOREIGN MATERIAL EXCLUSION PROCEDURES AND CORRECT WEAKNESSES REPORT EXTENT OF COMPLIANCE WITH AB0VE REQUESTED ACTIONS e STAFF WAS SURPRISED TO LEARN THAT SOME LICENSEE STATEMENTS OF " CLEANING" MEANT ONLY SPOT CLEANING.
e ON OCTOBER 16, LASALLE, UNIT 2, REPORTED FINDING SUFFICIENT FOREIGN MATERIAL BURIED UNDER SLUDGE THAT OPERABILITY OF EMERGENCY CORE COOLING SYSTEMS WAS CHALLENGED:
LASALLE HAD PREVIOUSLY ONLY " SPOT CLEANED" THE P0OL DEBRIS WAS FOUND FLOATING ON WATER INSIDE SOME DOWNCOMERS e ON OCTOBER 17, DURING A RE-INSPECTION OF THE SUPPRESSION POOL AREA, NINE MILE POINT, UNIT 2, REPORTED FINDING CLEANLINESS C0 VERS ON SEVEN DOWNCOMERS AND DEBRIS FLOATING ON THE WATER IN OTHER DOWNCOMERS:
LICENSEE HAD PREVIOUSLY THOROUGHLY CLEANED THE SUPPRESSION POOL e FOREIGN MATERIALS BELIEVED TO HAVE BEEN PRESENT SINCE INITIAL OPERATION.
e SOME AREAS ARE INACCESSIBLE AND DIFFICULT TO INSPECT AND CLEAN.
i
96-14 FOLLOWUP o AN INFORMATION NOTICE IS BEING PREPARED TO ALERT LICENSEES TO THE SIGNIFICANCE OF CHECKING DOWNCOMERS FOR CLEANL1 NESS.
e CONSIDERATIONS FOR ISSUING GENERIC COMMUNICATION: l 1
CLEANING ACTIVITIES AT LASALLE AND NINE MILE POINT, UNIT 2, WERE A CONSEQUENCE OF THE ACTIONS REQUESTED IN BULLETIN 95-02:
LASALLE WAS PERFORMING INITIAL THOROUGH CLEANING NINE MILE POINT, UNIT 2, WAS PERFORMING ENHANCED SURVEILLANCE 1
LICENSEES ESTABLISHED THEIR SCHEDULE FOR CLEANING l THE SUPPRESSION P0OL: l NOT ALL LICENSEES ARE KNOWN TO HAVE THOROUGHLY CLEANED THE P0OL SOME MAY HAVE ONLY REMOVED VISIBLE DEBRIS '
EXTENT OF CLEANING OF INTERFACING SYSTEMS / COMP 0NENTS VARIES GENERIC COMMUNICATIONS DID NOT EITHER DELINEATE SPECIFIC ACTIONS OR A SPECIFIC DATE FOR COMPLETION l OF LICENSEE CHOSEN ACTIONS:
LICENSEES MAY HAVE READ INFORMATION NOTICES !
NARROWLY AND LITERALLY THE SIGNIFICANCE OF THE GENERIC CONCERN l EXPRESSED IN BULLETINS AND A GENERIC LETTER MAY NOT HAVE BEEN APPRECIATED OR THE RAMIFICATIONS OF VARIOUS ASPECTS UNDERST0OD NOT LIKELY TO IMPACT LICENSEE'S SELECTION OF LARGER STRAINERS TO RESOLVE BULLETIN 96-03, VERSUS BACKFLUSH CAPABILITY OR SELF CLEANING STRAINERS. l
. . . - . . . _ - ~ . . - . - .,.~.~~.-. . - - - . . - , . . . . . . - - - . . -
! l l
REACTOR SCRAM Reporting Period: 10/21/% to 10/27/%
YTD YTD ABOVE BELOW YTD j QL1 PLANT & WIT ggg3 g CAUSE COMPLICATIONS 13 13 191& j 10/23/% V0GTLE 2 64 SA Equipment Feiture NO 2 0 2 10/24/ M NORTH ANNA 1 100 SA Equipment Felture NO 2 0 2 10/25/% OYSTER CREEK 1 100 SM Equipment Failure NO 2 1 3 1
l l
4-i 4
I Attachment 3 Mits: Year To Date (YTD) Totals include Events Within The Calender Year Indicated By The End Date of The Specified Reporting Period ETS-10 Page:1 10/31/ %
d.
s
I COMPARISON OF WEEKLY SCRAM STAftSTICS WITN INDUSTRY AVERAGES I
PERIOD ENDING 10/27/ %
I NUMBER 1996 1995 1994 1993 1992 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE l
l (YTD)
POWER GREATER TNAN OR EQUAL TO 15%
EQUIPMENT FAILURE 3 1.60 1.83 1.52 1.83 2.62 DESIGN / INSTALLATION ERROR 0 0.12 0.12 0.08 0.04 -
OPERATING ERROR 0 0.07 0.15 0.21 0.27 0.31 1
MAINTENANCE ERROR 0 0.53 0.38 0.54 0.52 0.50 l EXTERNAL 0 0.16 0.21 0.17 0.13 -
OTNER 0 0.09 0.06 - 0.02 -
Subtotal 3 2.57 2.75 2.52 2.81 3.43 POWER LESS TNAN 151 l 1
EQUIPMENT FAILURE 0 0.21 0.10 0.27 0.38 0.42 DESIGN / INSTALLATION ERROR 0 0.00 -
0.02 - - l
! OPERATING ERROR 0 0.09 0.13 0.08 0.13 0.15 MAINTENANCE ERROR 0 0.07 0.08 - 0.02 0.08 EXTERNAL 0 0.00 - -
0.04 -
OTNER 0 0.00 - - - -
l 54 total 0 0.37 0.31 0.37 0.57 0.65 l
l TOTAL 3 2.94 3.06 2.89 3.38 4.08 l
[
i 1996 1995 1994 1993 1992
- NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY I SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE f
- (YTD)
TOTAL AUTOMATIC SCRAMS 2 1.84 1.92 2.19 2.44 3.'06 TOTAL MANUAL SCRAMS 1 1.12 1.13 0.69 0.94 1.02 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF 3
i i
I EVS-14 Page: 1 10/31/ %
- NOTES
- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE
( WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
l SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD
, MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN l IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN l OPERATING LICENSE.
- 2. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
- 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL l
ERRORS UNRELATED TO CAUSE OF SCRAM.
- 4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 M:nual and Automatic Scrams for 1988 ------------------ 291 l Manual and Automatic Scrams for 1989 ------------------ 252 l Mnnual and Automatic Scrams for 1990 ------------------ 226
(
Mnnual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 ------------------ 175 l Manual and Automatic Scrams for 1994 ------------------ 150 Mnnual and Automatic Scrams for 1995 ------------------ 159 l Mnnual and Automatic Scrams for 1996 --(YTD 10/27/96)-- 127 l
l l
l t
l.
d
OPERATING REACTOR PLANTS SIGNIFICANT EVE".TS No Sort Specified ouERY> Event Type SIG & Event Date >= 09/24/ % & Event Date <= 09/24/96 & "0CONEE" S Plant Name DATE OF 50.72 OR CLOSEQUT PLANT & UNIT g 33g(( DESCRIPTION OF EVENT SIGNIFICANCE 3RIEFING PRESENTER RECORD OCONEE 2 09/24/% 31053 Water hammer caused steem line rteture and other - Water Nammer 96-12 KOSHY T. HIGHLIGHT significant injury to plant staff.
ATTACHMENT 4 ETS-11 Page:1 10/31/ %
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