Letter Sequence Other |
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TAC:M47146, (Open) TAC:M47158, (Open) TAC:M47159, (Open) TAC:M47161, (Open) TAC:M47164, (Open) TAC:M47165, (Open) TAC:M47166, (Open) TAC:M47171, (Open) TAC:M47172, (Open) TAC:M47173, (Open) TAC:M47176, (Open) TAC:M47180, (Open) TAC:M47181, (Open) TAC:M47182, (Open) TAC:M51994, (Open) |
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MONTHYEARML20195E5431988-06-10010 June 1988 Submits Status Summary Rept on Multi-Plant Action B-66, Natural Circulation Cooldown. Near-term OLs Should Not Be Added to Safety Issues Mgt Sys Listing for Subj Action Project stage: Other 1988-06-10
[Table View] |
Submits Status Summary Rept on Multi-Plant Action B-66, Natural Circulation Cooldown. Near-term OLs Should Not Be Added to Safety Issues Mgt Sys Listing for Subj ActionML20195E543 |
Person / Time |
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Site: |
Davis Besse, Oconee, Three Mile Island, 05000000 |
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Issue date: |
06/10/1988 |
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From: |
Capra R, Hodges M Office of Nuclear Reactor Regulation |
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To: |
Varga S Office of Nuclear Reactor Regulation |
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References |
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GL-88-21, TAC-M47146, TAC-M47158, TAC-M47159, TAC-M47161, TAC-M47164, TAC-M47165, TAC-M47166, TAC-M47171, TAC-M47172, TAC-M47173, TAC-M47176, TAC-M47180, TAC-M47181, TAC-M47182, TAC-M51994, NUDOCS 8806240076 |
Download: ML20195E543 (6) |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20209G2661999-07-14014 July 1999 Notification of 990728 Meeting with Util in Rockville,Md to Discuss Status of Review of Bg&E & Duke License Renewal Applications for Ccnpp,Units 1 & 2 & Ons,Units 1,2 & 3, Respectively ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196J8621998-12-0404 December 1998 Discusses Three Plants,Evaluated for Consideration as Abnormal Occurrences & Other Event of Interest.Oconee & Quad Cities Plants Are Being Considered as AOs & Big Rock Point Being Considered as Other Event Interest ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154K8531998-10-14014 October 1998 Informs That NRC Staff Has Set Up Single Electronic Mail Address to Receive All Communications Including Svc of Filings in Listed Preceeding ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20153E4451998-09-24024 September 1998 Informs That Ofc of Secretary Experienced Problems with Dedicated e-mail.In Effort to Maintain Electronic Mailbox for Parties Filing by e-mail,alternate Mailbox Created.With Certificate of Svc.Served on 980924 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20236R6751998-07-16016 July 1998 Notification of 980723 Meeting W/Util in Rockville,Md to Discuss Changes to Improved TSs Submittal ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 ML20206R9081998-05-0808 May 1998 Forwards Insp Criteria to Be Used During Future Insp of Oconee Activities ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20203L5321998-02-25025 February 1998 Notification of 980305 Meeting W/Tva in Rockville,Maryland to Discuss Browns Ferry Improved Std TS IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211N8651997-10-0707 October 1997 Responds to 970829 Memo Requesting write-ups for Events Which May Be Reportable as Abnormal Occurrences or Other Events of Interest for Fy 1997 Rept to Congress.Specifically Assessments for Two Oconee Events,One at Zion & Haddam Neck ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 1999-09-29
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20209G2661999-07-14014 July 1999 Notification of 990728 Meeting with Util in Rockville,Md to Discuss Status of Review of Bg&E & Duke License Renewal Applications for Ccnpp,Units 1 & 2 & Ons,Units 1,2 & 3, Respectively ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20203E0321999-02-11011 February 1999 Staff Requirements Memo Re 990211 Affirmation Session in Rockville,Md (Open to Public Attendance) Re Secys 99-044 & 99-045 ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196J8621998-12-0404 December 1998 Discusses Three Plants,Evaluated for Consideration as Abnormal Occurrences & Other Event of Interest.Oconee & Quad Cities Plants Are Being Considered as AOs & Big Rock Point Being Considered as Other Event Interest ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154K8531998-10-14014 October 1998 Informs That NRC Staff Has Set Up Single Electronic Mail Address to Receive All Communications Including Svc of Filings in Listed Preceeding ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20153E4451998-09-24024 September 1998 Informs That Ofc of Secretary Experienced Problems with Dedicated e-mail.In Effort to Maintain Electronic Mailbox for Parties Filing by e-mail,alternate Mailbox Created.With Certificate of Svc.Served on 980924 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20236R6751998-07-16016 July 1998 Notification of 980723 Meeting W/Util in Rockville,Md to Discuss Changes to Improved TSs Submittal ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20248H7001998-05-20020 May 1998 Staff Requirements Memo Re SECY-98-071,exemption to 10CFR72.102(f)(1) Seismic Design Requirement for TMI-2 ISFSI ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 ML20206R9081998-05-0808 May 1998 Forwards Insp Criteria to Be Used During Future Insp of Oconee Activities ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20203L5321998-02-25025 February 1998 Notification of 980305 Meeting W/Tva in Rockville,Maryland to Discuss Browns Ferry Improved Std TS IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211N8651997-10-0707 October 1997 Responds to 970829 Memo Requesting write-ups for Events Which May Be Reportable as Abnormal Occurrences or Other Events of Interest for Fy 1997 Rept to Congress.Specifically Assessments for Two Oconee Events,One at Zion & Haddam Neck 1999-09-29
[Table view] |
Text
_ _ _ _ _ _ _ _ - _ _ _
. June 10, 1988 .
MEMORANDilM FOR: Steven A. Varga, Director DISTRIBUTION Division of Reactor Projects, I/II =CaptseLJ11 era -
Office of Nuclear Reactor Regulation NRCPDR Local PDR FROM: Robert A. Capra, Director ?DI-1 Rdg.
Project Directorate I-1 BBoger Division of Reactor Projects, I/II CVogan
( Marvin W. Hodges, ihuf SMcNeil MWHodges Reactor Systens Branch RJones Divisior, of Engineering and RCapra l System Technology SUB.1ECT: MPA B-66, NATURAL C16CULATION C00LDOWN STATUS
SUMMARY
REPORT
- 1. Safety Significance
In evaluating the effects of void formation occurring during natural circulation cooldown of PWRs, the Reactor Systems Branch staff has detemined that this void fomation will not significantly impair core decay heat removal when appropriate emergency operating procedural guidance is provided to mitigate any void effects. The appropriate proccJural guidance has been reviewed and approved on a generic basis by the NRC staff. Consequently, the staff has concluded that MPA B-66 is not a safety *,ignificant issue for any PWRs with the exception of Davis-Basse I wF.1 h has implemented a unique head design modification.
P. Current Plan.
Currently, safety evaluations have been completed and sent to all pre-TMI-2
- 01. PWRs with the exception of Davis-Besse 1. The Davis-Pesse review has slipped into 1989 due to the licensee's failure to provide the required information to permit completion of the NRC review. The only plant where implementation of B-66 is not complete 's Oconee 1 and 2 where inplementation completion is scheduled for 1990.
In addition, all of the regions are now perfoming TI ?.515/86 to verify that all PWRs have implemented programs for the control of natural circulation cooldown in sccordance with GL 81-21.
In sumary, B-66 is not scheduled to be fully complete until after 1990.
- 3. Proposed Plan The staff review of 8-66 is complete for all PWRs that were OLs prior to the TMI-2 accident with the exception of Davis-Besse 1. For all TMI-2 NTDLs, void formation was considered in BTP RSB 5-1, "Design Requirements un88= 8:8%r A'
44 hl
'p f P f
e of the Residual Heat Removal System" of the Standard Review Plan.
Consequently, the effects of void formation for each NTOL were analyzed in each plant's Safety Evaluation Report during the plant licensing process.
It is therefore recommended that this issue be closed out as an MPA for all PWRs with future Davis-Besse review conducted as a plant-specific licensing action and with the Oconee 1 and 2 implementation maintained as a plant-specific TAC with that sole purpose. The Davis-Besse and Oconee Project Managers shall be requested to take out TACs for these issues.
Furthermore, it is recommended that the NT0LS not be added to the SIMS listing for this MPA, rather a statement providing the details of this issue's incorporation into the BTP RSB 5-1 review should be included in the SIMS MTA Solution description, as well as a discussion of the actions taken regarding Davis-Besse and Oconee 1 and 2. (See attached).
In completing this MPA, the applicable Project Managers will be provided with the correct SE Input Date and/or Imposition Completion Date, as appropriate, and will be requested to update their SIMS reports to reflect the correct dates.
Finally, as adequate procedural guidance has been reviewed and approved for the various owners' groups and has been determined to be sufficient to mitigate any consequences of void formation, review of plant-specific emergency operating procedures through regional performance of TI 2515/86 is not necessary. Hence, the staff recommends that the regions be ,
immediately informed that they should discontinue performance of TI 2515/86 !
and this TI should be cancelled. Cancellation of verification of the completion of this MPA should be reflected likewise in the SIMS MPA solution description (see attached) and the verification complete date ,
should be made N/A for any plant at which TI 2515/86 has not been l completed. '
Critifl!!pd b7 Ofiifr.d sfp ed h M.W. Hodges, Chief Robert A. Capra, Director Reactor Systems Branch Project Directorate I-1 Division of Engineering and Division of Reactor Projects, I/II l Systems Technology l
Enclosure:
As stated l
PDI-1 g PDI-1xi/M CVogan SMcNeil:mak MWHodges . apra ;
6/10/28 6/l0/88 6/ It/88 6/jp/88 l
1 1
av.. ua.u- . ~ . ,
R-1216310-MPA SYSTEM PACE 5AFETY ISSUES MANAGEMENT 1 MPA SAFETY ISSUE LEVEL INFORMA MPA NUMBER: B-66 TITLE: NATURAL CIRCULATION C00LDOHN CONTACT: 5. MCNEIL TYPE: MPA IDENTIFYING ORGANIZATION: NRR STATUS: ComPLE1E SPONSORING OFFICE: NRR PRIORITY: M TYPE OF REACTORS AFFECTED: fid8 OTHER:
DESCRIPTION SOLUTION (NEAR AND LONG TERM)
MPA PROBLEM BACKGROUND E:: Z - ^. - C""E M ..;;;TICA ;oa JN I T e htL'/ coNisDewe0 sie ST. LUCIE UNIT 1, HHILE COOLING DOHN ON NATURAL GENERIC LETTER 81-21, ISSUED MAY 5, 1981, REQUESTED: Soi CIRCULATION DUE TO A COMPONENT COOLING HATER 1. A DEMONSTRATION THAT NATURAL CIRCULATION C00LDOHN MALFUNCTION, DEVELOP.fD A STEAM SPACE IN THE UPPER BY PROCEDURE SHOULD NOT RESULT IN REACTOR VESSEL VOIDING, HEAD OF THE REACTOR VESSEL. CORE COOLING HAS NOT 2. A VERIFICATION THAT SUPPLIES OF CONDENSATE GRADE LOST, HOWEVER, THE COMPLEX SITUATION HAS DEEMED AN AUX FEEDHATER ARE SUFFICIENT, AND UNDESIRABLE CHALLENGE TO THE OPERATOR. ALL PHRS 3. A REVIEH OF ASPECTS OF TRAINING AND PROCEDURES HERE REQUESTED TO REVIEH PROCEDURES FOR PLANT C00LDOHN DEALING HITH THIS 0;;00L; SUBJECT. vorbitK ON NATURAL CIRCULATION TO DETERMINE IF VOIDING HILL f0^."LI""C" F0" "??'_ GAVC OC % g CT vehi "lL IC"*Jabuel)
^.,;;CD BY NRR f+# en OCCUR IN THE REACTOR VESSEL. IN VERIFYING LICENSEE COMPLIANCE HITH BIP RSB 5-1, COMMENTS " "DESIGN REQUIREMENTS OF THE RESIDUAL HEAT REMOVAL SYSTEM",
THERC IS A 9060 . 00SILILI!7 !;iC REGIGN.i TiA7 iiAVC ALRCA07 LOOXCO AT !" "20CEOU".EC. OF THE STANDARD REVIEW PLAN, 8M LE "*I' tr> T H E ." L A " ' ~r -G UJ O" r*t surt -S PEC# r SAFE,TY.
orn c .E.VA,LUATION 1 nu rn oc REPORT
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g b IIgFs roY A{1h 66 f6PFOA M D Til AU " G li yh CcHDtAcTIAIG 7( l1 S o S /f f,, V 58; D. NEED FOR VERIFICATION: suf 5Eq worrl'/,Rgnc,09 SYs'1 EMS 64 AAltra $'Aff E d ( Utn*0 r) OF 6 FYiG NEEDED OFFICE of v erbrH&. DETEENINSD T11/p .y pgasse smetGgacy PWOC&RI (YES/NO) RESPONSIBLE y y pc5g,g ppn9, g 79 pyypq497y yo;nygg gpyg(q g y gy,$
VERIFICATION. . . . . . . -VES- --
MPA VERIFICATION PRIORITY:'Ms. hj/A 15suG vas F LsTTLE NQ SAS g y y stGM1FocMCE.-
- 5. REQUIREMENTS IMPLEMENTATION BY LICENSEE AND VERIFICATION BY NRC (,c/vE #f t OidNE#5 ga@ospd Gu rD ANCe H AS 56e.
COMPLETION DATE OF A&vggweD AN() /):op#0 065) by N K 4, s7A ff STATUS (PLANTS) LAST PLANT IMPOSITION. . . . . . . . . . 48 0F .9&N T E J00 I N NOMu@ Gu'Dg5 [24 vi b f D /)Dt:Qu KI6 IMPLEMENTATION. . . . . . . .if7 R OF 5 TNT 00/90 /)S S i( 44NCG OF g/ O tt ) C-F FE (75 M' 7 'G E* 'O M '
VERIFICATION. . . . . . . . . 14 0.C 'M i{-9 06/88 Tf}sgeFORE, Ve d it:rms:Otl T!!!0 !Gli f6W* fN OF TT 9'ild % W3 CMC & L L G b .
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SAFETY ISSUES MANAGEMENT SYSTEM PAGE 2 MPA SAFETY ISSUE LEVEL INFORMA PiPA NUMBER: B-66 TITLE: NATURAL CIRCULATION C00LDOHN
(. REQUIREMENTS IMPLEMENTATION BY STAFF A. STAFF REQUIREMENTS -- TI 2515/86 - C ant t llE h COMPLETION DATE: N/A 0FFICE(S) RESPONSIBLE: NfA B. ROUTINE INSPECTION PROGRAM MODIFICATIONS: MODIFICATIONS NEEDED (YES/NO) NO MODIFICATION COMPLETION DATE: N/A M0DIFICATION TEXT NMM NO MODIFICATION TEXT FOR ISSUE NMM I
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O[ l[/M[88 h h n A b ,A & et vio a L[% MO I"y UN DAT 03/15 m SAFETY I5 SUES MANAGEMENT SYSTEM PAGE 3 PLANT LEVEL INFORMATION MPA NUMBER: B-66 TITLE: NATURAL CIRCULATICH C00LDOHN DOCKET IMPOS RAI SE IMPOS IMPLEM VERIFY PLANT JAC 8 PRIORITY _INIT RAI RESPONSE TER INPUT @MPL ET @ MI L E COMELE RKANSAS 1 M4/181 M 05/81C 07/11/85C 07/85C 07/85C 03/88 RKANSAS 2 M47161 M 05/81C 03/27/84C 03/84C 03/84C 09/87C EAVER VALLEY 1 M47146 M 05/81C 08/12/83C 08/83C 06/84C 00/00C ALVERT CLIFFS 1 M47158 M 05/81C 07/08/83C 07/83C 07/83C 10/87C ALVERT CLIFFS 2 M47159 M 05/81C 07/08/83C 07/83C A7/8;C 10/87C 00K 1 h47164 M 05/81C 12/09/83C 11/83C 00/83C 00/84C 09K 2 M47165 M 05/81C 12/09/83C 11/83C 00/83C 00/84C RYSTAL RIVER 3 M47166 H 05/81C 04/23/84 N/A 06/20/86C 06/86C 12/85C 01/88 AVI3-BESSE 1 M47182 M 05/81C 12/87 02/85C 02/88 lIABLO CANYON 1 M51994 07/83C 07/00/84C 07/84C 03/85C 07/87C lARLEY 1 M47172 M 05/81C 11/15/83C 11/83C 00/00C 04/88 lARLEY 2 M47173 M 05/81C 11/15/83C 11/83C 00/00C 04/88 iORT CALHOUN 1 M47180 M 05/81C N/A 10/28/83C 10/83C 02/84C' 12/87
!INNA M47176 M 05/81C 04/22/83C 04/83C 11/81C 06/88 lADDAM NECK M47171 M 05/81C 07/26/83C 07/ 07/83C 12/87
- NDIAN POINT 1 M47177 05/81C 06/22/84C Al N/A N/A
- N3IAN POINT 2 M47156 M 05/81C 08/01/83C 08/ 3C 10/85C 03/88
,NDIAN POINT 3 M47178 M 05/81C 06/10/83C 06/83C 10/85C ;1/87N
- E 4AUNEE M47160 05/81C 08/15/83C 08/83C 08/83C 08/83C lAINE YANKEE M47174 M 05/81C 05/31/83C 05/83C 00/83C 02/88
'u3UIRE 1 M51644 05/83C 09/30/84C 09/83C 00/83C 04/88
- C 3UIRE 2 M51645 05/83C 09/30/83C 09/83C 00/83C 04/88
,I.LSTONE 2 M47149 M 05/81C 06/22/84C 11/81C 11/81C 03/88
.0tTH ANNA 1 M47152 M 05/81C 10/19/83C 10/83C 10/83C 03/88N
.0tTH ANNA 2 M47155 M 05/81C 10/19/83C 10/83C 10/83C 03/88
- C ) NEE 1 M47183 M 05/81C 04/23/84 06/14/85C 06/85C 00/90 04/88 C) NEE 2 947184 M 05/81C 04/23/84 06/14/85C 06/85C 00/90 04/88 CINEE 3 M47185 M 05/81C 04/23/84 06/14/85C 06/85C 01/84C 04/88
-. . I S A DES M47186 M 05/81C 12/15/83C 12/83C 12/83C 09/87C
- - { NT BEACH 1 M47147' M 05/81C 11/08/83C 11/83C 00/81C 11/87N JINT BEACH 2 M47148 M 05/81C 11/08/83C 11/83C 00/81C 11/87N 01IRIE ISLAND 1 M47150 M 05/81C 07/18/83C 07/83C 07/83C 10/87 ,
1\IRIE ISLAND 2 M47151 M 05/81C 07/18/83C 07/83C 07/83C 10/87 1
?;4CHO SECO 1 M47170 M 05/81C 05/15/86C 05/86C 05/86C 03/88 I 3IN50N 2 M47175 M 05/81C 09/27/83C 09/83C 11/81C 04/88 l 4.EM 1 M47162 M 05/81C 08/15/83C 08/83C 00/82C 05/87C i 1.EM 2 M47165 M 05/81C 08/15/83C 08/83C 00/83C 00/83C T8 ONOFRE 1 M47169 M' 05/81C 08/09/83C 08/83C 08/83C 03/88 s 1 0"Or2C 2 M6284", -12/85C 12/95/97 et/su tf/65C o 'voo -- 1 H NOFRC 3 M6 28 49 -- - ----12/8 5C~ - -- - - - - - - - 12/31/87 01/88----12/MG-8&44-JUDYAH 1 M51789 06/83C 12/30/83C 12/83C 10/84C 10/87C 23:10YAH 2 M51790 06/83C 12/30/83C 12/83C 10/84C 10/87C LUCIE 1 M42252 H 06/80C 05/06/83C 04/83C 00/83C 02/88
? -1216310-MPA RUN DATE: 03/1h8 SAFETY ISSUES MANAGEMENT SYSTEM PAGE 4 PLANT LEVEL INFORMATION trA NUMBER: B-66 TITLE: NATURAL CIRCULATION COOLDOHN DOCKET IMPOS RAI SE IMPOS IMPLEM VERITY PLANT TAC 8 PRIORITY INIT RAI RESPONSE TER INPUT COMPLET C_Off!1El (Qf1P_L EI
>JRRY 1 M47167 M 05/81C 10/19/83C 10/83C 09/86C 04/88
% JRRY 2 M47168 M 05/81C 10/19/83C 10/83C 09/86C 04/88
.iEE MILE ISLAND 1 M47157 M 05/81C 06/22/84C 06/84C 07/85C 12/87 10JAN M47179 M 05/81C 08/12/83C 08/83C 08/83C 10/87C IRKEY POINT 3 M47154 M 05/81C 08/05/83C 07/83C 00/83C 04/88N iRKEY POINT 4 M47155 M 05/81C 08/05/83C 07/83C 00/83C 04/88N LHKEE-ROHE 1 M47145 M 11/81C 10/25/83C 10/83C 10/83C 12/87N c.ON 1 M47187 M 05/81C 08/09/83C 08/83C 00/85C 03/88
/_ ION 2 M47188 M 05/81C 08/09/83C 08/83C 00/85C 03/88 e
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