Letter Sequence Other |
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MONTHYEARML20246L9891989-03-17017 March 1989 Requests Assistance in Integrating Multi-Plant Action B-94, Mark I Containment Drywell Corrosion W/Current Efforts Re Development of New Requirements for Inservice Insp of Steel Containments Project stage: Other 1989-03-17
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217D0201999-10-12012 October 1999 Requests Assistance in Determining If Info Submitted by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C9671999-10-12012 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C6151999-10-0707 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu, Inc Meets Criteria Set Forth in 10CFR20 Subpart E for Release of Property to Be Sold by Gpu ML20207H3721999-06-10010 June 1999 Informs That Attached Draft Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding, Was Transmitted by Facsimile to G Busch of Gpu Nuclear to Be Discussed in Conference Call Scheduled for 990614 ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20202H6011999-02-0303 February 1999 Notification of 990218 & 19 Meetings with Util in Forked River,Nj Re Overview & Discussion of Licensee Efforts Concerning Possible Early Shutdown & Decommissioning of Plant ML20154K9781998-10-15015 October 1998 Notification of 981103 Meeting with Gpu Nuclear,Inc in Rockville,Md to Discuss Planning for Possible Shutdown of Oyster Creek & Related Decommissioning Activities ML20154J0271998-10-13013 October 1998 Notification of 981028 Meeting with Gpu Nuclear Inc,In Rockville,Md to Discuss Licensee Calculations Re 980505 Licensing Basis Change Request ML20154B3731998-09-29029 September 1998 Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments ML20236T0891998-07-21021 July 1998 Notification of Significant Licensee Meeting 98-64 W/Util on 980804 in Forked River,Nj to Discuss NRC SALP for Period of 961201-980613 ML20247N5021998-05-14014 May 1998 Notification of Significant Licensee Meeting 98-46 W/Util on 980529 in King of Prussia,Pa to Conduct pre-decisional Enforcement Conference Re Three Apparent Violations Re Automatic Depressurization Sys Issues ML20216G6261998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-24 W/Util on 980323 Predecisional Enforcement Conference to Discuss Apparent Violation in NRC Integrated Insp Rept 50-219/97-11 (EA-98-049) ML20217C1041997-09-18018 September 1997 Notification of 970930 pre-decisional Enforcement Conference W/Gpu Nuclear,Inc in King of Prussia,Pa to Discuss Five Apparent Violations Re Three Control Issues & One Control of Matl in Emergency Swp Issue ML20210J6161997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Possible Plant Operating Scenarios,Current Status & Planning Activities Associated W/Scenarios ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20137R4531997-04-0101 April 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of LBP-97-01 Expired. Decision Became Final Agency Action on 970326.W/Certificate of Svc.Served on 970401 ML20132F7651996-12-16016 December 1996 Forwards Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response in Support of Licensee Motion for Summary Disposition. Document Replaces Unsigned Affidavit Which Was Filed on 961206 ML20132F7571996-12-13013 December 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision LBP-96-23 Has Expired. Commission Declined Review & Decision Became Final Agency Action on 961204.W/Certificate of Svc.Served on 961213 ML20135F4841996-12-10010 December 1996 Informs That Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response to Licensee Motion for Summary Disposition Filed on 961206,will Be Provided as Soon as Possible ML20134M6331996-11-21021 November 1996 Discusses TIA Re 10 CFR 50.59 Evaluation Prepared by Licensee to Allow Movement of Spent Fuel from SFP to Dry Storage Facility While Plant Is in Cold Shutdown ML20134L4891996-11-12012 November 1996 Forwards Copy of 961107 Amend 187 to License DPR-16 & Safety Evaluation for Facility ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129F6401996-10-25025 October 1996 Requests That Encl Handout for Nuclear Energy Inst/GPUN-OG/ NRC Conference Call on Nuclear Energy Inst/Epri Revised Source Term Task Force for Plant,Be Placed in Docket File 50-219 ML20134G1731996-10-24024 October 1996 Informs Commission That Final No Significant Hazards Consideration Determination & License Amend Will Be Issued on or About 961030 to Gpu Nuclear Corp,Per Util 960415 Request to Revise TS 5.3.1.B ML20128L7191996-10-0909 October 1996 Forwards from Jc Fornicola to K Cozen Re Consideration of Oyster Creek as Pilot Plant for Submittal of Revised Source Term ML20129G7861996-10-0101 October 1996 Discusses 960923 Telcon from P Gunter Re Listed Topics. Update of Status of SPF 2.206 & Memo to Commission from Taylor, Resolution of Sf Storage Pool Action Plan Issues, Also Discussed ML20132A9681996-06-12012 June 1996 Forwards Copy of Ltr Requesting NRC to Investigate & Correct Highly Inaccurate Public Statement That Appeared in Gpu June 1996 Neighborhood Update ML20059J8431994-01-11011 January 1994 Notification of Significant Licensee Meeting 94-02 W/Util on 940125 Re Enforcement Conference to Discuss NRC Operational Safety Team Insp Findings ML20059M7931993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Oyster Creek Safety Related Piping ML20059F9551993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Plant Safety Related Piping.Meeting Time Changed as Listed ML20059J5661993-11-0909 November 1993 Notification of 931119 Meeting W/Util in Rockville,Md to Discuss Proposed ISFSI & to Receive Status Rept on Staff Effort to Issue Certificate of Compliance for Standardized NUHOMS Sys & to Discuss License Requirements ML20058P9701993-10-18018 October 1993 Notification of Significant Licensee Meeting 93-133 W/Util on 931029 in Forked River,Nj to Discuss Operational Safety Team Insp Public Exit ML20057B4751993-09-16016 September 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20057D7141993-08-0303 August 1993 Requests Assistance in Determining Adequacy of Plant Methodology for Determining Reportability of Plant Operation Above Licensed Core Thermal Limit ML20128K9051993-02-0303 February 1993 Notification of Significant Licensee Meeting 93-15 W/Util on 930208 to Discuss Results of NRC Review of Plant Operation W/Degraded Shutdown Cooling ML20127F3661993-01-0505 January 1993 Notification of Significant Licensee Meeting 93-002 W/Util on 930126 to Discuss Integration of Simulator Into Training Program ML20126J8041993-01-0404 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Matters Re Core Spray Downcomer Leak (Weld L3a) ML20126J9941993-01-0404 January 1993 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20126F4571992-12-18018 December 1992 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Reactor Bldg Access Modification for Facility ML20217B0841991-03-0505 March 1991 Forwards AEOD Diagnostic Evaluation Team Rept for Plant for Info.Rept Documents Team Findings & Conclusions & Includes Discussions of Licensee Strengths & Weaknesses ML20058D5561990-10-31031 October 1990 Notification of 901114 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058D5721990-10-26026 October 1990 Notification of 901107 Meeting W/Util in Rockville,Md to Discuss Matters Re Fuel Channel Box Bowing ML20058A3411990-10-18018 October 1990 Notification of 901029 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20058N9351990-08-13013 August 1990 Notification of 900816 Meeting in Bethesda,Md W/Util to Discuss Emergency Response Data Sys ML20058M4071990-08-0808 August 1990 Notification of 900829 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058L5781990-07-31031 July 1990 Notification of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion Problem ML20055C3341990-02-0909 February 1990 Notification of 900216 Enforcement Conference Meeting 90-19 W/Util in King of Prussia,Pa Re Safety Concern Process & Degraded ADS Logic ML20247K8611989-09-15015 September 1989 Notification of 890927 Meeting W/Util in Rockville,Md to Discuss site-specific Response Spectra & Methodology to Develop New Seismic Floor Response Spectra 1999-06-10
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217D0201999-10-12012 October 1999 Requests Assistance in Determining If Info Submitted by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C9671999-10-12012 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu,Inc on 990922 in Response to NRC Ltr ,meets Criteria Set Forth in 10CFR20,Subpart E for Release of Property to Be Sold by Gpu ML20217C6151999-10-0707 October 1999 Requests Assistance in Determining Whether Info Sent by Gpu, Inc Meets Criteria Set Forth in 10CFR20 Subpart E for Release of Property to Be Sold by Gpu ML20207H3721999-06-10010 June 1999 Informs That Attached Draft Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding, Was Transmitted by Facsimile to G Busch of Gpu Nuclear to Be Discussed in Conference Call Scheduled for 990614 ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20202H6011999-02-0303 February 1999 Notification of 990218 & 19 Meetings with Util in Forked River,Nj Re Overview & Discussion of Licensee Efforts Concerning Possible Early Shutdown & Decommissioning of Plant ML20154K9781998-10-15015 October 1998 Notification of 981103 Meeting with Gpu Nuclear,Inc in Rockville,Md to Discuss Planning for Possible Shutdown of Oyster Creek & Related Decommissioning Activities ML20154J0271998-10-13013 October 1998 Notification of 981028 Meeting with Gpu Nuclear Inc,In Rockville,Md to Discuss Licensee Calculations Re 980505 Licensing Basis Change Request ML20154B3731998-09-29029 September 1998 Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments ML20236T0891998-07-21021 July 1998 Notification of Significant Licensee Meeting 98-64 W/Util on 980804 in Forked River,Nj to Discuss NRC SALP for Period of 961201-980613 ML20247N5021998-05-14014 May 1998 Notification of Significant Licensee Meeting 98-46 W/Util on 980529 in King of Prussia,Pa to Conduct pre-decisional Enforcement Conference Re Three Apparent Violations Re Automatic Depressurization Sys Issues ML20216G6261998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-24 W/Util on 980323 Predecisional Enforcement Conference to Discuss Apparent Violation in NRC Integrated Insp Rept 50-219/97-11 (EA-98-049) ML20217C1041997-09-18018 September 1997 Notification of 970930 pre-decisional Enforcement Conference W/Gpu Nuclear,Inc in King of Prussia,Pa to Discuss Five Apparent Violations Re Three Control Issues & One Control of Matl in Emergency Swp Issue ML20210J6161997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Possible Plant Operating Scenarios,Current Status & Planning Activities Associated W/Scenarios ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20137R4531997-04-0101 April 1997 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of LBP-97-01 Expired. Decision Became Final Agency Action on 970326.W/Certificate of Svc.Served on 970401 ML20132F7651996-12-16016 December 1996 Forwards Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response in Support of Licensee Motion for Summary Disposition. Document Replaces Unsigned Affidavit Which Was Filed on 961206 ML20132F7571996-12-13013 December 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision LBP-96-23 Has Expired. Commission Declined Review & Decision Became Final Agency Action on 961204.W/Certificate of Svc.Served on 961213 ML20135F4841996-12-10010 December 1996 Informs That Signed Copy of Affidavit of RB Eaton in Support of NRC Staff Response to Licensee Motion for Summary Disposition Filed on 961206,will Be Provided as Soon as Possible ML20134M6331996-11-21021 November 1996 Discusses TIA Re 10 CFR 50.59 Evaluation Prepared by Licensee to Allow Movement of Spent Fuel from SFP to Dry Storage Facility While Plant Is in Cold Shutdown ML20134L4891996-11-12012 November 1996 Forwards Copy of 961107 Amend 187 to License DPR-16 & Safety Evaluation for Facility ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129F6401996-10-25025 October 1996 Requests That Encl Handout for Nuclear Energy Inst/GPUN-OG/ NRC Conference Call on Nuclear Energy Inst/Epri Revised Source Term Task Force for Plant,Be Placed in Docket File 50-219 ML20134G1731996-10-24024 October 1996 Informs Commission That Final No Significant Hazards Consideration Determination & License Amend Will Be Issued on or About 961030 to Gpu Nuclear Corp,Per Util 960415 Request to Revise TS 5.3.1.B ML20128L7191996-10-0909 October 1996 Forwards from Jc Fornicola to K Cozen Re Consideration of Oyster Creek as Pilot Plant for Submittal of Revised Source Term ML20129G7861996-10-0101 October 1996 Discusses 960923 Telcon from P Gunter Re Listed Topics. Update of Status of SPF 2.206 & Memo to Commission from Taylor, Resolution of Sf Storage Pool Action Plan Issues, Also Discussed ML20132A9681996-06-12012 June 1996 Forwards Copy of Ltr Requesting NRC to Investigate & Correct Highly Inaccurate Public Statement That Appeared in Gpu June 1996 Neighborhood Update ML20059J8431994-01-11011 January 1994 Notification of Significant Licensee Meeting 94-02 W/Util on 940125 Re Enforcement Conference to Discuss NRC Operational Safety Team Insp Findings ML20059M7931993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Oyster Creek Safety Related Piping ML20059F9551993-11-17017 November 1993 Notification of 940119 Meeting W/Util in Rockville,Md to Discuss Matters Related to Water Backed Welding of Plant Safety Related Piping.Meeting Time Changed as Listed ML20059J5661993-11-0909 November 1993 Notification of 931119 Meeting W/Util in Rockville,Md to Discuss Proposed ISFSI & to Receive Status Rept on Staff Effort to Issue Certificate of Compliance for Standardized NUHOMS Sys & to Discuss License Requirements ML20058P9701993-10-18018 October 1993 Notification of Significant Licensee Meeting 93-133 W/Util on 931029 in Forked River,Nj to Discuss Operational Safety Team Insp Public Exit ML20057B4751993-09-16016 September 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20057D7141993-08-0303 August 1993 Requests Assistance in Determining Adequacy of Plant Methodology for Determining Reportability of Plant Operation Above Licensed Core Thermal Limit ML20128K9051993-02-0303 February 1993 Notification of Significant Licensee Meeting 93-15 W/Util on 930208 to Discuss Results of NRC Review of Plant Operation W/Degraded Shutdown Cooling ML20127F3661993-01-0505 January 1993 Notification of Significant Licensee Meeting 93-002 W/Util on 930126 to Discuss Integration of Simulator Into Training Program ML20126J8041993-01-0404 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Matters Re Core Spray Downcomer Leak (Weld L3a) ML20126J9941993-01-0404 January 1993 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20126F4571992-12-18018 December 1992 Notification of 930112 Meeting W/Util in Rockville,Md to Discuss Reactor Bldg Access Modification for Facility ML20217B0841991-03-0505 March 1991 Forwards AEOD Diagnostic Evaluation Team Rept for Plant for Info.Rept Documents Team Findings & Conclusions & Includes Discussions of Licensee Strengths & Weaknesses ML20058D5561990-10-31031 October 1990 Notification of 901114 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058D5721990-10-26026 October 1990 Notification of 901107 Meeting W/Util in Rockville,Md to Discuss Matters Re Fuel Channel Box Bowing ML20058A3411990-10-18018 October 1990 Notification of 901029 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Plant ML20058N9351990-08-13013 August 1990 Notification of 900816 Meeting in Bethesda,Md W/Util to Discuss Emergency Response Data Sys ML20058M4071990-08-0808 August 1990 Notification of 900829 Meeting W/Util in Forked River,Nj to Discuss Status of Licensing Activities for Plant ML20058L5781990-07-31031 July 1990 Notification of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion Problem ML20055C3341990-02-0909 February 1990 Notification of 900216 Enforcement Conference Meeting 90-19 W/Util in King of Prussia,Pa Re Safety Concern Process & Degraded ADS Logic ML20247K8611989-09-15015 September 1989 Notification of 890927 Meeting W/Util in Rockville,Md to Discuss site-specific Response Spectra & Methodology to Develop New Seismic Floor Response Spectra 1999-06-10
[Table view] |
Text
_ __ _ _ _ - _ _ _ _ _
o UNITED STATES 7*# g )
-y g NUCLEAR REGULATORY COMMISSION j
.g E WASHINGTON, D. C. 20555 g March 17, 1989 MEMORANDUM FOR: Frank P. Gillespie, Director Program Management, Policy Development and Analysis Staff, NRR FROM: Gary M. Holahan, Acting Director Division of Reactor Projects III, IV, Y and Special Projects, NRR
SUBJECT:
MPA B-94, " MARK I CONTAINMENT DRYWELL CORROSION,"
RECOMMENDATION FOR RECLASSIFICATION AND PPIORITIZATION, (TAC 40566)
The purpose of this memorandum is to request your assistance in integrating MPA B-94 " Mark I Containment Drywell Corrosion," efforts with other current efforts related to development of new requirements for inservice inspection of steel .
containments.
BACKGROUND Mark I steel containment drywell vessels are supported at the bottom of the vessel by a concrete basemat. At the outer edge of the supporting concrete is a sand cushion ring which provides a gradual stress transition for the drywell, from fixed support to freestanding. The sand cushion is provided with drain piping discharging into the wetwell (torus) cha:nber of the reactor -
building. The purpose of the drains is to permit escape of any water leaking into the sand cushion. The most likely source of water leakage into the sand cushion is leakage from the refueling cavity seal at the drywell vessel head.
In 1980, while refueling, personnel at the Oyster Creek Nuclear Generating i Station observed water coming from drain lines connected to the drywell vessel sand cushion. In 1986, during refueling, water was again observed coming from the sand cushion drains. Due to concern about the potential for corrosion of the drywell caused by moisture in the sand cushion, the licensee removed sec-tions of the drywell concrete curb and floor to permit ultrasonic testing of the steel drywell in the area abutting the sand cushion. (Removalofsections of the concrete interior curb area and floor was necessary in order to permit placement of ultrasonic transducers against the drywell shell interior at lo-cations where the exterior rests on the sand.) It was determined that consid-erable corrosion and reduction of drywell shell thickness had occurred.
Analyses indicated that sufficient thickness remained to meet ASME Code requirements. .
STATUS On December 8, 1986 the staff issued INFORMATION NOTICE 86-99 informing Mark I owners of the Oyster Creek event. On March 12, 1987, the staff issued j
Generic Letter 87-05 to these licensees requesting their plans for (1) assuring sand cushions are properly drained, (2) assuring water leakage into the sand cushion (during refueling) is minimized, and l
(3) performing ultrasonic testing of the drywell shell. ,)[
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CONTACT:
]d'p W. Long, NRR/PDSNP 492-1103 Of03 .d h !
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Mr.: Frank P. Gillespie- March.17, 1989 MPA B-94 was established to provide project management and. tracking of the GL 87-05 responses. . It was subsequently found that other facilities had wet sand cushions. At Dresden (both units) the drain lines are found to be capped.
When the caps were removed a large amount.of water was~ released (1900 gallons from Unit 2.and 1100 gallons from Unit 3). During the ensuing inspections-
- involving drilling of large permanent holes in the concrete interior floor of the drywell for UT transducers,- it was found that the interior side of the drywell shell under the poured concrete floor was also wet (water appeared in the drilled holes)!
Since reviewing the licensees' GL 87-05 responses, the staff has determined that new generic requirements for augumented periodic inservice. inspection related to the sand cushion area of Mark I steel containments are necessary.
Note: Brunswick is a Mark I but not a steel containment and is therefore not a .
concern for this issue. WNP-2 has a Mark II containment, but does have a steel drywell and sand cushion and therefore is subject to this concern.
ACTION / RECOMMENDATIONS The staff is presently planning to issue a new generic letter outTining new periodic augumented inservice inspection requirements aimed at the GL 87-05 sand cushion corrosion problem. However, we note that there are other concerns and pending actions related to steel containment deterioration and degradation. . In addition to corrosion in the sand cushion area, there.is evidence that corrosion may be taking place at other. locations in Mark I's. Information Notice 88-82 describes concerns relating to torus corrosion resulting from coating deterioration. Also, corrosion may be taking -
place in tendons of concrete containments.
It is our recommendation that any future requirements for additional contain-ment inspections not only encompass the sand cushion problem, but also any other necessary new ISI needs for steel and concrete containments. In addition we recommend a review of the potential adverse effects on severe accident vulnerability of the. permanent removal of drywell floor concrete from
'the area opposite the sand cushion in Mark I's. We note that EPRI currently has a research project to investigate use of electromagnetic acoustic trans-ducers to enable the drywell shell thickness to be measured without removal of ,
concrete. The EPRI effort is being pursued in support of future license ex- I~
tension needs, but is directly applicable to the B-94 concern and should be evaluated by the staff as a potential surveillance or ISI requirement. As an initial action, we recomend that Task Action Plan / Issue B-49 be redesignated ;
_ Generic Issue B-49 and be subjected to prioritization by RES. j l
N N t-Gary M. Holahan, Acting Director Division of Reactor Projects III, IV, V and Special Projects, NRR t
. o 1
Mr. Frank P. Gillespie March 17, 1989 MPA 8-94 was established to provide project management and tracking of the GL 87-05 responses. It was subsequently i sand cushions. At Dresden (both units)y found the drainthat other lines facilities are found had to be wet capped. {
When the caps were removed a large amount of water was released (1900 gallons i from Unit 2 and 1100 gallons from Unit 3). During the ensuing inspections J involving drilling of large permanent holes in the concrete interior floor of )
the drywell for UT transducers, it was found that the interior side of the drywell shell under the poured concrete floor was also wet (water appeared in J the drilled holes)!
Since reviewing the licensees' GL 87-05 responses, the staff has determined that new generic requirements for augumented periodic inservice inspection related to the sand cushion area of Mark I steel containments are necessary.
Note: Brunswick is a Mark I but not a steel containment and is therefore not a concern for this issue. WNP-2 has a Mark II containment, but does have a steel drywell and sand cushion and therefore is subject to this concern.
ACTION / RECOMMENDATIONS The staff is presently planning to issue a new generic letter outlining new periodic augumented inservice inspection requirements aimed at the GL 87-05 sand cushion corrosion problem. However, we note that there are other concerns and pending actions related to steel containment deterioration and degradation. In addition to corrosion in the sand cushion area, there is evidence that corrosion may be taking place at other locations in Mark I's. Information Notice 88-82 describes concerns relating to torus corrosion resulting from coating deterioration. Also, corrosion may be taking place in tendons of concrete containments.
It is our recommendation that any future requirements for additional contain-ment inspections not only encompass the sand cushion problem, but also any other necessary new ISI needs for steel and concrete containments. In addition, we recommend a review of the potential adverse effects on severe accident vulnerability of the permanent removal of drywell floor concrete from the area opposite the sand cushion in Mark I's. We note that EPRI currently has a research project to investigate use of electromagnetic acoustic trans-ducers to enable the drywell shell thickness to be measured without removal of concrete. The EPRI effort is being pursued in support of future license ex-tension needs, but is directly applicable to the B-94 concern and should be evaluated by the staff as a potential surveillance or ISI requirement. As an initial action, we recomend that Task Action Plan / Issue B-49 be redesignated Generic Issue B-49 and be subjected to prioritization by RES.
Original sicaed by r Gary M. Holahan, Acting Director Division of Reactor Projects III, IV, Y and Special Projects ,
(MPA B-94 RECOMMENDATIONS) ,
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