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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone 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 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 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 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 ML20217A5291999-10-0505 October 1999 Notification of 991026 Meeting with Vynpc in King of Prussia,Pa to Discuss Licensee Responses to Maint Rule Violation of 10CFR50.65(a)(3), Balancing Reliability with Unavailability 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 ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20211A4361999-08-18018 August 1999 Notification of Significant Licensee Meeting 99-47 with Entergy Nuclear,Inc on 990831 to Discuss Results of NRC Plant Performance Review of Pilgrim Nuclear Power Station Issued on 990409 ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management 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 ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone 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 ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20212H9471999-06-22022 June 1999 Informs That No Addl Work Required on TACs M91735 & M95118 & Closes TACs Administratively ML20212H7621999-06-22022 June 1999 Notification of 990701 Meeting with NEI & Entergy in Rockville,Md to Discuss Price-Anderson Issues Re Transfer of Pilgrim License from Beco to Entergy ML20196F0581999-06-21021 June 1999 Discusses Update of Status of Petition,Dtd 961125,as Amended by Ltr,Dtd 961223,by Petitioners Re Millstone,Units 1,2 & 3 & Haddam Neck Nuclear Facilities 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 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 ML20207F0951999-06-0404 June 1999 Forwards Figure 1 to Millstone Combined Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05.Rept e-mailed on 990604 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 IR 05000336/19990041999-05-10010 May 1999 Forwards Database Used by Licensee to Track Questions Asked During Osti,Insp Rept 50-336/99-04.Summary of Licensee Responses Also Provided 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 ML20206A6041999-04-23023 April 1999 Notification of 990506 Meeting with Util in Rockville,Md to Provide Northest Nuclear Energy with Opportunity to Discuss Status of Development of post-shutdown Decommissioning Activities Rept for Unit 1 ML20206A1791999-04-22022 April 1999 Forwards Supplemental Info Related to Questions Re 50 Mile Ingestion Pathway Associated with Millstone Nuclear Facility That Were Raised During 990414 Commission Meeting on Remaining Issues Re Proposed Restart of Unit 2 DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20206B2371999-04-19019 April 1999 Forwards Questions & Answers Addressing Long Island Emergency Planning Issue Raised at Commission Meeting ML20205L0301999-04-0909 April 1999 Notification of 990413 Meeting with Boston Edison Co & Entergy Nuclear Generation Co in Rockville,Md to Discuss Sale & Transfer of Pilgrim Station from Boston Edison Co to Entergy Nuclear Generation Co ML20205N1641999-04-0606 April 1999 Notification of Significant Licensee Meeting 99-18 with Util on 990420 in King of Prussia,Pa to Discuss Plant Unit 3 Outage Plans ML20205J1961999-03-31031 March 1999 Discusses Clarification of Enforcement Discussion in 990319 Millstone Independent Review Team Rept ML20205C3041999-03-23023 March 1999 Notification of Significant Meeting 99-15 on 990407 with NNECO in Waterford,Ct,To Discuss Operational Safety Team Insp Exit Meeting for Millstone,Unit 2 ML20207M7641999-03-16016 March 1999 Forwards Monthly Rept of Status of 10CFR2.206 Petitions as of 990228.During Feb Director'S Decision DD-99-01,DD-99-02, DD-99-03 & DD-99-04,became Final Agency Actions & Closed. Attachment 3 Filed in Central Files ML20205J2011999-03-15015 March 1999 Forwards Annotated Draft Info Notice 99-XX Re Inadvertent Discharge of Carbon Dioxide Fire Suppression Sys in Cable Spreading Room,Reflecting Util Changes ML20204B6181999-03-12012 March 1999 Notification of 990329 Meeting in Forked River,Nj to Discuss Licensee Efforts Re Possible Early Shutdown & Decommissioning of Facility ML20205J2731999-03-0909 March 1999 Forwards Request for Addl Info Transmitted on 990224 to T Silko of Vermont Yankee Nuclear Power Corp.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207H4601999-03-0404 March 1999 Notification of 990318 Meeting with Northeast Nuclear Energy Co in Waterford,Connecticut to Discuss Exit Meeting Results of Millstone Unit 2 Independent C/A Program C/A Insp Performed by NRR ML20207K4011999-03-0404 March 1999 Rev 1 to Notification of Significant Meeting 99-12 with Util on 990318 in Waterford,Ct to Discuss Recovery of Millstone, Unit 2.Location of Meeting Has Been Changed ML20207K4071999-03-0404 March 1999 Notification of Significant Licensee Meeting 99-11 with Util on 990318 in Waterford,Ct to Discuss Plans,Schedules & Progress Toward Recovery of Plant,Unit 2 ML20206U3581999-02-0303 February 1999 Notification of Significant Licensee Meeting 99-08 with Util on 990217 Re 40500 Corrective Action Team Exit Meeting 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 ML20202H7791999-02-0202 February 1999 Forwards Draft Request for Addl Info Re Loss of Main Feedwater Transient Analysis ML20202H7171999-02-0202 February 1999 Forwards Draft RAI Re Reg Guide 1.97 Deviation Request Involving Containment Area Radiation 1999-09-02
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J8951999-10-21021 October 1999 Staff Requirements Memo Re Affirmation Session on 991021, Rockville,Md (Open to Public Attendance) ML20217P5261999-10-20020 October 1999 Forwards Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217J3001999-10-20020 October 1999 Notification of 991104 Meeting with Gpu Nuclear,Inc & Amergen in Rockville,Maryland Re Sale & License Transfer of OCNGS from Gpun to Amergen ML20217E9841999-10-14014 October 1999 Forwards Petition for Leave to Intervene Submitted on 991006 by Connecticut Coalition Against Millstone & Long Island Coalition Against Millstone ML20217D3601999-10-13013 October 1999 Staff Requirements Memo on SECY-99-223 Re Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Ofc of Investigation Cases Nda: 1-96-002,1-96-007 & 1-97-007 & Associated Recommendation 6 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 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 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 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 ML20217A5291999-10-0505 October 1999 Notification of 991026 Meeting with Vynpc in King of Prussia,Pa to Discuss Licensee Responses to Maint Rule Violation of 10CFR50.65(a)(3), Balancing Reliability with Unavailability 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 ML20216F3591999-09-15015 September 1999 Informs That Encl SRM on COMSECY-99-016 Being Released to Public,Effective 990915.Encl Documents Including 990406 SRM in Response to Millstone Independent Review Team 990312 Rept & 990713 Memo from G Caputo Previously Released ML20211K1431999-09-0202 September 1999 Notification of 990920 Meeting with Util in Rockville,Md to Discuss Recent Developments in New England Re Industry Deregulation & Restructuring Affecting Nu Use of Performance Indicators as Operating Plant ML20211A4361999-08-18018 August 1999 Notification of Significant Licensee Meeting 99-47 with Entergy Nuclear,Inc on 990831 to Discuss Results of NRC Plant Performance Review of Pilgrim Nuclear Power Station Issued on 990409 ML20210U1461999-08-13013 August 1999 Notification of 990827 Meeting with NNECO in King of Prussia,Pennsylvania to Discuss Engineering Initiatives & Backlog Management 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 ML20210E9311999-07-26026 July 1999 Notification of 990825 Public Meeting in Waterford,Ct Re PSDAR for Plant Unit 1 ML20210K1421999-07-22022 July 1999 Informs That Recipient Designated Chairman of Millstone Assessment Panel & E Adensam,Designated Co-Chairman.Panel Established to Assist Region I & NRR in Coordination of NRC Resources for Performance Monitoring & Inspecting Millstone 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 ML20209G0541999-07-13013 July 1999 Submits Director'S Guidance 99-001,effective Immediately,As Result of SRM in Response to Recommendations in Plant Independent Review Team Rept, ML20216F3651999-07-0707 July 1999 Staff Requirements Memo Re COMSECY-99-016, Recommendations 2 & 3 of Mirt,Re Witness Credibility & OI Conclusions,Staff Requirements Memo ML20212J5161999-07-0101 July 1999 Documents,For Public Record,Interaction Between NNECO & NRC Staff Re Licensee Proposed Licensing Action Now Being Reviewed by NRC Staff ML20209D7621999-06-29029 June 1999 Notification of Meeting 99-40 on 990715 with Nuclear Energy Advisory Council in Waterford,Ct to Discuss Millstone Safety Conscious Work Environ/Employee Concerns Program ML20209D7721999-06-29029 June 1999 Notification of 990715 Meeting 99-39 with Util in Waterford, CT Re Corrective Action & Safety Conscious Work Environ/ Employee Concerns Program Team Exit Meeting ML20212H9471999-06-22022 June 1999 Informs That No Addl Work Required on TACs M91735 & M95118 & Closes TACs Administratively ML20212H7621999-06-22022 June 1999 Notification of 990701 Meeting with NEI & Entergy in Rockville,Md to Discuss Price-Anderson Issues Re Transfer of Pilgrim License from Beco to Entergy ML20196F0581999-06-21021 June 1999 Discusses Update of Status of Petition,Dtd 961125,as Amended by Ltr,Dtd 961223,by Petitioners Re Millstone,Units 1,2 & 3 & Haddam Neck Nuclear Facilities 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 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 ML20207F0951999-06-0404 June 1999 Forwards Figure 1 to Millstone Combined Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05.Rept e-mailed on 990604 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 ML20212A8181999-05-25025 May 1999 Staff Requirements Memo Re SECY-99-010, Closure of Order Requiring Third-Party Oversight of Northeast Nuclear Energy Implementation of Resolution of Millstone Station Employee Safety Concerns 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 IR 05000336/19990041999-05-10010 May 1999 Forwards Database Used by Licensee to Track Questions Asked During Osti,Insp Rept 50-336/99-04.Summary of Licensee Responses Also Provided 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 ML20206B2261999-04-28028 April 1999 Staff Requirements Memo Re Briefing on Remaining Issues Related to Proposed Restart of Millstone Unit 2 (SECY-99-109) on 990414 in Rockville,Md.Briefing Open to Public Attendance ML20206B2501999-04-28028 April 1999 Staff Requirements Memo Re SECY-99-109,recovery of Millstone Nuclear Power Station,Unit 2.Commission Agreed with Staff Conclusions That Nene Satisfied 960814,independent Corrective Action Verification Program Order ML20206B9511999-04-28028 April 1999 Staff Requirements Memo Re Briefing on Remaining Issues Concerning Proposed Restart of Millstone Unit 2 (SECY-99-109) on 990414 in Rockville,Md (Open to Public) ML20206A6041999-04-23023 April 1999 Notification of 990506 Meeting with Util in Rockville,Md to Provide Northest Nuclear Energy with Opportunity to Discuss Status of Development of post-shutdown Decommissioning Activities Rept for Unit 1 ML20206A1791999-04-22022 April 1999 Forwards Supplemental Info Related to Questions Re 50 Mile Ingestion Pathway Associated with Millstone Nuclear Facility That Were Raised During 990414 Commission Meeting on Remaining Issues Re Proposed Restart of Unit 2 DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20206B2371999-04-19019 April 1999 Forwards Questions & Answers Addressing Long Island Emergency Planning Issue Raised at Commission Meeting ML20205L0301999-04-0909 April 1999 Notification of 990413 Meeting with Boston Edison Co & Entergy Nuclear Generation Co in Rockville,Md to Discuss Sale & Transfer of Pilgrim Station from Boston Edison Co to Entergy Nuclear Generation Co ML20205H7291999-04-0606 April 1999 Staff Requirements Memo in Response to Millstone Independent Review Team 990312 Rept on Allegations of Discrimination in NRC Office of Investigations Cases 1-96-002,1-96-007, 1-97-007 & Associated Lessons Learned ML20205H7501999-04-0606 April 1999 Staff Requirements Memo in Response to EDO Memo Re OIG Inquiry,Case 99-01S & Remaining Issues from SECY-98-292.Commission Approved C/As Described in EDO Memo ML20205N1641999-04-0606 April 1999 Notification of Significant Licensee Meeting 99-18 with Util on 990420 in King of Prussia,Pa to Discuss Plant Unit 3 Outage Plans ML20205J1961999-03-31031 March 1999 Discusses Clarification of Enforcement Discussion in 990319 Millstone Independent Review Team Rept ML20205C3041999-03-23023 March 1999 Notification of Significant Meeting 99-15 on 990407 with NNECO in Waterford,Ct,To Discuss Operational Safety Team Insp Exit Meeting for Millstone,Unit 2 ML20207M7641999-03-16016 March 1999 Forwards Monthly Rept of Status of 10CFR2.206 Petitions as of 990228.During Feb Director'S Decision DD-99-01,DD-99-02, DD-99-03 & DD-99-04,became Final Agency Actions & Closed. Attachment 3 Filed in Central Files ML20205J2011999-03-15015 March 1999 Forwards Annotated Draft Info Notice 99-XX Re Inadvertent Discharge of Carbon Dioxide Fire Suppression Sys in Cable Spreading Room,Reflecting Util Changes 1999-09-02
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t g UNITED STATES e p,
- 1 ATOMIC ENERGY COMMISSION ,,
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) DIRECTORATE OF REGULATORY OPERATIONS REGION lll */
s e % Pas o' 799 ROOSEVELT ROAD pag GLEN ELLYN. ILLINOIS 6o137 (312) 458-2840 July 31, 1973 S. Bryan, Senior Reactor Engineer, Field Support and Enforcement Branch Directorate of Regulatory Operations, Headquarters RU: Gaston Fiore111, Chief, Reactor Operations Branch Directorate of Regulatory Operations, Region III ELECTROMATIC RELIEF VALVE OPERATIONS Per your telephone request of July 18, 1973, an estimate of main steam electromatic relief valve operations at operating conditions was obtained from stations shown below. Preliminary summary was provided to you in a telephone conversation July 23, 1973. Monticello actuations were revised downward to eliminate tests at ambient pressure.
Valve Actuation Breakdown Total Valve Actuations Testing Reseating Operational Dresden 2 30 28 -
2 Dresden 3 6 5 -
1 Monticello 62 15 -
47 Quad Cities 1 30 6 3 20 Quad Cities 2 66 36 7 23
.0 W H."C. Dance Senior Reactor Inspector BWR Operations Section 8705050211 870428 PDR FOIA THOMAS 87-40 PDR
.,' l
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. SUlUtARY OF RELIEF VALVE OPERATiou AT QLHPS The following is the summary of relief valve operations (fi..nually or autcsneticcliv}
for both units"in response to AEC's request. This sun.1ary docs not include valve operations in pre-ops, logic tests, or cny relief volve operation ,with reactors at pressures below 100 lbs. This summary is based on documented evidence end invali-
. dates all previously given figures which were mainly based on educated guess.
1; D 2-7 3 - 1 (Unit 2) 1-3-73 HSIV CLOSURE A: 2 Times 8: 1 Time C: 1 Time' E: 1 Time SUDT01 AL-1: Ej'irm. .
- 2. 3-4-2-73-6 (Unit 2) 1-13-73 GEli TRIP / LOSS CF AUX.
A: 3 Times .
SUBTOTAL-2: 3 Tirey_ ,
- 3. D-4-2-73-9 (Unit 2) 1-20-73 RELIEF Fall.URE
. A: 2 Times 3 B: 2 Times C: 2 Tim 2s D: 1 Time E: 2 Times SUDTOYAL-3: (
.LT_ia.in
- 4. D-4-2-73-32 (Unit 2) 6-7-73 FEED UATER REG. VLV.
AIR LiliE Link.
A: 3 Times C: 1 Time E: 2 Times SUDTOTAL-4: 6 Tir-e.
5 STI -26 (Unit 2) 5-28-72--6-6-72 RELIEF VALVE TEST A: 1 Time B: 1 Time l , C: 1 Time l
i D: 1 Time E: 1 Time SUDRITAL-5: 3 Tinw
- 6. SURVEILLANCE (Unit 2) 4-30-73 (FOLLO'illNG li3DIFICATION)
A: 1 Time B: 1 Time C: 1 Time D: 1 Time E: 1 Time SUDTOTAL-6: 3 Tiras S
b l
,_ _ w,
v
..~
- 7. 'STI 98 Ass (Unit 2) 10- 19A72 -- 10-21 -72 SFECIAL REllEF TEST l
A 2 Times
- ,g C: 1 Time D: 1 Time f ,E : 6 Times ' '.
/ SUBTOTAL-7: 16 Tim _S, t
./ 8. STI 98 (Unit 2) 6-19-72 TORUS PRESS. 1! AVE TEST
/ A: 8 Times i
B: 7 Times C: 7 Tices D: 4 Times E: 3 Times SUBTOTAL-8: 20 Tines
- 9. STI 26 (Onit1) 4-21-72 REllEF VALVE TEST A: 1 Time 0: 1 Time C: 1 Time 0:
1 Time E: 1 Time SUBTOTAL-9: 3 Tina 3
- 10. SURVEILLn!'CE TEST (Unit 1) 5-8-73 (AFTER l'UDIF ICA~il0N)
A: 1 Time B: 1 Time C: 1 Time 0: 1 Time E: 1 Time SUBTOTAL-10: 5 TIEP.E
- 11. STI 31 (Unit 1) 7-2-77 LOSS OF AUX.
A: 20 Times SUBTOTAL-il: 20 Tinar.
' SUM TOTAL UillT - 1 _10_ ,
U!41T - 2 78 _
DDTH IG2 .l.21 SUM TOTAL FOR EACll VALVE:
UNIT-1 UNIT-?
A: 22 A: 22 D: 2 B: JR C: 2 C: 14 D: 2 D: ,8 ,
E: 2 E: 16 30 78 Prepared by,
, K. Salchl 8-1-73 E
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Facility: Millstone I (Millstone Point Company)
Source of Information: Jim Ferland, Assistant Plant Superintendent Layout of Relief Valves: Each of three relief valves discharges through an individual pipe into the torus.
History of Relief Valve Operations at Pressure and Temperature (18 events involving 40 cycles of valves to July 20, 1973)
Date Reason Valve: "A" "B" "C" 11/25/70 Test (one at a time) 1 1 1 12/03/70 Test (one at a time) 2 1 1 12/04/70 S.U. Test (three at once) 1 2 1 i 1/10/71 S.U. Test MSIV closure (2 at once) 1 1 0 j 2/14/71 Testing & Load Rejection (one at a time) 2
' 1 1 2/16/71 Test 0 0 1 2/18/71 Testing & Load Rejection (one at a time) 1 0 1 3/28/71 Test 0 1 0 5/12/71 Test -
1 0 0 1 5/31/71 Test 0 0 2 6/11/71 Test (one at a time) 1 0 1 6/29/71 Test 0 0 2 9/06/71 Test 0 0 1 9/09/71 Failure of Pressure Regulator 1 0 0 3
9/29/71 Test (one at a time) 0 1 2 10/10/71 Failure of Pressure Regulator 0 1 0 10/25/71 Test (one at a time) 1 1 1 3/07/73 .
Test (one at a time) 1 1 1 e
t e
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1-
Facility:
Vermont Yankee (Vermont Atomic Electric Co.)
u Note: Torus designed for 183 cycles per year for 40 ye'rs a (GE basis).
Source of Information: Bradford Riley, Plant Superintendent Layout of Valves: Each valve has an individual ramshead discharge point in the torus.
History of Relief Valve Operations at Pressure and Temperature (6 events involving about 14 cycles of valves to July 19, 1973 - estimated
- 257. error in number of cycles) 9/26/72 Manually opened each of 4 relief valves (startup test) at 207. power.
11/17/72 Manually operated 2 valves one at a time to relieve '
after MSIV closure occurring during shutdown ac-companying auxiliary transformer fire.
12/12/72 Manually opened one valve ("B") twice to relieve pressure. (No estimate of giuration.)
12/02/72 Automatic operation of "A", "C" and "D" valves simultaneously (and one safety valve opened temporarily) from 637. power with loss of
- normal power due to loss of startup trans-former. (No manual operation.)
1/17/73 Manual operation of "B" and' "D" one at a time -
to relieve pressure.
7/08/73 Manual operation "A" relief valve to relieve pressure.
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1 6 4 Fccility: Pilgrim (Boston Edison Co.)
Source of Information: Grant Baston Layout of Relief Valves: Each relief valve has individual tail-pipe to torus. (Of four steam lives, 4 relief valves are on three lines.)
History of Relief Valve Operations at Pressure and Temperature (13 events involving about 57 cycles of values to July 19, 1973) 7/21/72 Manually tested each of 4 relief valves for 1-5 seconds one at a time.
7/23/72 Manually operated one relief valve to relieve pressure '~
for 1-5 seconds.
9/16/72 Manually tested one relief valve (which had malfunctioned) for 1-5 seconds.
9/24/72 Manual operation of 2 or 3 valves to relieve pressure -
, total four times, total about a minute. (one valve at a time.
10/03/72 Manually tested one at a tLae 2 valves for about 15
. seconds each and 2 valves for about 20 seconds each.
10/26/72 Manually opened one valve at a time to relieve pressure,
, total of four times, about 20 seconds each, except that i last valve ("C") stuck open.
11/16/72 -
Manually tested one valve at a time each of 4 valves to determine capacity, aboct 10 seconds each.
j 11/29/72 Automatic opening two and then one relief valve about 5 seconds each after MSIV closure. (Then safety valve opened temporarily.)
Then three manual relief valve operation of about 30 seconds each were done one valve at a time.
12/30/72 About 8 manual operations of relief valves one at a time to relieve pressure (20-30 seconds each). (In hot standby after scram.)
1/01/73 D" relief valve failed to open on startup at about 940 lbs. and blev down to 600 lbs. before resetting (estimated about 2 minutes).
1/02/73 Manually tested replacement "D" valve for about 5 seconds.
9
Pilgrim - Pega 2 Jan & Feb'73 About six operations of B, C and D valves in attempts to seat the valves, about 5 seconds open each try.
3/06/73 About 13 valve operations following MSIV closure (estimated at 3 automatic and 10 manual of 5 seconds duration, respectively). (Manual operation was one at a time, automatic was not noted.)
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6 O
A I
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Facility: Oyster Creek (Jersey Central Power & Light Co.)
Source'of Information: Joe Carroll, Plant Superintendent Layout of Relief Valves: ; on one side of pressure vessel discharge into one downcomer 2 on the other side of pressure vessel dis-charge into one downcomer History of Relief Valve Operations at Pressure and Temperature (9 events involving about 36 cycles of valves to July 19,
. 1973) 12/25/70 At least one relief valve opene'd for an estimated 3 to 5 seconds following a stop valve closure.
9/26/71 Manually tested (opened) each of 4 (at that time) relief valves for 3-5 seconds following an outage, one valve at a time.
11/10/71 Manually tested (opened) the fifth or #E (newly in-stalled) relief valve for 3-5 seconds.
f 4/13/72 All 5 relief valves (assumed) opened after a turbine trip and reactor scram. EstLnated 3-5 seconds open all at the same time.
12/29/72 All 5 relief valves (assumed) opened. Estimated 3-5 4
seconds open all at the same time, and the "D" valve stuck open and blew down for about two hours.
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1/9/73 Manually tested all 5 relief valves. Estimated 3-5 seconds open one at a thme.
4/12/73 Manually tested 5 relief valves. One failed to open
- ('1") . Four valves were opened for 3-5 seconds one ,
at a time.
4 6/04/73 Manually tested 5 relief valves. Estimated 3-5 seconds open one at a time 6/30/73 All 5 relief valves (assumed) opened after a turbine trip and stop valve closure. Estimated 3-5 seconds open all at one time.
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- - - , . , . . . . . - . . , ,,n,,-n, .--,,,.-,...-n ,. ..~-:,-,.n,. . - , . . . - . , - , , ,n- , e,- -.-,,.-.,,v...,~._. r--w---,,----,n,-,, , -
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- Fccility: Nina Mile Point I (Nirgars Mohcwk PowIr Corp.)
Source of Information: Tom Perkins, Plant Superintendent Valve Layout: Each of six relief valves discharges through an individual pipe into the torus.
History of Relief Valve Tests at Pressure and Temperature. (Test on 9 dates involving 41 cycles of valves to July 20, 1973.)
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NIF' MIT2 POINT I *
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. Valve Cycles & Estimated Duration ,
D7tn Reasor, No. 111 No. 112 No. 113 No. 121 No. 122 No. 123 10/19/69 S.U. Test (Manual oper- 1 (2 sec.) 1 (5 min.) 3 (3 sec.) 1 (2 sec.) 1 (2 sec.) 1 (2 sec.)
ation, one at a time.)
11/01/69 same 0 1 (2 sec.) 1 (2 sec.) 1 (2 sec.) 1 (2 sec.) 1 (2 sec.)
11/01/69 same . 0 0 0 1 (2 sec.) 'l (2 sec.) 1 (2 sec.)
11/02/69 same 0 O O 1 (2 sec.) 0 -
0 5/26/71 Routine Test (Manual Oper- 2 (2 sec. 1 (4 sec.) 1 (3 sec.) 1 (2 sec.)- 1 (1 sec.) 1 (1 sec.)
ation,c one at a time.) ea.)
6/07/72 same 1 (4 sec.) 0 0 -
1 (4 se- ) 1 (2 sec.) 0 6/08/72 same 0 1 (1 sec.) 1 (1 sec.) 0 0 0 2 (2 sec.)
6/14/72 same 0 2 (1 sec. 0 0 0 0
,- ea.) .
'6/13/73 same ,
1 (1.7 sec.) 1.(1.4 sec.) 1 (45 min.*) 1 (1.0 sec.) 1 (1.4 sec.) 1 (1.2 sec.)
6/14/73 same 0 0 3** (2 sec. 0 0 0 ea.)
12/31/71 Automatic Operation 1 (4 sec.) 1 (3.5 sec.) 1 (1.4 sec.) 1 (4 sec.) 1 (4 sec.) 0-2/28/72 same 1 (2 sec.) 0 1 (2 sec.) 1 (2 sec.) 0 1 (2 sec.)
1 (3 sec.) 0 1 (3 sec.) 1 (3 sec.) 0 1 (3 sec.)
11/19/72 same 1 (4 sec.) 0 0 1 (4 sec.) 0 0 -
2/09/73 same 1 (1 sec.) 0 1 (1 sec.) 1 (1 sec.) 0 1 (1 sec.)
4/14/73 same 1 (4 sec.) 1 (4 sec.) 0 1 (4 sec.) 1 (4 sec.) O' 7/08/73 same 1 (3 sec.) 1 (3 sec.) 0 1 (3 sec.) 1 (3 sec.) 0 1.(6 sec.) 1 (6 sec.) 0 1 (6 sec.) 1 (6 sec.) 0
,v, .: ,- ,
e stuck open when tested **after valve was repaired a
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NEMO ROUTE SLIP _
5** =' tout taa- S or coccu"*aa- For act'oa-r rm AEC-95 8 Rev. Mar 14.1947) A EC 410240 i Net. s e ree w ra For stratu re. For saforastica.
- bNam. ar a watt) Inff8ALS REMAMS OPERATION OF AUTO'IATIC FRESSURE RELIEF SYSTEM AT BWR D. L. Ziemann, L FACILITIES oAn In response to a verbal request from John Riesland, Regulatorv Ooerations has made telechone incuiries nL to m cn. .no on.o n iiALs RuAAu present generation operating BWR facilities in order to obtain information en the number of tires the relief valves nave been operated (either real or test) oAn at operating temperature and pressure conditions. The results of these inquiries are provided as enclosures to this memo.
To (Name and uniu MTIALS A WAAM cc: D. Skovholt, L While the extent of data obtained varies from one faci:
gg' to another, I believe the specific information request (
H. Thornburg, R0 cAn by Mr. Riesland is included in the enclosures. If vou.-
R. Mc,Dermott, R0 desire further information, please let me know.
rnou cn.,n. .ns ue,v nuno
Enclosures:
- 1. Memo from Dance to Bryan, dtd. 7/31/73
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- 2. History of Relief Valve Operations -
E J. G..Keppler, R0 Millstone 1
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- 3. History of Relief Valve Operations- V.Y.
- ,fSJN,p,,s 4. History of Relief Valve Operations-Pilgric
- 5. History of Relief Valve Operations-Ovste_r_.
PHONE No. dan 6. History of Relief Valve Operations-9-Mile 7421 8/9/73 U$( 01 tR $10E FOR ACCITIC*eAL REMARM CPO r t ri 0 - 4 85 4'*
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.. u DRATT f2 dochet 1.'o. SU-2uS JIRiesla..J . sj i 10/3/72 t
Commonwealth Edison Company ATTN: Mr. Byron Lee, Jr.
' Assistant to the President Post Office Box 767 Chicago, Illinois 60690 Gentlemen .
1 Your letter datca Junc 7. 1972, describcd tne failurc of a number i
of ECCS suction header to suppression chamber hangers on Quad Citico Unit 2. 'Ih t re; ort dic t.ot provide adequate infornaticr. for our revio..
.iegula tor /- Operationu. however. cdvit.ec us that Courtonsecita Ecito:.
I Couinnf had agreed to huumit a ro;. ort to t;te Dirt etorate of Licer. sinc durina, t..c latter part of Augue.t 1>71.
We have not yet reccivee t..c I
t rcgort.
a fcilure of the ECCs suctiot. header uan3 cts was not u,. tic 1 rated I
c..6 . ca nc,t a.nal; m.; it. tat Safer.y t.nalysis Ee; ort. Cens eque..;1,.
tue fcilure i- conaldered by tue CouLission to Dc ar. carcvie. sed u.fctj
.usaticn. It. cccordance witn is CTR 3d.39. you nre required to submit an at:encmant to tae iSAR that described and evulunten t.ie ccrecqu;nces of a f ailure to tue ECCS suction header during norual or accident i
conditions and indicate the corrective measures, f any . hat arc i
required to eliminate deficiencies. Your submittal also should propose suryc111ance re<luirements for the ECCS suctiot header for incorporation in tac Technical Specifications.
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Cc:monucalth Edison Comi any 2 You are requested to provide the above information for Cotunission authorization to modify the ECCS suction header hangers with your schedule for completing the modification within 30 days.
Sincerely, Donald J. Skovholt Assistant Director for Operating Reactors virectorate of Licensing cc. . .r . C.iaries maituore President and Cuaircan Iowa -Illi:.ois uns a:.c ~
Liectric Companj idd East Second Avenut uavenport, Iowa 52601 J u ha 'n' . nowu, Esquire Isann iacolnat benle Counselors at Las Unc firs: 1;atici,a1 Plaza Lc.ic .:r.o . Illinoic vot7s t
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