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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217N4611999-10-22022 October 1999 Forwards Revised Pages 11,14 & 71 of Rept & Order Dtd 990608.Revs Are Textual Changes to Clarify & Confirm Action Taken by Nuclear Decommissioning Financing Committee 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 ML20210K4141999-08-0404 August 1999 Forwards Signed Originals of DD Issued Under 10CFR2.206. Without Encl 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 ML20206U9631999-05-18018 May 1999 Notification of Significant Licensee Meeting 99-27 with Util on 990602 to Discuss Predecisional Enforcement Conference - NRC Investigation ML20206R1691999-05-0707 May 1999 Rev 1 to Notification of 990602 Significant Licensee Meeting with Listed Attendees in King of Prussia,Pa Re Predecisional Enforcement Conference Concerning NRC Investigation.Rev Sighted Date Change ML20207G5681999-03-0808 March 1999 Informs That Commission Memorandum & Order (CLI-99-06), Issued on 990305,appointed TS Moore as Presiding Officer for Seabrook License Transfer Proceeding.With Certificate of Svc.Served on 990309 ML20197H1211998-12-0808 December 1998 Forwards Exam Rept with as Given Written Exam for Test Administered at Facility on 981019-23 ML20195C7641998-11-13013 November 1998 Forwards Pages That Were Faxed to J Peschel on 981113 in Preparation for Telcon That Will Be Scheduled Wk of 981116. Info in Attached Pages Based on Info Obtained from Licensee & Includes Specific Subjects to Be Discussed with Licensee ML20153E4211998-09-24024 September 1998 Informs That Ofc of Secretary Experienced Problems with Listed e-mail Address.Alternate Mailbox Has Been Created in Effort to Maintain Electronic Mailbox for Parties Filing by e-mail.With Certificate of Svc.Served on 980924 ML20153G0231998-09-24024 September 1998 Informs That Office of Secretary Experienced Problems with Dedicated e-mail Address.In Effort to Maintain Electronic Mailbox for Parties Filing by e-mail,alternate Mailbox Created.With Certificate of Svc.Served on 980924 ML20239A3361998-09-0404 September 1998 Forwards Request for Hearing & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League & New England Coalition on Nuclear Pollution Re Proposed License Amend for Seabrook Unit 1 ML20249A6691998-06-15015 June 1998 Forwards Request for Hearing, & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League. Petition Was Filed in Response to Notice of Proposed Determination by Staff ML20217M7161998-04-0303 April 1998 Notification of 980219 Meeting W/North Atlantic Energy Svc Corp in Rockville,Md to Discuss Great Power Corp Response to RAI Re Decommissioning Funding Assurance ML20216G5891998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-25 W/Util on 980324 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Rept 50-443/97-08 (EA-98-073) ML20198S4161998-02-26026 February 1998 Submits Impact of New Decommissioning Funding Rule on Great Bay.Staff Intends to Propose Some Addl Mechanisms That Appear to Offer Assurance Equivalent to What Existing Mechanisms Provide ML20203B9021998-02-0909 February 1998 Notification of 980219 Meeting W/North Atlantic Energy Service Corp in North Bethesda,Md to Discuss Proposed License Amends to Support Current Operating Cycle & Plans for Conversion to Improved Standard TSs ML20199E8881998-01-23023 January 1998 Notification of 980204 Mgt Meeting W/North Atlantic Energy Svc Corp in Rockville,Maryland to Discuss SALP for Period Covering 960505-971206 as Documented in SALP Rept 50-443/97-99 ML20198N0191998-01-0909 January 1998 Forwards Draft Rept, ,to Docket for Seabrook Station,Unit 1.Draft Rept Provides Licensee Preliminary Root Cause Analysis for Leaks in Piping of B Train of RHR System.Leakage Reported by Licensee on 971205 ML20203D2971997-12-0909 December 1997 Notification of 971216 Meeting W/Utils in Rockville,Md to Discuss Decommissioning Funding Assurance ML20211E7301997-09-23023 September 1997 Notification of 971028 Meeting W/North Atlantic Energy Service Corp in Rockville,Md to Discuss Approach for Extending Surveillances to 24-month Intervals ML20217B0471997-09-11011 September 1997 Notification of 970924 Meeting W/Eastern Utility Associates & North Atlantic Energy Service Corp in Rockville,Md to Discuss Proposed Electric Generating Asset Divestiture Plan ML20141D8191997-06-26026 June 1997 Forward 970624 Memo from P Milano to C Hehl Re Response to TIA Concerning Vantage 5H ZIRLO Fuel Problems at Plant,To Be Placed on Docket 50-443 & Made Publicly Available ML20141C9921997-06-24024 June 1997 Responds to 970605 TIA Re VANTAGE-5H ZIRLO Fuel Problems at Seabrook.Staff Has Not Identified Any Restart Concerns Re Reloading of VANTAGE-5H ZIRLO Fuel Used During Cycle 5 & W/Fresh VANTAGE-5H ZIRLO Fuel for Cycle 6 at Plant ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134H7931996-11-0606 November 1996 Partially Deleted Memo Re 950502 Meeting W/Northeast Utilities Re Listed Topics 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 ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20129C0271996-10-11011 October 1996 Notification of 961030 Public Meeting of Nuclear Decommissioning Committee ML20129E2011996-09-25025 September 1996 Notification of 960930 Meeting W/Util in Rockville,Md to Discuss Status of Great Bay Power Corp as Electric Util ML20147J3281996-07-10010 July 1996 Discusses Staff Response to SRM M960612, Briefing on Part 100 Final Rule on Reactor Site Criteria. Staff Believes That Draft Final Rule Language May Be Misinterpreted as Implicity Overruling in Conflict W/Seabrook Decision ML20129D1831996-07-10010 July 1996 Informs of 960716 Visit W/B Patricelli,Cm Cleveland & Gw Davis of Northeast Utilities,Inc Re Introductions & Discussions of Millstone Point & Haddam Neck Issues ML20134B6681995-10-13013 October 1995 Forwards Briefing Package on Status of Listed Plant Units,As Background for Visit by Northeast Utils on 951018-19 ML20087B8531995-07-25025 July 1995 Forwards State of Nh Nuclear Decommissioning Finance Committee Third Supplemental Order Approving Revised Funding Schedule by North Atlantic Energy Svc Corp ML20134B5861995-06-0101 June 1995 Forwards Briefing Package on Status of Plants as Background for Util Visit on 950608 ML20134B5721995-04-26026 April 1995 Forwards Briefing Package on Status of Listed Plants,As Background for Visit by Util on 950502.Supporting Documentation Encl ML20078S9391994-12-23023 December 1994 Forwards State of Nh Nuclear Decommissioning Finance Committee (Ndfc) Ndfc 93-1, Brief of Nh Public Utilities Commission Staff NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B4931994-02-16016 February 1994 Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation ML20059J8371994-01-0606 January 1994 Notification of Significant Licensee Meeting 94-05 W/Util Emergency Preparedness Mgt Working Group on 940210 ML20058L9281993-12-15015 December 1993 Notification of 931221 Meeting W/North Atlantic Energy Svc Corp,Yaec & Intl Tech Svcs,Inc in Rockville,Md to Discuss Application of YAEC-1856P Methodology to Plant ML20058C9681993-11-19019 November 1993 Notification of Significant Licensee Meeting 93-147 W/Util on 931208 Re SALP Mgt Meeting for Period of 920301-930828 ML20059J2321993-11-0505 November 1993 Forwards Safety Evaluation Accepting LAR 92-14,submitted Via for TS Changes to Allow Independent Fixed Incore Detector Sys at Facility to Be Used for Periodic in-core Power Distribution TS SRs ML20128K8601993-02-0202 February 1993 Notification of Significant Licensee Meeting 93-13 W/Util on 930210 to Discuss General Engineering Programs ML20126K1461993-01-0505 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Transfer of Control of Interest of Eua Power in Plant ML20126J6211992-12-24024 December 1992 Forwards LER 88-009-01 Issued on 921113,discussing Increased Thrust Bearing Loading for RHR Pumps When Pumps Run at Reduced Flows.Concern Raised That Inservice Testing May Not Detect Problem Soon Enough to Avoid Failure ML20125B4461992-11-30030 November 1992 Notification of 921203 Licensee Meeting in King of Prussia, PA to Discuss Auxiliary Operator re-licensing Plans ML20128C2131992-11-16016 November 1992 Notification of Postponement of 921124 Meeting W/Util in King of Prussia,Pa to Discuss Process for Reissuing Reactor Operator Licenses Terminated After Auxiliary Operator Performance Review ML20128C0271992-11-13013 November 1992 Notification of Significant Licensee Meeting 92-168 W/Util on 921124 to Discuss Process for Reissuing RO Licenses That Have Been Terminated After an AO Performance Review ML20097B5821992-05-27027 May 1992 Recommends That Methodology Specified in Order 20,475 Be Revised to Require Util to Include in Base Rates,Amounts Required by Nuclear Decommission Financing Committee 17th Supplemental Order 1999-09-16
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217N4611999-10-22022 October 1999 Forwards Revised Pages 11,14 & 71 of Rept & Order Dtd 990608.Revs Are Textual Changes to Clarify & Confirm Action Taken by Nuclear Decommissioning Financing Committee ML20217J8951999-10-21021 October 1999 Staff Requirements Memo Re Affirmation Session on 991021, Rockville,Md (Open to Public Attendance) 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 ML20210K4141999-08-0404 August 1999 Forwards Signed Originals of DD Issued Under 10CFR2.206. Without Encl 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 ML20206U9631999-05-18018 May 1999 Notification of Significant Licensee Meeting 99-27 with Util on 990602 to Discuss Predecisional Enforcement Conference - NRC Investigation ML20206R1691999-05-0707 May 1999 Rev 1 to Notification of 990602 Significant Licensee Meeting with Listed Attendees in King of Prussia,Pa Re Predecisional Enforcement Conference Concerning NRC Investigation.Rev Sighted Date Change ML20207G5681999-03-0808 March 1999 Informs That Commission Memorandum & Order (CLI-99-06), Issued on 990305,appointed TS Moore as Presiding Officer for Seabrook License Transfer Proceeding.With Certificate of Svc.Served on 990309 ML20207F5021999-03-0505 March 1999 Staff Requirements Memo Re 990305 Affirmation Session, Rockville,Md (Open to Public Attendance).Commission Approved Memo & Order Which Granted Util Intervention Petition & Request for Hearing ML20197H1211998-12-0808 December 1998 Forwards Exam Rept with as Given Written Exam for Test Administered at Facility on 981019-23 ML20195C7641998-11-13013 November 1998 Forwards Pages That Were Faxed to J Peschel on 981113 in Preparation for Telcon That Will Be Scheduled Wk of 981116. Info in Attached Pages Based on Info Obtained from Licensee & Includes Specific Subjects to Be Discussed with Licensee ML20153G0231998-09-24024 September 1998 Informs That Office of Secretary Experienced Problems with Dedicated e-mail Address.In Effort to Maintain Electronic Mailbox for Parties Filing by e-mail,alternate Mailbox Created.With Certificate of Svc.Served on 980924 ML20153E4211998-09-24024 September 1998 Informs That Ofc of Secretary Experienced Problems with Listed e-mail Address.Alternate Mailbox Has Been Created in Effort to Maintain Electronic Mailbox for Parties Filing by e-mail.With Certificate of Svc.Served on 980924 ML20239A3361998-09-0404 September 1998 Forwards Request for Hearing & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League & New England Coalition on Nuclear Pollution Re Proposed License Amend for Seabrook Unit 1 ML20249A6691998-06-15015 June 1998 Forwards Request for Hearing, & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League. Petition Was Filed in Response to Notice of Proposed Determination by Staff ML20217M7161998-04-0303 April 1998 Notification of 980219 Meeting W/North Atlantic Energy Svc Corp in Rockville,Md to Discuss Great Power Corp Response to RAI Re Decommissioning Funding Assurance ML20216G5891998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-25 W/Util on 980324 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Rept 50-443/97-08 (EA-98-073) ML20198S4161998-02-26026 February 1998 Submits Impact of New Decommissioning Funding Rule on Great Bay.Staff Intends to Propose Some Addl Mechanisms That Appear to Offer Assurance Equivalent to What Existing Mechanisms Provide ML20203B9021998-02-0909 February 1998 Notification of 980219 Meeting W/North Atlantic Energy Service Corp in North Bethesda,Md to Discuss Proposed License Amends to Support Current Operating Cycle & Plans for Conversion to Improved Standard TSs ML20199E8881998-01-23023 January 1998 Notification of 980204 Mgt Meeting W/North Atlantic Energy Svc Corp in Rockville,Maryland to Discuss SALP for Period Covering 960505-971206 as Documented in SALP Rept 50-443/97-99 ML20198N0191998-01-0909 January 1998 Forwards Draft Rept, ,to Docket for Seabrook Station,Unit 1.Draft Rept Provides Licensee Preliminary Root Cause Analysis for Leaks in Piping of B Train of RHR System.Leakage Reported by Licensee on 971205 ML20203D2971997-12-0909 December 1997 Notification of 971216 Meeting W/Utils in Rockville,Md to Discuss Decommissioning Funding Assurance ML20211E7301997-09-23023 September 1997 Notification of 971028 Meeting W/North Atlantic Energy Service Corp in Rockville,Md to Discuss Approach for Extending Surveillances to 24-month Intervals ML20217B0471997-09-11011 September 1997 Notification of 970924 Meeting W/Eastern Utility Associates & North Atlantic Energy Service Corp in Rockville,Md to Discuss Proposed Electric Generating Asset Divestiture Plan ML20141D8191997-06-26026 June 1997 Forward 970624 Memo from P Milano to C Hehl Re Response to TIA Concerning Vantage 5H ZIRLO Fuel Problems at Plant,To Be Placed on Docket 50-443 & Made Publicly Available ML20141C9921997-06-24024 June 1997 Responds to 970605 TIA Re VANTAGE-5H ZIRLO Fuel Problems at Seabrook.Staff Has Not Identified Any Restart Concerns Re Reloading of VANTAGE-5H ZIRLO Fuel Used During Cycle 5 & W/Fresh VANTAGE-5H ZIRLO Fuel for Cycle 6 at Plant ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134H7931996-11-0606 November 1996 Partially Deleted Memo Re 950502 Meeting W/Northeast Utilities Re Listed Topics 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 ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20129C0271996-10-11011 October 1996 Notification of 961030 Public Meeting of Nuclear Decommissioning Committee ML20129E2011996-09-25025 September 1996 Notification of 960930 Meeting W/Util in Rockville,Md to Discuss Status of Great Bay Power Corp as Electric Util ML20147J3281996-07-10010 July 1996 Discusses Staff Response to SRM M960612, Briefing on Part 100 Final Rule on Reactor Site Criteria. Staff Believes That Draft Final Rule Language May Be Misinterpreted as Implicity Overruling in Conflict W/Seabrook Decision ML20129D1831996-07-10010 July 1996 Informs of 960716 Visit W/B Patricelli,Cm Cleveland & Gw Davis of Northeast Utilities,Inc Re Introductions & Discussions of Millstone Point & Haddam Neck Issues ML20134B6681995-10-13013 October 1995 Forwards Briefing Package on Status of Listed Plant Units,As Background for Visit by Northeast Utils on 951018-19 ML20087B8531995-07-25025 July 1995 Forwards State of Nh Nuclear Decommissioning Finance Committee Third Supplemental Order Approving Revised Funding Schedule by North Atlantic Energy Svc Corp ML20134B5861995-06-0101 June 1995 Forwards Briefing Package on Status of Plants as Background for Util Visit on 950608 ML20134B5721995-04-26026 April 1995 Forwards Briefing Package on Status of Listed Plants,As Background for Visit by Util on 950502.Supporting Documentation Encl ML20078S9391994-12-23023 December 1994 Forwards State of Nh Nuclear Decommissioning Finance Committee (Ndfc) Ndfc 93-1, Brief of Nh Public Utilities Commission Staff NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B4931994-02-16016 February 1994 Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation ML20059J8371994-01-0606 January 1994 Notification of Significant Licensee Meeting 94-05 W/Util Emergency Preparedness Mgt Working Group on 940210 ML20058L9281993-12-15015 December 1993 Notification of 931221 Meeting W/North Atlantic Energy Svc Corp,Yaec & Intl Tech Svcs,Inc in Rockville,Md to Discuss Application of YAEC-1856P Methodology to Plant ML20058C9681993-11-19019 November 1993 Notification of Significant Licensee Meeting 93-147 W/Util on 931208 Re SALP Mgt Meeting for Period of 920301-930828 ML20059J2321993-11-0505 November 1993 Forwards Safety Evaluation Accepting LAR 92-14,submitted Via for TS Changes to Allow Independent Fixed Incore Detector Sys at Facility to Be Used for Periodic in-core Power Distribution TS SRs ML20128K8601993-02-0202 February 1993 Notification of Significant Licensee Meeting 93-13 W/Util on 930210 to Discuss General Engineering Programs ML20126K1461993-01-0505 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Transfer of Control of Interest of Eua Power in Plant ML20126J6211992-12-24024 December 1992 Forwards LER 88-009-01 Issued on 921113,discussing Increased Thrust Bearing Loading for RHR Pumps When Pumps Run at Reduced Flows.Concern Raised That Inservice Testing May Not Detect Problem Soon Enough to Avoid Failure ML20125B4461992-11-30030 November 1992 Notification of 921203 Licensee Meeting in King of Prussia, PA to Discuss Auxiliary Operator re-licensing Plans ML20128C2131992-11-16016 November 1992 Notification of Postponement of 921124 Meeting W/Util in King of Prussia,Pa to Discuss Process for Reissuing Reactor Operator Licenses Terminated After Auxiliary Operator Performance Review 1999-09-16
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- y. j NUCLEAR REGULATORY COMMISSION E REGION I
'+, ,o# KING OF PRUSSIA, PENNSYLVANIA 19406 MAR OG 7965 MEMORANDUM FOR: Robert L. Baer, Chief, Engineering and Communications Branch, IE FROM: Stewart D. Ebneter, Director, Division of Reactor Safety, Region I -
SUBJECT:
POTENTIAL GENERIC ISSUE CONCERNING CROSBY SAFETY VALVES The purpose of this memorandum is to advise you of a potentially generic issue which may affect operating nuclear facilities.
Region I received a construction Deficiency Report, 10 CFR 50.55(e), from Public Service of New Hampshire involving the steam generator safety valves for the Seabrook Station, Enclosure 1. In an effort to determine the appro-priate vent stack size for these valves, full flow testing was performed at . ,
Wyle Laboratory. The test parameters required the valve opening to be meas ' !
ured in order to confirm the valve travel of 1.12 inches. Under varying vent '
stack sizes, the maximum valve travel achieved was 50% of the required value.
The guide ring setting was adjusted from the factory value of +150 to 0 in order to achieve the full travel. The Regional staff contacted the Chief Engineer of Crosby Valve Company, Mr. Dick Zohorsky, telephone (617) 384-3121, on February 7, 1985, to discuss the cause of the problem and determine if a Part 21 Report is appropriate. Crosby Valve was only generally aware of the problem, and had not received enough information to make a full assessment of the problem. We erged Crosby to expeditiously resolve this problem and evaluate the generic impact on operating nuclear facilities.
The Regional staff is tracking this matter and will keep your office apprised of any major development. For further information, contact H. Gregg ~of my staff at FTS:488-1295.
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Tt wart D. Ebneter, Director Division of Reactor Safety cc w/ enclosure:
S. Collins, DRP R. Gallo, DRp A. Cerne, SRI ,
8605300283 860521 PDR FOIA MURPHY 86-266 PDR g
SEABROOK STATION Engin:sring Offico Pub 5c Service of New HampeNro Mew Hampshire Yan1cee Division January 17, 1985 SBN- 751 l T.F. Q2.2.2 j l
l l
United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Richard W. Starostecki, Director Division of Project and Resident Programs
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket ,
Nos. 50-443 and 50-444 l (b) Telecon of December 21, 1984, A. L. Legendre, Jr. (YAEC) to J. Grant (Region I)
Subject:
Interim 10CFR50.55(e) Report, " Main Steam Safety Valve Ring Setting Deficiency"
Dear Sir:
We previously reported [ Reference (b)] a potential 10CFR50.55(e) item to Region I regarding the apparent deficiency in Crosby Main Steam Safety Valve ring settings. The deficiency was discovered at Wyle Labs during full flow testing of the Crosby valves to detetuine the proper vent stack size. In order to determine full flow, the valve disc travel was measured and a disc travel of 1.12 inches was confirmed to us as being required by Crosby Valve Company via telecon on December 3, 1984 The tests determined that the disc )
only traveled approximately 50% of the required distance with 3% accumulation.
The same limited disc travel occurred on later tests with larger diameter vent stacks. After discussions with Crosby, the ring setting was adjusted. The valve was retested and the required disc travel was achieved.
The problem and its reportability occurs because uncorrected reduced valve disc travel may invalidate certain assumptions on the Main Steam System
~in the FSAR Accident Analysis. The Seabrook FSAR Accident Analysis performed ]
by Westinghouse Corporation assuces that the Main Steam Safety Valves are fully open with 3% accumulation. The ring settings are adjusted at Crosby Valve Company and the valve disc travel is not normally measured to confirm the required lift in field test.
@(o ? 0%d L3 7
/$Vf_ s
$f-oc - oy 1 P.O. Box 300 + Seobrook.NH03874 + Telem(603)474-%21 l
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$nitt.d Stetso Nuclscr R2gulatery Crmmiccien Attention: Mr. Richard Starostecki, Director Page 2 In conclusion, we are performing additional testing on the Crosby Main Steam Safety Valve to verify the ring setting problem without any stack in-fluence whatsoever, and to determine the new ring settings. The results of these tests will be reported in a future interim 10CFR50.55(e) report by March 31, 1985.
Very truly yours,
)(,v, s4~h"3I J. DeVincentis, Director Engineering and Licensing cc: Atomic Safety and Licensing Board Service List Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 1
I
' Diana Curran ,
- - *Hirkon, Weies & J:rdan 20001 S Strsst N.W. Crentwood Board cf Colcctmen RED Delton Road Suite 430 Brentwood, New Hampshire 03833 Washington, D.C. 20009 Robert G. Perlis Office of the Executive Legal Director . Edward F. Meany U.S. Nuclear Regulatory Commission Designated Representative of g Washington, DC 20555 the Town of Rye 155 Washington Road Robert A. Backus, Esquire Rye, NH 03870
. 116 Lowell Street '
P.O. Box 516 Calvin A. Canney Mancehster, NH 03105 City Manager City Hall Philip Ahrens, Esquire 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801 Department of the Attorney General Augusta, ME 04333 Dana Bisbee, Esquire Assistant Attorney General Mr. John B. Tanzer Office of the Attorney General Designated Representative'of 208 State House Annex the Town of Hampton Concord, NH 03301 5 Morningside Drive Hampton, NH 03842 Anne Verge, Chairperson Board of Selectmen Roberta C. Fevear Town Hall y Designated Representative of South Hampton, NH 03642 the Town of Hampton Falls Drinkwater Road Patrick J. McKeon Hampton Falls, NH 03844 Selectmen's Office 10 Central Road Mrs. Sandra Cavutis Rye, NH 03670 Designated Representative of the Town of Kensington Carole r. Kagan, Esq.
RFD 1 Atonic Safety and Licensing Board Panel East Kingston, NH 03827 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Jo Ann Shotwell, Esquire Assistant Attorney General Mr. Angie }Lehiros Environmental Protection Bureau Chairman of the Board of Selecteen Department of the Attorney General Town of Newbury One Ashburton Place, 19th Floor Newbury, MA 01950 Boston, MA 02108 Town Manager's Of fice Senator Gordon J. Humphrey Town Hall - Friend Street U.S. Senate Amesbury, Ma. 01913 Washington, DC 20510 (Attn: Tom Burack) Senator Gordon J. Humphrey 1 Pillsbury Street Diana P. Randall Concord, NH 03301 70 Collins Street (Aten: Herb Boynton)
SE4 brook, NH 03874 Richard E. Sullivan, Mayor Donald E. Chick City Hall Town Manager Newburyport, MA 01950 l Town of Exeter l 10 Front Street Exeter, NH 03833 J
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- 2 g' ati . UNITED STATES NUCLEAR REGULATORY COMMISSION awou s *
$[s gh &' G pq y $31 PARK AVENUE n No or enuss:4. PENNSYt.VANIA 19405 JUN 101985 MEMORANDUM FOR: Robert L. Baer, Chief, Engineering and Generic Communication Branch, IE FROM:
Jacque P. Durr, Chief, Engineering Branch, Division of Reactor Safety, RI g
SUBJECT:
POTENTIAL GENERIC ISSUE CONCERNING RING SETTINGS OF CROSBY SAFETY VALVES Our memorandum to you dated March 6,1985, Enclosure 1, advised you of a poten-tial generic issue concerning ring settings which produce only 50*,, lift on Crosby Steam Generator Safety Valves (SG-SVs). A 10 CFR 50.55(e) Construction Deficiency report was issued by Public Service of New Hampshire (PSNH) advising of the ring setting problem at Seabrook Station. Our major concern was not with the installation at Seabrook, a plant under construction, but that opera-ting plants could have SG-SVs that may not achieve full lift; whereby, actual flow capacities and/or accumulation pressure are not representative of analyses.
We have held several phone conversations with both PSNH and Crosby to determine if the observed effects on otherlift deficiences are common to this model of valve and possible plants.
this fact. To date, we have been unsuccessful in establishing %
PSNH sent us a copy of the Ivyle test data, Enclosure 2, which we forwarded to MEB (NRR). PSNH is planning additional tests to resolve their specific installation problem. In our conversations with Crosby, we were told they were awaiting a purchase order to perform testing. Regarding Cresby's response, we believe there should be a stronger commitment and confirmation e
that their factory guide ring sett1ng of +150 is correct if such is the case, Based on our review of the PSNH/Wyle test data of the Crosby 6R10 SV (this valve is in the "R" orifice size category), it is apparent that design lift is not achieved with the factory ring settings. We call to your attention that the "R" orifice is at the upper end of commercial valve sizes and has a nozzle bore dia. of 4.513 in. (16.00 sq. in. area). Generally, the capacity certifi- 3- '
cation and functional tests required by ASME Section III are performed by the 9 , _ . . . , .
valve coefficient of discharge method where the manufacturers testing is done '
on much smaller valves and the design is then extrapolated to the larger size valves.
This raises the concern that functional demonstration of these large SVs may never have been performed. Additionally, the problem may extend to other SG-SV suppliers.
We are recommending that NRC Headquarters advise licensee's of the problem through an IE Information Notice, Bulletin or Generic Letter and request licensee's to show that their SG-SVs have full lift.
H. Gregg of my staff is available to provide assistance or additional infor-mation at FTS 488-1295.
m
$ CA =
- / Jacque P. Durr, Chief Engineering Branch, DRS, RI
Enclosures:
As Stated
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Meme for R.,Baar 2
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ey cc w/o encis:
S. Ebneter, Director, DRS S. Collins, ORP R. Gallo, ORP A. Cerne, SRI F. Cherny, NRR H. Gregg, EB
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9, l SSINS No.: 6835 "
IN 86-05 i
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 J p N- f 6 -@e' p c, January 31, 1986 7
IE INFORMATION NOTICE NO. 86-05:
MAIN STEAM SAFETY VALVE TEST FAILURES AND RING SETTING ADJUSTMENTS Addressees:
All pressurized-water-reactor (PWR) facilities holding an operating license (0L) or a construction permit (CP).
Purpose:
This notice is being provided to alert recipients of a potentially significant problem pertaining to spring actuated main steam safety valves that may possess less than the full-rated flow capacity. It is expected that recipients will review the information for applicability to their facilities and consider actions, if appropriate, to preclude a similar problem at their facilities.
However, suggestions contained in this information notice do not constit' te u NRC requirements; therefore, no specific action or written response is required.
NRC is continuing to obtain and evaluate pertinent information. If specific actions are determined to be required by NRC, an additional notification will be made.
Description of Circumstances:
In the fall of 1984, Public Service of New Hampshire sent the main steam safety valves (MSSVs) for its Seabrook plant to Wyle t.aboratories for full-flow testing to determine the proper vent stack size. To determine full flow, Wyle measured discCogpany.
Valve and Gage travel of the model number 6R10 valves manufactured by the Crosby The results of the tests indicated that the valves could not achieve
(+155 notches).
the required disc travel with the factory set ring setting develop required steam flow capacity.The Adequate disc travel lift was achievedeven not attainable was 50% of the with the largest diameter tailpipe.
Additional ring settings.tests were done in July 1985 to determine the appropriateness of the Specifically, the tests were to determine if the "as-shipped" ring' settings of the valves would allow the required disc travel with minimum tailpipe backpressure and to determine the effects on valve disc travel for a range of backpressures between 180 and 390 psig. During these tests, the upper (guide) ring required discsetting travel.wasThis adjusted from +155 to 0 and then to +25 to achieve the is a substantial adjustment. Subsequently, the t
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IN 86-05 Janusry 31, 1986 Page 2 of 2 licensee consulted with the valve manufacturer and agreed on ring settings of
+25 for the ring (see guide figure 1).ring and -25 (the original setting) for the lower (nozzle)
Full flow, full size tests of the sort described in this notice are not normal-ly performed by the licensee or valve vendor for large secondary safety valves, nor are they required by the ASME Code,Section III. Instead the valves are certified by extrapolations on data from tests of smaller valves.
The MSSVs on most PWRs, while not necessarily the same model or manufacturer as those at Seabrook, are generally at the upper end of the valve size range.
This raises the concern that full-sized flow demonstratien may never have been performed for many MSSVs and these may have incorrect ring settings. In addition, similar problems with ring settings have been found when full size tests were performed for PWR primary safety valves. Thus, these MSSVs may not be capable of providing full relief capacity in accordance with facility design requirements.
NRC is continuing to obtain and evaluate pertinent infornation. If specific actions are determined to be required by NRC, an additional notification will be made.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate regional office or this office.
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dward . Jordan, Director Divis n of Emergency Preparedness an Engineering Response Office of Inspection and Enforcement Technical
Contact:
Mary S. Wegner (301) 492-4511 Attachments:
- 1. Figure 1, Typical Main Steam Safety Valve
- 2. List of Recently Issued IE Information Notices l
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Attachment 1 IN 86-05 i
January 31, 1986 I
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i FIG.I T r'PICAL !%IN STEAM SAFETY VALVE
_ . _ _ _ . _ _ __. _ . _ _ _ _ _ _ _ _ . _ . - _ . . _ _ _ . _ . _ . _ _ . _ _ . _ _ . _ _ _ . _ , . . _ . _ _ . _ _ . , _ _ _ _ _ _ . _ _ . _ _ _ . _ _ , _ _ _ . . ~ . . _ . _ _ _ _ _ _ . . . _
e Attachment 2 9 IN 86-05 January 31, 1986 LIST OF RECENTLY ISSUE 0 IE INFORMATION NOTICES Information Date of Notice No. Subject Issue Issued to 86-04 Transient Due To Loss Of 1/31/86 All power reactor Power To Integrated Control System At A Pressurized Water facilities holding an OL or CP Reactor Designed By Babcock
& Wilcox 86-03 Potential Deficiencies In 1/14/86 All power reactor Environmental Qualification facilities holding Of Limitorque Motor Valve an OL or CP Operator Wiring 86-02 Failure Of Valve Operator 1/6/86 All power reactor Motor During Environmental facilities holding Qualification Testing an OL or CP -
86-01 Failure Of Main Feedwater ~ 1/6/86 All power reactor Check Valve Causes Loss Of facilities holding -
Feedwater System Integrity an OL or CP And Water-Hammer Damage 85-101 Applicability of 10 CFR 21 12/31/85 All power reactor "
To Consulting Firms Providing facilities holding g Training an OL or CP 85-100 Rosemount Differential 12/31/85 All power reactor Pressure Transmitter Zero facilities holding Point Shift an OL or CP 85-99 Cracking In Boiling-Water- 12/31/85 All BWR facilities Reactor Mark I And Mark II having a Mark I or Containments Caused By Failure Mark II containment Of The Inerting System 85-98 Missing Jumpers From Westling- 12/26/85 All Westinghouse house Reactor Protection designed PWR System Cards For The Over-facilities holding Power Delta Temperature Trip an OL or CP Function t 1
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i OL = Operating License CP = Construction Permit , !
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