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Category:BOARD NOTIFICATION (TO LICENSING BOARD OR LICENSING
MONTHYEARML20134B7891996-06-25025 June 1996 Board Notification 96-005:discussing Issues Which Involve Challenge Whether Southern Nuclear Operating Co,Inc Possesses Requisite Character,Competence & Integrity & Willingness to Abide by Regulatory Requirements ML20134B7501996-06-0505 June 1996 Board Notification 96-003:discussing Secretary of Labor Decision & Remand Order Which Found That Gap Managers Discriminated Against One of Their Employees,M Hobby ML20134B6771995-11-13013 November 1995 Board Notification 95-017:notifies of Contention Challenging Application of Gpc for Amends to Authorize Southern Nuclear to Operate Plant ML20059M9191993-11-19019 November 1993 Board Notification 93-023:forwards Region II Allegation Review Summary Rept Re Alleger Concern on Plant Diesel Generators ML20056D2531993-08-10010 August 1993 Board Notification 93-020:responses to Stated Senate Committee Requests for Info Re one-party Taping of NRC Licensee Employee Conversations Encl ML20062J2131993-05-0707 May 1993 Board Notification 93-012:notifies of Info Re 930331 Telcon on DOJ Decision to Close Investigation Concerning Alleged Diesel Generator Misrepresentations ML20062J2111993-04-14014 April 1993 Board Notification 93-007:notifies of Submittal of Addl Info Re Open Discovery Matters on Investigation Concerning Diesel Generator Misrepresentations ML20062J2051993-04-14014 April 1993 Board Notification 93-006:notifies of Encl Re Issuance of Partial Decision That Addresses 900911 10CFR2.206 Petition ML20062J1461991-09-12012 September 1991 Board Notification 91-006:transmits Addl Info to Board Notification 91-05 Re TS Requirements for RHR Sys During Shutdown Conditions ML20206R6471986-09-15015 September 1986 Board Notification 86-019:forwards SER Re Reanalysis of Thermal Response of Asco Solenoid Valves Used at Facility. Use of Valves Acceptable ML20212M4501986-08-25025 August 1986 Board Notification 86-018:forwards Author to Util Requesting Addl Info on Main Steam Line Break Analysis Re Asco Solenoid Valves.Methodology Used for Qualification of Valves Exposed to Superheat Conditions Questioned ML20137W9271986-02-28028 February 1986 Board Notification 86-008:forwards List of Board Notifications Re Facility Licensing Review That Have Not Been Addressed in Fes,Ser & Sser I or Were Addressed & Resolved in Insp Repts 1996-06-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20217M4281999-10-0808 October 1999 Requests That Attached Request for Addl Info Be Placed in Pdr.Informs That RAI Faxed to J Bailey on 991008 & Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC Staff & SNC Staff ML20207E2431999-05-11011 May 1999 Requests That Encl RAI Be Placed in Pdr.Rai Faxed on 990511 to J Bailey of Snoc to Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & Snoc Staff ML20207L7111999-03-11011 March 1999 Informs That Attached Topics Faxed Today to J Bailey of Southern Nuclear Operating Co,Inc for Sole Purpose of Preparing Licensee Personnel for Upcoming Conference Call ML20204C4751999-03-11011 March 1999 Forwards Exam Repts 50-424/98-302 & 50-425/98-302 for Exams Administered on 980721 ML20204B3651999-03-11011 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980721 ML20207H9181999-02-0505 February 1999 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on 980413-15 at Plant ML20207H9401999-02-0505 February 1999 Forwards Exam Repts 50-424/98-301 & 50-425/98-301 with as Given Written Exam for Tests Administered on 980413-15 IR 05000425/20010871998-09-22022 September 1998 Redirects Info Encl & Previously Considered as Proprietary, Per .W Ltr NSD-NRC-98-5757 Stated That Encl Rept Is No Longer Considered Proprietary.Encls Originally Submitted as Part of File Package 9504250187 ML20236N6301998-04-0101 April 1998 Submits Task Interface Agreement (TIA-97-12) Suppl Evaluation of TS Required Monthly & Refueling Interval Testing of P-4 Interlock for Vogtle Units 1 & 2 ML20198M9691998-01-13013 January 1998 Notification of 980128 Meeting W/Util in Rockville,Md to Discuss Plant TSs Re Reactor Trip Setpoints & Associated Application for License Amend, ML20236N5921997-12-22022 December 1997 Forwards Task Interface Agreement (TIA-97-12) Evaluation of TS Required Monthly & Refueling Interval Testing of P-4 Interlock for Vogtle Units 1 & 2 ML20199G7471997-11-19019 November 1997 Forwards Memo from Hn Berkow to Jr Johnson, Re Task Interface Agreement 97-07 on Instrument Setpoints,To Be Placed in PDR ML20236N5341997-10-29029 October 1997 Forwards Task Interface Agreement (TIA-97-12) Evaluation of Monthly Surveillance Testing of Reactor Trip Bypass Breaker & ITS P-4 Interlock for Vogtle Units 1 & 2 in Response to 970505 Request from Region II ML20211D8861997-09-16016 September 1997 Forwards SG Tube Insp Results.Results Were Faxed to J Bailey in Preparation for Conference Call ML20199J2931997-09-16016 September 1997 Discusses Region II Request for NRR Position on Util Practice of Establishing Procedures for RTS & ESF Actuation Sys Instrument Setpoints to Be Nominal Values W/Tolerances Beyond TS Max & Min Allowed Values ML20236N2571997-08-0707 August 1997 Forwards TIA-97-07,evaluation Re Reactor Trip & Engineered Safety Features Actuation Sys Instrumentation Setpoints for Plant,Units 1 & 2 ML20141E1781997-05-16016 May 1997 Notification of 970522 Meeting W/Util in Rockville,Md to Allow Licensee to Brief NRC Staff on Results of Analyses of Damage to Unit 1 SG That Was Caused by Parts of Failed Guide Tube Pin Assembly on or About 960529 ML20137R4421997-04-0707 April 1997 Requests That Audio Tapes Identified Be Returned in Order to Return to Region II Office.Licensing Proceeding Terminated & Staff Acted on 10CFR2.206 Petition Initially Filed ML20134P0721997-02-21021 February 1997 Notification of 970304-06 Meeting W/Gpc in Waynesboro,Ga to Review Selected Aspects of Licensee 960515 Submittal to NRC Requesting Approval of Amend to Physical Security & Contingency Plan ML20133G1711997-01-10010 January 1997 Notification of 970116 Meeting W/Util in Rockville,Md to Discuss Schedule for Licensee Submittal & Staff Review & Approval of Plans to Install Addl Fuel Racks in Plant Fuel Pools ML20135F5111996-11-29029 November 1996 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Decision of Board (LBP-96-16) Has Expired.Decision Became Final Agency Action on 961129. W/Certificate of Svc.Served on 961129 ML20134B7891996-06-25025 June 1996 Board Notification 96-005:discussing Issues Which Involve Challenge Whether Southern Nuclear Operating Co,Inc Possesses Requisite Character,Competence & Integrity & Willingness to Abide by Regulatory Requirements ML20134B7501996-06-0505 June 1996 Board Notification 96-003:discussing Secretary of Labor Decision & Remand Order Which Found That Gap Managers Discriminated Against One of Their Employees,M Hobby ML20134B6771995-11-13013 November 1995 Board Notification 95-017:notifies of Contention Challenging Application of Gpc for Amends to Authorize Southern Nuclear to Operate Plant ML20205C2841995-09-15015 September 1995 Informs That Lou Will Not Be Able to Attend 950923 Meeting, Due to Attendance in Headquarters with Chairman Steering Committee.He Will Also Be Gone on 950924 to Work on Vogtle Case ML20128G2831995-03-10010 March 1995 Discusses Region II Review of Proposed Ack Ltr for Vogtle Civil Penalty (EA 93-304),informing That L Reyes,Deputy Regional Administrator,Concurred on Document on 950310 ML20128G2671995-03-0909 March 1995 Forwards Proposed Ack/Closeout Ltr After Receipt of Gpc Check for Listed Amount in Vogtle Edg/Inaccurate Info Enforcement Action.Requests Assistance W/Expedition of Region Comments & Concurrence Re Ack/Closeout on Vogtle ML20128F5261995-01-20020 January 1995 Partially Deleted Memo Notifying Commission of Results of Settlement Discussions Initiated by Counsel for Georgia Power Co & Staff Intent to Accept Licensee Proposal to Resolve Matter ML20128G2291994-12-20020 December 1994 Informs That Last Version of Memo to Commission on Proposed Resolution of Enforcement Action in Vogtle Included in Attached File.Hard Copy to Be Provided.W/O Encl ML20128Q0711994-11-15015 November 1994 Forwards Vogtle Coordinating Group Evaluation of Georgia Power Co Response to Notice of Violation & Demands for Info ML20128G1521994-10-28028 October 1994 Discusses Result of OI Analysis of Gpc Response to Enforcement Action Per Conclusions in OI Rept, Case 2-90-020R ML20128G1311994-08-16016 August 1994 Discusses 940816 Telcon W/E Blake Re Vogtle Licensing Proceeding.E Blake Expressed Concern Re Length of Time Projected for NRC Staff Review of Gpc Response to NOV & Proposed Imposition of Civil Penalty for Vogtle ML20128Q0461994-08-15015 August 1994 Responds to 940804 Memo & Informs That Plant Coordinating Group Being Reassembled to Expeditiously Review,Analyze & Formulate Position on Adequacy of Responses by Gpc ML20129F7351994-06-0909 June 1994 Recommends That Issue Concerning Failure to Take Appropriate Action for Calcon Switch Problems Identified Prior to 900320 Be Closed W/O Further Action ML20128F4891994-05-0909 May 1994 Discusses Factors Involved Re Possible Press Misinterpretation of Scheduled Press Release Concerning Vogtle Enforcement Action Against Gpc ML20128F5421994-05-0909 May 1994 Informs That J Lieberman States That All Vogtle Officials Notified & Press Release Scheduled for 940510 Approved.Task Force Recommended to Commission That Gpc Should Be Cited for Unacceptable Inaccuracies in Reporting to NRC Only ML20128F4751994-05-0606 May 1994 Requests That Gpc & Southern Nuclear Operating Co Be Notified Re Attached Vogtle Press Release for 940509 ML20128G4311994-03-31031 March 1994 Partially Deleted Memo Informing That DPR Has Reviewed Regional Enforcement Recommendation,Draft Commission Paper & Demands for Info Re Vogtle Electric Generating Plant ML20129H1911994-03-0808 March 1994 Partially Deleted Memo Informing That on 940223,first Draft of Proposed Enforcement Action for Georgia Power Co Submission of Inaccurate & Incomplete Info on Plant DG Problem,Distributed ML20129H1361994-02-23023 February 1994 Partially Deleted Memo Forwarding Proposed Enforcement Action for Georgia Power Co Submission of Inaccurate & Incomplete Info on Plant DG Problem,For Review,Evaluation & Comment ML20059L3601994-01-31031 January 1994 Notification of 940202 Meeting W/Util in Rockville,Md to Discuss Review of Various Requested Licensing Activities ML20058K7791993-12-0606 December 1993 Forwards Ltr as Result of 931117 order,LBP-93-22 & Informs That Staff Will Answer Questions Recently Filed by Util ML20059M9191993-11-19019 November 1993 Board Notification 93-023:forwards Region II Allegation Review Summary Rept Re Alleger Concern on Plant Diesel Generators ML20129F7291993-11-0505 November 1993 Informs How IIT Supporting Documents on Plant Accessed in Nudocs ML20057E2991993-10-0404 October 1993 Forwards Safety Evaluation Accepting Proposed Emergency Action Level Changes in Rev 15 of Plant Emergency Plan ML20129H0341993-09-16016 September 1993 Forwards for Implementation,Charter for Preparation of Enforcement Proposal Associated W/Oi Investigation Case 2-90-020 Re Reporting DG Reliability.Nominated Individuals to Review Info Collected by OI Listed ML20129H0121993-09-10010 September 1993 Summarizes 930908 NRC Meeting in Rockville,Md Re Plans for Reviewing Findings of Ongoing OI Investigation Concerning 930320 EDG Failures.Meeting Attendees Listed ML20056F7981993-08-24024 August 1993 Notification of 930908-09 Meeting W/Util in Rockville,Md to Discuss Status of Current Licensing Issues & Safety Initiatives for Plants ML20129F6481993-08-14014 August 1993 Documents Series of Meetings at Which Concerns Re Issues of Mgt Integrity & Attitude at Plant Presented & Discussed 1999-05-11
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0,, UNITED STATES i 78 o NUCLEAR REGULATORY COMMISSION
< ..9 5 .a WASHINGTON, D. C. 20555
% , , , , ,+* SEP 15 Egb Docket Nos.: 50-424 and 50-425 MEMORANDUM FOR: The Atomic Safety and Licensing Board Panel for Vogtle (M. Margulies, O. Paris, G. Linenberger)
'FROM: John W. Thompson, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
SUBJECT:
BOARD NOTIFICATION REGARDING ENVIRONMENTAL QUALIFICATION OF ASCO SOLEN 0ID VALVES FOR V0GTLE UNITS 1 AND 2 (B0ARD NOTIFICATION NO. 86-19)
Enclosed is a safety evaluation prepared by the staff that addresses the environmental qualification of the ASCO solenoid valves used in Vogtle Units 1 and 2. The evaluation resolves the concern raised in a previous Board Notification (BN), No. 86-18, dated August 25, 1986. In the pre-vlous BN, the staff informed the Board that the acceptability of the methodology used in justifying the qualification of the ASCO valves when exposed to superheated steam conditions following a MSLB outside contain-ment was in question. In a subsequent meeting on August 27-28, 1986 and in follow-up infonnation submitted on September 2,1986, the applicant presented their case for finding the ASCO valves appropriately qualified.
In the enclosed evaluation the staff finds the applicant's re-analysis of the thermal response of the ASCO solenoid valves to be acceptable, and, therefore, qualified.
! @m QM tc/
l Jo n W. Thompson, Project Manager R Project Directorate #4 Division of PWR Licensing-A
Enclosures:
As stated cc: ACRS(10)
EDO Parties to the Proceeding (Seenextpage)-
E 916006 l
C p.
3 ENCLOSURE 1 Suunnary of NRC Staff Evaluation Regarding Qualification of ASCO Solenoid Valves For Vogtle Units 1 and 2 By an NRC staff memorandum dated August 25, 1986 (Board Notification No.
86-18), the Atomic Safety and Licensing Board Panel for Vogtle was notified of a staff request for additional information from the applicants on the Vogtle main steamline break (MSLB) analysis. The staff's request questioned, in part, the applicability of the themal lag methodology used to establis,h the qualification of ASCO valves exposed to superheat conditions following a main steamline break outside containment.
Of the four ASCO valve models used in safety-related applications at the Vogtle plant, the only one to which these concerns applied is ASCO valve model NP8321 located in the Main Steam Isolation Valve (MSIV) area. The staff's request for infonnation did not, in any manner, question the environmental qualification of the other three ASCO valve models:
Model NP8320 valves are fully qualified by test to 420*F. This I
qualification level exceeds the expected conditions in the MSIV area.
~
Model NP8316 is not required to perfonn any function to mitigate a MSLB in the MSIV area.
Model 206-381 solenoids 'are not located in the MSIV area and perform no essential function for, a MSL.B in the MSIV area.
Applicants met with the sta'ff on August 27 and 28,1986, and provided information to address the staff's concerns. Additional supporting information was provided by letters from applicants dated August 21, 1986 and September 2,1986 to specifically address the environmental qualification of ASCO valve model NP8321 located in the MSIV area. Applicants provided the Vogtle-specific MSLB temperature profiles calculated for the locations in
7-t the MSIV area and performed a thermal lag analysis to demonstrate that the surface temperature of ASCO valve model. NP8321 exposed to the calculated conditions, would reach a maximum of 326*F. The surface temperature is enveloped by the staff accepted qualification temperature of 346*F for this valve.
The staff has reviewed the information submitted by applicants to support the above statements and has concluded that applicants have provided an acceptable response to the concerns raised in the August 12 request for information as it applies to ASCO valves. The staff has also reviewed the methodology used in calculating the Vogtle specific environmental conditions resulting from a MSLB in the MSIV area and found it to be acceptable. The~
staff's detailed technical evaluation which forms the basis for these conclusions is attached.
Based on the staf f's review, the staff finds that the concerns raised regarding the qualification of ASCO valves in Board Notification 86-18 have been adequately and fully resolved. The responses to the information requested in the August 12, 1986 letter do not impact or alter any previous conclusions or staff testimony on Contention 10.5 regarding the qualification of ASCO valves used in the Vogtle plant.
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[y; G ' SAFETY EVALUATION REPORT l .: .x.C.' - '
'! ENVIRONMENTAL-QUALIFICATION OF
' ASCO SOLEN 0ID VALVES V0GTLE ELECTRIC GENERATING PLANT, UNITS 1 & 2
,- . Docket Nos. 50-424/425
By' memorandum dated August 25,1986 (Reference 1), the staff notified the Vogtle Atomic Safety and Licensing Board that the methodology used for the qualification of ASCO valves exposed to superheated steam conditions following a main steam line break (MSLB) outside containment was in question. The staff's request for additional infonnation, dated August 12,1986 (Reference 2), was attached to
' Board Notification 86-18. The Applicant informed the staff by letter dated August 21, 1986 (Reference 3) that the staff's concern is confined to the four, NP 8321 ASCO solenoid valves in the control building. The other ASCO i valves would either not be subject to environmental conditions that exceed their qualification temperatures or are not required to function in the event of a MSLB.
In a subsequent meeting held on August 27-28, 1986 and by letter dated September 2,1986 (Reference 4), the applicant presented a re-analysis of the environmental qualification of the NP 8321 solenoid valves, using a methodology more conservative than that previo~usly used.'
] II. Evaluation The applicant's more recent analysis used Vogtle plant-specific mass and energy release data as input to Bechtel FLUD code to calculate the temperature profiles in the control building for a spectrum of MSLBs. A thermal lag analysis based on a more conservative methodology was then performed.
- The previou's into three thermal analysis divided the temperature response of a component phases:
(1) the component temperature rise from ambient to the saturation temperature corresponding to the environment pressure; (2) the component remaining at saturation until the condensate is completely vaporized; (3) the component temperature rise based on forced convection heat transfer. -
The staff's request for additional information (Reference 2) was primarily directed at the methodology for calculating the duration of the second phase. In the revised analysis, the first two phases were assumed to occur instantaneously,
- i.e., the initial component temperature was assumed to be the saturation temperature.
The staff finds this assumption acceptable since the approach is more conservative i
than that prescribed in NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment". .-
The applicant used the calculated component interior temperature, instead of the surfact temperature, as prescribed in NUREG-0588, to assess equipment qualifi-cation. However, the applicant demonstrated in attachment 3 of Reference 4 that the temperature difference across the valve body for the ASCO NP 8321 solenoid valves would be less than 0.8'F. Therefore, the applicant added l'F to the cal-l p culated NP 8321 valve body temperature to obtain a surface temperature of 326*F.
The qualification temperature of the NP 8321 valves based on test data is 346'F.
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With a 20*F margin, the staff concludes that the ASCO NP 8321 solenoid valves
,73 are qualified for the worst case. environmental conditions following a MSLB v outside containment. '
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In response to a staff concern over the acceptability of the FLUD code, the
' applicant discussed at length, in the meeting on August 27-28, 1986, the results of a code verification analysis that was performed. The infortnation for four pertinent cases was included in Attachment 1 to Reference 4. In all~ cases, the i results calculated by the FLUD code compared favorably with the Bechtel COPDA and COPATTA codes, Battelle Frankfurt test data, and state point hand calculations.
Based on the FLUD code verification results. There is reasonable assurance that the Vogtle environmental temperature profiles are acceptable.-
III. Conclusion Based on the above evaluation, the staff concludes that the ASCO UP 8321 solenoid valves used at Vogtle, Units 1 and 2 are qualified to withstand superheated steam conditions that may occur following a MSLB outside containment.
IV. References
- 1. Memorandum from M. Miller to the Atomic Safety and Licensing Board Panel for Vogtle, dated August 25, 1986, subject: Board Notification' No. 86-18 Regarding ASCO Solenoid Valves for Vogtle Units 1 and 2.
- 2. Letter from M. Miller (NRC) to R. Conway'(Georgia Power Company)', dated August 12, 1986, subject: Request for Additional Infonnation on Confirmatory
) Item 9 - Steamline Break Analysis Outside Containment.
3.
Letter from J. A. Bailey (Georgia Power Company) to H. Denton (NRC),
dated August 21, 1986, subject: SER Confirmatory Item 9 - Steamline Break Outside Containment.
4.
Letter from J. A. Bailey (GPC) to H. Denton (NRC), dated September 2,1986, SER Confinnatory Item 9 - Steam Line Break Outside Containment.
e 4
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