Letter Sequence Draft RAI |
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MONTHYEARML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI Project stage: Draft RAI ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant Project stage: RAI 1999-06-21
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205Q9521999-04-15015 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980223-0304 ML20205P4861999-04-15015 April 1999 Forwards NRC Operator Licensing Exam Rept 50-354/98-03OL, (Including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20205N7101999-04-0909 April 1999 Forwards Info Which Was Transmitted by Facsimile on 990409 to C Manges of Pse&G,To Facilitate Conference Call in Order to Clarify Licensees Submittal ,which Provided Addl Info Re Relief Request for First 10-year ISI for Plant ML20205F9811999-03-31031 March 1999 Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207K3941999-03-0808 March 1999 Notification of Significant Licensee Meeting 99-13 with Util on 990322 in King of Prussia,Pa to Review Util & NRC Assessments Re Dec 1998 Licensed Operator Exam,Including Applicant Performance & Quality of Util Proposed Exam ML20203F5431999-02-12012 February 1999 Notification of 990225 Meeting with Public Service Electric & Gas Co & Asea Brown Boveri in Rockville,Md to Discuss Fuel Design Changes for Hope Creek Generating Station ML20198S3281999-01-0606 January 1999 Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b ML20196H1441998-12-0303 December 1998 Forwards Info from J Priets of Public Service Electric & Gas to R Ennis,Nrc Hope Creek Project Manager,Transmitted to Facilitate NRC Review of License Change Request Associated with Facility Filtration,Recirculation & Ventilation Sys ML20196A6381998-11-25025 November 1998 Notification of 981207 Meeting with Util in Rockville,Md to Discuss Proposed License Change Request Re Filtration, Recirculation & Ventilation Sys for Plant ML20236S3371998-07-20020 July 1998 Notification of 980804 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Re Ush for Plant ML20249C1341998-06-17017 June 1998 Notification of Significant Licensee Meeting 98-59 W/Util on 980629 in King of Prussia,Pa to Discuss Licensed Operator Initial Training Program & Performance Problems at Plant for February 1998 Initial Exam ML20248M0371998-06-0909 June 1998 Notification of 980624 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Related to Filtration,Recirculation & Ventilation Sys for Hope Creek Generating Station ML20203B1211998-02-19019 February 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970929-1002 IR 05000354/19970081998-02-19019 February 1998 Forwards NRC Operator Licensing Exam Rept 50-354/97-08 (Including Completed & Graded Tests) for Tests Administered on 970929-1002 ML20198D1491997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-130 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Two Violations Re Performance Criteria for Sys & Components Associated W/Maint Rule Program ML20198D1421997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-129 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Violation for Failure to Follow Reactivity Manipulation Procedures for Control Rod Movements ML20149J9891997-07-22022 July 1997 Notification of Significant Licensee Meeting 97-88 W/Util on 970812 in King of Prussia,Pa to Conduct pre-decisional EC to Discuss Apparent Violations of 10CFR50.59 During Installation of Residual Heat Removal cross-tie Valve Mod ML20236M9111997-01-24024 January 1997 Describes Views on Broader Compliance Policy Concerns Associated W/River Bend Case Which Involves Complex Enforcement Policy Issues Associated W/Relationship Between Appropriate Use of Plant Administrative Controls ML20137B0781996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants IA-96-492, Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants1996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20135A6391996-11-20020 November 1996 Summarizes 940602 Meeting W/Listed Individuals to Discuss Items of Mutual Interest Re Plant Performance & Improvement Plans 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 ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20236M0141996-08-0505 August 1996 Recommends That Hope Creek Modify TS 3/4.5.1 to Conform W/ Sts,Which Specifies Steam Pressure & Flow as Necessary Conditions to Perform Test,To Avoid Further Interpretation Problems ML20135B3571996-02-27027 February 1996 Discusses 960222 Visit W/Listed Individuals to Discuss Issues Re Salem & Hope Creek Generating Stations ML20134K8691996-02-0909 February 1996 Partially Deleted Ltr Requesting OGC Interpretation of 10CFR50.5 Re Situation That Occurred at Util Plant ML18101A7851995-06-13013 June 1995 Advises That Util Current Drawer I Will Be Changed to Drawer 0509,effective 950612.Ltr from Hancocks Bridge Post Ofc Encl ML20134C6501995-05-0404 May 1995 Informs That Due to Pending EAs at Both Plants Scope of 950530 Eppr Has Been Reduced.Meeting Will Be Limited to 1 H ML20135B1791994-12-13013 December 1994 Discusses Pse&G 941129 drop-in Visit W/Listed Individuals to Discuss Items of Mutual Interest Including Plant Hope Creek & Salem Generating Station Performance ML20058C7731993-11-10010 November 1993 Notification of 931220 Enforcement Conference in Region I Ofc to Discuss Violations Noted in MOV NRC Team Insp ML20059G1621993-10-27027 October 1993 Notification of Significant Licensee Meeting 93-135 W/Util on 931207 to Discuss Hope Creek Motor Operated Valve NRC Team Insp Violation ML20135A8501993-08-0202 August 1993 Discusses 930723 Pse&G Visit W/Listed Individuals to Discuss Items of Mutual Interest Re Hope Creek & Salem,Units 1 & 2 NPP ML20134C7731993-07-0707 July 1993 Forwards Security & Safeguards SALP Input for Plants Covering Period 911229-930619 ML20128K2461993-02-12012 February 1993 Notification of 930224 Meeting W/Bwrog in Rockville,Md to Discuss Hope Creek Amend Request & SE Status (Increase MSIV Leakage,Remove Leakage Control Sys & Use Ms Lines & Condenser for Treatment) ML20134C8141992-01-16016 January 1992 Forwards SALP Input Relating to Emergency Preparedness for Period 900816-911231 ML20134C6441992-01-15015 January 1992 Forwards Security & Safeguards SALP Input for Plants.Input Covers Period of 900801-911228 ML20058D3211990-10-30030 October 1990 Documents Various Observations Made During INPO 900813-24 Evaluation Process at Facility ML18095A4331990-07-24024 July 1990 Advises That NRC Initiated Formal Section 7 Consultation W/ Dept of Commerce on 900618 Re Util Preparation of Biological Assessment of Plants ML20055G4331990-06-28028 June 1990 Forwards D Kwiatkowski of FEMA Transmitting FEMA Region I Rept for 881129-1201 Full Participation Exercise at Plants.Evaluation of 881202 Medical Drill Also Included in Rept.Encls Should Be Transmitted to Licensee 1999-08-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205Q9521999-04-15015 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980223-0304 ML20205P4861999-04-15015 April 1999 Forwards NRC Operator Licensing Exam Rept 50-354/98-03OL, (Including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20205N7101999-04-0909 April 1999 Forwards Info Which Was Transmitted by Facsimile on 990409 to C Manges of Pse&G,To Facilitate Conference Call in Order to Clarify Licensees Submittal ,which Provided Addl Info Re Relief Request for First 10-year ISI for Plant ML20205F9811999-03-31031 March 1999 Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207K3941999-03-0808 March 1999 Notification of Significant Licensee Meeting 99-13 with Util on 990322 in King of Prussia,Pa to Review Util & NRC Assessments Re Dec 1998 Licensed Operator Exam,Including Applicant Performance & Quality of Util Proposed Exam ML20203F5431999-02-12012 February 1999 Notification of 990225 Meeting with Public Service Electric & Gas Co & Asea Brown Boveri in Rockville,Md to Discuss Fuel Design Changes for Hope Creek Generating Station ML20198S3281999-01-0606 January 1999 Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b ML20196H1441998-12-0303 December 1998 Forwards Info from J Priets of Public Service Electric & Gas to R Ennis,Nrc Hope Creek Project Manager,Transmitted to Facilitate NRC Review of License Change Request Associated with Facility Filtration,Recirculation & Ventilation Sys ML20196A6381998-11-25025 November 1998 Notification of 981207 Meeting with Util in Rockville,Md to Discuss Proposed License Change Request Re Filtration, Recirculation & Ventilation Sys for Plant ML20236S3371998-07-20020 July 1998 Notification of 980804 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Re Ush for Plant ML20249C1341998-06-17017 June 1998 Notification of Significant Licensee Meeting 98-59 W/Util on 980629 in King of Prussia,Pa to Discuss Licensed Operator Initial Training Program & Performance Problems at Plant for February 1998 Initial Exam ML20248M0371998-06-0909 June 1998 Notification of 980624 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Related to Filtration,Recirculation & Ventilation Sys for Hope Creek Generating Station IR 05000354/19970081998-02-19019 February 1998 Forwards NRC Operator Licensing Exam Rept 50-354/97-08 (Including Completed & Graded Tests) for Tests Administered on 970929-1002 ML20203B1211998-02-19019 February 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970929-1002 ML20198D1421997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-129 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Violation for Failure to Follow Reactivity Manipulation Procedures for Control Rod Movements ML20198D1491997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-130 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Two Violations Re Performance Criteria for Sys & Components Associated W/Maint Rule Program ML20149J9891997-07-22022 July 1997 Notification of Significant Licensee Meeting 97-88 W/Util on 970812 in King of Prussia,Pa to Conduct pre-decisional EC to Discuss Apparent Violations of 10CFR50.59 During Installation of Residual Heat Removal cross-tie Valve Mod ML20236M9111997-01-24024 January 1997 Describes Views on Broader Compliance Policy Concerns Associated W/River Bend Case Which Involves Complex Enforcement Policy Issues Associated W/Relationship Between Appropriate Use of Plant Administrative Controls IA-96-492, Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants1996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20137B0781996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20135A6391996-11-20020 November 1996 Summarizes 940602 Meeting W/Listed Individuals to Discuss Items of Mutual Interest Re Plant Performance & Improvement Plans 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 ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20236M0141996-08-0505 August 1996 Recommends That Hope Creek Modify TS 3/4.5.1 to Conform W/ Sts,Which Specifies Steam Pressure & Flow as Necessary Conditions to Perform Test,To Avoid Further Interpretation Problems ML20135B3571996-02-27027 February 1996 Discusses 960222 Visit W/Listed Individuals to Discuss Issues Re Salem & Hope Creek Generating Stations ML20134K8691996-02-0909 February 1996 Partially Deleted Ltr Requesting OGC Interpretation of 10CFR50.5 Re Situation That Occurred at Util Plant ML18101A7851995-06-13013 June 1995 Advises That Util Current Drawer I Will Be Changed to Drawer 0509,effective 950612.Ltr from Hancocks Bridge Post Ofc Encl ML20134C6501995-05-0404 May 1995 Informs That Due to Pending EAs at Both Plants Scope of 950530 Eppr Has Been Reduced.Meeting Will Be Limited to 1 H ML20135B1791994-12-13013 December 1994 Discusses Pse&G 941129 drop-in Visit W/Listed Individuals to Discuss Items of Mutual Interest Including Plant Hope Creek & Salem Generating Station Performance ML20058C7731993-11-10010 November 1993 Notification of 931220 Enforcement Conference in Region I Ofc to Discuss Violations Noted in MOV NRC Team Insp ML20059G1621993-10-27027 October 1993 Notification of Significant Licensee Meeting 93-135 W/Util on 931207 to Discuss Hope Creek Motor Operated Valve NRC Team Insp Violation ML20135A8501993-08-0202 August 1993 Discusses 930723 Pse&G Visit W/Listed Individuals to Discuss Items of Mutual Interest Re Hope Creek & Salem,Units 1 & 2 NPP ML20134C7731993-07-0707 July 1993 Forwards Security & Safeguards SALP Input for Plants Covering Period 911229-930619 ML20128K2461993-02-12012 February 1993 Notification of 930224 Meeting W/Bwrog in Rockville,Md to Discuss Hope Creek Amend Request & SE Status (Increase MSIV Leakage,Remove Leakage Control Sys & Use Ms Lines & Condenser for Treatment) ML20134C8141992-01-16016 January 1992 Forwards SALP Input Relating to Emergency Preparedness for Period 900816-911231 ML20134C6441992-01-15015 January 1992 Forwards Security & Safeguards SALP Input for Plants.Input Covers Period of 900801-911228 ML20058D3211990-10-30030 October 1990 Documents Various Observations Made During INPO 900813-24 Evaluation Process at Facility ML18095A4331990-07-24024 July 1990 Advises That NRC Initiated Formal Section 7 Consultation W/ Dept of Commerce on 900618 Re Util Preparation of Biological Assessment of Plants ML20055G4331990-06-28028 June 1990 Forwards D Kwiatkowski of FEMA Transmitting FEMA Region I Rept for 881129-1201 Full Participation Exercise at Plants.Evaluation of 881202 Medical Drill Also Included in Rept.Encls Should Be Transmitted to Licensee 1999-08-05
[Table view] |
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- June 21, 1999 MEMORANDUM TO: Docket File !
Original signed by:
FROM: Richard B. Ennis, Project Manager, Section 2 Project Directorate I
. Division cf Licensing Project Management '
Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION, INCREASE OF ALLOWABLE MAIN STEAM ISOLATION VALVE (MSIV) LEAK RATE AND DELETION OF MSIV SEALING SYSTEM (TAC MA4471)
The attached draft request for additional information (RAI) was transmitted by facsimile on ' June 17,1999 to Mr. Gabe Salamon of Public Service Electric & Gas Company (PSE&G).
Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAl. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50 354
Attachment:
Draft RAI S C Rf CENTS CDPT DISTRIBUTION Docket File -
PUBLIC JClifford.
REnnis OFFICE ' PDI-2/PM l NAME- REnnis Y E l [/[!00 4 DATE 0 /M /99 l OFFICIAL RECORD COPY DOCUMENT NAME: G:\PDI-2\ Hope Creek \mema4471.wpd 9906240055 990621 PDR P
ADOCK 05000354 pg
19 3E00 g- % UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
%.....p June 21, 1999 MEMORANDUM TO: Docket File FROM: Richard B. Ennis, Project Manager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMA TION, INCREASE OF ALLOWABLE MAIN STEAM ISOLATION VALVE (MbiV) LE.4K RATE AND DELETION OF MSIV SEALING SYS1 EM (TAC MA4471)
The attached draft request for additional information (RAI) was transmitted by facsimile l on June 21,1999 to Mr. James Priest of Public Service Electric & Gas Company (PSE&G).
i Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAl. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
l l
Docket No. 50-354
Attachment:
Draft RAI
REQUEST FOR ADDITIONAL INFORMATION INCREASE OF ALLOWABLE MAIN STEAM ISOLATION VALVE (MSIV) LEAK RATE AND DELETION OF MSIV SEALING SYSTEM HOPE CREEK GENERATING STATION (TAC NO. MA4471)
References:
- 1. Letter from E. C. Simpson (PSE&G) Company to the Document Control i Desk (NRC), " Request for Change to Technical Specifications, increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate and Deletion of MSIV Sealing System," dated December 28,1998 )
- 2. Letter from F. M. Akstulewicz (NRC) to T. A. Green (BWROG)," Safety Evaluation of GE Topical Report, NEDC-31858P, Revision 2, 'BWROG Report for increasing MSIV Leakage Limits and Elimination of Leakage Control Systems,' September 1993," dated March 3,1999
- 1. Provide a detailed description of the altemate leakage treatment (ALT) pathway and the basis for its functional reliability, commensurate with its intended safety-related function.
Also, provide a descriptic' ->f the maintenance and test!ng program for the active components (such as valus) in the ALT pathway.
- 2. Clarify whether all pipe support anchorages in the ALT pathway have been seismically analyzed. if not; identify the pipe support anchorages that were not analyzed, and provide justification for the statement, made in Section 4.4 of Attachment 4 to Reference 1, that "all support anchorages have adequate capacities," without having all pipe support anchorages analyzed. ';; , , , _
l? E !: n 1' ,' o .
- 3. Discuss whether;the loading at the pipe support anchoragesp, as generated from the seismic analysisbf pipjng systems. If rgt, describe the meth%used.
4p m n u m
- 4. Describe the r}$thoisfi$ critdrid uhed t2 Otita 6ibe capacity $f Nipe support anchorage.
- 5. In Section 4.4 of Attachment 4 to Reference 1, you stated that pipe supports for the non-seismically designed portion of the ALT pathway have been evaluated using the Conservative Deterministic Failure Margin (CDFM) methodolog; from EPRI Report NP-6041. This methodology has not been approved by the NRC, as discussed in Reference 2. Therefore, a plant specific seismic evaluation for representative supports and anchorages associated with the non-seismically designed portion of the AtT patnway should be performed. The evaluation shou!d be performed using the plant 1 licensing basis methodology, or other methods acceptable to the staff. From this plant !
specific evaluation, provide a comparison of the resulting support loads to their capacities and the associated safety margins.
l ATTACHMENT
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2-
- 6. In relation to item (6) above, provide calculations for a typical pipe support anchorage that serve to illustrate the process of demonstrating the seismic adequacy of the support anchorage. ,
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- 7. Provide a bounding seismic analysis for the ALT pathway, subject to all the pertinent i design loading. Discuss the basis for the selection of the analyzed portion of the drain i line piping for the bounding analysis.
- 8. Provide your approved plant walkdown verification procedure for Hope Creek's ALT pathway. .
l
- 9. On page 3-1 of Attachment 4 to Reference 1 the high pressure condenser at Hope Creek is compared to similar condensers at Moss Landing Units 6 & 7 and Ormond Beach Units 1 & 2. The first sentence of the third paragraph on page 3-1 of Attachment 4 states, "_In summary, the condenser design and anchorage are similar to those at facilities in the earthquake experience database that have experienced earthquakes in excess of the Hope Creek design basis SSE (See Figure 4-1)." The Moss Landing response spectrum shown on Figure 4-1 of Attachment 4 is not the same as the spectrum that has been previously accepted by the staff. The response spectrum for Moss Landing, estimated from ground motion from the 1989 M6.9 Loma Prieta earthquake, that has been accepte oy the staff was developed by Pacific Gas &
Electric (PG&E)qFurthe.rmore, the Ormond Beach Po,wer Plant response spectrum, used because the condenser at Ormond Beach Power; Plant Is similar to the Hope s
Creek condense (Is not' plotted,on Eigure,(4-1. Provide a ses igte p 1 the Ormond Beach Powerflangesponse spectrum and the borrect Moss Landing ;
response spectrum. $ p gh $j is 10.
b M d 8#w M M 4 On page 4-4 of %decti$ent 4;toI Referede ddfirsthragrkhh the section entitled
" Comparison 6f HopdCfeek D6 sign SSE ~I Spebtiswith ths Earthh6ake Database Plants" states, "The Hope Creek design basis SSE ground response spectrum was compared with the ground motion spectra at several database power plant sites in the attached Figure 4-1. From a review of Figure 4-1, the database spectra is seen to ylgnificantly envelope the Hope Creek spectrum over the entire frequency range of interest."
Provide the frequency range of interest referred to above since the Valley Steam, NRC-approved Moss Landing, and the Ormond Beach spectra (see Reference 2) do not envelope the Hope Creek SSE design spectrum over all frequencies.
- 11. Figure 4-1 of Attachment 4 to Reference 1 shows zero period acceleration (ZPA) values for 4 facility experience database ground motions. It is the staff position that although peak ground acceleration has been used in the past to characterize earthquake strong ground motion, this single parameter does not have a good correlation with earthquake damage.L A much better correlation of ground motion damage potentialis the ground response spectrum which demonstrates the maximum amplitude of the ground motion as a function of the natural frequency. It is the NRC position that the appropriate characterization of the ground motion at a facility, to be u:ad to verify the adequacy of equipment similar to that in nuclear power plants, is the response spectra developed
3-from the ground motion recorded at or near a facility.
i The staff has accepted the Humboldt Bay response spectra from the 1975 Femdale I earthquake and the 1992 Petrolia earthquake as well as the Glendale response i spectrum from the 1971 San Femando earthquake as part of the earthquake database ground motion (Reference 2). If equipment from the Humboldt Bay Nuclear Power Plant or Glendale Power Plant is used to qualify equipment at Hope Creek, then provide a separate plot showing the Hope Creek SSE design spectrum and the entire 1975 and 1992 Humboldt Bay response spectra and the entire Glendale response spectrum.
- 12. In Table 1," Dose Comparisons," of Attachment 1 to Reference 1, you have provided control room operator doses for a postulated design basis accident for 30 days. Provide the unfiltered control room air infiltration rate assumed in the control room operator dose calculations and its bases. State if you have performed any control room unfiltered air inteakage test.
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