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| | number = ML112990142 | | | number = ML112990142 |
| | issue date = 10/25/2011 | | | issue date = 10/25/2011 |
| | title = Hope Creek Generating Station, Draft Request for Additional Information | | | title = Draft Request for Additional Information |
| | author name = Ennis R B | | | author name = Ennis R |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Chernoff H K | | | addressee name = Chernoff H |
| | addressee affiliation = NRC/NRR/DORL/LPLI-2 | | | addressee affiliation = NRC/NRR/DORL/LPLI-2 |
| | docket = 05000354 | | | docket = 05000354 |
| | license number = | | | license number = |
| | contact person = Ennis R B, NRR/DORL, 415-1420 | | | contact person = Ennis R, NRR/DORL, 415-1420 |
| | case reference number = TAC ME5748 | | | case reference number = TAC ME5748 |
| | document type = Memoranda, Request for Additional Information (RAI) | | | document type = Memoranda, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:October 25, 2011 | | {{#Wiki_filter:October 25, 2011 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ |
| | | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME5748) | | HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME5748) |
| | | The attached draft request for additional information (RAI) was transmitted on October 25, 2011, to Mr. Paul Duke of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Hope Creek Generating Station (HCGS) dated February 28, 2011, as supplemented on August 29, 2011. The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477. |
| The attached draft request for additional information (RAI) was transmitted on October 25, 2011, to Mr. Paul Duke of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee | | This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request. |
| =s amendment request for Hope Creek Generating Station (HCGS) dated February 28, 2011, as supplemented on August 29, 2011. The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-477, Revision 3, "Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems." Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477. | | Docket No. 50-354 |
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| This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. | |
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| Docket No. 50-354 | |
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| ==Attachment:== | | ==Attachment:== |
| Draft RAI | | Draft RAI |
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| October 25, 2011
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| MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | October 25, 2011 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME5748) | | HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME5748) |
| | | The attached draft request for additional information (RAI) was transmitted on October 25, 2011, to Mr. Paul Duke of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Hope Creek Generating Station (HCGS) dated February 28, 2011, as supplemented on August 29, 2011. The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477. |
| The attached draft request for additional information (RAI) was transmitted on October 25, 2011, to Mr. Paul Duke of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee | | This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. |
| =s amendment request for Hope Creek Generating Station (HCGS) dated February 28, 2011, as supplemented on August 29, 2011. The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-477, Revision 3, "Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems." Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477. | | Docket No. 50-354 |
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| This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request. | |
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| Docket No. 50-354 | |
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| ==Attachment:== | | ==Attachment:== |
| Draft RAI | | Draft RAI DISTRIBUTION PUBLIC HWalker, NRR/DSS/SCVB LPL1-2 R/F MHamm, NRR/DIRS/ITSB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMREnnis Resource ACCESSION NO.: ML112990142 OFFICE LPL1-2/PM NAME REnnis DATE 10/25/11 OFFICIAL RECORD COPY |
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| DISTRIBUTION PUBLIC HWalker, NRR/DSS/SCVB LPL1-2 R/F MHamm, NRR/DIRS/ITSB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMREnnis Resource ACCESSION NO.: ML112990142 OFFICE LPL1-2/PM NAME REnnis DATE 10/25/11 OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT ADD ACTION FOR TWO INOPERABLE CONTROL ROOM AIR CONDITIONING SUBSYSTEMS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 | |
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| By application dated February 28, 2011, as supplemented on August 29, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML110590636 and ML112420124, respectively), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request for the Hope Creek Generating Station (HCGS). The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS)
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| Change Traveler TSTF-477, Revision 3, "Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems." Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477.
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| The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
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| : 1. PSEG's response to request for additional information (RAI) question 3 in the supplement dated August 29, 2011, stated, in part, that:
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| HVAC system inoperability may result in CREF inoperability. In the event of a A(B)-P-400 chilled water pum p trip, the A(B)-K-400 chiller will trip, which will trip the A(B)-VH403 and the CREF system. Due to these interlocks, if the
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| Control Room AC subcomponents trip, then CREF will also be inoperable. However, the CREF function is to maintain habitability wi thin the Control Room Envelope via filtration. The CREF trains are independent of the Control Room AC system and would be functional for conditions that do not result in a trip of the Control Room AC system, for example reduced chiller heat removal capability.
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| The use of the word "independent" in the above statement is not clear. If the "CREF trains are independent of the Control Room AC system," why does a trip of the Control Room AC result in an inoperable CREF?
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| Attachment
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| : 2. Please confirm if the following statements are correct (if not, please clarify):
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| (a) Air exhausting from each CREF filter train (A(B)-VH400) goes to the respective Control Room Supply (CRS) unit (A(B)VH403) and then to the control room.
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| (b) Each CRS unit has a low efficiency filter, a high efficiency filter, a fan, a cooling coil (cooled by chilled water system), a heating coil and a humidifier. The cooling coil supports the control room AC function.
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| (c) In order for CREF to perform its design basis function, the fan portion of the CRS needs to be operating. CREF system functionality is not dependent on the control room AC temperature control function.
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| (d) Due to the electrical interlocks in the current plant design, if a control room AC subcomponent trips, the associated CRS unit will tr ip thus also making the associated CREF train inoperable (i.e., solely because the CRS fan is inoperable).
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| (e) If the proposed amendment is approved, the licensee may make a subsequent plant modification to remove the interlocks discussed in (d). This would enable control room AC to be inoperable without automatically tripping the CRS unit including its fan. As such, the associated CREF train would no longer need to be declared inoperable solely due to control room AC system inoperability.
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| (f) If the proposed amendment is approved and the licensee does not perform the plant modification discussed in (e) (i.e., interlocks are still in place), if a control room AC subcomponent trips, the associated CRS unit w ill trip thus also making the associated CREF train inoperable (i.e., solely because the CRS fan is inoperable).
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| (g) If the proposed amendment is approved (and before the plant modification is done), if both trains of the control room AC system were inoperable, then both trains of CREF would need to be declared inoperable and the plant would enter TS 3.0.3 per the CREF TS. This is no different than the current TS requirements.
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| (h) The proposed amendment does not change any of the assumptions in the HCGS licensing basis analyses of design basis accident consequences. | | DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT ADD ACTION FOR TWO INOPERABLE CONTROL ROOM AIR CONDITIONING SUBSYSTEMS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By application dated February 28, 2011, as supplemented on August 29, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML110590636 and ML112420124, respectively), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request for the Hope Creek Generating Station (HCGS). The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) |
| : 3. With an inoperable control room AC system and an inoperable CRS unit, will the control room return air (CRRA) fan and corresponding flow element be inoperable? Is the CRRA fan required to be operable in order for the CREF to be operable?}} | | Change Traveler TSTF-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477. |
| | The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal. |
| | : 1. PSEGs response to request for additional information (RAI) question 3 in the supplement dated August 29, 2011, stated, in part, that: |
| | HVAC system inoperability may result in CREF inoperability. In the event of a A(B)-P-400 chilled water pump trip, the A(B)-K-400 chiller will trip, which will trip the A(B)-VH403 and the CREF system. Due to these interlocks, if the Control Room AC subcomponents trip, then CREF will also be inoperable. |
| | However, the CREF function is to maintain habitability within the Control Room Envelope via filtration. The CREF trains are independent of the Control Room AC system and would be functional for conditions that do not result in a trip of the Control Room AC system, for example reduced chiller heat removal capability. |
| | The use of the word independent in the above statement is not clear. If the CREF trains are independent of the Control Room AC system, why does a trip of the Control Room AC result in an inoperable CREF? |
| | Attachment |
| | : 2. Please confirm if the following statements are correct (if not, please clarify): |
| | (a) Air exhausting from each CREF filter train (A(B)-VH400) goes to the respective Control Room Supply (CRS) unit (A(B)VH403) and then to the control room. |
| | (b) Each CRS unit has a low efficiency filter, a high efficiency filter, a fan, a cooling coil (cooled by chilled water system), a heating coil and a humidifier. The cooling coil supports the control room AC function. |
| | (c) In order for CREF to perform its design basis function, the fan portion of the CRS needs to be operating. CREF system functionality is not dependent on the control room AC temperature control function. |
| | (d) Due to the electrical interlocks in the current plant design, if a control room AC subcomponent trips, the associated CRS unit will trip thus also making the associated CREF train inoperable (i.e., solely because the CRS fan is inoperable). |
| | (e) If the proposed amendment is approved, the licensee may make a subsequent plant modification to remove the interlocks discussed in (d). This would enable control room AC to be inoperable without automatically tripping the CRS unit including its fan. As such, the associated CREF train would no longer need to be declared inoperable solely due to control room AC system inoperability. |
| | (f) If the proposed amendment is approved and the licensee does not perform the plant modification discussed in (e) (i.e., interlocks are still in place), if a control room AC subcomponent trips, the associated CRS unit will trip thus also making the associated CREF train inoperable (i.e., solely because the CRS fan is inoperable). |
| | (g) If the proposed amendment is approved (and before the plant modification is done), if both trains of the control room AC system were inoperable, then both trains of CREF would need to be declared inoperable and the plant would enter TS 3.0.3 per the CREF TS. This is no different than the current TS requirements. |
| | (h) The proposed amendment does not change any of the assumptions in the HCGS licensing basis analyses of design basis accident consequences. |
| | : 3. With an inoperable control room AC system and an inoperable CRS unit, will the control room return air (CRRA) fan and corresponding flow element be inoperable? Is the CRRA fan required to be operable in order for the CREF to be operable?}} |
Letter Sequence Draft RAI |
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TAC:ME5748, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B, Add Action for Two Inoperable Control Room AC Subsystems (Approved, Closed) |
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MONTHYEARLR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process Project stage: Request ML1108716882011-03-28028 March 2011 Acceptance Review for TAC ME5748 - Hope Creek - License Amendment Request - TSTF-477 Project stage: Acceptance Review ML1118605722011-07-0505 July 2011 Draft Request for Additional Information Project stage: Draft RAI ML1124201242011-08-29029 August 2011 Response to Request for Additional Information - License Amendment Request: Add Action for Two Inoperable Control Room Air Conditioning Subsystems Project stage: Response to RAI ML1129901422011-10-25025 October 2011 Draft Request for Additional Information Project stage: Draft RAI LR-N11-0372, Response to Request for Additional Information Dated October 25, 2011 - License Amendment Request: Add Action for Two Inoperable Control Room Air Conditioning Subsystems2011-12-16016 December 2011 Response to Request for Additional Information Dated October 25, 2011 - License Amendment Request: Add Action for Two Inoperable Control Room Air Conditioning Subsystems Project stage: Response to RAI LR-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process2012-01-26026 January 2012 Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process Project stage: Supplement ML1201800782012-02-0808 February 2012 Issuance of Amendment 191 Control Room Emergency Filtration System and Control Room Air Conditioning System Project stage: Approval 2011-03-28
[Table View] |
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Category:Memoranda
MONTHYEARML18269A2522018-10-12012 October 2018 F&O Closure Observation Hope Creek Fire PRA ML17023A1452017-01-23023 January 2017 Summary of Teleconference with PSEG Regarding Hope Creek HPCI ML16259A2042016-09-20020 September 2016 Hope Creek Generating Station - Safety Evaluation - Request to revise technical specifications - safety limit minimum critical power ratio.(TAC NO. MF7793) ML15015A6772015-01-16016 January 2015 Forthcoming Closed Meeting with PSEG Nuclear, LLC, Regarding a Planned Digital Instrumentation and Controls License Amendment Request Associated with Hope Creek Generating Station, Unit 1 IR 05000272/20132022013-12-20020 December 2013 IR 05000272-13-202, 05000311-13-202 & 05000354-13-201, September 9-13, 2013, Salem Nuclear Generating Station and Hope Creek Generating Station - Cover Letter ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13233A1132013-08-22022 August 2013 Notice of Forthcoming Meeting with PSEG Nuclear, LLC Regarding a Planned Digital Instrumentation and Controls License Amendment Request Associated with Hope Creek Generating Station, Unit 1 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML13196A2202012-06-0606 June 2012 Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML1129901422011-10-25025 October 2011 Draft Request for Additional Information ML1129700652011-10-21021 October 2011 Summary of PSEG Drop-in Visit, 9-28-2011 and Slides ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML1118605722011-07-0505 July 2011 Draft Request for Additional Information ML11181A1772011-06-30030 June 2011 June 29, 2011 Summary of Public Meeting to Discuss Observations and Lessons Learned During the Hope Creek Nuclear Generating Station Application of the Nuclear Energy Institute'S Nuclear Safety Culture Assessment Process ML11137A0762011-06-0202 June 2011 Summary of Telephone Conference Call Held on May 11, 2011, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning the Hope Creek License Condition for the Drywell ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML11105A0372011-05-0404 May 2011 Summary of Telephone Conference Call Held on March 25, 2011, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning Findings on the Hope Creek Generating Station Gas Turbine ML1111108862011-04-20020 April 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information LR-N11-0087, 2011 Annual Report - Guarantees of Payment of Deferred Premiums2011-03-31031 March 2011 2011 Annual Report - Guarantees of Payment of Deferred Premiums ML1106801152011-03-0808 March 2011 Draft Request for Additional Information ML1106005572011-03-0101 March 2011 Minutes of the Meeting of the Subcommittee on Plant License Renewal Regarding Hope Creek Generating Plant on November 3, 2010, in Rockville, Maryland ML1034909292011-02-0909 February 2011 Summary of Telephone Conference Call Held on November 18, 2010, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning Findings on the Hope Creek Generating Station Recent Outage ML1101901352011-01-18018 January 2011 Draft Request for Additional Information ML1029500062010-10-28028 October 2010 11/17/10 Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Hope Creek Generating Station and Salem Nuclear Generating Station Units 1 and 2 ML1027100672010-09-30030 September 2010 Advisory Committee on Reactor Safeguards Review of the Hope Creek Generating Station License Renewal Application - Safety Evaluation Report with Open Items ML1027207232010-09-29029 September 2010 Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal (Hope Creek), November 3, 2010 ML1024407062010-09-20020 September 2010 Summary of Telephone Conference Call Held on August 18,2010 Between Us NRC and PSEG Nuclear, LLC Concerning Questions Pertaining to the Hope Creek Generating Station License Renewal Application ML11263A0282010-09-16016 September 2010 E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo ML11263A0272010-09-14014 September 2010 E-mail with Attachment from T. Ghosh, RES, to L. Perkins, NRR Et Al, on Fyi Salem SAMA Transmittal ML1023201782010-09-0303 September 2010 Summary of Telephone Conference Call Held on 8/16/10, Between Us NRC and PSEG Nuclear,Llc,Concerning Draft Request for Additional Information Pertaining to the Hope Creek Generating Station, License Renewal Application ML1023201792010-09-0202 September 2010 Summary of Telephone Conference Call Held on 6/21/10 Between the USNRC and PSEG Nuclear LLC Concerning Responses to Requests for Additional Information Pertaining to the Hope Creek Generating Station License Renewal Application ML1022204762010-08-18018 August 2010 Summary of Telephone Conference Call Held on 8/4/10,Between Us NRC and PSEG Nuclear, LLC, Concerning Draft RAI Pertaining to the Hope Creek Generating Station, License Renewal Application ML1022200122010-08-13013 August 2010 Summary of Telephone Conf Call Held on 7/29/10, Between the USNRC and PSEG Nuclear LLC, Concerning Follow-Up Questions Pertaining to the Salem Nuclear Generating Station, Units 1 & 2, and Hope Creek Generating Station License Renewal Enviro ML1020105012010-07-20020 July 2010 Draft Request for Additional Information ML1018303472010-07-0202 July 2010 Draft Request for Additional Information ML1017600102010-06-24024 June 2010 Draft Request for Additional Information ML1011004322010-04-19019 April 2010 PSEG Slides for Salem and Hope Creek Annual Assessment Meeting, April 6, 2010 ML1009904032010-04-0808 April 2010 Draft Request for Additional Information LR-N10-0115, Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums2010-04-0101 April 2010 Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums ML11259A2702010-03-0101 March 2010 E-mail with Attachment from D. Logan, NRR, to S. Duda, Aecom Et Al, on Mitigation Memo ML1002907322010-01-28028 January 2010 Draft Request for Additional Information ML0934405582009-12-10010 December 2009 Notice of Closed Meeting with PSEG Nuclear LLC (PSEG) to Discuss Exemption from Schedular Requirements of 10 CFR 73.55 for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 ML0928706352009-10-23023 October 2009 11/05/2009 Notice of Meeting to Discuss License Renewal Process and Environmental Scoping for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station, License Renewal Application Review ML0923606212009-08-27027 August 2009 Logistics Trip Report to Delaware Emergency Management Agency Regarding Salem-Hope Creek License Renewal ML0920103212009-07-30030 July 2009 Logistics Trip Report to Salem and Hope Creek Nuclear Stations and Salem, New Jersey ML0919504062009-07-14014 July 2009 Draft Request for Additional Information ML0917302782009-06-22022 June 2009 PSEG Drop-in Visit (Salem and Hope Creek) on 6-18-2009 ML0913502412009-05-14014 May 2009 Draft Request for Additional Information ML0911701652009-04-27027 April 2009 Draft Request for Additional Information 2018-10-12
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21300A0222021-10-27027 October 2021 Notification of Conduct of a Fire Protection Team Inspection ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18120A2482018-04-27027 April 2018 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403 ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb ML17222A1652017-08-10010 August 2017 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502) ML17181A1352017-06-29029 June 2017 NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70) ML17164A4062017-06-13013 June 2017 NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462) ML17027A3282017-02-27027 February 2017 Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies ML16321A4642016-11-21021 November 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements ML16277A5142016-11-0303 November 2016 Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16271A2052016-11-0202 November 2016 Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML16231A4272016-08-24024 August 2016 Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16217A4302016-08-17017 August 2016 Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade ML16007A1742016-05-31031 May 2016 Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error ML16089A0792016-05-0505 May 2016 Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16124A5802016-05-0303 May 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes ML15055A3772015-03-10010 March 2015 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57 ML14197A6192014-07-24024 July 2014 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386) ML14168A2352014-07-0202 July 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML13309B5922013-11-22022 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13168A2762013-08-12012 August 2013 Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228) ML13193A2912013-07-22022 July 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031 ML13204A2532013-07-19019 July 2013 Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom ML13190A2212013-07-0202 July 2013 RAIs for Hope Creek Regarding Response to Order EA-12-051 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML12334A3102012-12-0505 December 2012 Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items ML12310A1672012-11-0101 November 2012 Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5 ML1227901012012-10-0505 October 2012 Clarifying Information for Question No. 4 (with Attachment) ML12212A1032012-08-0808 August 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information ML12216A1792012-08-0303 August 2012 Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML12213A6162012-07-30030 July 2012 Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic 2022-01-06
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October 25, 2011 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME5748)
The attached draft request for additional information (RAI) was transmitted on October 25, 2011, to Mr. Paul Duke of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Hope Creek Generating Station (HCGS) dated February 28, 2011, as supplemented on August 29, 2011. The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.
Docket No. 50-354
Attachment:
Draft RAI
October 25, 2011 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /ra/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NO. ME5748)
The attached draft request for additional information (RAI) was transmitted on October 25, 2011, to Mr. Paul Duke of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee=s amendment request for Hope Creek Generating Station (HCGS) dated February 28, 2011, as supplemented on August 29, 2011. The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477.
This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.
Docket No. 50-354
Attachment:
Draft RAI DISTRIBUTION PUBLIC HWalker, NRR/DSS/SCVB LPL1-2 R/F MHamm, NRR/DIRS/ITSB RidsNrrDorlLpl1-2 Resource RidsNrrDorlDpr Resource RidsNrrPMREnnis Resource ACCESSION NO.: ML112990142 OFFICE LPL1-2/PM NAME REnnis DATE 10/25/11 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT ADD ACTION FOR TWO INOPERABLE CONTROL ROOM AIR CONDITIONING SUBSYSTEMS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By application dated February 28, 2011, as supplemented on August 29, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML110590636 and ML112420124, respectively), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request for the Hope Creek Generating Station (HCGS). The proposed amendment would modify the HCGS Technical Specifications (TSs) to revise the existing TS for the Control Room Emergency Filtration (CREF) system and to add a new TS for the Control Room Air Conditioning (AC) system. The proposed amendment is based, in part, on Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard TS (STS)
Change Traveler TSTF-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems. Plant-specific deviations from TSTF-477 are proposed to accommodate differences between the HCGS TSs and the STSs originally used to develop TSTF-477.
The NRC staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.
- 1. PSEGs response to request for additional information (RAI) question 3 in the supplement dated August 29, 2011, stated, in part, that:
HVAC system inoperability may result in CREF inoperability. In the event of a A(B)-P-400 chilled water pump trip, the A(B)-K-400 chiller will trip, which will trip the A(B)-VH403 and the CREF system. Due to these interlocks, if the Control Room AC subcomponents trip, then CREF will also be inoperable.
However, the CREF function is to maintain habitability within the Control Room Envelope via filtration. The CREF trains are independent of the Control Room AC system and would be functional for conditions that do not result in a trip of the Control Room AC system, for example reduced chiller heat removal capability.
The use of the word independent in the above statement is not clear. If the CREF trains are independent of the Control Room AC system, why does a trip of the Control Room AC result in an inoperable CREF?
Attachment
- 2. Please confirm if the following statements are correct (if not, please clarify):
(a) Air exhausting from each CREF filter train (A(B)-VH400) goes to the respective Control Room Supply (CRS) unit (A(B)VH403) and then to the control room.
(b) Each CRS unit has a low efficiency filter, a high efficiency filter, a fan, a cooling coil (cooled by chilled water system), a heating coil and a humidifier. The cooling coil supports the control room AC function.
(c) In order for CREF to perform its design basis function, the fan portion of the CRS needs to be operating. CREF system functionality is not dependent on the control room AC temperature control function.
(d) Due to the electrical interlocks in the current plant design, if a control room AC subcomponent trips, the associated CRS unit will trip thus also making the associated CREF train inoperable (i.e., solely because the CRS fan is inoperable).
(e) If the proposed amendment is approved, the licensee may make a subsequent plant modification to remove the interlocks discussed in (d). This would enable control room AC to be inoperable without automatically tripping the CRS unit including its fan. As such, the associated CREF train would no longer need to be declared inoperable solely due to control room AC system inoperability.
(f) If the proposed amendment is approved and the licensee does not perform the plant modification discussed in (e) (i.e., interlocks are still in place), if a control room AC subcomponent trips, the associated CRS unit will trip thus also making the associated CREF train inoperable (i.e., solely because the CRS fan is inoperable).
(g) If the proposed amendment is approved (and before the plant modification is done), if both trains of the control room AC system were inoperable, then both trains of CREF would need to be declared inoperable and the plant would enter TS 3.0.3 per the CREF TS. This is no different than the current TS requirements.
(h) The proposed amendment does not change any of the assumptions in the HCGS licensing basis analyses of design basis accident consequences.
- 3. With an inoperable control room AC system and an inoperable CRS unit, will the control room return air (CRRA) fan and corresponding flow element be inoperable? Is the CRRA fan required to be operable in order for the CREF to be operable?