Forwards Draft Summary of 870825-26 Meetings W/Util to Discuss Comments on Tech Specs Upgrade ProgramML20235E095 |
Person / Time |
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Site: |
Fort Saint Vrain |
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Issue date: |
09/21/1987 |
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From: |
Heitner K NRC |
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To: |
NRC |
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References |
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NUDOCS 8709250479 |
Download: ML20235E095 (10) |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212G5351999-09-27027 September 1999 Forwards Signed Original Confirmatory Order (Effective Immediately)(Morrison Knudsen Corp,Cleveland,Oh) for Transmittal to Ofc of Fr for Publication.Without Encl ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20202D5011997-11-28028 November 1997 Forwards Table Summarizing Contractor Costs,Staff Hours & FTEs Expended in Removing Sites from Site Decommissioning Mgt Plan & Fsv & Shoreham Nuclear Power Facilities,In Response to C Paperiello 970605 Memorandum ML20141C8691997-05-0505 May 1997 Forwards Notice for Transmittal to Ofc of Fr Re Issuance of License Amend for Psc,Fort St Vrain Nuclear Generating Station Re Redesignated Approved Decommissioning Plan, & Approved Final Radiation Survey Plan ML20136D6041997-03-0404 March 1997 Forwards Signed Original of FRN for Transmittal to Ofc of Federal Register for Publication ML20134G2511996-11-0505 November 1996 Forwards Notice of Forthcoming Meeting W/Psc on Decommissioning & License Termination of Fsv ML20134F8951996-11-0505 November 1996 Notification of 961203 Meeting W/Public Service Co of Co in Rockville,Md to Discuss Decommissioning & License Termination of Fort St Vrain ML20236X0011996-09-12012 September 1996 Provides follow-up to Meeting Re Use of Natural or Depleted U in Storage Casks/Use of Neutron Absorbing Matls,In Order to Improve Basis & Shed Light on Direct Final Possibility ML20137H1331995-12-29029 December 1995 Responds to Request of 951108 for Investigative Assistance in Interviewing R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians at Fort St Vrain,Oi Case A4-95-064 ML20137H2951995-11-21021 November 1995 Forwards Copies of Transcripts of R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians Case A4-95-064.W/o Encls ML20136B2301995-11-17017 November 1995 Forwards Repy to NOV ML20136B1831995-08-31031 August 1995 Discusses Proposed Meeting Re OI 4-95-015 ML20136B1711995-08-31031 August 1995 Agrees W/Office of Enforcement Regional Approach ML20136B2121995-08-30030 August 1995 Confirms 950911 for OI Meeting Re OI 4-95-015 ML20136B1901995-08-30030 August 1995 Ack Receipt of Mail ML20137H2651995-08-25025 August 1995 Forwards Copy of OI Rept Where Investigation Did Substantiate That Seg Technician Deliberately Failed to Perform Response Checks in Accordance W/Procedures.W/O Encl ML20136B1661995-08-17017 August 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Records.W/O Encl ML20136B2191995-08-0707 August 1995 Informs That Enforcement Action Will Be Required Re OI 4-95-015 Concerning Failure to Perform Response Checks ML20136B1581995-06-20020 June 1995 Requests That General Counsel Anlayze Rept & Determine Whether Sufficient Evidence Exists to Take EA Re Falsification of Records ML20137H2551995-06-0303 June 1995 Forwards Copy of OI Rept,Reviewing Licensee Investigation Rept & Confirmed Licensee Conclusions That Radiation Survey Records & Radiation Work Permits Falsified.W/O Encl ML20136B1471995-05-26026 May 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Radiation Survey Records ML20137K0111995-04-20020 April 1995 Discusses Verbal DOJ Declination of Prosecution Re Public Svc Co of Colorado,For Plant ML20137K0781995-04-12012 April 1995 Documents Events Surrounding Segs Placement of Problematic Radiation Protection Technician on Administrative Leave ML20137K0611995-04-12012 April 1995 Documents Events Surrounding Discovery of Barrels Being Shipped from Plant to Richland Disposal Facility W/Different Radiation Exposure Readings than Were Listed on Shipping Manifest NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20137J8251994-04-14014 April 1994 Discusses Chronology of Events Since Preliminary Notification of Event or Unusual Occurrence Case 4-94-010 ML20137S2081994-03-28028 March 1994 Discusses 940325 Telcon from Listed Licensee & Contractor Personnel Re Rept of Falsified Survey Records IA-97-311, Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl1993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl ML20198H5751993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl ML20058B1681993-11-18018 November 1993 Notification of 931109 Meeting W/Psc in Rockville,Md to Discuss Fort St Vrain Decommissioning Status ML20059C2741993-10-25025 October 1993 Notification of Significant Licensee Meeting W/Util on 931116 to Discuss Decommissioning Status of Plant ML20058N9831993-10-0606 October 1993 Notification of 931109 Meeting W/Util in Rockville,Md for Briefing on Status of Plant Decommissioning ML20127D3281993-01-12012 January 1993 Notification of 930128 Meeting W/Util in Rockville,Md to Brief NRC on Plant Decommissioning Status ML20126A3141992-11-27027 November 1992 Forwards Insp Plan for Fsv,Developed for Current Fiscal Yr Ending 930930.Plan Based on Mc 2560,Decommissioning Insp Program ML20127L8411992-11-27027 November 1992 Forwards Insp Plan for Facility Which P Michaud Developed for Current Fy Ending on 930930.Plan Based on Mc 2560, Decommissioning Insp Program ML20059P0831990-10-12012 October 1990 Notification of 901017 Meeting W/Nrc in Rockville,Md to Discuss Decommissioning of Facilities ML20055F7381990-07-16016 July 1990 Notification of 900725 Meeting W/Util in Rockville,Md to Discuss Plant Status & Plans for Final Defueling & Decommissioning ML20248E8301989-09-26026 September 1989 Notification of 891013 Meeting W/Util in Rockville,Md to Discuss Plant Spent Fuel Storage.Agenda Encl ML20247J6831989-09-18018 September 1989 Forwards Comments on Facility Preliminary Decommissioning Plan,Per 890803 & 21 Memos Re Transfer of Regulatory Authority for Reactor Decommissioning ML20246F1871989-08-24024 August 1989 Summary of 890803 Meeting W/Util in Rockville,Md Re Preliminary Decommissioning Plan of 890630 for Plant.Related Info,Including List of Attendees & Util Info Re Use of Tax Deduction in Calculation of Funding Requirements Encl ML20245G5541989-08-0808 August 1989 Requests Support in Conducting Review of Plant Preliminary Decommissioning Plan.Areas to Be Reviewed,Requested Reviewers & Tentative Review Schedule Encl ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247K6271989-07-24024 July 1989 Forwards Revised Filing Instructions for Rev 7 to Updated FSAR ML20246L7971989-07-17017 July 1989 Submits Daily Highlight.Notifies of of 890718 Meeting W/Util in Rockville,Md to Discuss Defueling of Plant & Tech Spec Upgrade Program ML20246L3741989-07-12012 July 1989 Notification of 890803 Meeting W/Util & State of Co in Rockville,Md to Discuss Preliminary Decommissioning Plan ML20247H6041989-05-29029 May 1989 Requests Encl Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Power Reactors, Task CE 025-4 Be Forwarded to Util for Use in Preparing Preliminary Decommissioning Plan for Plant ML20247D7421989-03-27027 March 1989 Forwards FEMA 890313 Memo Transmitting FEMA Region Viii Update Rept of 870805 Exercise.Rept Includes Results of Remedial Drill Conducted on 880830 & Status of Areas Requiring Corrective Action ML20236B9461989-03-13013 March 1989 Notification of Significant Licensee Meeting W/Util on 890322 in Region IV Ofc to Review OL Requirements ML20155A2481988-09-28028 September 1988 Notification of 881013 & 14 Meetings W/Util in Platteville, Co to Discuss Potential Decommissioning & Conversion of Facility.Meeting Agenda Encl ML20155B4111988-09-27027 September 1988 Notification of Significant Licensee Meeting W/Util on 881003 to Discuss Items in Insp Repts 50-267/88-15 & 50-267/88-23,control of Special Processes,Welding Program & NDE Program 1999-09-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212G5351999-09-27027 September 1999 Forwards Signed Original Confirmatory Order (Effective Immediately)(Morrison Knudsen Corp,Cleveland,Oh) for Transmittal to Ofc of Fr for Publication.Without Encl ML20236W8131998-08-0404 August 1998 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed RM Entitled Miscellaneous Changes to Licensing Requirements for Independent Storage of Spent Nuclear Fuel & HLW Which Amended 10CFR72 ML20202D5011997-11-28028 November 1997 Forwards Table Summarizing Contractor Costs,Staff Hours & FTEs Expended in Removing Sites from Site Decommissioning Mgt Plan & Fsv & Shoreham Nuclear Power Facilities,In Response to C Paperiello 970605 Memorandum ML20149H4801997-07-24024 July 1997 Staff Requirements Memo Re SECY-97-138, Termination of Fort St Vrain Nuclear Generating Station Ol ML20141C8691997-05-0505 May 1997 Forwards Notice for Transmittal to Ofc of Fr Re Issuance of License Amend for Psc,Fort St Vrain Nuclear Generating Station Re Redesignated Approved Decommissioning Plan, & Approved Final Radiation Survey Plan ML20136D6041997-03-0404 March 1997 Forwards Signed Original of FRN for Transmittal to Ofc of Federal Register for Publication ML20134F8951996-11-0505 November 1996 Notification of 961203 Meeting W/Public Service Co of Co in Rockville,Md to Discuss Decommissioning & License Termination of Fort St Vrain ML20134G2511996-11-0505 November 1996 Forwards Notice of Forthcoming Meeting W/Psc on Decommissioning & License Termination of Fsv ML20236X0011996-09-12012 September 1996 Provides follow-up to Meeting Re Use of Natural or Depleted U in Storage Casks/Use of Neutron Absorbing Matls,In Order to Improve Basis & Shed Light on Direct Final Possibility ML20137H1331995-12-29029 December 1995 Responds to Request of 951108 for Investigative Assistance in Interviewing R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians at Fort St Vrain,Oi Case A4-95-064 ML20137H2951995-11-21021 November 1995 Forwards Copies of Transcripts of R Sawyer & K Zarht Re Alleged Discrimination & Wrongful Termination of Contractor Radiation Protection Technicians Case A4-95-064.W/o Encls ML20136B2301995-11-17017 November 1995 Forwards Repy to NOV ML20136B1711995-08-31031 August 1995 Agrees W/Office of Enforcement Regional Approach ML20136B1831995-08-31031 August 1995 Discusses Proposed Meeting Re OI 4-95-015 ML20136B2121995-08-30030 August 1995 Confirms 950911 for OI Meeting Re OI 4-95-015 ML20136B1901995-08-30030 August 1995 Ack Receipt of Mail ML20137H2651995-08-25025 August 1995 Forwards Copy of OI Rept Where Investigation Did Substantiate That Seg Technician Deliberately Failed to Perform Response Checks in Accordance W/Procedures.W/O Encl ML20136B1661995-08-17017 August 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Records.W/O Encl ML20136B2191995-08-0707 August 1995 Informs That Enforcement Action Will Be Required Re OI 4-95-015 Concerning Failure to Perform Response Checks ML20136B1581995-06-20020 June 1995 Requests That General Counsel Anlayze Rept & Determine Whether Sufficient Evidence Exists to Take EA Re Falsification of Records ML20137H2551995-06-0303 June 1995 Forwards Copy of OI Rept,Reviewing Licensee Investigation Rept & Confirmed Licensee Conclusions That Radiation Survey Records & Radiation Work Permits Falsified.W/O Encl ML20136B1471995-05-26026 May 1995 Forwards OI Rept of Investigation Re Alleged Falsification of Radiation Survey Records ML20137K0111995-04-20020 April 1995 Discusses Verbal DOJ Declination of Prosecution Re Public Svc Co of Colorado,For Plant ML20137K0611995-04-12012 April 1995 Documents Events Surrounding Discovery of Barrels Being Shipped from Plant to Richland Disposal Facility W/Different Radiation Exposure Readings than Were Listed on Shipping Manifest ML20137K0781995-04-12012 April 1995 Documents Events Surrounding Segs Placement of Problematic Radiation Protection Technician on Administrative Leave NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20137J8251994-04-14014 April 1994 Discusses Chronology of Events Since Preliminary Notification of Event or Unusual Occurrence Case 4-94-010 ML20137S2081994-03-28028 March 1994 Discusses 940325 Telcon from Listed Licensee & Contractor Personnel Re Rept of Falsified Survey Records ML20059G9501994-01-19019 January 1994 Staff Requirements Memo Re SECY-93-352,Proposed Export of Fort St Vrain Unirradiated HEU Fuel Assemblies to France for Recovery & Down-Blending to LEU XSNM-2748, & SECY-93-333, Final Amend to 10CFR55 on Renewal of Licenses.. ML20198H5751993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl IA-97-311, Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl1993-11-18018 November 1993 Submits Physical Security Info for Export of Unirradiated Fort St Vrain Fuel Containing high-enriched U Mixed W/Th to France for recovery,down-blending & Subsequent Use as Fuel in Research & Test Reactors.Supporting Documentation Encl ML20058B1681993-11-18018 November 1993 Notification of 931109 Meeting W/Psc in Rockville,Md to Discuss Fort St Vrain Decommissioning Status ML20059C2741993-10-25025 October 1993 Notification of Significant Licensee Meeting W/Util on 931116 to Discuss Decommissioning Status of Plant ML20058N9831993-10-0606 October 1993 Notification of 931109 Meeting W/Util in Rockville,Md for Briefing on Status of Plant Decommissioning ML20127D3281993-01-12012 January 1993 Notification of 930128 Meeting W/Util in Rockville,Md to Brief NRC on Plant Decommissioning Status ML20127L8411992-11-27027 November 1992 Forwards Insp Plan for Facility Which P Michaud Developed for Current Fy Ending on 930930.Plan Based on Mc 2560, Decommissioning Insp Program ML20126A3141992-11-27027 November 1992 Forwards Insp Plan for Fsv,Developed for Current Fiscal Yr Ending 930930.Plan Based on Mc 2560,Decommissioning Insp Program ML20059P0831990-10-12012 October 1990 Notification of 901017 Meeting W/Nrc in Rockville,Md to Discuss Decommissioning of Facilities ML20055F7381990-07-16016 July 1990 Notification of 900725 Meeting W/Util in Rockville,Md to Discuss Plant Status & Plans for Final Defueling & Decommissioning ML20248E8301989-09-26026 September 1989 Notification of 891013 Meeting W/Util in Rockville,Md to Discuss Plant Spent Fuel Storage.Agenda Encl ML20247J6831989-09-18018 September 1989 Forwards Comments on Facility Preliminary Decommissioning Plan,Per 890803 & 21 Memos Re Transfer of Regulatory Authority for Reactor Decommissioning ML20246F1871989-08-24024 August 1989 Summary of 890803 Meeting W/Util in Rockville,Md Re Preliminary Decommissioning Plan of 890630 for Plant.Related Info,Including List of Attendees & Util Info Re Use of Tax Deduction in Calculation of Funding Requirements Encl ML20245G5541989-08-0808 August 1989 Requests Support in Conducting Review of Plant Preliminary Decommissioning Plan.Areas to Be Reviewed,Requested Reviewers & Tentative Review Schedule Encl ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247K6271989-07-24024 July 1989 Forwards Revised Filing Instructions for Rev 7 to Updated FSAR ML20246L7971989-07-17017 July 1989 Submits Daily Highlight.Notifies of of 890718 Meeting W/Util in Rockville,Md to Discuss Defueling of Plant & Tech Spec Upgrade Program ML20246L3741989-07-12012 July 1989 Notification of 890803 Meeting W/Util & State of Co in Rockville,Md to Discuss Preliminary Decommissioning Plan ML20247H6041989-05-29029 May 1989 Requests Encl Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Power Reactors, Task CE 025-4 Be Forwarded to Util for Use in Preparing Preliminary Decommissioning Plan for Plant ML20247D7421989-03-27027 March 1989 Forwards FEMA 890313 Memo Transmitting FEMA Region Viii Update Rept of 870805 Exercise.Rept Includes Results of Remedial Drill Conducted on 880830 & Status of Areas Requiring Corrective Action ML20236B9461989-03-13013 March 1989 Notification of Significant Licensee Meeting W/Util on 890322 in Region IV Ofc to Review OL Requirements 1999-09-27
[Table view] |
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Subject:
Surntnar y o f August 25-26,1987 Meet 2 ng at Fort St. Vrain iFSV? tc di scuss NRC st af f corntnent s on FSV Technic al Spec i f i c at i on Upgrade Program (TSUP).
{'
ne staf f of the Public On August 25 and 26, 1987 the NRC staf f met v,th t Service Cornpany of Colorado (PSC) at the FSV f acility. Also in attendence I were NRC contractors f r om Idaho and Oak Pi r!ge Nat i onal Laboratory
' National Engineering Labor ator y (INEL)
(ORNL). The purpose of this rueeting was to discuss the status of theagenda, The meeting FSV TSUP. The rnecting attendees are listed in Enclosure 1. A proposed i which was followed fairly closely, i s attached as Enclosur e 2.
l schedule for the complet ion o f the TSUP effort, sent by NRC to PSC (Ref.1) was discussed and enodi fled at this meeting, A review of the proposed PSC responses to the NRC-RAIs (Requests f or Additional The newInformation) wasstatus dis-cussed during the major part of the meeting. cl assi fication {
l for theseThe responses, by NRC, are listed by TS-LCOs in tables in Enclo-acceptance status will be veri fied uhen PSC formally submits sure 5. future. The next meeting on TSUP was the draf t responses in the nearA meeting date and location will be l projected to be in 6-8 weeks. 4 weeks. Mike Holmes suggested established by teleconf er ence in about l about 11/15/87 or about two weeks af ter the PSC submission a date of responses l of their to RAIs on the Cooling Functions.
and the NRC contrac-The NRC sta f f has rnet previously with the PSC staff, tors, on the subject of TSUP (Ref er ences 2 and 3). These meetings were basec l prirnarily on the NRC sta f f' r eview (Reference As 4) of theoffinal a result thesedraft of the rneetings, FSV upgraded Technical Specifications (TS).
the NRC comrnents cont ained in Re f er ence 5 wer e r evi ewed and c at egor i zed into one of six categories (listed in e.g., r e f er ences 2 and 3) . For ease of r e f er ence, they are noted in Enclosure 3, attached. Reference 5 sumenar a r ed the NRC/PSC rneet i ng of 12/18/86 and transmitted RAIs. Folthat resolutions l owi ng these rneet ings, PSC subtni t t ed documentation of comrnent t o NRC were reached at the previous meetings with NRC in a letter These includes (Reference). Subsequent RAIs wer e sent to PSC by NRC. Electrical technical speci fi- ;
(1) References 7 & 8, RAls on the final draf t cations; (2) Ref erence 9 transmitted RAIs on safety related cooling functier t ted RAls to PSC on c ategor y A#, D and o
t o PSC; and (3) Reference 10 tr ansmiThe PSC proposed responses to the RAIs D# i t erns (Defined in enclosur e 3) . formed the basis of the meeting ;
submitted in the abovementioned r e f er ences, with PSC on 8/25-26/87.
As the basis for the cornpletion of the TSUP r eview, Ken Heitner discused the NRC letter of 5/30/06," Comtnents on the Final Draft of the FSV Upgraded focus.
Technical Sp ec i f i c at i ons" (Ref.4). The progress of the TSUP review is
[ on four items, which were expanded into a proposed review completion schedule (Ref.1).
The milestones for the first three line items in Fig 1 Task T-36 (ORNL), the 4th line item, on risk ~
(Ref.1) are on schedule.
a s s e s srn e n t , should be compl et ed by mid-Sept ember . Ken responded to two 1987-1988 Proposed Schedul e (ref.1). The quest ions on rail est ones in Fi g. 2, first question involved the NPC independent audit review of the TER. Men 1
DRAFT
4 m.-r 3
EFT ,
l explained that this was an NRC QA process under the guidance of the Technical Speci fic ations Br anch. The second question was on the de fini tion of the rnilestones activity calling for the PSC to certi fy that the final TS i Mods conf or m wi th the PSAR.
Mr. M.H. Holmes (PSC) provided a preliminary response to NRR's proposed l
schedule in terms of Ken Heitner's request for a worst case estimate. Mi ke Holmes believes that they rnet the 8/30/87 mil estone on the PSC r esponse to Sect i on 3/48 cornrnent s. However, Mike sees an overall 4 rnonth slippage in the proposed schedule, shown in Fig.1. The slippage involves two mi l est on es. On the 5/30/06 Comments line, Mr. Holmes- projects the PSC response to RAIs f rorn the proposed 9/1/87 to 1/15/88. On the Cooling Function Comments line, he projects PSC response to cornments from 7/15/87 to 11/1/87 . Mike said that he understood that these slippages may cause the However, he felt rel ease of the TS to PSC to be delayed f rom 5/88 to 8/88.
that there was suf ficient time to irnplement the upgraded TS prior to plant restart. This can be done by working on the various activities in parallel, rather than sequent i al l y.
It is PSC stated objective to use the upgraded technical spec i fi c at i ons for This activity operations following the fourth reactor re f ueling cycland e. 1/30/89 plant appears to be slipping to a 12/1/88 plant shutdown I
startup. The r e fueling schedule call s for a shutdown of 61 days. This estimate may increase as a result of planning for speci fic activi ties.But , -
if the shutddown period exceeds 90 days, oper ating FSV will no longer be ec onomi c al .
Nen Heitner asked PSC for a letter of ficially providing comments and con fi rmation of this schedul e. He also requested that PSC consider submit-the effect of the apparent slippages.
ting par tial packages to minimize Other i t erns highl ight ed dur ing the roeeting:
- 1. PSC provided NRC with a draft of a parallel activity to the TSUP, the PPS-Setpoint Overvicw. The dr af t information is included herein as Enclosure 4.
- 2. PSC will develop a new pr oposal for the ISI for Helium Circulators.
This will be done as a separate licensing action, outside the TSUP.
- 3. PSC accepted an action item to provide NRC with a report in 3-6 soonths to cl ar i f y what interlocks are def eated (r e the Interlock Sequence Switch) as a result of a change in the position- of the (node switch. The area of NRC interest was especially directed to changes for startup and low power operation.
- 4. Throughout the discussion, in response to an RAI, PSC indicated the possibility of rnoving an i t em from the TS to the Fire Protection Plan. PSC should highlight those TSs in this category and clari fy their current position.
5 Lub o e
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p e. m
. l 4
48 Indad.i
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- 5. Ken Heitner briefly described the status of the DBA-2 study by l j
ORNL/SAIC. As soon as a draft copy of this study is available, Ken will ;
place a copy into the PDR and send a copy to PSC. J j
- 6. Ken Heitner and David Moses recommended that PSC consider a require-ment that during power operation one of the 12.5% condensate pumps be op er abl e. This would provide assurance that FSV would avoid fuel damage ]
1 in the event of a lons of off-site power. X ,3 y,g l 7. Ken requested that PSC submit a draf t of their QA approach to )
assur e a good pr oduct for the TSUP. This draft will be reviewed with the TS Branch for the adequacy of the PSC approach. !
i I
l 'l i
l
~
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1 l
0 CLASSIFICATION STATUS OF TSUP ITEMS-RESULTS OF 8/25-26/87 KTG
~
NRC COMMENTS TO' PSC LTR. NRC TENTATIVE P-87272 AGREEMENT PSC (G-87056 & COMMENTS G-87161) LCOs NITACID4ENT f 1 (T0 P-87272) -
3.8.1.1 ACTIONS a.2 D1 ,
and a.4 B B (Joe) 4.8.1.1.2.a5 D A (Ken) Review TBD by Ed Tomlinson 4.8.1.1.2c2 D* D*(Ken) 4.8.1.1.2f A B (Ken / Joe)
Table 4.8.1-1 Af A (Joe / Ken)
Fig.3.8.1-1 Af A (Joe) PSC accepted and incorporated 3.8.2.1 Action A Af A,A,A(Dave)
NRC suggestions per p.6, Attachment 1 to P-87272 Attachment #2 to P-87272 (Electrical systems)
D Af (Ken) Transferred to PPS review 1 Cover in PPS submittal; covered -
2 D B (Joe) by general operability rqmts.
3 D Af (Ken) 4 D B (Joe / Ken) 5.2 D B (Joe / Ken) 5.6 & 11 D B (Ken) 5.7 D C (Ken) l 5.8 D B (Ken) 5.10 D B (Ken) 5.11 D B (Ken)
D* Review TDB by Ed Tomlinson 5.13,14,15 D 6.2 D B (Joe)
! 6.4 D A (Joe) 6.5 D B (Ken) 6.c D D* (Ken) 6.d D B (Ken)
D A 6.6 A
6.8 D
'c DMFT
I b'
I 1
NRC COMMFXT PSC LTR NRC TENTATIVE COMMENTS i P-87272 AGREEMENT ATTACHMENT # 3 TO P-87272 I B B (Ken) l 1 l 2 D,D A,B D .A (Dave / Ken) l 3
B l 4c D 5 D A 6.a.3 D B
- ' i
^
DR;ff 9 D A 10 D A j
11 D A _
12 D D' (Joe) PSC to give more info. i D B (Joe)- J 12e j 13 D B (Joe) i 14b D A 15 D B,A (Joe) ;
16 D B,B (Joe) 17 D D*D* (Ken) No generic guidance available from NRC (STS) 18 D A 19 D A (Joe)
D A l 20 j 21 D A i
i 22 D B i l 23 D A 24 D A 25a D B 25b D A 25c D Af,D* Expand- have to address DC l
' bus (Note resolution refers to #17 above) 26 D A 27 D A 28f Al D As per comment #17 l
28g D B f
l '
1 Unrut i
i
L
})
I XRC COMMENTS TO PSC LTR. NRC TENTATIVE COMMENTS PSC (G87131) P-87272 AGRFlMENT Iros Al, F A re Safe Shutdevn Cooling, FSAR De f .1. 34 clarification RAI-PO-TSUP*
Table 1.1#1 Al Af Table 1.1#2 B B (Dave) re LCO 3.9.1
. 3.2f1 F. F (Dave) RAI-PO-TSUP' 3.2.2 F F (Dave) RAI-PO-TSUP*
3.4f1 A,B,B D*,B,B (Dave) PSC agreed to use .one 12.5%
condensate purp available for i
power operation 3.4f2 B,B F Af Al re spec for tondensate pump operability 3.4f 3, f 4 B.B F D*,B,F D* re Circ Water System-Service Water System FSAR clarification, ' RAI-PO-3.4f5 F F TSUP*
3.4f6 A A 3/4.5 B B (Dave)
- 3. 5.1.1 # 1 Al A (Dave) 3.5.1.1 f 2 Af A (Dave)
- 3. 5.1 # 3 Al A (Dave)
- 3. 5.1.1 # 4 B,B . A,B (Dave)
- 3. 5.1.1 f 5 Al A (Dave / Ken)
- 3. 5.1.1 # 6 A A (Dave)
- 3. 5.1.1 # 7 Af Af (Ihve)
- 3 . 5.1.1 # 8,9 A.Al A, A (Dave) 3.5.1.1#10 B B (Dave / Ken) Classification could change
- 3. 5.1.1 f11 B B (Dave / Ken) 3.5,1,1f12 A A (Dave / Ken) 3.5.1.1#13 A A (Dave) 3.5.1.1114 A A (Dave) 3.5.1.1#15 B B (Dave)
- 3. 5.1.1 f 16 Al Al (Dave) Pending review of small condensate pump TS
- 3. 5.1.1 f 17 B B (Dave / Ken) '
- 3. 5.1.1 f 18 A A (Dave / Ken)
- 3. 5.1.1 f 19 Af,F Al,F (Dave) PSAR clarification, RAI-PO-TSUP*
f 3.5.1.1#20 B B (Ken Dave)
- 3. 5.1.1 f 21 Al A (Dava) 3.5.1.1f 22 B B (Dave, h )
3 RIFT
- P.A1-PO-TSUP= RAI potentially outside of TSUP scope L
j' ..
hQ
.m . .
l NRC COMMENTS TO PSC 12 NRC TENTATIVE COMMENTS P-8727e AGREDfENT l PSC (G87131)
F F (Dave)- See Note 3.5.1.1f 23 below
. 3. 5.1. l f 23 3.5.1.1724 B B (Dave) i l 3. 5.1.2 f 1,3 Af,Al Al,Al (Dave) 3.5.1.2f 2 Af A (Dave) 3.5.1.2f4,5 A,B A,B (Dave)
B B (Ken / Dave)~
FSAR Clarification; 3.6.2.1 f 1 RAI-PO-TSUP B B (Ken / Dave) 3.6.2.1#2 3.6.2,173- B B (Dave / Ken) add explanation with ref. in writeup of P-87272 3.6.2.1#4 B B (Dave)
- 3. 6. 2.1 #5 B B (Dave) 3.6.2.2#1,3 D D (Dave) PSC to find ref.; could chan8e'to A 3.6.2.2f2 B B (Dave) 3.6.3f1 B 'A,B (Dave)
B B (Dave) PSC to provide previous
'3.6~.3#2' ref. on this issue F FSAR Clarification, 3.6.3#3 F RAI-PO-TSUP 3.7#1 B,Af B, Af(Dave / Ken) Later, may move. Sect.3/4.7.6 (ACM comments & 3/4.7.7 to Fire Protection Program Plan !
only) j 3.7#2 B B (Ken) Accept 11 days offsite storage supply, then can resupply.
3.7.1.lf1 Af,B A#,B (Ken)
Af,B A#,D* (Dave) Later, discuss re TS on 12.5%
3.7.1.1#2 condensate purp.
3.7.1.113 Al Al F (Dave) Corrected in updated FSAR 3.7.1.1f4 F Rev. 5 3.7.1.1f5 B B (Dave) l 3.7.1.2 B (Rewrite), B,Al Psc to explicitly include Al these valves in SLRDIS TS i 3.7.1.5 A A 3.7.1.6 B B 3.7.3 B B PSC to clarify PCRV contain-3.7.5 B B (Dave) ment function in bases for LCOs 3.75 & 3.4.1 &
Appendix D in. upgraded FSAR i
Note 3.5.1.1f23: FSAR clarification; RAI-PO-TSUP, but FSAR Chap- )
ter 14 analysis implies that this feature is part of the primary l success path for accommodating loss of normal cooling transient- ;
l TS may be needed.
i l
.i
9 i
NRC TENTATIVE COMMEFTS NRC COMMENTS TO PSC LTR P-87272 AGREEMENT PSC(G87131) _
3.7.8#1 A Al (Deve)
Al Al (Dave) 3.7.8#2 n 3.7.8f3 3.7.8f4 F
B F
B y r]em '"
~
Al Al (Dave) 't 3.9.1(Part 1) 3.9.1(Part 2) F F (Dave)
B B (Ken) PSC' concludes that it has to SR 4.5.1.1 rely on analysis; can't do a simulated test.
ENCLOSURE 2 TO P87272 NRC COMMENTS PREVIOUS NRC TENTATIVE .
CLASS.* AGREEMENT COMMENTS l TO PSC __ _
B (Joe) re ISS switch; Ken rqstd a Table 1.0-1 Al i report in 3-6 months A,B C (Joe)
)
SL 2.2.1-5 i LCO 3.0 E A (Ken) 3.1.1-1 Af A 3.1.3-4,-8 A F (Ken / Dave) see basis for LCO 3.1.3 3.1.6-6 B D 3.2.1-1 A A (Ken) 3.3.2.3-3 A,D* A A#,D* D* new input from NRC staff to 3.3.2.3-4 be requested l 3.5.4 B A (Dave)
Al F (Dave / Ken) PSC to document basis for 3.6.4-2 past practice 3.7.2-4 B A (Joe)
D* D (Dave / Ken) possible move to Fire ,
3.7.6.3-3 Protection Plan 3.7.8-4 Al A (Dave) 3.7.10-3 A F (Dave)
Al Af,B (Joe) specific new TS for monitors 3.9.1-2 3.9.1-3 Af,P* A (Joe)
D* B (Ken) 6.3/6.4-1 6.5.1.6a A# A,B (Joe) $$3 UIL aj 6.5.1.7b D B (Joe)'
6.9.1.2a D Al (Joe)
Al Al SLRDIS valve should have a TS.
NRC Action 3 Reference SLRDIS analysis and any EQ recently put in FSAR.
- Based on NRC letters dated 10/7/86 and 12/1/86 '
1
- r. j ENCLOSURE 3 TO P-67272 (PSC responses to NRC Letter G-87131)
ItAI . PSC LTR. NRC TENTATIVE DESIGNATOR P-87272 AGRED4ENT COMMENTS
- 3. 5.1.1 f 1 Al A (Dave) (LCO 3.5.1.1a2)
Al A (Dave) re SR 4.5.1.lb (b.2-b 4);
3.5.1.1f2 new SR 4.5.1.lb2 Al A (Dave) (LCO 3.5.1.1, 4th page. basis) 3.5.1.1f 3 Basis to be revised by PSC 3.5.1.1#4 B Al 3.5.1.1#5 Al Al (Dave) PSC to rewrite basis of this TS '
- 3. 5.1.2 # 1 A A (Daye) 3.5.1.2f 2 B Al (Dave) PSC to revise basis of this TS
- 3. 5,1,2f 3 A,B A,B (Dave) 3.5.1.2f4 Al Al (Dave) PSC.to remove ref. to irrad.
fuel in all If0s where limits are not needed. .J 3.5.1.2f 5 Af A (Dave) Add new par. 3.0.5 defining calc. bulk core temp.
3.5.3.1#1 Al A (Dave) 3.5.3.lf2 A,B A,B (Dave) 3.5.3.2#1 Af Al (Dave / Ken) PSC to change TS to: orderly 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shutdewn and delete ref. to irrad. fuel.
3.5.3.2#2,3,4 Al,Af A, A, A,B (Dave)-
3.5.4 Al Al (Dave) change 10 min to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; re shutdown cooling 8 no ref. l to irrad. fuel. !
3.6.2.2#1 B B (Dave) f 3.6.2.2f2 A# A# (Dave) one loop of PCRV LCS must be operable or primary coolant flow be maintained when CBCT <760 deg.F' 3.6.2.2#3 B A (Dave) 3.6.2.2#4 A# A (Dave) !
3.7.1.6 Af A (Dave) 3.7.4.2 Al A (Dave) -
3.7.1.1 A,B A,B (Dave) ,
' " ' ' ' - - - -____u________ _ __