Letter Sequence Other |
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MONTHYEARML20236N4671997-10-14014 October 1997 Forwards TS Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests Project stage: Other ML20211Q0921997-10-16016 October 1997 Forwards TS Interpretations for Auxiliary Feedwater & Safety Injection Sys Operability for Plant,Units 1 & 2 Project stage: Other ML20236N5001997-10-18018 October 1997 Forwards Technical Specification Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests Project stage: Other 1997-10-16
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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 ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies 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 ML20209H6241999-07-16016 July 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered Wk of 990517 ML20209H7951999-07-16016 July 1999 Forwards NRC Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) (Including as-given Written Exam) for Tests Administered During Week of 990517 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 ML20212H7701999-06-18018 June 1999 Notification of 990715 Meeting with ABB-CE to Discuss Issues Re Steam Generator Welded Sleeve Problem Identified at Unit 1 ML20206S9241999-05-19019 May 1999 Forwards Insp Plans Re Prairie Island & Quad Cities,Which Identified Insp Activities That Would Be Completed at Facilities Over Next 6 to 12 Months 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 ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20204J3521999-03-26026 March 1999 Requests That Encl Document Be Entered in NRC Pdr.Documents Consists of Composite of Attachments to NSP Ltrs, & 990308 & Should Be Linked to Both Ltr ML20198J4801998-12-21021 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss License Amend Request to Allow Limited Inoperability of Boric Acid Storage Tank Level Channels & Transfer Logic Channels for Required Testing & Maint ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils 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 ML20236U2071998-07-22022 July 1998 Forwards Corrected Copy of Ltr Transmitting Licensee Insp Repts 50-282/98-08 & 50-306/98-08.Date Has Been Corrected to Show Issuance on 980702 ML20217E9701998-04-20020 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Mod to Plant Units 1 & 2,which Will Add Diverse RTS to Shut Down Reactor in Event of ATWS Event ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20202F6011997-12-0101 December 1997 Notification of 971211 Meeting W/Util in Rockville,Md to Discuss Intake Canal Seismic Issue at Plant ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20236N5001997-10-18018 October 1997 Forwards Technical Specification Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20236N4671997-10-14014 October 1997 Forwards TS Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20211A4651997-09-16016 September 1997 Requests for Waiver of Fee Billing for Replacement Pilot Insp.Nrr in Process of Developing headquarters-led Insp Procedure for Future Use at All NPP Licensee Sites ML20217K8081997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Revised Methodology Used to Calculate MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration ML20210K6081997-08-13013 August 1997 Informs That Operator Licensing Exams Administered Wk of 970616 at Prairie Island,Units 1 & 2.Listed Info for Processing Through Nudocs & Distribution to NRC Staff, Including NRC PDR Also Encl ML20217M0321997-08-13013 August 1997 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on Wk of 970616.Info Submitted for Processing Through Nudocs & Distribution to NRC Staff ML20141F0451997-06-26026 June 1997 Notification of 970709 Meeting W/Nsp in Rockville,Maryland to Discuss ATWS Protection at PINGP & Possible Installation of Diverse Scram Sys ML20147J2641997-04-16016 April 1997 Responds to 961126 Request Re Task Interface Agreement 96-0440, Defining Dry Cask Storage Terms. Basic Reasons to Return Cask to SFP & Unload Sf Assemblies Are Either to Retrive or Dispose or Respond to Event or Condition ML20136D5311997-03-0707 March 1997 Notification of 970312 Meeting W/Util in Rockville,Md to Discuss Issues Pertaining to Prairie Island Amend of Cooling Water Sys Emergency Intake Design Bases ML20134N5851997-02-19019 February 1997 Notification of 970224 Meeting W/Northern States Power in Rockville,Md to Discuss Issues Pertaining to Prairie Island Amend of Cooling Water Sys Emergency Intake Design Bases ML20134J9331997-02-10010 February 1997 Notification of 970213 Meeting W/Util in Rockville,Md to Discuss Results from Recent SG Insps Performed on Facility ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134C2821997-01-29029 January 1997 Notification of 970206 Meeting W/Nsp in Rockville,Md to Discuss ISI at Prairie Island & Adoption of ASME Code Case N-521 ML20135C3791996-11-25025 November 1996 Informs That Commission Provided Guidance to Staff to Ensure That Rights of Sovereign Tribal Govts Fully Respected & to Operate within govt-to-govt Relationship w/federally- Recognized Native American Tribal Govts 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 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 ML20128E6401993-01-29029 January 1993 Notification of 930209 Meeting W/Util in Rockville,Md to Discuss V(Z) Analysis Issues at Plant ML20128E7811993-01-26026 January 1993 Notification of 930202 Meeting W/Util in Rockville,Md to Discuss Instrumentation TS Issues at Plant ML20058H8631990-11-16016 November 1990 Notification of 901219 Meeting W/Util in Rockville,Md,To Discuss NRC Bulletin 88-008 Concerns ML20055D5791990-06-27027 June 1990 Requests Position on Allowability of Radios or Tape Players in Control Room of Nonpower Reactors ML20246E6201989-08-23023 August 1989 Discusses Certification of Pnl Contractor Personnel as PWR Examiners.S Carrick Completed Required Written & Operating Exam Activities at Facilities During Wk of 890612.Oral Exam Audit Encl.W/O Encl ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20247M1331989-05-24024 May 1989 Forwards Input to SALP 8 Rept for Units 1 & 2.Evaluation Conducted Per 880606 Rev to NRC Manual Chapter 0516, Systematic Assessment of Licensee Performance & Provides Input Per Guidelines in Rl Hague 890412 Memo ML20207K8911988-10-13013 October 1988 Advises That Encl Revised Criteria for Determining Justification for Continued Operation When Encountering Major Discrepancies in As-Built Safety-Related Piping Acceptable from Anomaly Discovered to Next Refueling Outage ML20196G5121988-06-28028 June 1988 Notification of 880719 Meeting W/Util in Rockville,Md to Discuss Plans for Installation of Two Addl Diesel Generators That Would Provide Alternate Power Capability to Meet NRC Station Blackout Requirements.Meeting Agenda Encl ML20155G7431988-06-0707 June 1988 Forwards F Miraglia 880527 Memo for Review & Requests Proposed Priorities for Actions on Project Manager Rept by C.O.B. 880609 ML20154Q1661988-05-27027 May 1988 Discusses Updating Project Managers Rept (Pmr) in Accordance W/New Priority Ranking Sys.Mods Have Been Made So That Pmr Will Now Accept New Priority Data.Old Priority Data Will Be Deleted During Wk of 880530.Sample Data Format Encl ML20151X9101988-04-28028 April 1988 Notification of 880512 Meeting W/Puc of Mn to Discuss & Review Status of Spent Fuel Consolidation Project at Plant. Meeting Agenda Encl ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20148A7571988-03-14014 March 1988 Forwards Project Directorate III-1 Slides for 880317 Briefing of Executive Team.Slides Marked P Primary Slides Directorate Plans to Show.Other Slides Backup for Possible Ref 1999-09-23
[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 ML20212F5461999-09-23023 September 1999 Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211G9701999-08-30030 August 1999 Notification of 990909 Meeting with Util in Rockville,Md to Discuss Licensing Issues That May Result from Ongoing Merger Activities Between NSP & New Century Energies 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 ML20209H6241999-07-16016 July 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered Wk of 990517 ML20209H7951999-07-16016 July 1999 Forwards NRC Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) (Including as-given Written Exam) for Tests Administered During Week of 990517 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 ML20212H7701999-06-18018 June 1999 Notification of 990715 Meeting with ABB-CE to Discuss Issues Re Steam Generator Welded Sleeve Problem Identified at Unit 1 ML20206S9241999-05-19019 May 1999 Forwards Insp Plans Re Prairie Island & Quad Cities,Which Identified Insp Activities That Would Be Completed at Facilities Over Next 6 to 12 Months 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 ML20137H5041999-04-0808 April 1999 Informs That Licensee Requesting Listed Changes to Boilerplate Distribution Lists Used by NRR for Docketed Info.Add Site General Manager to Both Prairie Island & Monticello Lists ML20204J3521999-03-26026 March 1999 Requests That Encl Document Be Entered in NRC Pdr.Documents Consists of Composite of Attachments to NSP Ltrs, & 990308 & Should Be Linked to Both Ltr ML20198J4801998-12-21021 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss License Amend Request to Allow Limited Inoperability of Boric Acid Storage Tank Level Channels & Transfer Logic Channels for Required Testing & Maint ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils 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 ML20236U2071998-07-22022 July 1998 Forwards Corrected Copy of Ltr Transmitting Licensee Insp Repts 50-282/98-08 & 50-306/98-08.Date Has Been Corrected to Show Issuance on 980702 ML20217E9701998-04-20020 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Mod to Plant Units 1 & 2,which Will Add Diverse RTS to Shut Down Reactor in Event of ATWS Event ML20198G1911997-12-23023 December 1997 Notification of 980107 Meeting W/Util in Rockville,Md to Discuss Plans for Conversion to Improved STS for Plants ML20202F6011997-12-0101 December 1997 Notification of 971211 Meeting W/Util in Rockville,Md to Discuss Intake Canal Seismic Issue at Plant ML20198R4951997-10-27027 October 1997 Notifies of 971030 Meeting W/Util in Rockville,Md to Discuss Licensee Operability Determinations for Sys & Components w/limited-scope Weld Insps & Licensee Plans for Submitting Formal Relief Requests Per 10CFR50.55a(g)(5)(iv) ML20236N5001997-10-18018 October 1997 Forwards Technical Specification Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20236N4671997-10-14014 October 1997 Forwards TS Interpretation for Auxiliary Feedwater & Safety Injection Systems Operability for Prairie Island 1 & 2 in Response to 970912 & 15 Requests ML20211A4651997-09-16016 September 1997 Requests for Waiver of Fee Billing for Replacement Pilot Insp.Nrr in Process of Developing headquarters-led Insp Procedure for Future Use at All NPP Licensee Sites ML20217K8081997-08-14014 August 1997 Notification of 970826 Meeting W/Util in Rockville,Md to Discuss Revised Methodology Used to Calculate MSLB Containment Pressure Response in Anticipation for License Amend Request to Reduce Boron Concentration ML20217M0321997-08-13013 August 1997 Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on Wk of 970616.Info Submitted for Processing Through Nudocs & Distribution to NRC Staff ML20210K6081997-08-13013 August 1997 Informs That Operator Licensing Exams Administered Wk of 970616 at Prairie Island,Units 1 & 2.Listed Info for Processing Through Nudocs & Distribution to NRC Staff, Including NRC PDR Also Encl ML20141F0451997-06-26026 June 1997 Notification of 970709 Meeting W/Nsp in Rockville,Maryland to Discuss ATWS Protection at PINGP & Possible Installation of Diverse Scram Sys ML20147J2641997-04-16016 April 1997 Responds to 961126 Request Re Task Interface Agreement 96-0440, Defining Dry Cask Storage Terms. Basic Reasons to Return Cask to SFP & Unload Sf Assemblies Are Either to Retrive or Dispose or Respond to Event or Condition ML20136D5311997-03-0707 March 1997 Notification of 970312 Meeting W/Util in Rockville,Md to Discuss Issues Pertaining to Prairie Island Amend of Cooling Water Sys Emergency Intake Design Bases ML20134N5851997-02-19019 February 1997 Notification of 970224 Meeting W/Northern States Power in Rockville,Md to Discuss Issues Pertaining to Prairie Island Amend of Cooling Water Sys Emergency Intake Design Bases ML20134J9331997-02-10010 February 1997 Notification of 970213 Meeting W/Util in Rockville,Md to Discuss Results from Recent SG Insps Performed on Facility ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134C2821997-01-29029 January 1997 Notification of 970206 Meeting W/Nsp in Rockville,Md to Discuss ISI at Prairie Island & Adoption of ASME Code Case N-521 ML20135C3791996-11-25025 November 1996 Informs That Commission Provided Guidance to Staff to Ensure That Rights of Sovereign Tribal Govts Fully Respected & to Operate within govt-to-govt Relationship w/federally- Recognized Native American Tribal Govts 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 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 ML20128E6401993-01-29029 January 1993 Notification of 930209 Meeting W/Util in Rockville,Md to Discuss V(Z) Analysis Issues at Plant ML20128E7811993-01-26026 January 1993 Notification of 930202 Meeting W/Util in Rockville,Md to Discuss Instrumentation TS Issues at Plant ML20058H8631990-11-16016 November 1990 Notification of 901219 Meeting W/Util in Rockville,Md,To Discuss NRC Bulletin 88-008 Concerns ML20055D5791990-06-27027 June 1990 Requests Position on Allowability of Radios or Tape Players in Control Room of Nonpower Reactors ML20246E6201989-08-23023 August 1989 Discusses Certification of Pnl Contractor Personnel as PWR Examiners.S Carrick Completed Required Written & Operating Exam Activities at Facilities During Wk of 890612.Oral Exam Audit Encl.W/O Encl ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20247M1331989-05-24024 May 1989 Forwards Input to SALP 8 Rept for Units 1 & 2.Evaluation Conducted Per 880606 Rev to NRC Manual Chapter 0516, Systematic Assessment of Licensee Performance & Provides Input Per Guidelines in Rl Hague 890412 Memo ML20207K8911988-10-13013 October 1988 Advises That Encl Revised Criteria for Determining Justification for Continued Operation When Encountering Major Discrepancies in As-Built Safety-Related Piping Acceptable from Anomaly Discovered to Next Refueling Outage ML20196G5121988-06-28028 June 1988 Notification of 880719 Meeting W/Util in Rockville,Md to Discuss Plans for Installation of Two Addl Diesel Generators That Would Provide Alternate Power Capability to Meet NRC Station Blackout Requirements.Meeting Agenda Encl ML20155G7431988-06-0707 June 1988 Forwards F Miraglia 880527 Memo for Review & Requests Proposed Priorities for Actions on Project Manager Rept by C.O.B. 880609 ML20154Q1661988-05-27027 May 1988 Discusses Updating Project Managers Rept (Pmr) in Accordance W/New Priority Ranking Sys.Mods Have Been Made So That Pmr Will Now Accept New Priority Data.Old Priority Data Will Be Deleted During Wk of 880530.Sample Data Format Encl ML20151X9101988-04-28028 April 1988 Notification of 880512 Meeting W/Puc of Mn to Discuss & Review Status of Spent Fuel Consolidation Project at Plant. Meeting Agenda Encl ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20148A7571988-03-14014 March 1988 Forwards Project Directorate III-1 Slides for 880317 Briefing of Executive Team.Slides Marked P Primary Slides Directorate Plans to Show.Other Slides Backup for Possible Ref 1999-09-23
[Table view] |
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October 18, 1997 4 . i MEMORANDUM TO: J:hn N. Hannon Prrject Dir:ct: rate 111-1 Division cf React:r '1ojects lil/IV, NRR t
FROM: William D. Beckner, Chief Technical Specifications Branch Original Signed By Associate Director for Projects, NRR
SUBJECT:
TECHNICAL SPECIFICATION INTERPRETATION FOR AUXlLIARY FEEDWATER AND SAFETY INJECTION SYSTEMS OPERABILITY - PRAIRIE ISLAND 1 AND 2 (7AC NOs. M99666, M99667, M99669, and M99670)
In letters to the NRC dated September 12 and 15,1997, Northern States Power (NSP) requested interpretations of the Prairie Island Technical Specifications (Pl TS) with respect to Safety injection (SI) System OPERABILITY during changing plant conditions and Auxiliary Feedwater System (AFW) OPERABILITY when the AFW pump selector switches are in MANUAL and SHUTDOWN AUTO positions and the pump discharge valves are throttled, respectively. The Technical Specifications Branch (TSB) has reviewed the two letters and supporting documentation. TSB's interpretation of the Pl TS for the Si and AFW Systems are included in Attachments 1,2, and 3.
TSB agrees with the licensee that the SI System is OPERABLE and there is no violation of the TS between RCS temperatures of 310' F and 200* F with both Si control switches in the pullout position, and that the operator has a reasonable amount of time to perform the actions necessary to place the control switch in the pullout or AUTO position at the RCS transition temperatures of 310' F and 200' F. However, TSB recommends that NSP request a TS change to eliminate any ambiguity or questions regarding OPERABILITY during changing plant conditions.
TSB also agrees with the licenses that P1 TS 3.4.B.1.c allows the AFW pump discharge valves to be throttled under administrative control during startup and shutdown operations.
However, TSB does not agree with the NSP interpretation that in MODE 2 with the AFW pump selector switch in SHUTDOWN AUTO or MANUAL position which disables Function 7.d - sutomatic AFW pump start on main feedwater pump trip - that the AFW system is OPFr1ABLE. Since Function 7.d is required to be OPERABLE in MODES 1 and 2 in act,ordance with Pl TS Table TS 3.5-28, placing the AFW pump selector switch in the SHUTDOWN AUTO or MANUAL position would violate the TS requirements and require enter into the appropriate ACTIONS. TSB recommends that NSP request a TS change to Table 75 3.5 2B to change the APPLICABILITY from MODES i and 2 to MODES 1 and 2 l above 2% power, as well as TS 3.4.B.1.c to explicitly state shutdown operations for the throttle valves.
Attachments: As stated DISTRIBUTION:
FILE CENTER FMReinhart TSB R/F
- MWeston TSB Staff
\ _RPZimmerman NWDBeckner RJGiardina DOCUMENT NAME: G:\MWW/AFW123.Itr (WF6.1) i OFFICE TSB:ADPR:NRR TSB:ADPR:NRR TkADPR:NRJV C:TSB:ADPR:NRR NAME RJGiardinaqd_ MWWeshhFMRe WDBeckneN DATE 10/le/97 10//dS7 1[ /97\ 10//Y/97 OFFICIAL RECORD COPY 9807150148 980624 -- - - - - -
PDR FOIA l
UNNERST98-155 PDR l
,l,,
l
- km KatyN g 1 UNITED STATES g
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 3D806 4001 9.....
MEMORANDUM TO: John N. Hannon l Project Directorate lil-1 Division of Reactor Projects Ill/lV, NRR , k V
FROM: William D. Beckner, Chief Technical Specifications Branch M
Associate Director for Projects, NRR
SUBJECT:
TECHNICAL SPECIFICATION INTERPRETATION FOR AUXILIARY FEEDWATER AND SAFETY INJECTION SYSTEMS OPERABILITY - PRAIRIE ISLAND 1 AND 2 (TAC NOs. M99666, M99667, M99669, and M99670) in letters to the NRC dated September 12 and 15,1997, Northem States Power (NSP) requested interpretations of the Prairie Island Technical Specifications (Pl TS) with respect to Safety injection (SI) System OPERABILITY during changing plant conditions and Auxiliary
'- Feedwater System (AFW) OPERABILITY when the AFW pump selector switches are in MANUAL and SHUTDOWN AUTO positions and the pump discharge valves are throttled, respectively. The Technical Specifications Branch (TSB) has reviewed the two letters and supporting documentation. TSB's interpretation of the Pl TS for the Si and AFW Systems l are included in Attachments 1,2, and 3.
TSB agrees with the licenses that the SI System is OPERABLE and there is no violation of the TS between RCS temperatures of 310' F and 200* F with both Si control switches in the pullout position, and that the operator has a reasonable amount of time to perform the actions necessary to place the control switch in the pullout or AUTO position at the RCS
- transition temperatures of 310' F and 200' F. However, TSB recommends that NSP i
request a TS change to eliminate any ambiguity or questions regarding OPERABILITY during )
changing plant conditions.
TSB also agrees with the licenses that Pl TS 3.4.B.1.c allows the AFW pump discharge
! valves to be throttled under administrative control during startup and shutdown operations.
l However, TSB does not agree with the NSP interpretation that in MODE 2 with the AFW l pump selector switch in SHUTDOWN AUTO or MANUAL position which disables Function 7.d - automatic AFW pump start on main feedwater pump trip - that the AFW system is OPERABLE. Since Function 7.d is required to be OPERABLE in MODES 1 and 2 in accordance with PI TS Table TS 3.5 2B, placing the AFW pump selector switch in the SHUTDOWN AUTO or MANUAL position would violate the TS requirements and require entry into the appropriate ACTIONS. TSB recommends that NSP request a TS change to Table TS 3.5-2B to change the APPLICABILITY from MODES 1 and 2 to MODES 1 and 2 above 2% power, as well as TS 3.4.B.1.c to explicitly state shutdown operations for the throttle valves.
1 Attachments: As :tated CONTACT: R. J. Giardina, TSB (301) 415 3152 M. W. Weston, TSB (301) 415-3151 W-
,4 . .
Attachment 1 o Technical Specification interpretation for Safety injection System Operability During Movement into Different Plant Conditions.
Pl TS 3.3.A.1.c requires two Si pumps to be OPERABLE when the Reactor Coolant System (RCS) temperature is 2310' F . When the RCS temperature is <310' F, PI TS 3.3.A.3 and
,t 3.3.A.4 determine Si pump OPERABILITY. Pi TS 3.3.A.3 requires that at least one Si pump l control switch in the control room be in the pullout position whenever the RCS temperature
! <310' F, while 3.3.A.4 requires both SI pump control switches to be in the pullout position whenever the RCS temperature <200'F.
In an effort to satisfy both of these requirement, the Pl TS have recently been interpreted to require plant operators to instantaneously place the one remaining Si pump control switch in pullout when the RCS cools to 200* F . Ukewise, as the RCS is heated, when the plant l reaches 310' F, the second Si pump control switch is required to be instantaneously placed in the " AUTO" position. With the control switch in the " AUTO" position, no Si switches can be in pullout or the heatup has to be stopped. Yet, the SI pump control switch can not be placed in AUTO position prior to reaching 310' F because this would violate the l requirements of TS 3.3.A.3 which requires at least one Si pump control switch in pullout l when less than 310' F. Since you can not satisfy these requirements instantaneously, both l of these circumstances were considered non-compliance with TS requirements which l required reporting under 10 CFR 509.73 as a licenses event report (LER 1-97-09).
For changing plant conditions at 200' F, NSP has r&@.terpreted the TS to allow both SI pump control switches to be in pullout position. This is t.esed on the interpretation that l both TS 3.3.A.3 and 3.3.A.4 requirements can be met if tte TS phrase "at least one" is interpreted to allow both SI pump control switches to be placed in pullout prior to cooling down to 200' F. Thus, one switch will be placed in pullou'. when the RCS is below 310'F until the temperature approaches 200' F. At that time both switches will be placed in pullout. This maintains the plant in a safe condition since events which require operation of the Si system at low RCS temperatures occur slowly and allow emple time for the operator l to manually place the SI system in service. The staff agrees that the phrase "at least one"
! will allow both Si control switches to be placed in the pullout position at anytime the RCS l
temperature is <310' F. !
i 1 For changing plant conditions as the RCS temperature reaches 310' F, NSP interpreted TS l 3.3.A.1.c and TS 3.3.A.3 to allow some reasonable time f.or operators to place the second Si pump control switch in the AUTO position. This reasonable time does not require definition since the plant is not in any imminent danger if the second Si pump control switch is not instantaneously placed in the AUTO position. This is based on the fact that l the temperature of 310' F is a target temperature at which the operators take their actions to implement low temperature overpressure protection. However,it was not expected the operator actions would occur precisely at 310' F since the instrumentation which provides ,
the RCS temperature indication is not exact and this temperature was based on heatup and '
cooldown curves where a precise temperature was not calculated. Thus, it is not reasonable to expect operator action instantaneously at the precise temperature of 310* F.
The staff agrees with the licenses that the temperature is a target temperature at which actions need to be taken and that the actions cannot be taken instantaneously. However, the staff would expect the operator actions to be taken immediately upon reaching 310* F.
Immediately is defined in the STS (NUREGs 14301434) as actions that should be pursued
Attachmc.it 1 e
without delay and in a controlled manner. Thus, the staff agrees with the licenses that a reasonable time limit for operator action is acceptable. However, TSB recommends that NSP request a TS change to eliminate any ambiguity or questions regarding OPERABILITY during changing plant conditions.
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l Attachment 2 l
Technical Sp:cificati:ns Int:rpr:tati:n f r Auxill ry Feedwat:r System Oper bility with l
Throttled Pump Discharge Valves.
Whenever the unit is critical or the RCS average temperature exceeds 350' F, for single unit operation, TS 3.4.B.1.s requires the turbine driven AFW pump associated with the operating reactor and a motor driven AFW pump be OPERABLE and for two unit operation, TS 3.4.8.1.b requires all four plant AFW pumps to be OPERABLE. TS 3.4.B.1.c requires all valves and piping associated with the AFW pumps to be OPERABLE whenever the unit is critical or the RCS average temperature exceeds 350' F. This specification makes an exception that "during STARTUP OPERATION necessary changes may be made in motor-l operated valve position". During normal plant startup and shutdown operation, the AFW l pump discharge valves are throttled to control steam generator levels. NSP questions l whether the AFW pump discharge valves are OPERABLE when they are throttled ,
particularly during shutdown operations. The staff has reviewed TS 3.4.B.1.c and concludes that the term *STARTUP OPERATION"is encompasses to MODES 2 thru 4 in the P1 TS. However, based on the definition of STARTUP OPERATION in Section 1.0 of the Pl TS, the words "during STARTUP OPERATION" apply only when the plant is going up in power (startup). For shutdown operations the Pl TS are not as explicit. However, the staff l
concludes that the definition of OPERABLE - OPERABILITY in Section 1.0, the Objective of TS 3.4
- assure the capability of removing decay heat from the reactor," and the allowance to change the throttle valves position on start-up and manual valve position during operations, provides sufficient justification to conclude that the throttle valves can he throttled during shutdown operations. Thus, there is no question that the AFW pump discharge valves can be throttled as long as the throttling is done under direct administrative control, and that the valves and the system are considered OPERABLE.
l However, the staff recommends that TS 3.4.B.1.c be modified to explicitly state that the l motor operated valves' position can be changed both on startup and shutdown. ,
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Attachment 3
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Technical Specifications interpretation for Auxillary Foodwater System Operability with AFW Pump Selector Switch in Shutdown Auto in MODE 2.
AFW pump selector switches have three positions, AUTO, MANUAL, and SHUTDOWN AUTO. When the selector switch is in the AUTO position, all required automatic AFW start functions listed in Table TS 3.5-2B are unabled for the AFW pump. In the MANUAL position the AFW pump can be started or stopped by placing the associated pump control switch in the START or STOP positions, respectively. In the MANUAL position, no automatic AFW pump start functions apply to the pump. The SHUTDOWN AUTO position enables all automatic AFW start functions on the pumps except the automatic start for loss of both l
main feedwater pumps. P1 TS Table TS 3.5-28 requires the AFW system to automatically
! start for Function 7.e (SI) during MODES 1,2,3 and/or 4, for Functions 7.b, and 7.f during l MODES 1,2, and 3 and for Functions 7.c and 7.d during MODES 1 and 2. Function 7.d is l the trip of both main feedwater pumps.
l During startup and shutdown operation when there is e low feed demand, the normal
[ . method for providing steam generator feedwater is by using the motor driven AFW pump.
l This in required because at low power levels, extended operation of the main feedwater pumps in the recirculation mode would cause damage to the main feedwater pumps due to heating and vibration of the pumps. Thus, safe, prudent operation of the plant requires l
placement of the AFW pump selector switches in SHUTDOWN AUTO during plant startup and shutdown. During startup operations, as the plant approaches 2% power the motor I driven AFW pump is operating and both putnp selector switches are in SHUTDOWN AUTO.
l The first main feedwater pump !s started and once stable operation is confirmed, the motor l driven AFW pump selector switch is briefly placed in MANUAL, the pump control switch is turned to STOP to secure the pump and then the AFW pump selector switch is set on ,
AUTO. Likewise, during plant shutdown, once the plant is below 2% power one AFW l pump selector switch is momentarily torned to MANUAL, the pump is started and then the switch is placed in the SHUTDOWN AUTO position and the other AFW pump selector l switch is placed in SHUTDOWN AUTO. 'Then the last operating main feedwater pump is secured. During both startup and shutdown evaluations the AFW pump selector switches are temporarily in SHUTDOWN AUTO or MAHUAL while a main feedwater pump is operating.
l Thus, NSP proposed that the P1 TS Table TS 3.5-2B Functional Unit 7.d requirement for MODE 2 OPERABILITY be interpreted to only reiluire automatic AFW pump start on loss of both main feedwater pumps when one or both risin feedweter pumps are required for operation in MODE 2, and that AFW pumps be considered OPERABLE within the
- requirements to Table TS 3.5 28, Functional Unit 7.d for the brief period of time when the AFW pumps are operating in SHUTDOWN AUTO or MANUAL while the main feedwater pumps are operating.
The staff has reviewed the subject TS and concludes that the NSP interpretation is not correct. The TS require Functional Unit 7.d to be OPERABLE in MODE 2, placing the AFW l pump selector switch in the SHUTDOWN AUTO or MANUAL positions makes this function (7.d), as well as the other AFW start functions for the manual position, inoperable. This ;
then would require entry into the appropriate ACTIONS for the TS for inoperable instrumentation and/or AFW systerr. While the staff agrees that use of the AFW system during startup and shutdown to avoid main feedwater pump damage is required at Prairie Island,interpretating the TS to allow this type of operation is not correct. The TS should be revised to limit the OPERABILITY of fanctional Unit 7.d to MODE 2 above 2% power or other quantifible limit.
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