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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20212J3501999-06-23023 June 1999 Forwards Draft Ltr for Use in Transmitting FERC Rept Re 981008 Audit to Licensee & Copy of FERC Insp Rept ,containing Color Photographs.Without Encls ML20196H9721999-06-23023 June 1999 Requests Attached Request for Addl Info Be Put Into NRC Public Document Room.Encl RAI e-mailed to W Sparkman of Southern Nuclear Operating Co on 990610 IA-96-023, Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier1999-06-18018 June 1999 Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier ML20205N7511999-04-13013 April 1999 Requests That Attached RAI Re TS 3/4.4.7.2e Be Placed in NRC Pdr.Informs That RAI Was Faxed to W Sparkman on 990413 & Will Be Used to Facilitate Discussions During Upcoming Telcon Between NRC & Snoc Staff ML20205M8681999-04-13013 April 1999 Requests That Encl Topics for Discussion Be Made Available in NRC Pdr.Items Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & SNC Staff ML20205J1401999-04-0505 April 1999 Notification of 990419 Meeting with Util to Discuss Licensee Justification of Certain TS Changes Need to Implement Improved Standard Ts.Meeting Was Held in Rockville,Md ML20205G5781999-04-0101 April 1999 Notification of 990416 Meeting with Snoc in Rockville,Md to Discuss Farley Npp,Unit 1 SG Operational Assessment ML20205C8771999-03-31031 March 1999 Requests That Encl questions,e-mailed to W Sparkman of Southern Nuclear Operating Co,Inc,Which Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & Util Be Made Available in NRC PDR ML20207J4931999-03-0101 March 1999 Forwards NRC Operator Licensing Exam Repts 50-348/98-300 & 50-364/98-300 (Including Completed & Graded Tests) for Tests Administered on 980313 ML20207J4681999-03-0101 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980313 at Farley NPP ML20202E1621999-01-29029 January 1999 Requests That Encl RAI Be Made Available in NRC Pdr.Subj Document Neither Constitutes Formal Request for Info Nor Represent Formal NRC Position.Encl RAI Faxed on 990129 to W Sparkman of Snoc ML20198H5741998-12-22022 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss Licensee Justification of Certain TS Changes Needed to Implement Improved Standard TSs ML20197J0501998-12-14014 December 1998 Requests That Encl Memo & Attachments Associated with Task Interface Agreement (TIA 96-023) Fraley License Basis & Acceptability of Kaowool as Electrical Raceway Fire Barrier Be Placed in NRC PDR ML20196H1181998-12-0404 December 1998 Forwards Message Faxed to M Ajluni of Southern Nuclear Operating Co (SNC) on 981204,to Prepare SNC for Conference Call.Message Does Not Constitute Formal Request for Info or Represent Formal NRC Staff Position ML20196E2911998-12-0101 December 1998 Notification of 981215 Meeting with Util in Rockville,Md to Discuss Matters Re Kaowool Fire Barriers Installed at Plant ML20195B7721998-11-12012 November 1998 Forwards Message That Had Been Faxed to M Ajluni on 981112. Purpose of Message Was to Prepare Licensee Personnel for Conference Call Re SG Tube Insp Results for Farley NPP Unit 1 ML20196F7001998-11-0202 November 1998 Notification of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Maryland to Discuss Matters Re Current SG Tube Insps at Farley NPP Unit 1 ML20154L1171998-10-15015 October 1998 Notification of 981026 Meeting with Util in Rockville,Md to Discuss Westinghouse BE-LOCA Abbreviated Reanalysis for Plant,Units 1 & 2 New SG ML20154B0681998-09-29029 September 1998 Notification of 981008 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Repair of SG Tubes ML20154B0411998-09-29029 September 1998 Notification of 981014 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Justification of Certain TS Changes Needed to Implement Improved Std TSs ML20217B1371998-04-21021 April 1998 Forwards Three Documents Associated W/Farley Nuclear Plant, Units 1 & 2-licensing/design Basis for Tornado Missile Protection to Be Made Available in PDR ML20217H4431998-04-0101 April 1998 Forwards Message Faxed on 980401 to M Ajluni of Southern Nuclear Operating Co,Inc (Snc).Purpose of Message Was to Prepare SNC Personnel for Conference Call & Does Not Consitute Formal Request for Info ML20217B1811997-12-18018 December 1997 Discusses Design Insp of Farley Units 1 & 2,for Jan-March of 1997,identified Tornado Missile Protection Issue Re Exhaust Piping & Silencers for EDG for Both Units (Including Station Blackout DG) ML20198S9281997-10-31031 October 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Plans & Schedule for SG Replacement ML20217B1961997-10-15015 October 1997 Discusses Review of Farley Nuclear Plant,Units 1 & 2 Licensing & Design Basis for Protection Against Tornado Missiles at Farley in Accordance w/970402 Memo from RM Gallo ML20217D9721997-09-30030 September 1997 Notification of 971022 Meeting W/Licensee in Rockville,Md to Discuss Licensee Initiatives That Focus on Planned Licensing Actions for FNP & Corrective Measures Related to Problems Considered by Licensee Mgt to Warrant Special Attention ML20216G2151997-09-0505 September 1997 Notification of 970916 Meeting W/Snoc in Rockville,Md to Discuss Improved Standard Technical Specification Conversion Application & Schedule for Submittal ML20236N3231997-08-21021 August 1997 Forwards SER in Response to Licensee 970522 Requested Interpretation of TS 4.8.1.1.2.e for Two Shared EDGs ML20148J8131997-06-16016 June 1997 Notifies of 970701 Meeting W/Util in Rockville,Md to Discuss Util Initiatives That Focus on Planned Licensing Actions for Plant & Corrective Measures Re Problems Considered by Util Mgt ML20141B0131997-06-16016 June 1997 Notification of 970701 Meeting W/Southern Nuclear Operating Co in Rockville,Md to Discuss SNC Initiatives That Focus on Planned Licensing Action for FNP & Corrective Measures. Meeting Cancelled ML20217B2111997-04-0202 April 1997 Informs That During Insp of Farley Units 1 & 2 in Jan-March 1997,NRR Led Insp Team Identified Tornado Missile Protection Issue W/Exhaust Silencers for DG for Both Units ML20236M9961997-03-27027 March 1997 Forwards Response to Questions Re Ventilation Specs for Farley ML20137C2501997-03-20020 March 1997 Forwards Message to M Ajluni of Southern Nuclear Operating Re Preparing Licensee Personnel for Conference Call ML20236M9661997-02-12012 February 1997 Discusses from Southern Nuclear Operating Co Requesting NRC Review Interpretation of Application of TS 3/4.9.13 at Farley Nuclear Plant,Units 1 & 2 During Modes 5 or 6,or When Defueled ML20134B3421997-01-27027 January 1997 Notification of 970205 Meeting W/Listed Attendees in Rockville,Md to Discuss Util Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair Method in Repair of SG ML20197J0751996-11-26026 November 1996 Requests Technical Assistance in Evaluation of Issues Identified During Routine Insp at Plant.Insp Rept Summary with Justification Encl ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20149E9221994-02-18018 February 1994 Responds to 930215 Request from J Strosnider Re Documentation of Concerns Re Plant Two Volt IPC Proposal & Resolution of Public Comments Concerning Voltage Based Repair Criteria ML20058J7101993-11-18018 November 1993 Notification of Significant Licensee Meeting W/Util on on 931123 to Discuss Plant SALP Board Assessment for Period of 930531-0925 IR 05000364/19930261993-11-10010 November 1993 Notification of Significant Licensee Meeting W/Util on 931117 in Atlanta,Ga to Discuss Violation 50-364/93-26-01 Re Personnel Error Resulting in Losses of Configuration Control During Performance of Maint & Testing Activities ML20057C3131993-09-15015 September 1993 Notification of Significant Licensee Meeting W/Util on 931013 to Discuss SALP Performance of Facility During Period 920531-0925 ML20056E4221993-08-0606 August 1993 Requests Written Inputs on Performance of Farley Facilities During Completed SALP Cycle 11 During Period 920531-930925 Using Encl Feeder Forms.Salp Board Meeting for Farley Scheduled for 931013 ML20127J5121993-01-19019 January 1993 Notification of 930202-03 Meetings W/Licensee in Columbia,Al Re Safety Audit of Storage Pond Dam & Dike by NRC & FERC ML20126B1451992-12-11011 December 1992 Notification of 921218 Meeting W/Util in Rockville,Md to Discuss Amend Request for Steam Generator Tube Alternate Plugging Criteria ML20058F4581990-11-0505 November 1990 Submits Daily Highlight.Notifies of 901107 Meeting W/Util to Discuss Technical & Regulatory Concerns Re Steam Generator Tube Collapse Under LOCA & Safe Shutdown Earthquake Loads ML20058E8271990-11-0202 November 1990 Notification of 901106 Meeting W/Licensee in Rockville,Md to Discuss Facility Steam Generators & Use of EPRI Alternative Tube Plugging Criteria.Agenda Encl ML20058E0461990-11-0202 November 1990 Notification of 901120 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Actions ML20058H8871990-11-0202 November 1990 Notification of Cancellation of 901120 Meeting W/Util to Discuss Status of Licensing Actions 1999-06-23
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217F3351999-10-14014 October 1999 Notification of 991103-04 Southern Nuclear Operating Licensing Workshop in Birmingham,Alabama with Goal of Improving Licensing Interface Between Licensee & NRC ML20212J3501999-06-23023 June 1999 Forwards Draft Ltr for Use in Transmitting FERC Rept Re 981008 Audit to Licensee & Copy of FERC Insp Rept ,containing Color Photographs.Without Encls ML20196H9721999-06-23023 June 1999 Requests Attached Request for Addl Info Be Put Into NRC Public Document Room.Encl RAI e-mailed to W Sparkman of Southern Nuclear Operating Co on 990610 IA-96-023, Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier1999-06-18018 June 1999 Forwards Response to TIA-96-023 Re Review of Plant,Units 1 & 2 Licensing Basis & Acceptability of Kaowool as Electrical Raceway fire-barrier ML20205N7511999-04-13013 April 1999 Requests That Attached RAI Re TS 3/4.4.7.2e Be Placed in NRC Pdr.Informs That RAI Was Faxed to W Sparkman on 990413 & Will Be Used to Facilitate Discussions During Upcoming Telcon Between NRC & Snoc Staff ML20205M8681999-04-13013 April 1999 Requests That Encl Topics for Discussion Be Made Available in NRC Pdr.Items Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & SNC Staff ML20205J1401999-04-0505 April 1999 Notification of 990419 Meeting with Util to Discuss Licensee Justification of Certain TS Changes Need to Implement Improved Standard Ts.Meeting Was Held in Rockville,Md ML20205G5781999-04-0101 April 1999 Notification of 990416 Meeting with Snoc in Rockville,Md to Discuss Farley Npp,Unit 1 SG Operational Assessment ML20205C8771999-03-31031 March 1999 Requests That Encl questions,e-mailed to W Sparkman of Southern Nuclear Operating Co,Inc,Which Will Be Used to Facilitate Discussions During Upcoming Conference Call Between NRC & Util Be Made Available in NRC PDR ML20207J4931999-03-0101 March 1999 Forwards NRC Operator Licensing Exam Repts 50-348/98-300 & 50-364/98-300 (Including Completed & Graded Tests) for Tests Administered on 980313 ML20207J4681999-03-0101 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980313 at Farley NPP ML20202E1621999-01-29029 January 1999 Requests That Encl RAI Be Made Available in NRC Pdr.Subj Document Neither Constitutes Formal Request for Info Nor Represent Formal NRC Position.Encl RAI Faxed on 990129 to W Sparkman of Snoc ML20198H5741998-12-22022 December 1998 Notification of 990107 Meeting with Util in Rockville,Md to Discuss Licensee Justification of Certain TS Changes Needed to Implement Improved Standard TSs ML20197J0501998-12-14014 December 1998 Requests That Encl Memo & Attachments Associated with Task Interface Agreement (TIA 96-023) Fraley License Basis & Acceptability of Kaowool as Electrical Raceway Fire Barrier Be Placed in NRC PDR ML20196H1181998-12-0404 December 1998 Forwards Message Faxed to M Ajluni of Southern Nuclear Operating Co (SNC) on 981204,to Prepare SNC for Conference Call.Message Does Not Constitute Formal Request for Info or Represent Formal NRC Staff Position ML20196E2911998-12-0101 December 1998 Notification of 981215 Meeting with Util in Rockville,Md to Discuss Matters Re Kaowool Fire Barriers Installed at Plant ML20195B7721998-11-12012 November 1998 Forwards Message That Had Been Faxed to M Ajluni on 981112. Purpose of Message Was to Prepare Licensee Personnel for Conference Call Re SG Tube Insp Results for Farley NPP Unit 1 ML20196F7001998-11-0202 November 1998 Notification of 981215 Meeting with Southern Nuclear Operating Co in Rockville,Maryland to Discuss Matters Re Current SG Tube Insps at Farley NPP Unit 1 ML20154L1171998-10-15015 October 1998 Notification of 981026 Meeting with Util in Rockville,Md to Discuss Westinghouse BE-LOCA Abbreviated Reanalysis for Plant,Units 1 & 2 New SG ML20154B0681998-09-29029 September 1998 Notification of 981008 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Repair of SG Tubes ML20154B0411998-09-29029 September 1998 Notification of 981014 Meeting with Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Justification of Certain TS Changes Needed to Implement Improved Std TSs ML20217B1371998-04-21021 April 1998 Forwards Three Documents Associated W/Farley Nuclear Plant, Units 1 & 2-licensing/design Basis for Tornado Missile Protection to Be Made Available in PDR ML20217H4431998-04-0101 April 1998 Forwards Message Faxed on 980401 to M Ajluni of Southern Nuclear Operating Co,Inc (Snc).Purpose of Message Was to Prepare SNC Personnel for Conference Call & Does Not Consitute Formal Request for Info ML20217B1811997-12-18018 December 1997 Discusses Design Insp of Farley Units 1 & 2,for Jan-March of 1997,identified Tornado Missile Protection Issue Re Exhaust Piping & Silencers for EDG for Both Units (Including Station Blackout DG) ML20198S9281997-10-31031 October 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Southern Nuclear Operating Co,Inc Plans & Schedule for SG Replacement ML20217B1961997-10-15015 October 1997 Discusses Review of Farley Nuclear Plant,Units 1 & 2 Licensing & Design Basis for Protection Against Tornado Missiles at Farley in Accordance w/970402 Memo from RM Gallo ML20217D9721997-09-30030 September 1997 Notification of 971022 Meeting W/Licensee in Rockville,Md to Discuss Licensee Initiatives That Focus on Planned Licensing Actions for FNP & Corrective Measures Related to Problems Considered by Licensee Mgt to Warrant Special Attention ML20216G2151997-09-0505 September 1997 Notification of 970916 Meeting W/Snoc in Rockville,Md to Discuss Improved Standard Technical Specification Conversion Application & Schedule for Submittal ML20236N3231997-08-21021 August 1997 Forwards SER in Response to Licensee 970522 Requested Interpretation of TS 4.8.1.1.2.e for Two Shared EDGs ML20148J8131997-06-16016 June 1997 Notifies of 970701 Meeting W/Util in Rockville,Md to Discuss Util Initiatives That Focus on Planned Licensing Actions for Plant & Corrective Measures Re Problems Considered by Util Mgt ML20141B0131997-06-16016 June 1997 Notification of 970701 Meeting W/Southern Nuclear Operating Co in Rockville,Md to Discuss SNC Initiatives That Focus on Planned Licensing Action for FNP & Corrective Measures. Meeting Cancelled ML20217B2111997-04-0202 April 1997 Informs That During Insp of Farley Units 1 & 2 in Jan-March 1997,NRR Led Insp Team Identified Tornado Missile Protection Issue W/Exhaust Silencers for DG for Both Units ML20236M9961997-03-27027 March 1997 Forwards Response to Questions Re Ventilation Specs for Farley ML20137C2501997-03-20020 March 1997 Forwards Message to M Ajluni of Southern Nuclear Operating Re Preparing Licensee Personnel for Conference Call ML20236M9661997-02-12012 February 1997 Discusses from Southern Nuclear Operating Co Requesting NRC Review Interpretation of Application of TS 3/4.9.13 at Farley Nuclear Plant,Units 1 & 2 During Modes 5 or 6,or When Defueled ML20134B3421997-01-27027 January 1997 Notification of 970205 Meeting W/Listed Attendees in Rockville,Md to Discuss Util Plans & Schedule for Submitting Proposed TS Amend Request Re Use of Direct Tube Repair Method in Repair of SG ML20197J0751996-11-26026 November 1996 Requests Technical Assistance in Evaluation of Issues Identified During Routine Insp at Plant.Insp Rept Summary with Justification Encl ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20149E9221994-02-18018 February 1994 Responds to 930215 Request from J Strosnider Re Documentation of Concerns Re Plant Two Volt IPC Proposal & Resolution of Public Comments Concerning Voltage Based Repair Criteria ML20058J7101993-11-18018 November 1993 Notification of Significant Licensee Meeting W/Util on on 931123 to Discuss Plant SALP Board Assessment for Period of 930531-0925 IR 05000364/19930261993-11-10010 November 1993 Notification of Significant Licensee Meeting W/Util on 931117 in Atlanta,Ga to Discuss Violation 50-364/93-26-01 Re Personnel Error Resulting in Losses of Configuration Control During Performance of Maint & Testing Activities ML20057C3131993-09-15015 September 1993 Notification of Significant Licensee Meeting W/Util on 931013 to Discuss SALP Performance of Facility During Period 920531-0925 ML20056E4221993-08-0606 August 1993 Requests Written Inputs on Performance of Farley Facilities During Completed SALP Cycle 11 During Period 920531-930925 Using Encl Feeder Forms.Salp Board Meeting for Farley Scheduled for 931013 ML20127J5121993-01-19019 January 1993 Notification of 930202-03 Meetings W/Licensee in Columbia,Al Re Safety Audit of Storage Pond Dam & Dike by NRC & FERC ML20126B1451992-12-11011 December 1992 Notification of 921218 Meeting W/Util in Rockville,Md to Discuss Amend Request for Steam Generator Tube Alternate Plugging Criteria ML20058F4581990-11-0505 November 1990 Submits Daily Highlight.Notifies of 901107 Meeting W/Util to Discuss Technical & Regulatory Concerns Re Steam Generator Tube Collapse Under LOCA & Safe Shutdown Earthquake Loads ML20058E8271990-11-0202 November 1990 Notification of 901106 Meeting W/Licensee in Rockville,Md to Discuss Facility Steam Generators & Use of EPRI Alternative Tube Plugging Criteria.Agenda Encl ML20058E0461990-11-0202 November 1990 Notification of 901120 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Actions ML20058H8871990-11-0202 November 1990 Notification of Cancellation of 901120 Meeting W/Util to Discuss Status of Licensing Actions 1999-06-23
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NUCLEAR REGULATORY COMMISSION k wAsumorow, o.c. asses.aom
- ( February ~ 12, 1997 MEMORANDUM TO: Jacob 1. Zimmerman, Project Manager Project Directorate 1-2 1 FROM: Christopher 1. Grimes, Chief
, 4 I gL i Technical Specifications nch v ,
SUBJECT:
REQUEST FOR WRITTEN INTERPRETATION OF TECHNICAL SPECIFICATIONS By letter dated November 27,1996, Southern Nuclear Operating Company (SNC) requested NRC review of its interpretation of the application of Technical Specification (TS) 3/4.9.13,
" Storage Pool Ventilation (Fuel Movement)," at Farley Nuclear Plant (Farley) Units 1 and 2 during modes 5 or 6, or when defueled. SNC had prepared the interpretation to address a concern stemming from an observation made by the NRC resident inspectors during the Farley Unit 2 fall 1996 refueling outage. This concern was documented as Unresolved item 50-364/96-13-01, " Penetration Room Filtration Operability Requirements for Spent Fuel Pool," in NRC inspection Report 50-364/96-13, dated December 23,1996. Specifically, on ,
October 30,1996, while fuel movement within the spent fuel pool was in progress, the I inspectors observed Farley performing surveillance testing on Train B of the penetration l room filtration (PRF) system, making the system inoperable with respect to the spent-fuel- !
room-filtration function. The inspectors' concern was that, during the test, PRF Train A appeared to be inoperable also. This concern was based upon a literal reading of TS 3.9.13, which requires two ladaaaadant PRF systems to be operable during fuel movement, and the TS definition of operability, which requires both a normal and an emergency ac electrical l power source. During the testing, the Train A PRF system was supported by the Train B ,
offsite and onsite emergency ac power sources, because the Train A ac sources were I inoperable.
l In its written interpretation for applying TS 3/4.9.13 during modes 5 and 6 and when defueled, SNC concluded that a single offsite ac source and a single onsite emergency ac source are sufficient to satisfy the ac electrical power requirements to support the l operability of the two required independent PRF systems. This conclusion is based on i
consistency with (a) TS 3/4.8.1.2, "A.C. Sources Shutdown," which only requires a single l offsite ac source and a single onsite emergency ac source to be operable, and (b) the degree of mechanical and electrical indeperidence necessary to satisfy the licensing basis during i modes 5 and 6 and when defueled. That is, the assumption of a single failure and concurrent loss of all offsite or onsite power is not required.
i CONTACT: Craig Harbuck, TSB/NRR 415-3140 9007140344 980624 PDR FOIA PDR L d
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Jacob 1. Zimmerman February 12, 1997 Although TS 3.8.1.2 only requires a single operable offsite ac source and a single operable onsite emergency ac source, satisfying these requirements is insufficient to meet TS 3.9.13, which requires two operable PRF systems. Each PRF system must be able to start automatically to satisfy the assumptions for the PRF apont fuel room-filtration function as described in FSAR Section 15.4.5 for the design basis fuel handling accident. The analysis or any design basis accident during shutdown conditions, including the analysis of the design basis fuel handling accident, assumes a loss of the offaite ac source (but not a concurrent single failure). In the Farley design, with both trains of the onsite ac electrical power distribution system cross connected and supported by a single onsite emergency sc source, a loss of the offsite ac source will result in load shedding of the opposite train loans I which defeats the automatic actuation capability of the opposite train PRF system.
Therefore, each PRF system must have its own operable onsite emergency ac source to maintain its automatic actuation capability and be considered operable in accordance with TS 3.9.13. Consequently, the NRC staff does not agree with SNC's interpretation of the application of TS 3/4.9.13 during modes 5 and 6 and when defueled. The Electrical Engineering Branch believes this issue may have ger;eric implications and is accordingly _-
referring it separately to the Events Assessment and Generic Communications Branch.
With respect to the situation observed by the resident inspectors, the staff concludes that the Train A PRF system became inoperable when the Train A onsite emergency ac source was made inoperable for maintenance. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of Train A becoming inoperable, fuel movement within the spent fuel pool should have ceased in accordance with Action a of TS 3/4.g.13. By concurrently making the Train B PRF system inoperable for surveillance testing, Farley created a loss of function condition because the Farley PRF system, as designed, would not have been capable of automatically mitigating the consequences of the Farley design basis fuel handling accident. In this situation, fuel movement within the spent fuel pool should have ceased immediately.
It is recognized that the assumptions of the fuel handling accident as described in FSAR Section 15.4.5 may be overly conservative. Nevertheless, TS must ensure that the 1 assumptions of the FSAR accident analysis remain valid. TS 3.9.13 and the Farley TS !
definition of operability do this. If SNC desires a less restrictive licensing basis relative to !
the fuel handling accident, it should consider revising its licensing basis analysis and TS )
3/4.9.13 be seeking a license amendment in accordance with 10 CFR 50.90. Until such a '
change in the operating license is granted by the Commission, Farley Units 1 and 2 must be operated in compliance with the current TS requirements, cc: RZimmerman SVarga JZwoiinski AChaffee 1
4 l
F i , 1 l > .
Jacob 1. Zimmerman February 12, 1997 Although TS 3.8.1.2 only requires a single operable offsite ac source and a single operable onsite emergency ac source, satisfying these requirements is insufficient to meet TS 3.9.13, which requires two operable PRF systems. Each PRF system must be able to start l
automatically to satisfy the assumptions for the PRF apont-fuel-room-filtration function as l described in FSAR Section 15.4.5 for the design basis fuel handling accident. The analysis or any design basis accident during shutdown conditions, including the analysis of the design basis fuel handling accident, assumes a loss of the offsite ac source (but not a '
concurrent single failure), in the Farley design, with both trains of the onsite ac electrical power distribution system cross connected and supported by a single onsite emergency ac .
source, a loss of the offsite ac source will result in load shedding of the opposite train loads which defeats the automatic actuation capability of the opposite train PRF aystem.
Therefore, each PRF system must have its own operable onsite emergency ac source to maintain its automatic actuation capatiility and be considered operable in accordance with l
TS 3.9.13. Consequently, the NRC staff does not agree with SNC's interpretation of the l application of TS 3/4.9.13 during modes 5 and 6 and when defueled. The Electrical Engineering Branch believes this issue may have generic implications and is accordingly referring it separately to the Events Assessment and Generic Communications Branch.
With respect to the situation observed by the resident inspectors, the staff concludes that the Train A PRF system became inoperable when the Train A onsite emergency ac source
! was made inoperable for maintenance. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of Train A becoming inoperable, l fuel movement within the spent fuel pool should have ceased in accordance with Action a l of TS 3/4.9.13. By concurrently making the Train 8 PRF system inoperable for surveillance testing, Farley created a loss of function condition because the Farley PRF system, as ,
designed, would not have been capable of automatically mitigating the consequences of the l Farley design basis fuel handling accident. In this situations, fuel movement within the spent i fuel pool should have ceased immediately.
It is recognized that the assumptions of the fuel handling accident as described in FSAR l
Section 15.4.5 may be overly conservative. Nevertheless, TS must ensure that the assumptions of the FSAR accident analysis remain valid. TS 3.9.13 and the Farley TS definition of operability do this. If SNC desires a less restrictive licensing baals relative to the fuel handling accident, it should consider revising its licensing basis analysis and TS 3/4.9.13 be seeking a license amendment in accordance with 10 CFR 50.90. Until such a change in the operating iicense is granted by the Commission, Farley Units 1 and 2 must be operated in compliance with the current TS requirements.
cc: RZimmerman JZwolinski SVerga AChaffee DISTRlRijTION:
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