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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211P4961999-09-0909 September 1999 Revised Notification of 990916 Meeting with Tva.Meeting Will Be Closed to Public Due to Proprietary Info Contained in Westinghouse TR WCAP-15128 to Be Discussed ML20211H7841999-08-31031 August 1999 Notification of 990916 Meeting with Util in Rockville,Md to Discuss TVA Intent to Aply for License Amend to Use Alternate Steam Generator Repair Criteria for Stress Corrosion Cracking Evaluated in W TR WCAP-15128 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 ML20210G9951999-07-20020 July 1999 Discusses 990628 Meeting Re New NRC Reactor Insp & Oversight Process.List of Attendees & Matl Used in Presentation Enclosed 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 ML20207A4771999-05-18018 May 1999 Notification of 990629 Meeting with Util in Rockville,Md to Discuss long-range Planning with Regard to Dry Storage of Sf at Sequoyah Site ML20206M0061999-05-12012 May 1999 Notification of 990616 Meeting with TVA in Rockville,Md to Discuss long-range Planning with Regard to SG Replacement.Draft Agenda Encl 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 ML20207M6711999-03-12012 March 1999 Forwards Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 Administered on 980928-1001,with as Given Written Exam Encl ML20204B5541999-03-12012 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980928-1001 ML20196H1561998-12-0303 December 1998 Notification of 981215 Meeting with TVA in Rockville,Md to Discuss Current & Future Licensing Activities ML20151X3091998-09-11011 September 1998 Notification of 980930 Meeting with Util in Rockville,Md to Discuss License Amend Request for Extending Sequoyah Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20237D4351998-08-21021 August 1998 Notification of 980901 Meeting W/Util in Rockville,Md to Discuss Planned SG Insp During Sequoyah Unit 1 Cycle 7 Refueling Outage in September 1998 ML20236X7041998-06-22022 June 1998 Notification of 980714 Meeting W/Tva in Rockville,Md to Discuss Status of Current Licensing Activities Re Sequoyah Nuclear Plant.Meeting Replaces Meeting W/Tva Scheduled for 980715 ML20249B7451998-06-19019 June 1998 Notification of 980708 Meeting W/Util in Rockville,Md to Discuss NRC Review of Installation of Lead Use Assemblies Containing U-236 Into Plant Core ML20249B7391998-06-19019 June 1998 Notification of 980715 Meeting W/Util in Rockville,Md to Discuss Status of Current Licensing Activities Re Plant ML20216B7171998-05-0707 May 1998 Notification of 980514 Meeting W/Util in Rockville,Md to Discuss NRC RAI Re TS Change Request to Extend Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20236N6021998-02-25025 February 1998 Responds to 980203 Memo Requesting Assistance in Responding to Operator License Appeal.Ts Branch Concurred in Interpretation ML20203K3261998-02-19019 February 1998 Revised Notification of 980305 Meeting W/Tvs in Rockville, Md.Meeting Being Held at Request of Utility to Discuss Special Project Being Pursued W/Doe,Use of Downblended Highly Enriched U in Fuel Used at Sequoyah Nuclear Plant ML20202D1571998-02-12012 February 1998 Requests That Encl Documents Be Placed on Docket for Sequoyah,Units 1 & 2 & in PDRs for Plant ML20202C5291998-02-11011 February 1998 Requests That Encl Documents Be Placed on Docket & in PDRs for Plant ML20202D1681998-02-11011 February 1998 Discusses MOV Terminal Voltage Issue,Per GL 98-10 Program at Plant.Concludes That Licensee Approach for Determining Operating Voltage for safety-related Movs,Acceptable ML20203A0311998-02-0505 February 1998 Notification of 980305 Meeting W/Tva in Rockville,Md to Discuss Special Projects Being Pursued W/Doe Including Use of Downblended Highly Enriched U in Fuel Used at Plant ML20236N5961997-12-31031 December 1997 Responds to Request for Technical Assistance (TIA 97-019) Re Interpretation of Intent of Sequoyah Nuclear Plant TS 4.10.3.2 ML20203B2651997-12-0303 December 1997 Notification of Meeting W/Tva on 971218 in Rockville,Md to Discuss Plans to Employ Electrosleeving Process to Repair Minor Cracks in Plants SG ML20202H9991997-12-0303 December 1997 Notification of 971210 Meeting W/Util in Rockville,Md to Discuss Current Licensing Activities Re Plant ML20236N4851997-10-16016 October 1997 Responds to 961016 Memo from Region II Requesting Technical Assistance (TIA 96-017) Re Interpretation of Sequoyah TS 3.2.4 on Quadrant Power Tilt Ratio ML20236N4471997-10-0101 October 1997 Responds to 961003,request from Region II for Technical Assistance Re Interpretation of Sequoyah TS 3/4.3.1, Specifically Items 10 & 11 on Table 3.3-1 ML20217D9131997-09-25025 September 1997 Notifies of 971002 Meeting W/Tva in Rockville,Md to Discuss Plans to Employ an Electrosleeving Process to Repair Minor Cracks in Plant SG ML20217P3451997-08-20020 August 1997 Notification of Licensee Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant Unit 1 SG Tube Insp Conducted in Apr 1997.Time & Meeting Room Changed ML20210K3301997-08-15015 August 1997 Notification of 970822 Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant,Unit 1 SG Tube Insp Conducted in Apr 1997 ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20205D9761997-07-0202 July 1997 Ack Receipt of Licensee Response to NOV (SL-IV) on Firewatches (EA 97-092).Licensee Requested That Region II Reconsider Violation as NCV ML20140F6191997-06-11011 June 1997 Forwards Documents Re Snp to Be Placed on Docket & in PDR ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20141K7251997-05-28028 May 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication. W/O Encl ML20140F6471997-05-0707 May 1997 Forwards P Blanch Comments Re Snp Pressurizer Draindown Event for Review ML20140F6351997-05-0505 May 1997 Forwards P Blanch Comments on TVA Evaluation of 970324 Pressurizer Draindown Event.Disagrees W/Conclusion That TVA Failed to Identify Root Cause ML20138D1481997-04-29029 April 1997 Forwards Documents Re Meetings W/Tva Ig Ofc Concerning Review of TVA Nuclear Employees Concerns Resolution Program. Documents Should Be Forwarded to NRC PDR ML20138B5721997-04-25025 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant,Units 1 & 2 to Upgrade Fire Barriers That Contain Thermo-Lag Matl ML20140F4151997-04-25025 April 1997 Notification of 970425 Meeting W/Tva in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant to Upgrade Fire Barriers That Contain Thermo-Lag Matl.Meeting Cancelled ML20205M1931997-04-14014 April 1997 Informs That Lieberman Offers No Objection to Releasing TVA OI Report 2-96-009 to Licensee & PDR Provided That Report Released in Accordance with Guidance in Section 8.2.4 of Investigative Procedures Manual ML20205E3591997-04-10010 April 1997 Discusses Sequoyah NOV Response Extension.Two Weeks Extension Has Been Granted ML20137F7941997-03-28028 March 1997 Requests Technical Assistance Re Design of AFW Control Sys at Plant ML20137C1841997-03-20020 March 1997 Notification of Upcoming Meeting W/Tva on 970321 in Rockville,Md to Discuss Status of Currently Ongoing Applications for Amend of TS for Plant ML20137A6441997-03-19019 March 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication ML20135A6471997-02-25025 February 1997 Notification of 970227 Meeting W/Util in Rockville,Md to Discuss Response to NRC Request for Info Re Plant Amend Request 96-01 ML20203C0591997-02-12012 February 1997 Discusses OI Rept 2-96-009 Re Alleged Falsification of Firewatch Journals.Both Individuals Were Subsequently Terminated ML20205D9591997-02-11011 February 1997 Forwards Copy of OI Rept 2-96-009 Issued on 970124 Re Alleged Falsification of Firewatch Journals at Sequoyah Nuclear Plant.Concludes That Both Firewatch Personnel Failed to Patrol All Assigned Areas & Falsified Firewatch Journals ML20133E8681997-01-0909 January 1997 Notification of 970116 Meeting W/Framatome Cogema Fuels in Rockville,Md to Discuss Use of Bwu Critical Heat Flux Correlation at Sequoyah 1999-09-09
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211P4961999-09-0909 September 1999 Revised Notification of 990916 Meeting with Tva.Meeting Will Be Closed to Public Due to Proprietary Info Contained in Westinghouse TR WCAP-15128 to Be Discussed ML20211H7841999-08-31031 August 1999 Notification of 990916 Meeting with Util in Rockville,Md to Discuss TVA Intent to Aply for License Amend to Use Alternate Steam Generator Repair Criteria for Stress Corrosion Cracking Evaluated in W TR WCAP-15128 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 ML20210G9951999-07-20020 July 1999 Discusses 990628 Meeting Re New NRC Reactor Insp & Oversight Process.List of Attendees & Matl Used in Presentation Enclosed 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 ML20207A4771999-05-18018 May 1999 Notification of 990629 Meeting with Util in Rockville,Md to Discuss long-range Planning with Regard to Dry Storage of Sf at Sequoyah Site ML20206M0061999-05-12012 May 1999 Notification of 990616 Meeting with TVA in Rockville,Md to Discuss long-range Planning with Regard to SG Replacement.Draft Agenda Encl 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 ML20204B5541999-03-12012 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980928-1001 ML20207M6711999-03-12012 March 1999 Forwards Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 Administered on 980928-1001,with as Given Written Exam Encl ML20196H1561998-12-0303 December 1998 Notification of 981215 Meeting with TVA in Rockville,Md to Discuss Current & Future Licensing Activities ML20151X3091998-09-11011 September 1998 Notification of 980930 Meeting with Util in Rockville,Md to Discuss License Amend Request for Extending Sequoyah Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20237D4351998-08-21021 August 1998 Notification of 980901 Meeting W/Util in Rockville,Md to Discuss Planned SG Insp During Sequoyah Unit 1 Cycle 7 Refueling Outage in September 1998 ML20236X7041998-06-22022 June 1998 Notification of 980714 Meeting W/Tva in Rockville,Md to Discuss Status of Current Licensing Activities Re Sequoyah Nuclear Plant.Meeting Replaces Meeting W/Tva Scheduled for 980715 ML20249B7451998-06-19019 June 1998 Notification of 980708 Meeting W/Util in Rockville,Md to Discuss NRC Review of Installation of Lead Use Assemblies Containing U-236 Into Plant Core ML20249B7391998-06-19019 June 1998 Notification of 980715 Meeting W/Util in Rockville,Md to Discuss Status of Current Licensing Activities Re Plant ML20216B7171998-05-0707 May 1998 Notification of 980514 Meeting W/Util in Rockville,Md to Discuss NRC RAI Re TS Change Request to Extend Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20236N6021998-02-25025 February 1998 Responds to 980203 Memo Requesting Assistance in Responding to Operator License Appeal.Ts Branch Concurred in Interpretation ML20203K3261998-02-19019 February 1998 Revised Notification of 980305 Meeting W/Tvs in Rockville, Md.Meeting Being Held at Request of Utility to Discuss Special Project Being Pursued W/Doe,Use of Downblended Highly Enriched U in Fuel Used at Sequoyah Nuclear Plant ML20202D1571998-02-12012 February 1998 Requests That Encl Documents Be Placed on Docket for Sequoyah,Units 1 & 2 & in PDRs for Plant ML20202C5291998-02-11011 February 1998 Requests That Encl Documents Be Placed on Docket & in PDRs for Plant ML20202D1681998-02-11011 February 1998 Discusses MOV Terminal Voltage Issue,Per GL 98-10 Program at Plant.Concludes That Licensee Approach for Determining Operating Voltage for safety-related Movs,Acceptable ML20203A0311998-02-0505 February 1998 Notification of 980305 Meeting W/Tva in Rockville,Md to Discuss Special Projects Being Pursued W/Doe Including Use of Downblended Highly Enriched U in Fuel Used at Plant ML20236N5961997-12-31031 December 1997 Responds to Request for Technical Assistance (TIA 97-019) Re Interpretation of Intent of Sequoyah Nuclear Plant TS 4.10.3.2 ML20202H9991997-12-0303 December 1997 Notification of 971210 Meeting W/Util in Rockville,Md to Discuss Current Licensing Activities Re Plant ML20203B2651997-12-0303 December 1997 Notification of Meeting W/Tva on 971218 in Rockville,Md to Discuss Plans to Employ Electrosleeving Process to Repair Minor Cracks in Plants SG ML20236N4851997-10-16016 October 1997 Responds to 961016 Memo from Region II Requesting Technical Assistance (TIA 96-017) Re Interpretation of Sequoyah TS 3.2.4 on Quadrant Power Tilt Ratio ML20236N4471997-10-0101 October 1997 Responds to 961003,request from Region II for Technical Assistance Re Interpretation of Sequoyah TS 3/4.3.1, Specifically Items 10 & 11 on Table 3.3-1 ML20217D9131997-09-25025 September 1997 Notifies of 971002 Meeting W/Tva in Rockville,Md to Discuss Plans to Employ an Electrosleeving Process to Repair Minor Cracks in Plant SG ML20217P3451997-08-20020 August 1997 Notification of Licensee Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant Unit 1 SG Tube Insp Conducted in Apr 1997.Time & Meeting Room Changed ML20210K3301997-08-15015 August 1997 Notification of 970822 Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant,Unit 1 SG Tube Insp Conducted in Apr 1997 ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20205D9761997-07-0202 July 1997 Ack Receipt of Licensee Response to NOV (SL-IV) on Firewatches (EA 97-092).Licensee Requested That Region II Reconsider Violation as NCV ML20140F6191997-06-11011 June 1997 Forwards Documents Re Snp to Be Placed on Docket & in PDR ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20141K7251997-05-28028 May 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication. W/O Encl ML20140F6471997-05-0707 May 1997 Forwards P Blanch Comments Re Snp Pressurizer Draindown Event for Review ML20140F6351997-05-0505 May 1997 Forwards P Blanch Comments on TVA Evaluation of 970324 Pressurizer Draindown Event.Disagrees W/Conclusion That TVA Failed to Identify Root Cause ML20138D1481997-04-29029 April 1997 Forwards Documents Re Meetings W/Tva Ig Ofc Concerning Review of TVA Nuclear Employees Concerns Resolution Program. Documents Should Be Forwarded to NRC PDR ML20140F4151997-04-25025 April 1997 Notification of 970425 Meeting W/Tva in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant to Upgrade Fire Barriers That Contain Thermo-Lag Matl.Meeting Cancelled ML20138B5721997-04-25025 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant,Units 1 & 2 to Upgrade Fire Barriers That Contain Thermo-Lag Matl ML20205M1931997-04-14014 April 1997 Informs That Lieberman Offers No Objection to Releasing TVA OI Report 2-96-009 to Licensee & PDR Provided That Report Released in Accordance with Guidance in Section 8.2.4 of Investigative Procedures Manual ML20205E3591997-04-10010 April 1997 Discusses Sequoyah NOV Response Extension.Two Weeks Extension Has Been Granted ML20137F7941997-03-28028 March 1997 Requests Technical Assistance Re Design of AFW Control Sys at Plant ML20137C1841997-03-20020 March 1997 Notification of Upcoming Meeting W/Tva on 970321 in Rockville,Md to Discuss Status of Currently Ongoing Applications for Amend of TS for Plant ML20137A6441997-03-19019 March 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication ML20135A6471997-02-25025 February 1997 Notification of 970227 Meeting W/Util in Rockville,Md to Discuss Response to NRC Request for Info Re Plant Amend Request 96-01 ML20203C0591997-02-12012 February 1997 Discusses OI Rept 2-96-009 Re Alleged Falsification of Firewatch Journals.Both Individuals Were Subsequently Terminated ML20205D9591997-02-11011 February 1997 Forwards Copy of OI Rept 2-96-009 Issued on 970124 Re Alleged Falsification of Firewatch Journals at Sequoyah Nuclear Plant.Concludes That Both Firewatch Personnel Failed to Patrol All Assigned Areas & Falsified Firewatch Journals ML20133E8681997-01-0909 January 1997 Notification of 970116 Meeting W/Framatome Cogema Fuels in Rockville,Md to Discuss Use of Bwu Critical Heat Flux Correlation at Sequoyah 1999-09-09
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i, i , 0-/3 H /b February 25, 1998 MEMORANDUM TO. Robert M. Gallo, Chief Operator Licensing Branch Division of Reactor Controls and Human Factors Omce of Nuclear Reactor Regulation FROM: Frederick J. Hebdon, Director Project Directorate ll-3 Division of Reactor Project - 1/II ,
Office of Nuclear Reactor Regulation l
SUBJECT:
TECHNICAL SPECIFICATION INTERPRETATION - SEQUOYAH This responds to your memorandum dated February 3,1998, requesting assistance in l responding to an operator license appeal. The questions in the attachment to your memo I regarding interpretation of a reactor coolant system boration Technical Specification (TS) at the Sequoyah Nuclear Plant are answered in the attachment to this memo.
Our interpretation of how much time is reasonable to "immediately initiate ... boration" in the event of inadequate margin is 15 minutes, based primarily on the position taken for this event in j the Westinghouse Standard Technical Specifications (NUREG-1431) but also considering the low probability of a Main Steamline Break Accident (the basis for the shutdown margin requirement) at a time when shutdown margin is below that required by the TS. The Technical Specifications Branch has concurred in this interpretation.
Docket Nos. 50-327, 50-328 l
Attachment:
As stated Distnbution-Docket File !
SQN Reading l I
DOCUMENT NAME: G:\SQN\gallores. app To receive a copy of this document. Indicate in the box C=Oopy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy OFFIC PM:PD2- E LAPD2-3 E BC:TSB E D:PD2-3 E E
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NAME RHernan h BClaytona f WBeckne[/1 FHebdon h DATE 2/ d /98 2/ / Y /98 2/ #/ /98 2/ 3 5' /98 OFFICIAL RECORD COPY 9007150193 900624
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% ,,,,, # February 25, 1998 l MEMORANDUM TO: Robert M. Gallo, Chief Operator Licensing Branch Division of Reactor Controls !
and Human Factors Office of Nuclear Reactor Regulation 1
FROM: Frederick J. Hebdon, Director Q -
l Project Directorate ll-3 y -
l Division of Reactor Project - t/II I Office of Nuclear Reactor Regulation
SUBJECT:
TECHNICAL SPECIFICATION INTERPRETATION - SEQUOYAH j This responds to your memorandum dated February 3,1998, requesting assistance in responding to an operator license appeal. The questions in the attachment to your memo regarding interpretation of a reactor coolant system boration Technical Specification (TS) at the Sequoyah Nuclear Plant are answered in the attachment to this memo.
Our interpretation of how much tirne is reasonable to "immediately initiate ... boration" in the event of inadequate margin is 15 minutes, based primarily on the position taken for this event in the Westinghouse Standard Technical Specifications (NUREG-1431) but also considering the low probability of a Main Steamline Break Accident (the basis for the shutdown margin requirement) at a time when shutdown margin is below that required by the TS. The Technical Specifications Branch has concurred in this interpretation.
Docket Nos. 50-327,50-328
Attachment:
As stated l
l l
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o SPECIFIC QUESTIONS
- 1. Doen o failu o to satisfy Sequoyah T.S. SURVEILLANCE REQUIREMENT 4.1.1.1.ti).b. require the licensee to take the action required by T.S. 3.1.1.1 ACTION STATEMENT. that action is to immediately initiate boration?
Answer: Yes, the TS would require "immediate" initiation of boration in that event.
However, the TS simplistically assumes that, if control rod bank position is below ,
the rod insertion limit (RIL) curves in the COLR, shutdown margin has dropped l to less than the required 1.6% ak/k. There is margin between control rod l position dropping below the Rll curves and shutdown margin dropping below l l
1.6% ak/k. The surveillance uses rod position to determine that required l l shutdown margin is met because it is simpler than performing a calculation every i 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I The term immediate is not defined in the Sequoyah TS. The Westinghouse l l Revised Standard TS (NUREG-1431) states that "when 'immediately' is used as l a completion time, the Required Action should be pursued without delay and in a l controlled manner." At Sequoyah, operators are mandated to use the " STAR" j philosophy, that is Stop,Ihink,6ct, and Beview. Also, the alarm response l procedure for a Low-Low Rod insertion Alarm is not required to be committed to i l memory, in fact, operators are trained to read and make sure they understand the procedure hafore taking any action. Furthermore, the corresponding TS (Shutdown Margin) in NUREG-1431 allows 15 minutes for the operator to j commence boration in this event. - I
- 2. Does a failure to satisfy Sequoyah T.S. SURVEILLANCE REQUIREMENT l 4.1.1.1.[1].b require the licensee to take the action required by T.S. 3.1.3.6.
ACTION STATEMENT- that action is to restore the control banks to within the limits (of the COLR) within two hours.
Answer- Yes, both TS are related to maintaining adequate shutdown margin and are therefore related to control rod bank position complying with the limits in the COLR. Failure of surveillance requirement 4.1.1.1.1.b (i.e. rod position not within the COLR limits) would require implementation of one of the TS 3.1.3.6 action statements (i.e., restore control rod position within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, reduce reactor power to below that for the existing control rod position on the RiL curve within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or be in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).
- 3. If the licensee concludes that T.S. SURVEILLANCE REQUIREMENT 4.1.1.1.[1].b is l not met, and that boration is necessary to restore SHUTDOWN MARGIN, how does the NRC interpret the action statement to "immediately initiate" boration?
How much time is considered acceptable to "lNITIATE" the boration?
Answer: As discussed above, the staff has taken the position in NUREG-1431 that, for I this event,15 minutes is a reasonable time to initiate boration.
r ATTACHMENT l
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d 2-
- 4. Is it a correct Technical Specification interpretation that the licensea must begin boration immediately (T.S. 3.1.1.11 and has 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore the control rod banks to the COLR limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />?
l Answer. The only interpretation invobed here is what is a reasonable time fiume associated with the word "imenediate." Even using the definition cor.tained in NUREG-1431, the elapsed tiras between symptom and action is not ..learly .
defined but depends on the es ent, the complexity of the procedure goveming the action and the complexity of tha action itself. For example, actions takin solely by control room operators woukt be expected to bis more timely than those taken by personnel outside the control room, such as auxiliary operators, beca1se of the required communications and coordination.
l l 5. The above questions address the apparent difference between the requirements of T.S. 3.1.1.1. and 3.1.3.6. Both T.S. focus on the control bank position. T.S.
l 3.1.1.1. specifies that the control bank position outside the COLR limits requireo l Immediate action. T.S. 3.1.3.6 specifies that the control bank outside of the
- COLR limit requires actions to restore control rods to within liraits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Answer. Although the two TS would appear to be inconsistent, TS 3.1.1.1 is intended to cover a wider range of events, including an inadvertent boron dilution event as l well as shutdown margin reduction due to control rod insertion. The Sequoyah TS are more conservative than NUREG-1431 in two ways:
- 1) The Sequoyah TS surveillance for shutdown margin is every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; the NUREG-1431 surveillance frequency is every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ' based on the generally slow [ rate of] change in required boron concentration and the low ;
l probability of an accident occurring without the required SDM." !
1 l 2) The Sequoyah TS requires boration to comrnonce immediately; NUREG-1431 allows 15 minutes. I As discussed above, shutdown margin can be dete' mined by calculation at power or shut down. At power, it is more convenient to determine that shutdown margin is met by observing control rod bank position than to perform calculations. It is a fact that, if control rods are above the insertion limits, shutdown margin requirements are met. But is not necessarily true that, if rod insertion limits are not met, shutdown margin is less tha'i that required by TS.
With the plant shut down, shutdown margin must be determined by calculation, taking into consideration RCS boron concentration, control bank position, RCS temperature, fuel bumup, xenon and samarium concentration, and isothermal temperature coefficient.
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