|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] |
Text
. . _ . _ _ . _ - . . _ _ _ . _ _ _ _ __ _._ _ _ _ _ . _ ..
- .jZ(o S To
- United States of America 00CKETE'D Nuclear Regulatory Commission ggg l i .
Subject:
Commission's Review of the Presiding Officers Decision in the matter of Ralph L. Tetrick.
I Docket No. 55-20726-SP 0FFICE OF SECRETARY 00CKETlHG & SERVICE i BRANCH j I, Ralph L Tetrick respectfully request that if the Commission reviews the decision of the Presiding i i Officer that they also review the decision on question #63.
The Staff states that "immediate" action is required under the stated conditions of question #63, because personnel would quickly be exposed to high levels of radiation due to the loss of water. The Staff also
- conte,ds that two annunciators sounding together (le. H-1/1 SFP LOW LEVEL and G-9/5 CNTMT SUMP Hi-LEML) is enough corroboration to act immediately to prevent injury to the health of plant employees i without , egard to actual conditions.
l 3-ONOP-033.2 states: With an irradiated assembly full up in the manipulation crane and maximum ,
refueling cavity seal leakage, the refueling bridge radiation levels will reach 10 rem /hr in about 22 -
minates (see attached procedure).
At Turkey Point there are two Spent Fuel Pool level Indications and five sump level Indications in the control room. I contend that the 10 to 20 seconds it takes to verify the alarm would not expose personnel inside containment to high levels of radiation, also, this brief period of time to verify the alarms is preferable to causing panic and possible hard to personnel evacuating containment ifjhe alarm is ;
invalid. N '
With regard to the above, I respectfully request the presiding Office to reverse his decision on question
- 63, I am also including a letter written by Brian J. Stamp, Acting Operations Supervisor at Turkey Point Nuclear Facility regarding question number 63.
Sincerely, x
Ralph L Tetrick ,
i enc.
1 9705080157 970423 PDR C
ADOCK 05000250 PDR j>U3 o
i y = = = - -
L Florida Power & Light Company i
l r. . .
, Turkey Point Nuclear Plant 4 s j Unit 3 i ,
i 1 a. i t ,
1 vi /, )
! w 3 j e
i i c2 i :. : .i-i 1 i
- t. 1 l
- 3<
t . 1.
t a
0
! : A: i %
{ .1. . [
j I 3-ONOP-033.2 M...i; i e s i:. t i .O&
i i
Ss,
=
a i, A
- V:.?:0 l I i
\ t
Title:
Refueling Cavity Seal Failure 1
Safety Related Procedure i Responsible Department: Operations ;
'93-149 Reviewed by PNSC: ,
t- Approved by Plant GeneralManager: 6/24/93 ;
I Periodic Review Due: 4/20/96 '
R T55 87-0377P, 88-2210, 89- 1021, 90-2205, 91- 1565P, 91-0561 T R TSs 92 1251P, 92- 1032P, 92 1358P, 93-0930P PCIM 89-332,92-031
. . Proceowre No.: Frocsoure ritie: pag, g 3 ONOP-033.2 Refucling Cavity Se21 Failuro *'8/5U33 l
i LIST OF EFFECTIVE PAGES 8
i
} Revision j P_aage Date
! 1 06/24/93
- 2 06/24/93
! 3 10/21/92 4 06/24/93 l
i 5 10/21/92 6 10/21/92
{ 7 10/21/92 8 10/21/92 ,
)
! 9 10/21/92 2
10 10/21/92 l 11 10/21/92 4
4 4
J 1
1 On ,
.- - - , ,- - . . ~ - . - _ - . . . - . - - - . . . _ . . . . . . . . - - - . . - - . . . . . - ~ - . . - . . . . _ - ~ _ ~ . . . . .
. Proced ure ido.; Procscure Title; Pa gg,-
i .
. 3 Approvat Date.
Refueling Cavity Ssal Failurs 10/21/92 1 3.ONOP.033.2l -
i i
i TABLE OF CONTENTS Section Page a i
1.0 PURPOSE ........................................ 4 2.0 SYMPTOMS ....................................... 4 l
3.0 AUTOMATIC ACTIONS .............................. 5 1
l 4.0 IMMEDIATE ACTIONS ............................... 5
- 5.0 ,S U B S E Q U E NT A CTIO N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-
6.0 REFERENCES
/ RECORDS REQUIRED /
COMMITMENT DOCUMENTS ......................... 11 l
1 l
l .
3 I .
i l>
l .
4 E
I 9'
9
proceours No.; proczowre Titie: Page-
, . , 4 3 ONOP 033.2 Rsfusling Cavity Smel Failurs ' 5TUO3 4
1.0 PURPOSE j 1.1 This procedure provides instructions for protecting plant personnel and j assuring that public health and safety is not jeopardized in the event of a j - _ Reactor to Refueling Cavity seal failure. [ Commitment - Step 6.3.1) 1.2' Irradiated fuel shall not be placed in the RCC change out baskets until an engineering evaluation is completed. Therefore, t2is procedure does not address an irradiated fuel bundle in the RCC change out baskets.
l I 2.0 SYMPTOMS j 2.1 Annunciators l ,
2.1.1 Annunciator H-1/1, SFP LO LEVEL, alarmed i 2.1.2 Annunciator G-9/5, CNTMT SUMP HI LEVEL, alarmed
! 2.1.3 Annunciator I-4/6, CNTMT SUMP HI LEVEL, alarmed -
i 2.1.4 Annunciator X-4/1, ARMS HI RADIATION, alarmed 4
! 1. Channel R-2, Unit 3 Containment - operating floor level, El,58 ft
- 2. Channel R-7, Unit 3 Spent Fuel Building - transfer canal area, El 58 ft i i 3. Channel R-19, Spent Fuel Pit Exhaust Duct t
! 4. Channel R-21, Unit 3 Spent Fuel Pit - north wall 4
2.1.5 Annunciator, H-1/4, PRMS HI RADIATION, alarmed 2.1.6 Annunciator H-1/5, CHRMS HI RADIATION, alarmed l 4
! 2.1.7 Annunciator I-7/3, RX VESSEL DRAINDOWN LO EO LEVEL l 2.2 Indications
- 2.2.1 Increase in local dose rate monitors.
2.2.2 Decreasing refueling cavity and spent fuel pit levels as observed
' locally.
4 2.2.3 Increase in Containment Sump Water Level Monitcrs, LI-3-6308A l and B .
- 2.2.4 Increase in Containment Water Level Monitors, LI-3-6309 A and B i
2.2.5 Containment Radiation Monitor R 3-12 increasing or alarmed.
4 1
5 i */RSE/bsm/rs/ctb i
i I
- . . - . ~. - , __ _ . - . _ _ , -
. Pro (Ecure NO . ProCSdste Tit:3 Page Approval Date 3-ONOP 033.2 Refueling Cavity Ss21 Fcitura 10/21/92 3.0 AUTOMATIC ACTIONS 1
3.1 Possible containment ventilation isolation due to high containment radiation levels.
l 3.2. Possible Control Room ventilation isolation due to high containment l radiation levels.
. 4.0 IMMEDIATE ACTIONS 4.1 Sound containment evacuation alarm.
5.0 SUBSEQUENT ACTIONS
! C AUTION S i
e With an irradiated assembly full up on the manipulator crane and maximum refueling cavity seal leakage, the refueling bridge radiation levels will reach 10
. Remlbrin about 22 minutes. -
- As reactor internals are exposed, airborne contamination levels in containment
{ willincrease.
5.1 Refueling Operator (s) in Containment 5.1.1 WHEN informed by H.P. that any of the following occurs, THEN exit the containment building immediately:
- 1. Area radiation levels exceed 10 Rem /hr ,
1 OR
- 2. Airborne contamination levels exceed 1000 times pre-event level OR l
- 3. Cumulative dose exceeds 10 Rem whole body or 50 Rem to the thyroid.
,._. ._._._._._._._._. ._. ._._._._._._._._._._.3
. NOTE .
I I
Steps S. I.2 and S.1.3 should be performed at the same time.
l
-- i._._._._._._._._._._._._._._._._._._._._._._._.;l 5.1.2 LF F an irradiated fuel assembly is in the fuel transfer car, THEN lay assembly down AND transfer assembly to the Spent Fuel Pool.
.-_-_.....m.. .._.__--m
. . Procecure No ProCec6re Title. Pegg.
Approva Date, 3
3 ONOP 033.2 Rofusling Ca*>ity Saal Fciture 10/21/92 m
l I
5.1.3 IF an irradiated fuel assembly is latched on the manipulator crane, j TI4EN perform the following:
I'
- 1. Fully insert assembly in the core AND leave assembly latched.
j - . .
- 2. .IfF assembly can NOT be inserted into the core, THEN move
- assembly to the upender AND transfer assembly to the spent fuel
,! building.
! 5.1.4 WHEN allirradiated fuel assemblies are in the core O R in the spent fuel building, THEN perform the following:
- 1. Move the fuel transfer car to the spent fuel building.
- 2. Direct refueling operator in the spent fuel building to close SFP j Transfer Tube Gate Valve,3-12-031.
5.1.5 IF the upper or lower internal assemblies are being removed from or Installed into the reactor vessel TH E N either-
- 1. Install the upper or lower internal assembly into the reactor vessel ifit is located on the reactor vessel guide studs.
91
- 2. Place the upper or lower internal assembly in a safe condition.
5.1.6 Inflate the inflatable cavity seal by;
- 1. Open the instrument air supply valve to the inflatable cavity seal and pressurize the seal to 30 to 35 PSIG.
- 2. Exit the containment building !
5.2 Refueling Operator (s)in Soent Fuel Building 5.2.1 WHEN informed by H.P. that any of the following occurs, THEN exit <
the spent fuel buildmgimmediately:
- 1. Area radiation levels exceed 10 Rem /hr QR
- 2. Airborne contamination levels exceed 1000 times pre-event level QR .
- 3. Cumulative dose exceeds 10 Rem whole body or 50 Rem to the thyroid.
, * /RSE/bsrn/rsirs
P'O Od wr t NO . ProCecor e Titie. Page Approvai Date.
l 3 ONOP 033.2 Refueling Cavity Ssel Failurs 10/21/92 1
i 5.2.2 IF an irradiated fuel assembly is latched to the spend fuel pit bridge
.; crane, TH E N insert assembly in a fuel rack.
C AUTION If more than one irradiated fuel assembly must be removed from containment, 't i
least one of the assemblies shall-be transferred to a fuel rack within the first 22 minutes of the event.
- 5.2.3 IF more than one irradiated fuel assembly must be removed from containment, THEN move one assembly from the transfer car to a fuel rack.
g._._._._._._._._._._._ g.,_._._._._._._._._._._.)
I I
- One irradiated fuel assembly may be left in the transfer car provided that the opender .
I remainsin the fulldown position. I l._._....._..,....._._._._._.._._.._._..J 5.2.4 WHEN all irradiated fuel assemblies are in the core or in the spent fuel building, TH EN perform the following:
- 1. Verify the fuel transfer car is in the spent fuel building.
- 2. Verify the fuel transfer car is in the down position.
- 3. Close SFP Transfer Tube Gate Valve,3-12-031.
5.3 Control Room Operator 5.3.1 Direct Health Physics to perform the following:
- 1. Limit access to containment
- 2. Limit access to spent fuel building .
- 3. Monitor radiation levels in containment and spent fuel building
- 4. Monitor containment for airborne contamination
- 5. Monitor cumulative whole body AND thyroid doses for operators in containment AND spent fuel building.
5.3.2 Isolate containment as follows:
- 1. Manually initiate containmentisolation phase A.
- 2. Verify containment isolation phase A valve white lights on VPB are all bright.
- 3. Verify Unit 3 containment purge exhaust and supply fans are off.
- 4. Verify Unit 4 containment purge exhaust and supply fans are off.
. - -. . . _ . . - ~ . - . - - .-~ ..~ -. . - - _ . = = _ _ . - ... . . . - . . . -
Procgours No.; P'oc50wre Ltie: Pigs Approval Date .
3 ONOP 033.2 Rtifusling Cavity Sect Failura 10/21/92 L ._.
i 1
5.3.2 (Cont'd) i 5. Verify all Containment Pur Isolation Valves are closed. ge Supply AND Exhaust l
- ~
- a. POV-3 2600 (outside containment)
- b. POV-3-2601 (inside containment)
- c. POV-3-2602 (outside containment) i 4
- d. POV-3-2603 (inside containment)
- 6. IF any Containment Purge Supply AND Exhaust Isolation
< V~alve is NOT closed,TH sN behindVPB, pull fuse for any i open purge valve.
i'
- a. XEP for POV-3-2600 l b. XLAG for POV-3-2601 ,
- c. XEQ for POV-3-2602
- d. XLAH for POV-3-2603
- 7. Verify Containment Instrument Air Bleed Isolation Valves are closec .
- a. CV-3-2819
- b. CV-3-2826
- 8. Verify all normal containment coolers are tripped AND associated outlet dampers are closed.
- 9. Verify containment sump pumps are tripped. :
- 10. Verify control building ventilation is in emerg'ency recirculation mode using ONOP-10308.1, Control Building Heating Ventilation and Air Conditioning System (HVAC) 5.3.3 Close allinner AND outer containment access hatches. l 5.3.4 Stop SFP cooling pumps.
5.3.5 Shutdown all non-essential electrical equipment in the containment lowerlevels. .
5.3.6 IJ_least at one emergency contr.inment filter fan.any em e/R$[/bsm/rs/r5
- . _ _ . - - _ _ _ _ . - .--._m._m._._._m . - - . . ~ . . _ . . . . _ . . . . . _ . . . . - _ . . _ . _ - . _ . _ _ . - - . . _ . . . . - . . . _ ~ . _ . . ~ . _ . .
- . irOCeCurt No . PROC % Cure Ttt@ Page Approval Datt.
3 ONOP 033.2 Refueling Cavity Ssal Felluro 10/21/92 i
5.3.7 Maintain RHR system operation:
- 1. Verify RHR pump motor amps stable AND less than 38 amps l l
- 2. Verify RHR flow on FI-3-605 between 3000 and 3750 gpm
- 3. Verify annunciator H 6/2, RHR HX HI/LO FLOW, clear
. 5.3.8 Restore s >ent fuel pit level to normal using 3-OP-033, SPENT FUEL i PIT COOLING SYSTEM.
1 5.3.9 Maintain spent fuel pit boron concentration greater than 1950 ppm as follows:
1
- 1. Direct Health Physics to monitor exposure for personnel entering the spent fuel pit building.
- 2. Direct Chemistry Department to sample spent fuel pit for boron ;
concentration. .
- 3. Borate spent fuel pit as necessary to maintain spent fuel pit boron l concentration greater than 1950 ppm.
5.3.10 Direct Nuclear Plant Supervisor to perform the following: J
- 1. Check for applicability to conditions listed in EPIP-20101,.
DUTIES OF EMERGENCY COORDINATOR.
- 2. Check for~ applicability to conditions listed in AP-0103.12, NOTIFICATION OF SIGNIFICANT EVENTS TO NRC.
- 3. Check for ap"slicability to conditions listed in AP 0103.6, EVALUATIOb AND REPOP"TNG OFIN-HOUSE EVENTS.
- 4. Verify applicable Technical Spect...ation Limiting Conditions for Operauon are satisfied. .
5.3.11 WHEN spent fuel pit level has been restored to between 56 ft 10 inches and 57 ft 2 inches, THEN perform the following:
- 1. Stop makeup to spent fuel pit l l
- 2. Startup the Spent Fuel Pit Cooling System l
l
-.. _- - . - _ , .-. . -. _ _ ~ . . . .- . - -
Proccoure No . Proc $ cure Titic: page ,
' - 10 ,
Approvai Oa te 3 ONOP-033.2 Refueling Cavity Saal Failura 10/21/92
! I j
I NOTE I 2
l l
. When refueling cavity level and RCS level are at the top of the reactor vessel flange, .
1 l Draon Down Level. LIS-3-6421 and 6423, should indica te approximately 60 percent. l L._._._._._._._._._._._._._._._._._._._._._._._.]
i 5.3.12 WHEN refueling cavity level drops to the top of the reactor vessel
- flange, THES perform the following
4 l 1. Verify containment sump level stops increasing.
i' 2. IF RCS level continues to decrease below the top of the reactor Essel flange, THEN add makeup to the RCS using charging pumps as necessary to maintain RCS water level at the reactor j vessel flange. ,
. I i .
l 5.3.13 _ W HEN plant conditions are stable AND radiation levels permit, .
TH EN initiate repairs to the refueling cavity seal.
- l l 5.3.14 Go to appropriate plant procedure as determined by Nuclear Plant
- Supervisor.
e a
4 a
f 4
i
}4 6
. . Procedure No.. Procecure Titte; Sage.
ADDroval Oate .
- 3.ONOP 033.2 Refueling Cavity Seal Failure 10/21/92
6.0 REFERENCES
/ RECORDS REQUIRED / COMMITMENT DOCUMENTS 6.1 References
. - 6.1.1 Technical Specifications, Section 3/4.9 Refuel Operations 6.1.2 FSAR
- 1. Section 9.5, Fuel Handling System
- 2. Section 11.2, Radiation Protections
- 3. Appendix 14E, Spent Fuel Storage Facility Modifications Safety )
Analysis Report i 6.1.3 Civil Drawing,5610-C-562, Rev 3 6.1.4 General Arrangement, 21774-1, General Arrangement of Fuel Transfer System .
6.1.5 Operating Procedures
- 1. ONOP-10308.1, Control Building Heating Ventilation and Air Conditioning System (HVAC)
- 2. 3-OP-033, Spent Fuel Pit Cooling 6.1.6 IE Bulletin 84-03, Refueling Cavity Water Seal.
6.1.7 FPL Letter JPE-PTP0-84-1546, Re: REA TPN 84-64 (Response to IE bulletin,84-03, Refueling Cavity Water Seal).
6.1.8 NRC Exit Meeting Minutes Dated 4/19/85
Subject:
Refueling Activities. IE Bulletin 84-03.
6.1.9 INPO SOER 85-1 (4 and 5), Reactor Cavity Seal Failure 6.1.10 FPL Letter JPN-PTN-90-2609, Re: RE A TPN-90-272 6.2 Records Reauired 6.2.1 None 6.3 .Qommitment Documents 6.3.1 NRC Inspection Report 89-053, March 14,1990 END OF TEXT FINAL PAGE
l I
l To: Peter B. Block, Presiding Officer Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission i Washington, DC 20555 i
Subject:
NRC Staffs' motion for reconsideration in the matter of Ralph L. Tetrick.
1 It is expected that the Licensed Operators at Turkey Point verify plant conditions when one or more annunciators are received in the control room prior to taking corrective actions. -
In the case of Question #63, I fully expect the Operators to verify the decrease in the Spent Fuel Pool level and the increase in the Containment Sump level by the indicators located within the surveillance area of the control room. This action would only take seconds and could preclude erroneously sounding the containment evacuation alarm. During refueling outages, there are numerous jobs going on simultaneously inside the containment.
Requiring all personnel to evacuate the area unnecessarily could pose a larger safety hazard than would the increased radiation levels at the refueling stations for those few seconds. In addition, the Training Departments question bank has been revised concerning the correct answer to Question #63.
hn LbY B'rian/J . Stamp '
Acting Operations Supervisor Turkey Point Operations Department e
N C
l0Ud[ .