|
---|
Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) 2024-02-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML23318A1782023-11-13013 November 2023 FAQ 23-03- Turkey Point IE01 05000251/LER-2017-0012017-11-0707 November 2017 Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control, LER 17-001-00 for Turkey Point, Unit 4, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control 05000250/LER-2017-0012017-05-16016 May 2017 Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations and Loss of Safety Injection Function, LER 17-001-00 for Turkey Point, Unit 3, Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function L-2017-090, LER Special Report Regarding Accident Monitoring Instrumentation2017-05-11011 May 2017 LER Special Report Regarding Accident Monitoring Instrumentation 05000250/LER-2016-0012016-04-0707 April 2016 Loose Breaker Control Power Fuse Caused 3B Emergency Containment Cooler to be Inoperable Longer Than Allowed, LER 16-001-00 for Turkey Point, Unit 3 Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to be Inoperable Longer Than Allowed 05000250/LER-2015-0012016-01-19019 January 2016 Diesel Generator Start Resulting From Switchyard Protective Relay Actuation, LER 15-001-00 for Turkey Point, Unit 3 Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation L-2015-217, Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation2015-08-27027 August 2015 Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation L-2014-139, Special Report Regarding Accident Monitoring Instrumentation2014-05-14014 May 2014 Special Report Regarding Accident Monitoring Instrumentation L-2009-293, Special Report - Accident Monitoring Instrumentation2009-12-15015 December 2009 Special Report - Accident Monitoring Instrumentation L-2009-155, LER 09-02-00 for Turkey Point, Unit 3 MSIV Drain Line Leak Causes Technical Specification Required Shutdown; Failure to Perform PMT Causes Inoperable MSIV2009-07-0202 July 2009 LER 09-02-00 for Turkey Point, Unit 3 MSIV Drain Line Leak Causes Technical Specification Required Shutdown; Failure to Perform PMT Causes Inoperable MSIV ML0906404452008-10-0606 October 2008 Enclosure 11 - Case Study 7: Turkey Point NCV on TS 3/4.4.10, Structural Integrity (Applicability of Sr'S 'And Actions) - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf ML18227D3941978-08-25025 August 1978 08/25/1978 Letter Attached Report of Abnormal Indications from Metal Impact Monitoring System, Which Occurred During Unit Cooldown for Refueling ML18228A4811978-04-0404 April 1978 04/04/1978 Letter Response to Request for Additional Information on System Disturbance of May 16, 1977 L-78-104, Transmitting Evaluation Report of Abnormal Indications from Metal Impact Monitoring System, Turkey Point Unit No. 4.1978-03-23023 March 1978 Transmitting Evaluation Report of Abnormal Indications from Metal Impact Monitoring System, Turkey Point Unit No. 4. ML18227D4511977-09-30030 September 1977 09/30/1977 Letter Report of Abnormal Indications from Metal Impact Monitoring System ML18227A5101977-09-0606 September 1977 LER 1977-251-07 for Turkey Point, Unit 4 - Pressurizer Heatup Rate L-77-191, 06/23/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/19771977-06-23023 June 1977 06/23/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/1977 ML18227B2481977-06-23023 June 1977 06/23/1977 Letter Proposed Amendment to Appendix a of Facility Operating Licenses, Concerning Analysis Performed by Applicant'S NSSS Vendor Results Related to Reactor Core Thermal Power Output ML18227B2491977-06-23023 June 1977 06/23/1977 Letter Proposed Amendment to Appendix a of Facility Operating Licenses, Concerning Analysis Performed by Applicant'S NSSS Vendor Results Related to Reactor Core Thermal Power Output ML18227A4241977-05-0202 May 1977 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 4/18/1977 for Nominal Power ML18227A4251977-02-0707 February 1977 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide 30-day Notification, Occurrence on 1/8/1977 for Bfd Relays ML18227D2871977-01-14014 January 1977 Submit Personal Radiation Exposure Report in Accordance with the Requirements of 10 CFR 20.405 ML18227D2881977-01-14014 January 1977 Submit Personal Radiation Exposure Report in Accordance with the Requirements of 10 CFR 20.405 ML18227A4281976-10-20020 October 1976 Submit Licensee Event Report of Turkey Point Unit 3, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 10/6/1976 for Boron Injection Tank ML18227A4261976-10-0606 October 1976 Referring Licensee Event Report Submitted on 8/25/1976 with Occurrence Date of 7/26/1976. in the Report, Reportable Occurrence Report No 250-72-2 Should Be Changed to 250-76-2. Attached Corrected Report ML18227A4271976-08-25025 August 1976 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide 30-day Notification, Occurrence on 7/26/1976 for Malfunction of 4B Starting Transformer Breaker ML18227A4291976-08-19019 August 1976 Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 8/5/1976 for ECCS Analysis ML18227A4311976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/12/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4331976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration, Occurred in Unit 4 on 6/11/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4301976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/12/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4321976-06-25025 June 1976 Letter Transmitting Licensee Event Report, Low Boron Concentration Occurred in Unit 4 on 6/11/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4351976-06-0404 June 1976 Transmitting Letter to Correct Report Sent on 5/27/1976. Line 2 of Description Words Steam Generator 4 Needs to Be Corrected to Steam Generator 4C Attached Corrected Page 1 ML18227D3541976-06-0404 June 1976 Correction to Licensee Event Report Which Occurred on 5/17/1976 by Correcting Steam Generator 4 to Steam Generator 4C on Event Description ML18227A4341976-05-27027 May 1976 Letter Transmitting Licensee Event Report, Steam Generator Tube Support Plate, Occurred in Unit 4 on 5/17/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4361976-05-27027 May 1976 Letter Transmitting Licensee Event Report, Steam Generator Tube Support Plate, in Unit 4 Occurred on 5/17/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4381976-02-26026 February 1976 Letter Transmitting Licensee Event Report, Low Level in Refueling Water Storage Tank in Unit 4 Occurred on 2/14/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4391976-02-26026 February 1976 Letter Transmitting Licensee Event Report, Low Level in Refueling Water Storage Tank in Unit 4 Occurred on 2/14/1976 in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification ML18227A4401976-02-25025 February 1976 Letter Transmitting Licensee Event Report, High Setpoint for Overtemperature Delta-T Reactor Trip Channel II in Unit 4 Occurred on 1/30/1976 in Accordance with Technical Specification 6.9.2 to Provide 30-day Notification ML18227A4411975-12-22022 December 1975 Letter Reporting Abnormal Occurrence of Low Boron Concentration in Unit 4 Boron Injection Tank on 12/12/1975 ML18227B0221975-07-0707 July 1975 Reporting Unusual Event No. 251-75-1 of Revised ECCS Analysis, for Value for Peak Clad Temperature Is in Error 2023-11-13
[Table view] |
Text
fJHC roAM 196
'(2-7G I lO NRC DISTRII UTION roA PART GQ FROM:
DOCI(ET MA1 ERIAL t
V.S. NUCLEAA IREGVLATOAYCOMMISSION DOCKET NUMOf;A FILE NUMOEA XNCXDFHT REPORT DATL OF DOCUMENT N. C. Moseley Florida Power 6 Light Co 2-26-76 Miami, Fla.. 33101 DATE AECEIVED A.D. Schmidt 3-5-76 LETTF A QNOTOAIZED P AOP- INPUT FOAM NVMeEA OF COPIES AEcr IUED 0 A IGINAL 0 UN C LASS IF I E D aPCOPY 1 cy',
DESCRIPTION ENCLOSV AE Ltr trans the following Licensee Event Rpt 50'-251-76-2 on 2-14-.76 re Low Leuel in Refueling Water.,Storage Tank r
ACKNOWLEDGED (1 cy encl.).;("
DO NOT REMOVE PLANT NAIIE: Turkey Pt g4 NOTE: XH PERSONNEL EXPOSURE XS INVOLVED SEND DIRECTLY TO I<REGER/J ~ COLLXNS SAP)'TY FOB ACTION/INFORMATION ENVXRO BRA)iCH CHIEF:
~W 3 CVS )'nR ACTION I.ICE ASST:
I)/ CVS ACRS CYS 1&BBRS/bHNT TO LA INTERNAL DISTRIBUTION II'.Cv I'XI')"
NRC PDR X@H (g)
EXP SCHROHDHR/XPPOIXTO J.QI JS~OJs HOV/Il~jC'IECK
>ii~ia5~isri'Hpà ii GAGE VLLXE S6 ~iALMl~
i'Ll)HSCOQHAC(~!A
' )pJh
))Al',
SIIAO VOLT.III:R BUh'Ct(
1(P,Igf",RJ T~QO).LXNS EXTERNAL DISTRIBUTION CON NUMI)ER Li'Dll: Miami Fla.
TXC NSXC 2232,
N IS [
d
~, ~
P.O. BOX 3100 MIAMI, FLORIDA 3310I yiilQ~
FLORIDA POWER & LIGHT COMPANY 0~go atoTT@L~~
February 26, 1976 PRN-LI-76-33 g, rPPPPgp Mr..Norman C. Moseley, Director, Region Office of Inspection and Enforcement II U. S. Nuclear Regulatory Commission /~iQ~%g~
230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303
Dear Mr. Moseley:
REPORTABLE OCCURRENCE 251-76-2 TURKEY POINT UNIT 4 DATE OF OCCURRENCE: FEBRUARY 14, 1976 LOW LEVEL IN REFUELING WATER STORAGE TANK The'ttached Licensee Event Report is being submitted in accordance with Technical Specification 6.9.2 to provide prompt notification of the subject occurrence.
Very truly yours,
+c S'(j,: +C~ID A. D. Schmidt 4%yg0 Vice President I"I8g Power Resources ( II
+Zs p.
gg~
MAS/jn Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (40)
Director, Office of Management Information and Program Control (3)
HELPING BUILD FLORIDA
f kl C
/ lh
/ la '
1 ~
d C
LlCENSEE EVENT REPORT CONTROL BLPCK: SE PRINT AU. REQUIRED INFORIHATIDN) 1 UCENSEE UCENSE EVENT NAME LCENSE NUMBER TYPE TYPE
[ODi] F L T F 5 4 0 0 0 0 0 0 0 0 0 4 1 1 1 ~01 7'89
~
14 15 25 26 30 31 32 REPORT. REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT OATE AEPORT OATE
~01 OONT T ~L 0 5 0 0 2 5 1 0 2 1 4 7 6 0 2 2 6 7 6 7 8 57 58 59 60 T51 68 69 74 75 80 I
EVENT OESCRIPTION IOO~j Durin a routine eriodic check performed in accordance with Operating Procedure 7 8 9 80 0204.2 a s ecial test a e was used to determine the actual water level in the 7 8 9 80
~0 4 Refu'elin Water Stora e Tank. The tank was found to.contain 316,800 allons which 7 8 9 80 Jog a io Concurrent 7 8 9 80 Qp 6 with makeup to the tank, a unit shutdown per Administrative Procedure 0103.8 was 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COBE COOE . COMPONENT COOE SUPPUEA MANUFACTURER 7
[Oarj ~IF 8 9 10
~B 11 12 I N 5 T R 0 17
~
N 43 44 B 0' 0 47 Y
48 CAUSE OESCRIPTION
[OD~] At the time of the occurrence, the control room age read 323,000 gallons. The gage 7 8 9 80 tOOI is a wide range Baile Ty e PM multi-point indicator gage. The proposed long range 7 89 80
[iso] corrective action includes the installation of a narrow range gage in the Control 7 8.9 80 FACIUTY METHOO OF STATUS % POWER OTHER STATUS OSCOVEAY OISCOVEAY OESCAIPTION
~>1 ~E ~10 0 NA b Weekly RWST level check 7 8 9 10 12 13 44 45 46 80 FOAM OF ACTMTY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY . LOCATION OF RELEASE Pig . z ~z NA NA r 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCAIPTION
~s ~oo z NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER OESCAIPTION Q4] ~oo o NA 7 89 11 12 80 PROBABLE CONSEQUENCES Qi7s NA 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPTION
~z NA 7 89 10 PUBLICITY NA 7 89 80 AOOITIONAL FACTORS
[gg See followin a e for continuation of Event Description and Cause Description.
7 89 80 7 89 80 M. A. Scho man PHONE. 305/552-3779 GP0 8I51 ~ Eel
Reportable Oocur'rence 251-76-2 Licensee Event Report
.Page Two Event Descri tion continued) initiated. Approximate'ly one-half hour later, the tank level was within specification. This is the first Reportable Occurrence related to a non-conservative Refueling Water Storage Tank level. (251-76-2).
Cause Descri tion (continued)
Room as a backup to the wide range gage, and the installation of an Ashcroft test gage on each RWST as a permanent local backup to the Control Room gages. If local gages are installed, a program will be developed to provide adequate periodic calibration. A design review of the RWST level indicating system is being conducted to evaluate the feasibility of the proposed corrective action. A supplementary report will be submitted if the actual corrective action's different from the proposed corrective action.