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Category:Letter
MONTHYEARL-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report ML24291A2882024-10-24024 October 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal 05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 2024-09-25
[Table view] Category:Operating Report
MONTHYEARL-2022-039, and Point Beach, Units 1 & 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2022-04-14014 April 2022 and Point Beach, Units 1 & 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2021-097, and Independent Spent Fuel Storage Installation - 10 CFR 72.48(d)(2) Summary Report2021-05-13013 May 2021 and Independent Spent Fuel Storage Installation - 10 CFR 72.48(d)(2) Summary Report L-2021-096, 10 CFR 50.59(d)(2) Summary Report2021-05-11011 May 2021 10 CFR 50.59(d)(2) Summary Report L-2021-018, 10 CFR 50.46 Emergency Core Cooling System LBLOCA 30-Day Report2021-02-16016 February 2021 10 CFR 50.46 Emergency Core Cooling System LBLOCA 30-Day Report L-2020-065, Submission of Periodic Reports2020-04-0909 April 2020 Submission of Periodic Reports ML18227A9832018-08-15015 August 2018 Submit First Year Operation Report. L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/082008-11-10010 November 2008 Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08 L-2007-053, Annual Radiological Environmental Operating Report2007-05-0404 May 2007 Annual Radiological Environmental Operating Report L-2004-097, Annual Radiological Environmental Operating Report2004-05-11011 May 2004 Annual Radiological Environmental Operating Report ML18227B0771978-03-17017 March 1978 03/17/1978 Letter Operating Summary Reports of February 1978 ML18227A4231978-03-0404 March 1978 Attached February, 1978 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0631978-03-0404 March 1978 03/04/1978 Letter Operating Status Reports of February 1978 ML18227A4221978-02-14014 February 1978 Attached January, 1978 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0641978-02-14014 February 1978 02/14/1978 Letter Operating Status Reports of January 1978 ML18227A4211978-02-0404 February 1978 Attached January, 1978 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0651978-02-0404 February 1978 02/04/1978 Letter Operating Status Reports of January 1978 ML18227A4201978-01-0707 January 1978 Attached December, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0671978-01-0707 January 1978 01/07/1978 Letter Operating Status Reports of December 1977 ML18227A4191977-12-0303 December 1977 Attached November, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0681977-12-0303 December 1977 12/03/1977 Letter Operating Status Reports of November 1977 ML18227A4171977-11-0505 November 1977 Attached October, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0691977-11-0505 November 1977 11/05/1977 Letter Operating Status Reports of October 1977 ML18227B0701977-10-0505 October 1977 10/05/1977 Letter Operating Status Reports of September 1977 ML18227B0711977-09-0303 September 1977 09/03/1977 Letter Operating Status Reports of August 1977 ML18227A4151977-09-0303 September 1977 Attached August, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0731977-08-0505 August 1977 08/05/1977 Letter Operating Status Reports of July 1977 ML18227A4141977-08-0505 August 1977 Attached July, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0741977-07-0707 July 1977 07/07/1977 Letter Operating Status Reports of June 1977, and a Revised Operating Data Report for May 1997 for Turkey Point Unit 3 ML18227A4131977-07-0707 July 1977 Attached June, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1. May, 1977 for Unit 3 Incorrectly Reported for Some Values. Attached Revised May, 1977 Operating Data Report for Unit 3 ML18227B0751977-06-0606 June 1977 06/06/1977 Letter Operating Status Reports of May 1977 ML18227A4121977-06-0606 June 1977 Attached May, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0761977-05-0505 May 1977 05/05/1977 Letter Operating Status Reports of April 1977 ML18227A4111977-05-0505 May 1977 Attached April, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227A4101977-04-0404 April 1977 Attached March, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1. Maximum Dependable Capacity (MWe-Net) for St. Lucie No. 1 Was Revised from 802 MWe-Net to 777 MWe-Net (Estimated) ML18227B0781977-04-0404 April 1977 04/04/1977 Letter Operating Status Reports of March 1977 ML18227B0791977-03-0707 March 1977 03/07/1977 Letter Operating Status Reports of February 1977 ML18227A4091977-03-0707 March 1977 Attached February, 1977 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0801977-02-0707 February 1977 02/07/1977 Letter Operating Status Reports of January 1977 ML18227B0811977-01-0707 January 1977 01/07/1977 Letter Operating Status Reports of December 1976 ML18227A4081977-01-0707 January 1977 Attached December, 1976 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0821976-12-0606 December 1976 12/06/1976 Letter Operating Status Reports of November 1976 ML18227B0831976-11-15015 November 1976 11/15/1976 Letter Corrected Copies of Operating Data Reports for October 1976 ML18227B0841976-11-0808 November 1976 11/08/1976 Letter Operating Status Reports of October 1976 ML18227A4061976-11-0808 November 1976 Attached October, 1976 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227A4071976-11-0505 November 1976 Attached Corrected Copies of October, 1976 Operating Data Reports for Turkey Point Unit Nos. 3 and 4 ML18227A4051976-10-0808 October 1976 Attached September, 1976 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0861976-09-0707 September 1976 09/07/1976 Letter Operating Status Reports of August 1976 ML18227A4031976-09-0707 September 1976 Attached August, 1976 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1 ML18227B0871976-08-0505 August 1976 08/05/1976 Letter Operating Status Reports of July 1976 ML18227A4021976-08-0505 August 1976 Attached July, 1976 Operating Status Reports for Turkey Point Unit Nos. 3 & 4 and St. Lucie Unit No. 1. St. Lucie Unit No. 1 Was Previously Reported to Be in Commercial Operation, in Error. Attached Corrected June 1976 for St. Lucie No. 1 2022-04-14
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NRC FOAM 195 NUCLEAR REGULATORY C NRC DISTRI8UTION FDA PART 50 DOCI(ET IVIATERIAL FlDRIDA PCNER &'IGHT CO SSION DOCKET 50-25 251 FILE NUMBEA ER 35 MONTHLY REPORT DATE OF DOCUMENT 8-5-76 MIAMI, FIA DATE RECEIVED A D SCHMIDT 8-13-76 LETTE R QNOTORIZED PAOP INPUT FORM NUMBER OF COPIES RECEIVED gQCOPY ORIG INAI UN C LASS IF I E D 1 SIGNED DESCRIPTION LETTER TRANS THE FOLLOWING MONTHLY REPORT FOR JULY 1976 PLANT & COMPONENT OPERABILITY &
AVAILABILITY, THIS REPORT TO BE USED IN PREPARING GRAY BOOK BY PLANS & OPERATIONS.
NOPE: ATZACHED ALSO IS CORRI~K) COPY FOR ST LUCIE Nl FOR JUNE 1976..
PLANT NAME: ST LUCIE Nl tACKNOmgpgpg TURKEY POINTS N3 g y4
'@P)JfQVS DO gag FOR ACTION/INFORMATION MIPC W CYS FOR ACT ON INTERNAL D IST R I BUT ION
>DR BRANCH CHIEF L EXTERNAL DISTRIBUTION CONTROL NUMBER NAC FOAM IBS (2 7G)
4 'I
. BOX 013100, MIAMI, I:iORIDA 33101 FLORID* PO'vl'":R 5 '.',chili OO'.1PAi'JY
~RI<<DCCke< 8<4 August 5, 1976
~, n>1i=,
Office of Management Information /
and Program Controls U. S. Nuclear Regulatory Commission < <cry, Washington, D. C. 20555 Gentlemen:
Attached are the July, 1976 Operating Status Point Unit Nos. 3 and 4 and St. Lucie Unite-.
Reports,'urkey 1.
St. Lucie Unit No. 1 was previously reported to be in commercial operation, in error. We are attaching the corrected June, 1976 Operating Status Report for St. Lucie Unit No. 1.
We regret. any inconvenience caused by this error.
(,) I Very truly yours, (g REGETYE0 D. Sc midt P-l3-7, '
k4@ III/GEAR RSCVIATCRY Vice President 00MM ISS ION (boll S ~ ctloa Power Resources VTC/pm ~l/ IIg~
Attachments cc: Mr. Norman C. Moseley Jack R. Newman, Esquire
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL Docxzr No. 50 - 250 UNIT Turkey Point Unit No.
DATE Au . 5 19/6 comLETED BY v. T. chilson TELEPHONE (305) 552 - 3830 NONTH Jul 1'976 DAY AVERAGE DAILY POWER LEVEI DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe Net) 1 660 17 643 636 18 642 6 4 19 639 655 20 641 651 21 639 649 22 640
'3 644 652 24 637 650 25 638 10 654 26 634 652 27 64 12 646 28 637
.644 29 636 14 644 30 632 15 639 31 632 16 641 NOTE: Daily average power level greater than 666 aVHe due to cooler condenser cooling water.
APPENDIX C OPERATZttQ DATA REPORT DOCKET NO 50 250
.-UNIT Turkey Point Uaic No. 3
'DATE Au . 5 1976 REPORT MONTH Jul 1976 COMPLETE) BY V- T- Chilson OPERATZNC STATUS' lo REPORTING PERIOD8001,76,07 01 GROSS'OURS IN ~ORTIHQ PERZOD: 744.0 THROUGH 2400 76 07 31 CURPZNTL~Q (I u ~HER L~L (NÃt) t 2
MAXO DEPENDS CAPACITY (MWe ttet): ~O 2200
- 3. POWER LEVEL TO hHZCH RESTRICTED (ZF At)Y) (YAe-Net) t HONE 4~ REASOttS FOR RESTRXCTZON (ZF A.'Pl) 2 THXS MO.'P8 YEAR TO DATE CUMULAT "V.
So NL20)ER OF HOURS REACTOR hVsS CRXTXCAL.... 744.0 4 509.9 25 790.0 6~ REACTOR RESERVE SHUTDO)PDt HOURS ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ -0 64.2 7 ~ HOURS CEtt tATOR ON LINE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 744.0 4 437.6'4 807.6 8 ~ UNIT RESERVE SHUTDOh.t HOURS ...~ ~ ~ ~ . -0 0- 85.0 9~ GROSS THERt(AL ENERGY GENERATED (MWH)...... 1 629 884 9 580 710 46 892 970 10 'ROSS ELECTRICAL ENERQY Q-;,-RA -D (tQ1H), 503 700 3 045 360 15 '060 596 ll. NET ELECTRZCAL E'tERGY CE::ERA D (MWH) ~ ~ 478 780 2 890 825 14'46 587 12 'EACTOR SERVICE FACTOR. ... . . .'.. . 100.0 88. 2 80.4 13 ~ REACTOR AVAILABILITYFAC-OR. ~ ~ ~ ~... ~.... '00.0 89.5 80.6
- 14. UNIT SERVICZ FACTOR........ 100.0 86.8 77.4 15o UNIT AVAILABILITYFACTOR ~ .~~~~~D~~ ~~o 100.0 86.8 77~
- 16. UNIT CAPACITY FACTOR (Using MDC)......... 96:6 84.9 67.7
- 17. UNIT CAPACITY FACTOR (Using Design tide).. ~ 81.6 64.1 18 ~ UNIT FORCED OUAAQE RPHT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 0.2 3.2 19 'HUTDO'PWS SCHEDULED OVER 'tEXT 6 MONTHS (TYPES DAT , AND DURATION OF MCH)
Refuellag, nsinceaeace, and inspeccioas - Oc'cober 4 chrough Hovectber 14, 1))76 20, IP SHOTOOttH AT -SD OP PPPORT P RICD, ~
S-TI.JtTHD DAT CP ST&ITCH:
2lo UNITS IN TEST STATUS (PRIOR TO CO)P'HZRCDZ OPERATZOit): FORECAST ACHZW. FD INITIAL CRXTZC'LZTY IANITZAL ELECTRICI-Y COK tZRCIAL OPERATIOtt
APPEtfDIX D DOCKlaT HO.
(I) REASON UNIT SIIUTDONIIS AND PURER REDUCTIONS UNIT Nht!E Turkey Point Unit No. 3 A: EQUIPMENT FAILURE (EXPLAIN)
B: MAINT. Oft TEST DATE Au ust 5 1976 Ci rxrUCLIIIC D: PECULATORY RESTRICTION. COHPLETED BY V. T- Chilson Et OPERATOR TRAINING AtfD Fi LICENSE EXAtlItfhTION ADMItlISTRATIVE TELEPIIONE 305 552 - 3830 eepoIIT nOIITII~Jol 1976 G: OPEBhTIOtIAL ERROR (EXPLAIN)
H3 OTHER (EXPLAIN)
(2) METIIOD METIIOD OF I 3 MANUAL TYPE SHUTTING DOWII 2 I MANUAL SCRAH Ff FORCED DURATION TIIE REACTOR OR 3 I AUTOMATIC SCRAM NO. DATE Si SCHEDULED (IIOURS) REASON(l) 'REDUCING PotfER(2) CORRECTIVE ACTIONS COMMENTS 43 OTHER (EXPLAIN) I NONE seminar 'Unit No. 3 operated at approyimately 100 9 R.p. dnripg month.
APPENDIX 8 AVERAGE DAILY UNIT PC4&R MVEL DOCKET NO. 50 - 251 UNIT Turke Point Unit No. 4 DATE Au . 5 1976 COMPLETED BY V. T. Chilson MONTE DAY AVERAGE DAI Y POWER MVEL DAY AVERAGE DAILY POWER Lc~rL (MWe-Net) (MWe Net) 1 666 17 662 18 661 6 7 60 20 662 21 67 22 658 669 23 661 671 24 654 25 656'66 10 74 26 670 27 659 12 659 28 657 13 29 653 14 656 652 15 31 628 16 663 NOTE: Daily average power level greater than 666HWe due to cooler condense" cooling water.
APPENDIK C OPERATING DATA REPORT DOCKET NO 50 - 25l UNIT Turke Point U i o. 4
>ATEAug. 5, 1976 REPORT MONXH Jul 1976 CONPLETED BY V. T. Chilson TELEPHONE 05 OPERATING STATUS' 1, IIEPORTZHO PEII100:0001.76 07 01 GROSS HOURS Zll REtORTZ\'C PERZOO THROUGH 2400 76 07 31 PCN R LWlZL (MHt) - 2200 OEP .'tO. CAPAC TZ OSI tl DESIGN ELECTRZCAL RATZNG (MHe-Heel:
tl:
3 POWER LEVEL TO NHZCH RESTRZCTED (ZF ANY) (Mite-Net) z NO 8 46 REASONS FOR RESTRZCTZOAV {IF AR)Y) 5 THIS MONTH YEAR TO DAT CUMUL RT"VE 5, ROSSER OP HOURS STACKER SM CR1T CRZ.- -~ ~ ~ 741 ~ 3 3 627 4 ~3 4
- 6. IIEACtOR (ESCAPE SAZITOC.t HO(IRS.. ~ . ~ ~ .. ~ . ~ I}-
7 HOURS GENERATOR ON LINE............ ~.... 738.4 3 456.6 18 F70.2 8~ UNIT RESERVE SHUTDO(fà HOURS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ re -0 5, CROSSZHERIAt EEERO (0"HEI(A'TEO (UO(l .. ~ . ~ 1~61 492 7 305 040 37 953 6 6
- 10. GROSS LEC R CAL ENERGY GENERAT.D (MNH) . ~ 511 520 2 345 221 12 324 298 NET ELECTRICAL ENERGY GENERATED (RE%).... 487 161 2 223 446 1~~7 12 'EACTOR SERVZCE FACTOR. 99.6 71.0 74.8 130 REACTOR AVAILABILITYFACTORS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '9.6 71.0 75.2 14 ~ UNIT SERVICE FACTOR. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 99.2 67.6 7$ .5
- 15. UNIT AVAILABILITYFACTOR. ~ ~ . ~ ~ ~ ~ ~ ........ 99.2 67.6 70.5
- 16. UNIT CAPACITY FACTAOR (Using MDC) ......... 98.3 65.3 68.9
- 17. UNIT CAPACITY FACTOR (Using Design MÃe) .. ~ 94.5 62.8 65.4 18 'NIT FORCED OUTAGE RATE. .... .. ,..... 0.8 5.6 3.6) 19 ~ SHUTDOHNS SCHEDULED OVER NEXT 6 R)OANTHS {TYPE, DATE, AND DURATZON OF EACH'.:
NONE 20 ~ IF SHUTDOHN AT END OF REPORT P RZOD ~ ESTIMATED DAT OF STARTUP:
- 21. UNITS ZN TEST STATUS {PRIOR TO COK~ZPC AL OPHMZON): FORECAST ACH EYED INITIAL CRITICALITY IVAITZAL ELECTRICITY COMR(ERCIAL OPERATZOIV
APPENDIX D DOCEET NO 6
I) REASON UNIT Sl!UTDOHNS AHD POHEB REDUCiIONS UNIT HARE Turke Point Unit Ho. 4 A: EQUI PHENT FAILURE tEXPLAIH)
B. HAIWT OB TEST . DATE u ust 5 1976 c: rErUELING D: BEGl'LATOBY RESTRICTION COHPLETEU BY V. T. Chilson Ef OPERATOR TRAINING AND LICENSE EXAllIHATION TELEP llONE 552 3830 F: ADHIHISTBATIVE REPORT HONTH July 1976 G: OPERATIONAL ERROR (EXPLAIN) ll: OTllER (EXPLAIN)
(2) HETHOD HETIIOD OF 12 HAHUAL TYPE S NUTTING DOHN 2 f HANUAL SCBAH Ff FORCED DURATION TIIE REACTOR OR 3 f AUTOHATIC SCRAH NO. DATE Sf SCllEDULED (HOURS) REASON (I) REDUCING POHER(2) CORRECTIVE ACTIONS/COMHENTS 42 OTHER (EXPLAIN) l l5 76-07-2 5.6 Reactor tripped during transient condition resulting from loss of steam generator feedwater pump Ho. 4A when the pump low suction pressure trip actuated.
Corrective action included testing and recalibrating the low suction pressure trip. (Non-nuclear System) e ilnit No. 6 operated at approximately 100 9 R.p. during month except for outage of July 26, 1976.
APPMDZX B AVERAGE DAZLY DNZT PAAR LEVEL DOCKET Nor 50 - 335 DNzT St. Lucie Unit No.
19'/6 1'ATE Au . 5 CONPLETED BY V. T. Chilson TELEPHONE (305) 552 - 3830 NONTH Jul '1976 DAY AVERAGE DAZLY PO'KR ~c, DAY AVERAGE DAZLY PONER LEV=L (NWe-Net)
(MNe-Net) 58 17 2 75 18 3 561 19 4
' 563 20 566 21 531 22 23 334 24 10 94 26 27 12 28 13 29 30 31 16
WIZAciir>U, %U . G '6 APPENDIX C OPERATZNC DATA REPORT DOCKET NOO 50 335 UNIT S
'DATE Au .' 7 REPORT MONIH Jul 1976 COMPLETED BY V. T Chilson 6~
OPERATINC STATUS' 744.0 THROUGH 2400 76 07,31 r MAX~ DEPEND ~ CAPACITY {Mde-Net) 9 timated)
- 3. POWER LEVEL TO WHICH RESTRICTED {ZF ANY) (MWe-Net): 722 4~ REASONS FOR RESTRZCTZQIV (ZF AVY) c "Temporary 902 restriction pending reactor coolant flow analysis" THIS MO.'iTH Y>>~R TO DATE CUMULATIVE 5 N{L>>ABER OF HOURS REACTOR WAS CRZTICAL..... 360.1 366.6 1 366.6 6~ REACTOR RESERVE SHUTDOiUl HOURS' ~ ~ ~ ~ ~ ~ ~ N/A(1) N/A(1) N/A(1)
- 7. UOURU 6"INAYOR OII LZIIE.........,.....,.. 189.9 I 121.9 1 121.9 N/A(1). N/A(I)
UNIT RESERVE N/A (1)
$~ SHUTDOlCAl HOURS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
9~ CROSS THER{AL E cRCY CENERA ED ('.'6{) ~ ~ ~
~08~'0.
CROSS ELEC RZCAL:l RCY CENERAT-D ()lWH) .. 89 830 418 670 '418 670
- 11. LEY ELECIRZCAL E:IERGY 6 IIERAZEO (IAUII .... ~86 A)7~4!t) ~144IIL
- 12. REACTOR SFRVICE FACTOR. ~ .~ .~.~ ....'.... 48. 4 66.1 ' 66.1 136 REACTOR AVAILABILITYFACTOR. ~ ~ ~ ~ ~ .r.. . '8.4
~ 66.1 66.1 14 ~ UNIT SERVICE FACTOR................ 25.5 54.9 54.9
- 18. OOZY AVAZLAEZLaYYAC OR ~4~
- 16. UNIT CAPACITY FACTOR (Using MDC) ~........ 13:8 22.8 22.8
- 17. UNIT CAPACZT>> FAC OR (Using Design MWe) .. 13.8 22.8 22.8
~7. ~o
~
18 URZY YORCEII OU,AGE IN .................. r k.9 19 ~ SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (T PER DATEU AND DURATION OF E)46'H} c N/A<')
20 ~ ZF SHUTDOWN AT END Oc REPORT PERIOD, ESTZR~TED DAT OF STARTUPc 216 UNITS ZN TEST STATUS {PRZOR TO CONXZRCIEAL OPERATZOIl) c FORECAST ACHY=-:E" INITIAL CRITICALITY ~AY(~, 1976 IVAITZAL ELECTRICITY '(6~976 CONA)ERCIAL OPERATION 4
NOTE: (1) Unit in test status
APPENDIX D DOCKET NO. 50 335 ail) REASON UNIT SHUTDONNS AND POWER REDUCTIONS =
UNIT NAHE St. Lucie Unit No. 1 Af EQUIPHENT FAILURE (EXPLAIN) August 5, 1976 HAINT OR TEST
'f
~ DATE Cf PEFUELINC D: PXCULATORY RESTRICTION COHPLETED-BY V T Chilson E OPEPATOR TRAINING AND LICE:eSE EXAHIHATION TELEPHONE (305) 552 - 3830 Ff AD!IIHISTBATIVE REPORT HOIITH JulY 1976 Gf 01'EBATIOHAL ERROR (EXPLAIN)
H: OTHER {EXPLAIN)
{2) METHOD HETHOD OF 1 f HAWUAL TYPE SHUTTING DOWH 2I HANUAL SCBAH FI FORCED DURATION TIIE REACTOR OR 3i AUTOHATIC SCBAH, NO. DATE Sg SCHEDUIED {IIOURS) REASON (1) REDUCING POIIEB{2) CORRECTIVE ACTIONS COHHENTS 4f OTHER {EXPLAIN) 12 76-07-0 F 29.2 Unit was removed from service to repair leak in the generator hydrogen system. (Hon-nuclear System) 13 76-07-0 3.8 Reactor was tripped by steam generator level trip during return of unit to power operation after outage.
(Hon-nuclear System) 14 5.0 Unit was removed from service to investigate and correct problem with turbine control system. (Non-nuclear System) 76-07-0'5 76-07<6 N/A Load reduction to clean condensate pump suction strainer.
(Hon-nuclear System) 16 76-07-1 516.3 F Unit was removed from service for reactor tests and inspection. (Nuclear System) seminally st. Lucis Unit No. i power Ascension Test program continued service for reactor tests and inspection.
untii duty ip,. igyp wheri the unit was removed from
APPENDZX B
'IL AVERACE DAZLY UNZT P(ÃfER LEVEL DocKET Noi 50 335 UNZT St. Luce.e Unxt No. 1 DATE Au . 5, 1976 CONPLETED BY V. T. Chilson NONTE June 1976 (Corrected)
DAY AVERACE DAZLY PONER LEVEL DAY AVERACE DAZLY PO¹R LEVEL (MNe Net) (MNe-Net) 327 17 18
~
3 32 330 20 21 462 22 458 149 23 330 316 24 318 25 10 319 26 526 322 27 322 12 22 28 410 13 29 541 14 30 546 15 16 NOTE: Corrected Unit No. 1 'was previously reported to be in commercial ope ation, in error. The unit remained in test status.
APPFNDIX C OPERATING DATA REPORT DOCKET No. 50 - 335 UNZT St. Lucie Unit No. 1
'DATE Aug. 5, 1976 REPORT MONTH June 1976 Corrected) COMPLETED BY V. T..chilson J
OPERATZNG STATUS-li REPORTING PERIOD: 000 THROUGH 2400 76 0 GROSS EDGES ZG REPORTZR PEIIZOD:720 0.
~ MAX. DEPEND. CAPACITY ())Ne-ffet): stimated)
- 3. Pof(ER LEVEL TO ffHZCH RESTRZCTED (ZF ANY) (Mffe-Net)f 722 4~ REASONS FOR RESTRZCTZOif (ZF ANY) f "Temporary 90Z restriction 'ending reactor coolant flow analysis" 5.
6, 7.
8~
9~
10.
N(LVBER OF HOURS REACTOR REAGZOR IIESE'RPE SHIIZDOIIH HOG!IS GE!IESATOR 0H UNiT RESERVE SHUTDONJ Hm CRZTZGAL.....
HOGIIS...........
EZIE" ~ . ~ ~
HOURS GROSS" THER(AL ENERGY GEifERATED GROSS ~~ CTRZCAL ENERGY
~ ~ "~
~ ~ ~ ~ ~ ~ ~ ~ ~
GEf:ERAT D (AH) ..
~ ~ ~ ~ ~
~ ~ ~ ~ ~
(Ri&)....,. 750 137 THIS
~6.6 MONTH 524.1 H/A (3)
N/A(3)
ZII 690 BAR To DAT 1.006.5
~92.4 N/A(3).
1 187 069 328 840
'4 (3)
CUffULAIT"VE 1
1 006.5 N/A(3) 187 069 328 840 (3) 7 11 NET ELECTRICAL EffERGY GENERATED ()fHH).... 189 436 291 784 291 784 12 REACTOR SERVICE FACTOR... 9 . 72.8 76.2
- 13. REAcToR AVAZLmzLITY FAcAoR.............. f 72.8 76.2 ~6 14 ~ UNIT SERVIC- FACTORS ~ ~ .~~~ ~ ~ ~ ~ ~ ~ ~ .~ ~ .. ~ ~ 71.8 71.8
- 15. UNIT AVAILABILITYFACTOR...... ~ 9 . ~.... ~ ~ 71.8 71.8 7) .8
- 16. UNIT CAPACITY FACTOR (Using MDC)......... 32;8 28.0 28.0
- 17. UNIT CAPACITY FACTOR (Using Design MWe) .. ~ 32.8 28.0 28.0 18 'iNZT FORCED OUTAGE RATE... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4.2 14. 6 14.6 19 'HUTDOffNS SCHEDU~ OVER NEXT 6 MONTHS (TYPES DATE, AND DURATION OF E62CH) .
N/A(')
- 20. ZP SHDTDOIIH AT EIID OP IGPORT P RZOD, ES'ZZ A'ZED DA 0 STARTIIP:
219 UNITS IN TEST STATUS (PRIOR To COYAERCZAL OPERATIO'fl): FORECAST ACHZ VED ZNZTZAL CRITICALITY APE41 22, 1976 INZTZAL EfiECTRZCZTY H~a7 1976 COMMERCIAL OPERATION NOTE: (1) Corrected - Sc. Lucio Unit No. 1 was previously reporced co be in .commercial operation, in error. The unit remained in test scatus.
(2) Revised values, beginning with initial power generation-co-date.
(3) Unit in'ast status.
API'Its!IJX u UucrET tlo. UU - 335 (I) BEASOII ) UNIT SIIUTDOWNS AND POWFB REDUCTIONS UNIT HppIE St. Lucie Unit No. 1 A: EOUIPMEHT FAILURE (EXPLAIN)I BI MAINT. OR TEST ~ DATE August 5, 1976 Ct EEFUELItlc Dz PEGULATOBY PZSTRICTION EI OPERATOR TRAINItlo AND coMPLETEU BY V. T. Chilson LICEtlSE FXAtlIHATION ADMItlISTRATIVE TELEPHONE (305) 552 - 3830 OPERATIONAL ERROR (EXPLAIN)
BEPoBT MOHTII June 1976 (Corrected)
OTHER (EXPLAIN)
(2) METHOD METIIOD OP 1I MANUAL TYPE SNUTTIHG DOWN 2I MANUAL SCRAM FI FORCED DURATIOtt TIIE REACTOR OB 3I AUTOMATIC SCRAM No. DATE S I SCIIEDULED (HOURS) REAsoH (I) REDUCING POWER(2) CORRECTIVE ACTIONS COMMENTS OTIIER (EXPLAIN) I 08 76-06-07 10.1 Reactor was manually tripped due to drop of a CEh during the performance of reactor physics tests.
(Nuclear System) 09 76-06-1 180.5 Performing test, generator trip with shutdown outside control room. (Nucliar System)
Outage continued for maintenance. (Nuclear and Non-nuclear Systems) 10 76-06-2 12.8 Reactor was tripped during transient condition caused by closure. of a MSIV when power supply to a vi'tal instrument bus was lost. (Nuclear System) 11 76-06-2 N/A Load reduction to.clean condensate pump suction strainer.
(Non-nuclear System)
SUMMABYI St. Lucie Unit No. 1 power Ascension Test program continued..
NOTEI Corrected -.'t. Lucie Unit No. 1 was previously reported to be'n commerical operation, in error.
The unit was continued in Test Status.