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| {{Adams
| | #REDIRECT [[05000302/LER-1994-006, :on 950118,determined That Potential Existed for CR-3 to Have Operated Outside Plant Improved TSs Re RPS Setpoints.Caused by Personnel Error.Procedure Changes Initiated & Setpoints Recalibrated]] |
| | number = ML20137N761
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| | issue date = 04/04/1997
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| | title = Forwards Corrected Page One of LER 94-006-06 Which Had Typo in Block 7, Rept Number
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| | author name = Holden J
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| | author affiliation = FLORIDA POWER CORP.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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| | docket = 05000302
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| | license number =
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| | contact person =
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| | document report number = 3F0497-31, 3F497-31, NUDOCS 9704090048
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| | package number = ML20137N763
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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
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| | page count = 1
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| }}
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| {{LER
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| | Title = Forwards Corrected Page One of LER 94-006-06 Which Had Typo in Block 7, Rept Number
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| | Plant =
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| | Reporting criterion = 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(ii), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(i)(B)
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| | Power level =
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| | Mode =
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| | Docket = 05000302
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| | LER year = 1994
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| | LER number = 6
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| | LER revision = 6
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:+
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| FLORIDA POWER CORPORATION April 4, 1997 3F0497-31 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Subject: Licensee Event Report (LER) 94-006-06 Correction Reference: Licensee Event Report (LER) 94-006-06,3F0397-30, dated 3/26/97
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| ==Dear Sir:==
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| Enclosed please find corrected page one of Licensee Event Report (LER) 94-006-06 which was sent to you on March 26, 1997. A typographical error was discovered in Block 7,
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| " Report Number". The original submittal incorrectly listed the year as 96 rather than 97.
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| If you have any questions, please contact Mr. J. A. Frijouf, Senior Nuclear Regulatory Assurance Specialist, at (352) 563-4754.
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| Sincerely, pks /
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| J.cJ. Holden m
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| Director, Nuclear Engineering and Proj.ects
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| -(
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| JJH/JAF 9704090048 970404 PDR ADOCK 05000302 Att.
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| s pon xc:
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| Regional Administrator, Region 11 Senior Resident Inspector NRR Project Manager 080148 CRYSTAL RIVER ENERGY COMPLEX 15760 W. POWER LINE STREET CRYSTAL RnTR, FL 34428-6708
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| NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 H2)
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| EXPlRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY W:TH THIS LICENSEE EVENT REPORT (LER)
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| U""E"HE$# NEE 8E'ud 0""#EwlEr^$
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| M e
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| AND RECORDS MANAGEMENT BRANCH {MNBB 7?t4) U.S. NUCLEAR REGUI.ATORY COMMfS5 TON, WASHINGTON. DC 20$55 0001. AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits / characters for each block)
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| MANAGEMENT AND BUDGET, WASHINGTON, DC 20503 K41UTV NAME (1)
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| DOCKET NUMBER (2)
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| CRYSTAL RIVER UNIT 3 (CR-3)
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| PAGE70 05000 1 oF I""W Deficiency in Understr.nding of Technical Requirements Leads to Nonconservative Safety Systems Setpoint and Violations of Improved Technical Specifications EVENT DATE (5)
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| LER NUMBER (6' REPORT NUMBER (7)
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| OTHER FACILITIES INVOLVED (8) l MONTH DAY YEAR YEAR MONTH DAY YEAR g
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| o 01 18 95 94
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| -- 006 06 03 26 97 05000 OPERATING y
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| THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (Check one or more) (11)
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| MODE (9) 20 402(b) 20.405(c) 50.73(a)(2)0v) 73.71(b)
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| POWER 20 405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
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| LEVEL (10) 100 20.405(alm 06) 50.36(c)(2) 50.73(a)(2)(vi )
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| OTHER 20.405la)(1)0ii)
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| X 50.73(a)(2)(i) 50.73(a)(2)(viii)(A)
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| {s i{A s 20 405(a)(1)0v) 50.73(a)(2)(ii) 50 73(a)(2)(vui)(B)
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| Fo,m assA) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) l LICENSEE CONTACT FOR THIS LER (12)
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| ~
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| j James A. Frijouf, Sr. Nuclear Regulatory Specialist
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| ""*"""'*'TBWB63-4754 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
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| ==CAUSE==
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| SYSTEM COMPONENT MANUTACTURER
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| ==CAUSE==
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| SYSTEM COMPONENT MANUFACTURER O RS 1
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| I SUPPLEMENT AL REPORT EXPECTED (14)
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| EXPECTED MONTH DAY YEAR l
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| YEs SUBWSSON
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| )(
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| uo (If yes, complete EXPECTED SUBM!ESION DATEp DATE (15)
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| ABSTRACT (Umit to 1400 spaces, i.e., approximately 15 single-spaced typewr%n'i nes) (16) l On October 6.1994. Florida Power Corporation's (FPC) Crystal River Unit 3 (CR-
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| : 3) was in MODE ONE (POWER OPERATION). operating at 100% power.
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| It was determined that the potential existed for CR-3 to have o)erated outside plant Improved Technical Specifications (ITS) relative to the Reactor Protection l
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| System (RPS) setpoints.
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| FPC personnel were reviewing a revised calculation when it was discovered that RPS setpoints may not be conservative relative to ITS.
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| i A further review of RPS setpoints determined that the Variable Low Pressure Trip (VLPT) setpoint was set at the ITS limit without provision for instrument error.
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| The Shutdown Bypass trip setpoint was also found to be set at its ITS limit.
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| This condition is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B).
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| The remainder of the RPS trip setpoints were determined to be in compliance with ITS requi rements.
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| Subsequent evaluations determined that one Emergency Feedwater Initiation and Control System (EFIC) setpoint two Engineered Safeguards Actuation System Bypass bistable setpoints, and instruments used to monitor i
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| Reactor Coolant System (RCS) total flow were also potentially non-conservative relative to ITS.
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| The cause of these events was personnel error.
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| Corrective i
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| actions include: implementation of a setpoint action plan encompassing i
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| recalibration. procedure changes, and assuring adequate setpoints for other actuation systems.
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| 9704090050 970404 PDR ADOCK 05000302 S
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| PDR
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| ~
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| }}
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