View source for 05000302/LER-1994-006, Forwards Corrected Page One of LER 94-006-06 Which Had Typo in Block 7, Rept Number

{{Adams
| number = ML20137N761
| issue date = 04/04/1997
| title = Forwards Corrected Page One of LER 94-006-06 Which Had Typo in Block 7, Rept Number
| author name = Holden J
| author affiliation = FLORIDA POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000302
| license number = 
| contact person = 
| document report number = 3F0497-31, 3F497-31, NUDOCS 9704090048
| package number = ML20137N763
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
}}
{{LER
| Title = Forwards Corrected Page One of LER 94-006-06 Which Had Typo in Block 7, Rept Number
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000302
| LER year = 2094
| LER number = 6
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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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

==Dear Sir:==

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,
              " Report Number". The original submittal incorrectly listed the year as 96 rather than 97.
If you have any questions, please contact Mr. J. A. Frijouf, Senior Nuclear Regulatory Assurance Specialist, at (352) 563-4754.
Sincerely, pks /
J.cJ. Holden Director, Nuclear Engineering and Proj.ects                                     -
m JJH/JAF
(
9704090048 970404 PDR Att.          s      ADOCK 05000302 pon xc:     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 H2)                                                                                                              APPROVED BY OMB NO. 3150-0104 EXPlRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY W:TH THIS e
LICENSEE EVENT REPORT (LER)                                                 U""E"HE$#
M NEE 8E'ud 0""#EwlEr^$
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)              MANAGEMENT AND BUDGET, WASHINGTON, DC 20503 K41UTV NAME (1)
DOCKET NUMBER (2)
CRYSTAL RIVER UNIT 3 (CR-3)                                                                               05000                                PAGE70 1 oF I""W Deficiency in Understr.nding of Technical Requirements Leads to Nonconservative Safety Systems Setpoint and Violations of Improved Technical Specifications l
EVENT DATE (5)                              LER NUMBER (6'                REPORT NUMBER (7)                  OTHER FACILITIES INVOLVED (8)
MONTH            DAY       YEAR      YEAR                                       MONTH       DAY    YEAR g
o 01               18       95       94        -- 006           -
06          03         26       97 05000 OPERATING y       THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (Check one or more) (11)
MODE (9)                          20 402(b)                              20.405(c)                          50.73(a)(2)0v)                         73.71(b)
POWER                            20 405(a)(1)(i)                        50.36(c)(1)                        50.73(a)(2)(v)                         73.71(c)
LEVEL (10)             100          20.405(alm 06)                         50.36(c)(2)                        50.73(a)(2)(vi )                       OTHER 20.405la)(1)0ii)                     X 50.73(a)(2)(i)                     50.73(a)(2)(viii)(A)
{s         i{A s 20 405(a)(1)0v)                        50.73(a)(2)(ii)                    50 73(a)(2)(vui)(B)             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)
            ~
j                            James A. Frijouf, Sr. Nuclear Regulatory Specialist                                             ""*"""'*'TBWB63-4754 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE          SYSTEM        COMPONENT         MANUTACTURER                                     CAUSE   SYSTEM    COMPONENT O RS                                                               MANUFACTURER 1
I l
l SUPPLEMENT AL REPORT EXPECTED (14)                                                       EXPECTED        MONTH       DAY   YEAR l                 YEs                                                                                                                        SUBWSSON (If yes, complete EXPECTED SUBM!ESION DATEp                         )(  uo DATE (15)
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-
: 3) was in MODE ONE (POWER OPERATION). operating at 100% power. 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                          System (RPS) setpoints. FPC personnel were reviewing a revised calculation when i                           it was discovered that RPS setpoints may not be conservative relative to ITS.
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.
The Shutdown Bypass trip setpoint was also found to be set at its ITS limit.
This condition is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B). The remainder of the RPS trip setpoints were determined to be in compliance with ITS requi rements.            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                          Reactor Coolant System (RCS) total flow were also potentially non-conservative                                                                            !
:                           relative to ITS. The cause of these events was personnel error. Corrective                                                                               ;
i                         actions include: implementation of a setpoint action plan encompassing i                         recalibration. procedure changes, and assuring adequate setpoints for other actuation systems.
9704090050 970404 PDR          ADOCK 05000302 S                                   PDR
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