05000302/LER-1994-006-01, :on 950118,deficiency in Understanding of Technical Requirements Led to Nonconservative Safety Sys Setpoint & Violations of Improved Ts.Caused by Personnel Error.Implemented Setpoint Action Plan

:on 950118,deficiency in Understanding of Technical Requirements Led to Nonconservative Safety Sys Setpoint & Violations of Improved Ts.Caused by Personnel Error.Implemented Setpoint Action Plan

ML20137N771
Person / Time
Site:	Crystal River
Issue date:	03/26/1997
From:	Frijouf J FLORIDA POWER CORP.
To:
Shared Package
ML20137N763	List: 05000302/LER-1994-006-01, :on 950118,deficiency in Understanding of Technical Requirements Led to Nonconservative Safety Sys Setpoint & Violations of Improved Ts.Caused by Personnel Error.Implemented Setpoint Action Plan 05000302/LER-1994-006-06, Forwards Corrected Page One of LER 94-006-06 Which Had Typo in Block 7, Rept Number
References
LER-94-006-01, LER-94-6-1, NUDOCS 9704090050
Download: ML20137N771 (2)

LER-1994-006, on 950118,deficiency in Understanding of Technical Requirements Led to Nonconservative Safety Sys Setpoint & Violations of Improved Ts.Caused by Personnel Error.Implemented Setpoint Action Plan

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3021994006R01 - NRC Website

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i NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 4

$921 EXPIRES 5/31/93 i

ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS I

, LICENSEE EVENT REPORT (LER)

$%7E"ReGS$'S!"RU#fSEATMOTE iNrl2u"*^2 1

AND FIECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR i

REGULATORY COMMISSJON, WASHINGTON, DC 20555 0001, AND TO THE PAPERWORK REDUCTION PFiOJECT (31504104). OFFICE OF

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l (see reverse for required number of digits / characters for each block)

MANAGEMENT AND BUDGET, WASHINGTON, DC E0503.

F ACILITY NAME (1) j CRYSTAL RIVER UNIT 3 (CR-3)

DOCerET NUMBER (2)

PAGE 05000 1OF 0

"'N Deficiency in Understanding of Technical Requirements Leads to Nonconservative Safety Systems Setpoint and Violations of Improved Technical Specifications EVENT DATE (5)

LER NUMBER (6i REPORT NUMBER (7)

OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR MONTH DAY YEAR g

01 18 95 94

- 006 06 03 26 97 T3oy"""

OPERATING y

THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (Check one or more) (11) i MODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POWER 20 405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73 71(c) l

]

LEVEL (10) 100 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii)

OTHER

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20.405(a)(1)(di)

)( 50.73(a)(2)(i) 50.73(a)(2)(viii)(A)

WP'cdY

• Ab'"*c' 20 405(a)(1)(iv) 50 73(a)(2)(ii) 50.73(a)(2)(viii)(B)

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20 405(a)(1)(v) 50.73(a)(2)(iii) 50 73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

James A. Frijouf. Sr. Nuclear Regulatory Specialist

""""' *""*"""'T57f '563-4754 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCmBED IN THIS REPORT (13)

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CAUSE

SYSTEM COMPONENT MANUFACTURER

CAUSE

SYSTEM COMPONENT MANUFACTURER RDS i

il 1

l i

k SUPPLEMENTAL REPORT EXPECTED (14)

EXPECTED

• N'"

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pi y. compici. EXPECTED SUBMrSSION DATE:

DATE (15) i ABSTRACT (Limit to 1400 spaces, i e., approximately 15 single spaced typewritten lines) (16)

J 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 operated outside plant l

Improved Technical Specifications (ITS) relative to the Reactor Protection System (RPS) setpoints.

FPC personnel were reviewing a revised calculation when

[

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 2

i (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 requirements.

Subsequent evaluations determined that one Emergency Feedwater j

Initiation and Control System (EFIC) setpoint, two Engineered Safeguards Actuation System Bypass bistable setpoints, and instruments used to monitor Reactor Coolant System (RCS) total flow were also potentially non-conservative relative to ITS.

The cause of these events was personnel error.

Corrective actions include: implementation of a setpoint action plan encompassing recalibration, procedure changes, and assuring adequate setpoints for other actuation systems.

i' 9704090050 970404 PDR ADOCK 05000302

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S PDR

4 REQUIRED NUMBER OF DIGITS, WARACTERS FOR EACH BLOCK BLOCK NUMBER OF ITLE NUMBER DIGITS / CHARACTERS 1

UP TO 46 FACILITY NAME 2

DOCKET NUMBER 3 IN ADDITION TO 05000 3

VARIES PAGE NUMBER 4

UP TO 76 TITLE 5

ENT DATE 2 PER BLOCK 7 TOTAL

^

6 LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 7

REPORT DATE 2 PER BL CK UP TO 18 - FACILITY NAME 8

^'

8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000 9

1 OPERATING MODE 10 3

POWER LEVEL Il REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES 0 50 M NAME 12 LICENSEE CONTACT 14 FOR TELEPHONE CAUSE VARIES 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES

'4 NA R

ECTED CHECK BOX THAT APPLIES 15 EXPECTED SUBMISSION DATE 2 PER BL CK