ML20198P225
| ML20198P225 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/29/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20198P142 | List: |
| References | |
| 50-302-97-21, NUDOCS 9801220038 | |
| Download: ML20198P225 (6) | |
See also: IR 05000302/1997021
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U.S.' NUCLEAR REGULATORY COMMISSION
REGION II
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- Docket No.
50 302
License No.
DPR 72-
Report No -
50 302/97 21-
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Licensee::
Florida Power Corporation
Facility:
Crystal . River 3 Nuclear Station
Location:
15760 West Power Line Street
Crystal River, F1 34428 6708
. Date:
December 3, 1997
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. Inspectors:.
S. Cahill, Senior Resident Inspector
T. Cooper, Resident Inspector
R. Schin, Reactor Inspector
S. Ninh, Project Engineer
Approved-
K. Landis, Chief, Projects Branch 3
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Division of Reactor Projects
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EXECUTIVE SUMMARY
Crystal River 3 Nuclear Station
NRC Inspection Report 50 302/97 21
This special inspection report included a review of Licensee Event Reports
(LERs) submitted by Florida Power Cc7 oration (FPC) from 1995 through 1997.
These LERs documented engineering design deficiencies at Crystal River 3
Nuclear Station.
Based on results of our review, the inspectors determined that violations of
NRC requirements occurred. These violations involve a number of examples of
noncompliances in design control,10 CFR 50.59, procedural adecuacy/ adherence,
reportability, and corrective actions. These examples includec unanalyzed
conditions and conditions that were outside the design basis of Crystal River
Unit 3.
Some of the deficiencies have existed since plant licensing. A list
of the conditions identified and the corresponding LERs is attached. The
majority of these conditions were identified by your staff during a
comprehensive review of the Crystal River engineering program and a
reassessment of the plant design margins.
The inspectors determined that the information regarding the reasons for the
violations, the corrective actions taken and planned to correct the violations
and prevent recurrence are adequately addressed on the docket in the LERs you
have'provided to the NRC. Although no additional information regarding
corrective actions is required at this time, the NRC will continue to examine
the implementation of your corrective actions during future inspections.
As discussed in detail in the cover letter, the NRC has concluded that while
violations did occur associated with the events documented in the LERs,
enforcement discretion in accordance with Section VII.B.2 of the " General
Statement of Policy and Procedures for NRC E:1forcement Actions" (Enforcement
Policy), NUREG 1600, is warranted. Therefore no Notice of Violation is being
issued in this case.
The exercise of enforcement discretion in this case is identified as non cited
violation (NCV) 50 302/97 21 01, Examples of Noncompliances in Design Control,
10 CFR 50.59 Evaluations, Procedural Adequacy / Adherence, Reportability, and
Corrective Actions. This NCV will be used to track the exercise of
enforcement discretion and will be used as a reference upon satisfactory
completion of your corrective actions for the individual LERs.
Attachment: List of Licensee Event Reports (LERs)
Included in NCV 50 302/97-21 01
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LIST OF LICENSEE EVENT REPORTS (LERs)
INCLUDED IN NCV 50 302/97 21 01
LER NUMBER
Title
EVENT DATE
REPORT DATE.
95 001
INSPECTION DETERMINES CONTROL COMPLEX HABITABILITY ENVELOPE
01/24/95
IN LEAKAGE AREA EXCEEDS REQUIREMENTS RESULTING IN CONDITION
03/07/95
POTENTIALLY OUTSIDE DESIGN BASIS.
95 004
PERSONNEL ERROR CAUSES CONTROL COMPLEX HABITABILITY ENVELOPE
03/21/95
BREACH RESULTING IN OPERATION OUTSIDE DESIGN BASIS.
04/12/95
95 019
SERVICE WATER SYSTEM REVIEW DISCOVERS LEAK INSTRUMENTATION
09/29/95
UNABLE TO PERFORM ITS FUNCTION RESULTING IN OPERATION OUTSIDE
10/26/95
THE DESIGN BASIS OF THE PLANT.
95 021
INADEQUATE PIPE SUPPORTS ALLOW STRESS ON MOTOR COOLER N0ZZLE
10/04/95
RESULTING IN OPERATION OUTSIDE THE DESIGN BASIS.
11/03/95
95 026
UNQUALIFIED FLOW INSTRUMENT USED IN DETERMINING HPI PUMP
11/07/95
RUNOUT CONDITIONS CAUSED BY FAIL!.'RE TO RECOGNIZE
12/07/95
APPLICABILITY OF REG GUIDE 1.97
95 028
OPERATION OUTSIDE DESIGN BASIS CAUSED BY PERSONNEL ERRORS AND
12/13/95
INADEQUATE DOCUMENTATION OF B0 RATED WATER STORAGE TANK VACUUM
01/12/96
BREAKER CAPACITY.
96 004
POTENTIAL LEAKAGE INTO CONTROL COMPLEX HABITABILITY ENVELOPE
01/12/96
AB0VE DESIGN LIMITS DUE TO WORN AND HISSING DAMPER.
02/08/96
96 008
AMBIGU0US NOTE CAUSES MISINTERPRETATION AND FAILURE TO
03/04/96
PERFORM REQUIRED SURVEILLANCE PRIOR TO MODE ASCENSION.
04/02/96
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96 015
PERSONNEL ERRORS CAUSE CABLE SEPARATICN/ ISOLATION CONCERNS
04/08/96
RESULTING IN OPERATION OUTSIDE THE DESIGN BASIS. (Toxic Gas-
05/20/96
Monitors)
96 019
CLASSIFICATION OF TRANSFER SWITCH CAUSES POTENTIAL FOR LOSS
06/13/96
0F POWER TO ES STATUS LIGHTS.
07/15/96
96 021
DELAYED ENTRY INTO TECHNICAL SPECIFICATION ACTION FOR IN0P
09/28/96
RPS CHANNEL
L
10/28/96-
96 022
DESIGN ERROR REGARDING HOT SHORTS RESULTS IN OPERATION
11/22/96
0UTSIDE 10 CFR 50 APPENDIX R DESIGN BASIS.
12/20/96
Attachment
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LIST OF LICENSEE EVENT REPORTS (LERs)
Page 2
INCLUDED IN NCV 50 302/97 21 01
LER NUMBER'
Title-
EVENT DATE'
REPORT DATE-
97 004-
THERMAL RELIEF VALVES INSIDE THE CONTAINMENT DO NOT MEET THE
02/07/97
REQUIREMENTS FOR DESIGN BASIS ACCIDENTS
03/10/97
97 006
SURVEILLANCE TESTING RESULTS IN REDUCTION OF EMERGENCY DIESEL
02/19/97
GENERATOR RATING LIMIT DUE TO INADEQUATE ACCEPTANCE CRITERIA.
03/20/97
97 008
DISCOVERY OF ORIGINAL DESIGN CONFIGURATION RESULTING IN
03/07/97
UNANALYZED CONDITION REGARDING HIGH PRESSURE INJECTION PUMP
04/07/97
RECIRCULATION LEADING TO POSSIBLE PUMP FAILURE AND DOSE
CONSEQUENCES.
97 011
POTENTIAL DESIGN BASIS CONDITION FROM PRESSURE LOCKING 0F
05/29/97
EMERGENCY FEEDWATER ISOLATION VALVES CAUSED BY INSUFFICIENT
06/27/97
OVERSIGHT / REVIEW 0F CALCULATIONS.
97 012
PORTIONS OF INDUSTRIAL COOLING SYSTEM NOT DESIGNED TO
05/31/97
APPLICABLE CODE RESULTING IN OPERATION OUTSIDE THE DESIGN
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06/26/97
BASIS.
97 013
EMERGENCY DIESEL GENERATOR ROOM COULD EXCEED MAXIMUM DESIGN
05/30/97
TEMPERATURE DURING OPERATION DUE TO INADEQUATE R00H COOLING.
06/26/97
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97 014
DUE TO ENGINEERING DESIGN ERRORS. REACTOR BUILDING
06/11/97
PENETRATIONS DO NOT MEET APPLICABLE CODES RESULTING IN A
07/11/97
CONDITION OUTSIDE THE DESIGN BASIS.
97 015
NON CONSERVATIVE DIFFERENTIAL PRESSURE RATING FOR LETDOWN
06/12/97
LINE INBOARD CONTAINMENT ISOLATION VALVE PROHIBITING SAFETY
07/11/97
FUNCTION PERFORMANCE.
97 016
DUE TO ENGINEERING ERROR. OMISSIONS IN REACTOR BUILDING
06/13/97
C0ATING CALCULATIONS RESULT IN CR 3 BEING IN AN UNANALYZED
07/11/97
CONDITION.
97 017
PERSONNEL ERROR CAUSED INADEQUATE ELECTRICAL SEPARATION OF
06/21/97
THE HIGH PRESSURE FLOW INDICATORS.
07/21/97
97 018
A HIGH ENERGY LINE BREAK IN THE INTERMEDIATE BUILDING'(IB)
07/02/97
COULD RESULT IN LOSS OF CHILLED WATER TO THE CONTROL COMPLEX
07/26/97
VENTILATION SYSTEM DUE TO DESIGN ERROR.
97 019-
ELEVATED EDG SUPPLY AIR TEMPERATURES DUE TO EDG RADIATOR
07/03/97
DISCHARGE AIR RECIRCULATION EFFECT.
08/01/97
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LIST OF LICENSEE EVENT REPORTS (LERs)
Page 3
INCLUDED IN NCV 50 302/97 21 01
LER NUMBER:
Title
EVENT DATE-
REPORT.DATE:
97 020
MISINTERPRETATION LEADS TO NONCOMPLIANCE WITH TECHNICAL
07/18/97
SPECIFICATION CRITERIA INVOLVING PAST IN PLACE FILTER
08/18/97
TESTING.
97 021
LOSS OF "A" BATTERY LEADS TO THE INABILITY TO BYPASS ES
07/21/97
ACTUATION SIGNALS AS A RESULT OF INADEQUATE SYSTEM KNOWLEDGE.
08/20/97
97 022
CALCULATION ERRORS ASSOCIATED WITH CONTROL COMPLEX
07/21/97
HABITABILITY ENVELOPE UNFILTERED AIR INLEAKAGE COULD ALLOW
08/18/97
OPERATOR DOSE LIMITS TO BE EXCEEDED.
97 023
DESIGN ENGINEERING PROCESS ALLOWS INSTALLATION OF VITAL BUS
07/30/97
INVERTERS CONTAINING AN UNANALYZED TRIP CIRCUIT.
08/25/97
97 024
FEEDWATER VALVES DO NOT MEET THE REQUIREMENTS FOR MAIN STEAM
07/31/97
LINE OR FEEDWATER LINE BREAK EVENT HITIGATION DUE TO
08/27/97
INADEQUATE DESIGN AND CALCULATION ERRORS.
97 026
FAILURE TO PERFORM A FIELD VALIDATION RESULTED IN A DEVIATION
08/14/97
TO 10 CFR 50 APPENDIX R REQUIREMENTS.
09/13/97
97 027
FAILURE TO ADD ANTIFREEZE TO THE DIESEL GENERATOR COOLANT
07/07/97
RADIATORS MAY RENDER EMERGENCY DIESEL GENERATOR INOPERABLE
10/03/97
DURING SUB FREEZING TEMPERATURES.
97 028
FLOW ELEMENT ACCURACY UNCERTAINTY MAY BE GREATER THAN ASSUMED
09/02/97
DUE TO A DESIGN ERROR.
10/02/97
97 029
FAILURE TO PERFORM A FIELD VALIDATION RESULTED IN A DEVIATION
09/17/.7
0F 10 CFR 50 APPENDIX R REQUIREMENTS.
10/14/97
97 030
INSTALLATION ERROR RESULTS IN A CONTAINMENT ISOLATION CHECK
09/23/97
VALVE DISC STICKING IN THE OPEN POSITION.
10/21/97
97 032
INADEQUATE ELECTRICAL ISOLATION ON A SAFETY RELATED POWER
04/06/97
SUPPLY DUE TO A DESIGN ERROR
11/05/97
97 033
LOSS OF CONTROL COMPLEX VENTILATION SYSTEM DUE TO ELECTRO
08/07/97
THERM 0 LINK AND FUSIBLE LINK FIRE DAMPER AUTOMATIC CLOSURE
11/10/97
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. LIST OF LICENSEE EVENT REPORTS (LERs)'
Page 4.
INCLUDED IN NCV 50 302/97 21 01.
LER'NUSER:
Title;
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EVENT DATEi
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REPORT DATEv
R:
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97 034
NONCONSERVATIVE ASSUMPTION IN BREAKER SETPOINT CALCULATIONS
10/08/97-
COULD PREVENT STARTING 0F MOTOR OPERATED EQUIPMENT
11/06/97-
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97 035-
A DESIGN ERROR RESULTED IN THE INABILITY TO PROVIDE REACTOR-
10/16/97
COOLANT SYSTEM INVENTORY MAKEUP DURING A POSTULATED APPENDIX
11/13/97
R EVENT
97 036-
THERMAL OVERLOAD RELAYS IN MANUAL RESET POSITION RESULTED IN
10/24/97
OPERATION OUTSIDE DESIGN BASIS.
11/21/97
97 037
CONTAINMENT INTEGRITY CANNOT BE PROVEN FOLLOWING CALIBRATION
10/24/97
0F BUILDING SPRAY PRESSURE SWITCHES AND TRANSMITTERS
11/21/97
97 038
AN ENGINEERING OVERSIGHT RESULTED IN OPERATION OUTSIDE DESIGN
03/17/97
BASIS FOR THE WASTE GAS DISPOSAL SYSTEM.
11/22/97
97 039
UNQUALIFIED MATERIAL LEFT IN REACTOR BUILDING DURING-
06/02/97
CONSTRUCTION COULD AFFECT POST LOCA C00LDOWN CAPABILITY.
12/03/97.
97 040
INADEQUATE ENGINEERING DOCUMENTATION FOR SAFETY RELATED LARGE
01/08/97
BORE PIPING ANALYSIS AND PIPE SUPPORTS.
12/04/97
97 041
CONTROL COMPLEX CHILLER MAY BE RENDERED UNAVAILABLE DUE TO
11/10/97
DESIGN ERROR.
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12/10/97
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