|
|---|
Category:ARCHIVE RECORDS
MONTHYEARML20202E6751999-01-22022 January 1999
Rev 0 to Calculation M-99-0017, Deterministic Operational Assessment for Freespan ODSCC Degradation at Crystal River Unit 3
ML20202E6911999-01-21021 January 1999
Rev 0 to Calculation AES-C-3543-1, Deterministic Operational Assessment for Free-Span Outside Diameter Stress Corrosion Cracking Degradation at Crystal River,Unit 3
ML20198N6091998-09-30030 September 1998
Rev 0 to FPC Calculation F-98-0010, FTI Calculation 32-5000218-00,Adjusted Ref Temperatures for 32 EFPY for CR-3
ML20198N5941998-09-30030 September 1998
Rev 0 to FPC Calculation F-98-0013, FTI Calculation 32-5001746-00,CR-3 32 EFPY P/T Limits
ML20236F1671998-06-0303 June 1998
Rev 1 to Calculation S98-0021, Review of Crystal River Unit 3 Plant Structures & Components Summary Rept. Page 31 of 58 of Incoming Submittal Not Included
ML20217G6991998-04-0606 April 1998
Post-LOCA Boron Concentration Mgt for CR-3
ML20217G3831998-03-25025 March 1998
Rev 1 to M-98-0012, Leak Near RWV-129
ML20203K4891998-02-23023 February 1998
Rev 6 to Calculation M97-0098, Boron Dilution by Hot Leg Injection
ML20203J3151997-12-12012 December 1997
Rev 0 to S97-0541, Confirmatory Study of Selected Safe Shutdown Equipment Anchorage for USI A-46
ML20203F0791997-12-11011 December 1997
Rev 0 to M-97-0146, Post-LOCA Boron Concentration Mgt for CR-3
ML20203J3851997-12-0909 December 1997
Rev 0 to S97-0542, CR3 Structural Seismic Margin Evaluation (Study)
ML20203J3031997-12-0909 December 1997
Rev 0 to S97-0316, Seismic Evaluation of Emergency Feedwater Tank EFT-2
ML20203J3701997-12-0404 December 1997
Rev 1 to S-96-0013, Qualification of Tanks Per USI A-46
ML20203F1281997-11-28028 November 1997
Rev 0 to Calculation M97-0121, Pipe Stress Analysis, Evaluation of Effects of Pressurizer Surge Line LOCA Break on Svc Water Piping Sys at Crystal River,Unit 3
ML20202E3781997-11-0101 November 1997
Rev 1 to M97-0097, Low Pressure Auxiliary Spray Flow Rate for Boron Precipitation. W/Simulator Exercise ROT-9-200, Boron Precipitation Control
ML20203K4801997-09-0707 September 1997
Rev 0 to Calculation M97-0088, Hydraulic Analysis for LPI Hotleg Injection to Rcs
ML20196H0381997-07-18018 July 1997
To CR-3 15 EFPY Lwop Limits
ML20212D0011997-07-15015 July 1997
Rev 2 to CR3 15 EFPY LTOP Limits
ML20133K2671997-01-16016 January 1997
Press Release II-97-10, NRC Staff to Hold Predecisional Enforcement Conference to Discuss Crystal River Engineering Concerns W/Fl Power Corp
ML20133C6891997-01-0707 January 1997
Press Release II-97-04, NRC Names New Senior Resident Inspector at Crystal River Npp
ML20133B1891997-01-0202 January 1997
Press Release II-97-01, NRC Schedules Meeting at FPC Crystal River Plant
ML20135E3721996-12-0909 December 1996
Press Release II-96-103, NRC Commissioner Diaz to Visit Crystal River Nuclear Plant
ML20134N6561996-11-26026 November 1996
Press Release II-96-98, NRC Staff Issues Appraisal of Performance at Crystal River Nuclear Power Plant in Fl
ML20134G4401996-11-12012 November 1996
Press Release II-96-91, NRC Establishes Restart Panel for Crystal River Plant,Schedules Corrective Action Meeting in Atlanta
ML20129B6291996-10-22022 October 1996
Press Release II-96-86, NRC Reschedules Two Meetings 961031 at Crystal River Npp
ML20128K4231996-10-0707 October 1996
Press Release II-96-84, NRC Postpones Two Meetings Scheduled for Wednesday,961009 at Fl Power Corp Crystal River Plant
ML20129F0901996-10-0303 October 1996
Press Release II-96-82, NRC Schedules Two Meetings at Fl Power Corp Crystal River Plant
ML20116J8191996-08-0101 August 1996
Rev 0 to Qualification of Pipe Supports MSH-13B & MSH-27B
ML20116J9881996-08-0101 August 1996
Rev 0 to Evaluation of Effect of Bent Hanger Rod on Piping Analysis CR-5
ML20107L1821996-04-22022 April 1996
Rev 1 to 102075RCS01, Comparison of Calculated & Measured Pressures at Junction of Makeup Tank Surge Line & Pump Suction Pipe
ML20101M5941996-04-0404 April 1996
Mut/Bwst Hytran Analysis
ML20101M5891996-04-0404 April 1996
Mut Vapor Pressure Evaluation
ML20101M5801996-04-0404 April 1996
Mut Dissolved Gas Evolution Analysis
ML20101M5841996-04-0404 April 1996
Mut Vortexing Evaluation
ML20101M5641996-03-12012 March 1996
Allowable MUT-1 Indicated Overpressure Vs Indicated Level
ML20101M5611996-02-13013 February 1996
Effect of Mut Temp on Max Allowable Mut Pressure
ML20137G2831996-02-0909 February 1996
Rev 0 to S-96-0013, Qualification of Tanks Per USI A-46
ML20101M5521996-01-24024 January 1996
Potential Uncertainty in Total Head Loss from Bwst to Mut Tie-In
ML20101M5441996-01-17017 January 1996
Combination of Mut Pressure & Level Errors
ML20101M5291996-01-11011 January 1996
Mut Pressure
ML20101M5111996-01-11011 January 1996
Max Allowable Mut Pressure
ML20101M5201996-01-0505 January 1996
Head Loss in Bwst to Makeup Pump Flow
ML20084U2521995-06-0101 June 1995
EFIC - Main Steam Instrumentation Loop String Accuracy & Setpoints
ML20084U2701995-04-13013 April 1995
Rc Pressure (Wide Range) Loop Accuracy,RC-158-PT & RC-159-PT
ML20080U2461995-02-23023 February 1995
Nonproprietary Version of CR-3,Pressurizer Surge Nozzle Stresses
ML20078A3971994-12-0606 December 1994
Allowable Swhe Tube Blockage Vs Vhs Temp
ML20116J8051994-11-18018 November 1994
Rev 0 to Piping Analysis CR-5 Rev 0:Main Steam from Pen 107 to Turbine Stop Valve
ML20116J8121994-09-23023 September 1994
Rev 0 to Piping Analysis CR-6 Rev 0:Main Steam from Pen 201 to Turbine Stop Valve
ML20069M7091994-04-0808 April 1994
Rev 0 to CR-3 Analysis of S/N ECT Data for SG Tubes
ML20069M6951994-04-0808 April 1994
Rev 0 to Statistical Analysis of Defect Depth of SG Tubes
1999-01-22
[Table view]
Category:PRESS RELEASE OR NEWS ARTICLE
MONTHYEARML20133K2671997-01-16016 January 1997
Press Release II-97-10, NRC Staff to Hold Predecisional Enforcement Conference to Discuss Crystal River Engineering Concerns W/Fl Power Corp
ML20133C6891997-01-0707 January 1997
Press Release II-97-04, NRC Names New Senior Resident Inspector at Crystal River Npp
ML20133B1891997-01-0202 January 1997
Press Release II-97-01, NRC Schedules Meeting at FPC Crystal River Plant
ML20135E3721996-12-0909 December 1996
Press Release II-96-103, NRC Commissioner Diaz to Visit Crystal River Nuclear Plant
ML20134N6561996-11-26026 November 1996
Press Release II-96-98, NRC Staff Issues Appraisal of Performance at Crystal River Nuclear Power Plant in Fl
ML20134G4401996-11-12012 November 1996
Press Release II-96-91, NRC Establishes Restart Panel for Crystal River Plant,Schedules Corrective Action Meeting in Atlanta
ML20129B6291996-10-22022 October 1996
Press Release II-96-86, NRC Reschedules Two Meetings 961031 at Crystal River Npp
ML20128K4231996-10-0707 October 1996
Press Release II-96-84, NRC Postpones Two Meetings Scheduled for Wednesday,961009 at Fl Power Corp Crystal River Plant
ML20129F0901996-10-0303 October 1996
Press Release II-96-82, NRC Schedules Two Meetings at Fl Power Corp Crystal River Plant
1997-01-07
[Table view] |
Text
_.._..
Y o
f U.S. Nuclear Regulatory Commission Region II 101 Marietta Street. N.W.
Suite 2900 Atlanta, GA 30323 j
No: II-96-98 FOR IMMEDIATE RELEASE
Contact:
Ken Clark (404) 331-5503 (Tuesday November 26, 1996) i Roger Hannah (404) 331-7878 NRC STAFF ISSUES APPRAISAL OF PERFORMANCE AT CRYSTAL RIVER NUCLEAR POWER PLANT IN FLORIDA Overall Performance Declines From Previous Assessment Period The Nuclear Regulatory Commission staff has issued a Systematic Assessment I
of Licensee Performance (SALP) report for Florida Power Corporation's Crystal River nuclear power plant, located near Crystal River. Florida, which NRC l
officials say indicates an overall decline in performance at the facility since its previous assessment.
The NRC staff evaluated performance at Crystal River for a period from September 17. 1995 through October 5 of this year and found that performance in the functional areas of Operations and Engineering declined from " good" to
)
" acceptable" while performance in the functional area of Plant Support declined from " superior" to " good."
Performance in the functional area of Maintenance l
was sustained at a " good" level.
l It was the second consecutive decline in assessment for Engineering, which has seen its assessment over the last two SALP periods drop twice, from i
" superior" to " good" to " acceptable".
Stewart D. Ebneter. Administrator of the NRC's Region II office in i
Atlanta, said " common threads" running through the assessment. which contributed to the performance decline, were weak management oversight ineffective self-l assessment, insufficient involvement in quality assurance, and an " insensitivity" to regulatory requirements.
r Operations addresses the control and execution of activities directly related to operating the plant. Maintenance involves activities in the areas of testing and maintaining plant structures, systems and components.
Engineering involves activities associated with the design of plant modifications and support for operations, maintenance, surveillance (testing) and licensing activities.
Plant Support addresses radiological controls radioactive effluents, chemistry emergency preparedness, security, fire protection and housekeepiong controls.
The NRC staff assesses performance in these areas at all commercial nuclear power plants in the United States on a periodic basis as being in one of three categories. Category 1 is considered superior. Category 2 is considered good, and Category 3 is acceptable.
NRC officials will meet with company management at the plant site at 12:30 p.m. on Monday. December 2. to discuss details of the report.
The meeting is open to observation by the public and the press, and NRC officials will be available at its conclusion to answer questions from interested observers.
7 9611270069 961126 p{2.O!
PDR PRESS R RC-II-96-098 PDR Ol
-
