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Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo)ML20154H046 |
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Farley ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
06/30/1998 |
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Hardin B NRC |
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Shared Package |
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ML20154G968 |
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References |
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NUDOCS 9810140061 |
Download: ML20154H046 (4) |
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Category:NRC TECHNICAL REPORT
MONTHYEARML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20212B0321986-12-17017 December 1986 Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept ML20126F8181981-02-13013 February 1981 Equipment Evaluation Rept by Ofc of Nuclear Reactor Regulation Equipment Qualification Branch for AL Power Co Jm Farley Unit 1, Partial Review 1998-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 L-99-020, Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20205N0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20204D7271999-03-15015 March 1999 ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1 ML20207M6421999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 ML20198B2561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20195C9681998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20237A2181998-07-24024 July 1998 Jm Farley Unit 2 ISI Rept Interval 2,Period 3 Outage 1, Refueling Outage 12 ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236M5981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20154H0461998-06-30030 June 1998 Technical Evaluation Rept on Review of Farley Nuclear Plant IPEEE Submittal on High Winds,Flood & Other External Events (Hfo) ML20248M3121998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20247F3631998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20247E8851998-03-31031 March 1998 FNP Unit 2 Cycle 13 Colr ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20216D5941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20216J6851998-03-16016 March 1998 Revised Pages 58 & 59 to Fnp,Units 1 & 2,Power Uprate Project BOP Licensing Rept ML20216D9811998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Jm Farley Nuclear Plant,Units 1 & 2 1999-09-30
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TECHNICAL EVALUATION REPORT ON THE :
REVIEW OF THE FARLEY NUCLEAR PLANT-INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) SUBMITTAL ON HIGH WINDS, FLOOD, AND OTHER EXTERNAL EVENTS (HFO) l
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Brad Hardin, USNRC June,1998
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9810140061 981001 PDR ADOCK 05000348 P PDR 1 C{t}DhDDio\
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a l 2 Farley Nuclear Plant
. IPEEE Review Results j High Winds, Floods and 4
Other Extemal Events (HFO) l
- 1. Introduction Farley is a two-unit, Westinghouse three-loop PWR located on the Chattachoochese River in l southeast Alabama. (Dothan is the largest nearby city.) The plant began commercial operation in j 1977. The 1975 Standard Review Plan (SRP) was still under development during the construction of the plant, and it was not necessary for the plant to commit to the 1975 SRP criteria. However, the licensee's HFO IPEEE process used the progressive screening approach described in NUREG-1407 and focussed on demonstrating that the design and construction of
, the plant in the HFO areas meet the 1975 SRP criteria. The licensee's evaluation also confirmed that no plant changes had occurred since the issuance of the original Operating License that
! would impcet on the HFO areas of review.
- 2. High Winds
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- The licensee reviewed the original design against high winds and tomadoes and determined that j the plant design conformed to the 1975 SRP criteria with the exception that some additional j analysis was needed regarding the tomado missile spectrum that was originally considered to
- include a potential automobile impact at elevations 30 feet above grade. An analysis was
! performed, and acceptable results were indicated. Structures that are important to safety at i Farley are designed to withstand a 115 mph wind. The maximum wind speed experienced at '
- Farley is 90 mph which is estimated to have a 100 year recurrence interval. It was estimated that
{ the contribution to core damage frequency (CDF) from tomado missiles was less than 1E-9/ry.
4 Data over a 40 year period (1950-1992) were used in the assessment, ar;d it was concluded that
- the Farley plant was designed to withstand hazards associated with high winds with no identified
- vulnerabilities. In addition, a walkdown was performed, and no significant changes were found j since the Operating License was issued.
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i 3. External Floods
- The licensee reviewed the plant design against floods and determined that it was in conformance l with the 1975 SRP criteria regarding floods. The review included a review of historical flood e levels in the area (including data from 1905 to 1974), an analysis using world record precipitation levels to evaluate the probable maximum flood level, an evaluation of potential dam failures, and potential flooding of the Chattahoochee River from ice blockage effects. Generic Safety Issue 103, Design for Probable Maximum Precipitation, was included in the evaluation. It was determined that the plant's storage pond, which is capable of providing the plant's shutdown cooling requirements, is higher in elevation than either the historical flooding levels or the conservatively analyzed levels, it was also concluded that even if the Chattachoochee River were to severely flood to a level of 144 feet (assuming 50 mph winds and 9 foot waves), the storage pond would still be resistant to flooding. (i.e., it is safe up to a level of 158 feet.) in addition, a walkdown did not disciose any other significant unique issues regarding flooding.
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- 4. Transportation and Nearby Facility Accidents The licensee performed and documented a detailed evaluation of transportation hazards
' including highway, aircraft, and barge and ship accidents. The licensee also evaluated industrial hazards involving spills of chemicals, explosions including flammable vapor clouds, and accidents involving chemicals stored on site (e.g., chlorine). The results of these evaluations indicated that the plant is in conformance with the 1975 SRP criteria in these areas. A walkdown was also performed, and no significant plant changes that could affect the review conclusions were identified. The only potentially significant changes since the issuance of the Operating License involved certain types and quantities of hazardous materials transported on the Chattanooga railroad (i.e., sulfuric acid, caustic soda and turpentine). An evaluation of these conditions with regard to the guidelines in Regulatory Guides 1.78 and 1.91 indicated that these hazards could be screened out. Aircraft flight pattems were reevaluated, and it was concluded that there was no significant vulnerability due to aircraft accidents. The licensee concluded that the Farley plant design is consistent with the 1975 SRP criteria for these types of events. l l
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- 5. Other External Events NUREG-1407, in Section 2.12, notes that alllicensees should confirm that no plant-unique !
extemal events known to the licensee today with potential severe accident vulnerability are being i excluded from the IPEEE. The licensee has stated that no such vulnerabilities have been l identified for the Farley Plant. I i
- 6. Generic Safety issue (GSI) Resolution GSI-103, " Design for Probable Maximum Precipitation" The licensee has assessed GSI-103 and concluded that the new Probable Maximum Precipitation (PMP) criteria will not have any impact on Farley. The staff finds that the licensee's ,
GSI-103 evaluation is consistent with the guidance provided in Section 6.2.2.3 of NUREG-1407.
GSI 172, " Multiple System Responses Program (MSRP)"
There is one MSRP issue related to the HFO area which is entitled " Effects of Flooding and/or Moisture Intrusion on Non-safety Related and Safety Related Equipment." The effects of flooding on safety related equipment were addressed in the licensee's submitta! (Section 5.2), but such possible effects on non-safety related equipment were not addressed.
- 7. Conclusions Strengths in the IPEEE submittalinclude the overall clarity and completeness of the documentation. The minor differences with the 1975 SRP were thoroughly analyzed with a clear description of the analysis method and results.
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4 Although there was one MSRP issue that was not explicitly addressed in the submittal, the staff does not believe that this is significant weakness in the overall IPEEE documentation. There were no other weaknesses or vulnerabilities identified in the HFO assessment, and no plant improvements were indicated.
It is concluded that the Farley submittal for the HFO areas meets the intent of GL 88-20, and no requests for additional information (RAls) are needed.
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