Sser Re Effect of Breakwater Damage on Saltwater Intake StructureML20215D909 |
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Site: |
Diablo Canyon |
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Issue date: |
02/15/1983 |
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NRC |
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Shared Package |
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ML20197F583 |
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References |
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FOIA-86-679 NUDOCS 8610140358 |
Download: ML20215D909 (10) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20207A7181999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 132 to Licenses DPR-80 & DPR-82,respectively ML20206H2861999-05-0303 May 1999 Safety Evaluation Supporting Amends 133 & 131 to Licenses DPR-80 & DPR-82,respectively ML20206D5661999-04-29029 April 1999 Safety Evaluation Supporting Amends 132 & 130 to Licenses DPR-80 & DPR-82,respectively ML20205B6061999-03-26026 March 1999 Safety Evaluation Supporting Amends 131 & 129 to Licenses DPR-80 & DPR-82,respectively ML20249B6881998-06-11011 June 1998 Safety Evaluation Supporting Amends 128 & 126 to Licenses DPR-80 & DPR-82,respectively ML20249B5961998-06-0505 June 1998 Safety Evaluation Supporting Amends 127 & 125 to Licenses DPR-80 & 82,respectively ML20249B6041998-06-0505 June 1998 Safety Evaluation Supporting Amends 126 & 124 to Licenses DPR-80 & DPR-82,respectively ML20248D4041998-05-28028 May 1998 Safety Evaluation Supporting Amends 125 & 123 to Licenses DPR-80 & DPR-82,respectively ML20248L8761998-03-12012 March 1998 Safety Evaluation Supporting Amends 124 & 122 to Licenses DPR-80 & DPR-82,respectively ML20197B7091998-02-27027 February 1998 Safety Evaluation Supporting Amends 123 & 121 to Licenses DPR-80 & DPR-82,respectively ML20203L4881998-02-17017 February 1998 Safety Evaluation Supporting Amends 122 & 120 to Licenses DPR-80 & DPR-82,respectively ML20203L2981998-02-13013 February 1998 Safety Evaluation Supporting Amends 121 & 119 to Licenses DPR-80 & DPR-82,respectively ML20203M4321998-02-0303 February 1998 Safety Evaluation Supporting Amends 120 & 118 to Licenses DPR-80 & DPR-82,respectively ML20149H4281997-07-17017 July 1997 Corrected SE Re Amends 119 & 117 to Licenses DPR-80 & DPR-82,respectively ML20129G9351996-10-25025 October 1996 Safety Evaluation Supporting Amends 117 & 115 to Licenses DPR-80 & DPR-82,respectively ML20129G7771996-10-25025 October 1996 Safety Evaluation Supporting Amends 116 & 114 to Licenses DPR-80 & DPR-82,respectively ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary ML20117E5541996-08-19019 August 1996 Safety Evaluation Supporting Amends 115 & 113 to Licenses DPR-80 & DPR-82,respectively ML20117K4671996-05-28028 May 1996 Safety Evaluation Supporting Amends 113 & 111 to Licenses DPR-80 & DPR-82,respectively ML20092F3411995-08-23023 August 1995 Corrected SE Supporting Amends 107 & 106 to Licenses DPR-82 & DPR-80,respectively ML20082H9121995-04-11011 April 1995 Safety Evaluation Supporting Amends 99 & 98 to Licenses DPR-80 & DPR-82,respectively ML20063M1481994-03-0303 March 1994 Safety Evaluation Supporting Amends 90 & 89 to Licenses DPR-80 & DPR-82,respectively ML20063M1111994-03-0202 March 1994 Safety Evaluation Supporting Amends 89 & 88 to Licenses DPR-80 & DPR-82,respectively ML20063M0431994-02-24024 February 1994 Safety Evaluation Supporting Amends 88 & 87 to Licenses DPR-80 & DPR-82,respectively NUREG-0675, SER Concluding That Seismic Margins of Structures & Equipment/Components at Plant Reported in LTSP Final Rept Are Adequate Even After Considering Staff Estimate of Increased Seismic Ground Motions1992-04-17017 April 1992 SER Concluding That Seismic Margins of Structures & Equipment/Components at Plant Reported in LTSP Final Rept Are Adequate Even After Considering Staff Estimate of Increased Seismic Ground Motions ML20092E0021992-01-22022 January 1992 Safety Evaluation Supporting Amends 67 & 66 to Licenses DPR-80 & DPR-82,respectively ML20082V1441991-09-0606 September 1991 Safety Evaluation Supporting Amends 66 & 65 to Licenses DPR-80 & DPR-82,respectively ML20082V2621991-09-0505 September 1991 Safety Evaluation Supporting Amends 65 & 64 to Licenses DPR-80 & DPR-82,respectively ML20081L3021991-06-27027 June 1991 Safety Evaluation Supporting Amends 62 & 61 to Licenses DPR-80 & DPR-82,respectively ML20081F2021991-05-23023 May 1991 Safety Evaluation Supporting Amends 61 & 60 to Licenses DPR-80 & DPR-82,respectively ML20070H1821991-03-0606 March 1991 Safety Evaluation Supporting Amends 59 & 58 to Licenses DPR-80 & DPR-82,respectively ML20246K9501989-07-10010 July 1989 Safety Evaluation Supporting Amends 42 & 41 to License DPR-80 & DPR-82,respectively ML20245F8371989-06-22022 June 1989 Safety Evaluation Supporting Amends 41 & 40 to Licenses DPR-80 & DPR-82,respectively ML20244C8771989-06-0707 June 1989 Safety Evaluation Supporting Amends 40 & 39 to Licenses DPR-80 & DPR-82,respectively ML20244C8551989-06-0707 June 1989 Safety Evaluation Supporting Amends 39 & 38 to Licenses DPR-80 & DPR-82,respectively ML20247H9771989-05-23023 May 1989 Safety Evaluation Supporting Amends 38 & 37 to Licenses DPR-80 & DPR-82,respectively ML20247B1201989-05-10010 May 1989 Safety Evaluation Supporting Amends 37 & 36 to Licenses DPR-80 & DPR-82,respectively ML20245L2511989-04-25025 April 1989 Safety Evaluation Supporting Amends 36 & 35 to Licenses DPR-80 & DPR-82,respectively ML20245H6991989-04-14014 April 1989 Safety Evaluation Supporting Amends 34 & 35 to Licenses DPR-82 & DPR-80,respectively ML20247L2931989-03-27027 March 1989 Safety Evaluation Supporting Amends 34 & 33 to Licenses DPR-80 & DPR-82,respectively ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20196E4811987-12-28028 December 1987 Safety Evaluation Supporting Amends 26 & 25 to Licenses DPR-80 & DPR-82,respectively ML20238C4611987-12-16016 December 1987 Safety Evaluation Supporting Amends 24 & 23 to Licenses DPR-80 & DPR-82,respectively ML20238C6061987-12-16016 December 1987 Safety Evaluation Supporting Amends 25 & 24 to Licenses DPR-80 & DPR-82,respectively ML20235G7671987-09-18018 September 1987 Safety Evaluation Supporting Amends 21 & 20 to Licenses DPR-80 & DPR-82,respectively ML20238D3871987-09-0303 September 1987 Safety Evaluation Supporting Amends 19 & 18 to Licenses DPR-80 & DPR-82,respectively ML20238D3931987-09-0303 September 1987 Safety Evaluation Supporting Amends 20 & 19 to Licenses DPR-80 & DPR-82,respectively ML20237L5631987-08-31031 August 1987 Safety Evaluation Supporting Amends 18 & 17 to Licenses DPR-80 & DPR-82,respectively ML20237G5541987-08-27027 August 1987 Safety Evaluation Supporting Amends 17 & 16 to Licenses DPR-80 & DPR-82,respectively ML20236H3811987-07-27027 July 1987 Safety Evaluation Supporting Amends 16 & 15 to Licenses DPR-80 & DPR-82,respectively 1999-05-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20207A7181999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 132 to Licenses DPR-80 & DPR-82,respectively ML20206H2861999-05-0303 May 1999 Safety Evaluation Supporting Amends 133 & 131 to Licenses DPR-80 & DPR-82,respectively ML20206D5661999-04-29029 April 1999 Safety Evaluation Supporting Amends 132 & 130 to Licenses DPR-80 & DPR-82,respectively ML20205B6061999-03-26026 March 1999 Safety Evaluation Supporting Amends 131 & 129 to Licenses DPR-80 & DPR-82,respectively DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20249B6881998-06-11011 June 1998 Safety Evaluation Supporting Amends 128 & 126 to Licenses DPR-80 & DPR-82,respectively ML20249B5961998-06-0505 June 1998 Safety Evaluation Supporting Amends 127 & 125 to Licenses DPR-80 & 82,respectively ML20249B6041998-06-0505 June 1998 Safety Evaluation Supporting Amends 126 & 124 to Licenses DPR-80 & DPR-82,respectively ML20248D4041998-05-28028 May 1998 Safety Evaluation Supporting Amends 125 & 123 to Licenses DPR-80 & DPR-82,respectively ML20248L8761998-03-12012 March 1998 Safety Evaluation Supporting Amends 124 & 122 to Licenses DPR-80 & DPR-82,respectively ML20197B7091998-02-27027 February 1998 Safety Evaluation Supporting Amends 123 & 121 to Licenses DPR-80 & DPR-82,respectively ML20203J5141998-02-26026 February 1998 LER 98-S02-00:on 980127,following Security Sys Failure Compensatory Measures Were Not Implemented within 10 Minutes Due to Personnel Error.Caused by Failed Disk Drive. Replaced Disk Drives,Reviewed Security Computer Maint Plans ML20203L4881998-02-17017 February 1998 Safety Evaluation Supporting Amends 122 & 120 to Licenses DPR-80 & DPR-82,respectively ML20203L2981998-02-13013 February 1998 Safety Evaluation Supporting Amends 121 & 119 to Licenses DPR-80 & DPR-82,respectively ML20203M4321998-02-0303 February 1998 Safety Evaluation Supporting Amends 120 & 118 to Licenses DPR-80 & DPR-82,respectively ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML20149H4281997-07-17017 July 1997 Corrected SE Re Amends 119 & 117 to Licenses DPR-80 & DPR-82,respectively ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML20129G9351996-10-25025 October 1996 Safety Evaluation Supporting Amends 117 & 115 to Licenses DPR-80 & DPR-82,respectively ML20129G7771996-10-25025 October 1996 Safety Evaluation Supporting Amends 116 & 114 to Licenses DPR-80 & DPR-82,respectively ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary ML20117E5541996-08-19019 August 1996 Safety Evaluation Supporting Amends 115 & 113 to Licenses DPR-80 & DPR-82,respectively ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20117K4671996-05-28028 May 1996 Safety Evaluation Supporting Amends 113 & 111 to Licenses DPR-80 & DPR-82,respectively ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092F3411995-08-23023 August 1995 Corrected SE Supporting Amends 107 & 106 to Licenses DPR-82 & DPR-80,respectively ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML20082H9121995-04-11011 April 1995 Safety Evaluation Supporting Amends 99 & 98 to Licenses DPR-80 & DPR-82,respectively ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML20063M1481994-03-0303 March 1994 Safety Evaluation Supporting Amends 90 & 89 to Licenses DPR-80 & DPR-82,respectively ML20063M1111994-03-0202 March 1994 Safety Evaluation Supporting Amends 89 & 88 to Licenses DPR-80 & DPR-82,respectively ML20063M0431994-02-24024 February 1994 Safety Evaluation Supporting Amends 88 & 87 to Licenses DPR-80 & DPR-82,respectively ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 1999-07-12
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Supplement to Safety Evaluation Report Diablo Canyon Nuclear Power Plant Units 1 and 2 Docket Nos. 50-275 and 50-323 2.0 Site Characteristics 2.4 Ef fect of Breakwater Damage on Saltwater Intake Structure The plant obtains both its normal and emergency cooling water from the Category I Saltwater Intake Structure located on-the shoreline of a cove south of Units 1 and 2.
This cove is protected from storm waves by two breakwaters (east and west) with their crest constructed to elevation +20 feet Mean, Lower Low Water (MLLW). Although the breakwaters are not designated as safety-related structurese they do provide flood protection to the safety related Auxiliary Saltwater (ASW) pumps located within the Intake Structure. These ASW pumps are designed to remain functional during the design basis flood event.
As discussed in SER Supplement No.13, April 1981, during a winter storm on January 28r 1981, the West Breakwater was damaged by storm waves.
Approximately 120 feet of the seaward end of the breakwater sustained substantial damage consisting of displacement of concrete cap units, tribar armor units, and underlayer quarrystone to approximately 0 feet MLLW.
Subsequent storm waves in 1981 and 1982 extended this damage to a total length of about 240 feet (as of December 1982).
8610140358 861006 FOIA PDR PDR BISHOP 86-679 i
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' As a result of the January 1981 storm, which degraded a portion of the west breakwater to a level of about Elevation 0 feet MLLW, a breakwater configuration was presented that was more severe than any condition previous l
postulated for the Design Basis Flood event. Based on available information, neither the staff nor the applicant were in a position to evaluate:
I (a) the potential for and limits ofi further breakwater degradatione l
(b) the extent to which a significantly degraded breakwater would limit wave runup on the Intake Structure to a level below the design level of +30 feet MLLW during the design or lesser flooding events, and l
(c) the implications of this and associated events on operation of l
safety-related equipment.
l It was determined that if the wave ruoup on the Intake Structure exceeded the design level of +30 feet MLLW, the only safety-related equipment that might be affected are the Auxiliary Saltwater pumps located in the Intake Structure. The ASW pump motors are located approximately six feet (El 6.5 feet, MLLW) above the floor of the watertight ASW pump chambers.
These pumps are necessary for heat transfer from the component cooling heat exchangers. The water-tight ASW pump chambers are each provided with a ventilation stack which extends through the roof of the Intake Structure to Elevation +30 feet, MLLW.
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In order to preclude having to defend the safety of the plant in the future if the breakwaters wece to sustain further damage or be repaired and damaged agains the applicant proposed to reanalyze the ability of the Intake Structure to withstand the effects of the Design Basis Flood event with the breakwaters severely damaged. Based on studies by Wiegeli 1982 and I
Seeds 1982r the applicant selected elevation 0 feet, MLLW as the postu(ated minimum degraded level for be$h of the br,eakwaters and conducted hydraulic model tests of the effects of the Design Basis Flood evente i.e.i " Probable Maximum Tsunami" concurrent with annual storm waves (SER Supplement No. 5e September 1976). Additional model tests were conducted with " Maximum Credible Wave Events" combined with high tide and sea level anomaly.
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applicant also studied the probability of vessels impacting on the Intake Structure (Kirchere Monzon-Despang and Morris, 1982). The vessels were limited to those with sufficient draft to cross over the degraded breakwater 4
and sufficient displacement to infl/ct significant damage to the Intake Structure.
The hydraulic model studies utilized a laboratory testing facility measuring 80 feet by 120 feet by 4 feet deep which reproducede at a 1:45 model to prototype scaler the Intake Structurer the breakwaterse and the adjacent nearshore and offshore bathometry.
This represented a prototype area of 446 acres measuring 3600 by 5400 feet.
Detailed discussion of test procedures and results of the hydraulic model studies are reported by Lillevang, Raichtene and Caser 1982; Lillevange 1982 and Raichtene 1982. The application of the results of these studies on the ability of the ASW pumps to safely operate during these D8F events are reported by Matsudar 1983.
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. The applicant has concluded that the SW Intake Structurer with minor modificatione is capable of withstanding the effects, including wave forcess of the postulated Design Basis Flood events, thereby assuring continuous protection of the Auxiliary Saltwater (ASW) pumps. The Design Basis Flood events consist of the postulated degradation of both breakwaters to O feet MLLW combined with 1) the " Probable Maximum Tsunami" concurrent with storm waves of more than annual severity (estimated return period of about 41 years), or 2) the " Maximum Credible Wave Event" combined with high tide and sea level anomaly.
The SW Intake Structure modifications consist of:
a) extending and reinforcing the ventilation stack for each of the AWS pump chambers to El 52.0 feet MLLW:
b) modifying manholes that provide access to the SW intake structure forbay so as to reduce venting and to withstand pressures greater than 97 feet of seawater; and c) providing a concrete fill at the intersection of the underside of the deck slab and the rear of the curtain wall so as to mitigate slam or wave impact pressures.
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The applicant concluded that extending the ASW pump ventilation shafts (stacks) preclude the ingestion of seawater to the extent that the operation of the ASW pumps would not be impaired during the postulated Design Basis Flood events (Ryani 1982).
The applicant concluded that the probability of large vessels (i.e. gre,ater than 250 tons displacement) crossing the degraded breakwater and impacting
-6 the intake structure is acceptably low (storm-independent case is 6.7 x 10 events per yeari Kircherr Monzon-Despanze and Morrise 1982). With respect to the safety-related function of the ASW pumpse the impact of vessels displacing less than 250 tons on the intake structure would be inconsequential.
The applicant is in the process of reconstructing and strengthing the damaged portion of the west breakwater.
The staff and its consultante the U.S. Army Coastal Engineering Research Center (CERC)r were actively involved in the planninge monitoring and evaluation of the hydraulic model studies. The staff has determined that the licenseer during the progress of the physical hydraulic studiese has comphdwiththeguidanceprovidedinRegulatoryGuide1.125. Additionallyr X
.because the breakwaterse even in their assumed degraded condition, will provide a degree of wave protection to the Intake Structurer they are considered flood protection barriersi as defined in Regulatory Guide 1.102.
The staff, with the assistance of CERC have reviewed the applicant's reports and has drawn the following conclusions:
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.- a.
Although. sufficient evidence has been provided to indicate that breakwater degradation below the level of 0 feet MLLW is rarer the information provided by the applicant does not substantiate the assumption that a rubble-mound breakwater cannot degrade below that level.
b.
The applicant has applied the most critical wave heights periode and direction of wave approach associated with both the " Probable Maximum Tsunami Annual Storm Wave Event" and the " Maximum Credible Wave Event".
The staff concludes that there are appropriate design basis and are in concordance sith Regulatory Guide 1.59.
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Extending the ventilation stack for each of the Auxiliary Saltwater c.
pump chambers on the Intake Structure to elevation +52 feet, MLLW will prevent significant ingestion of wave runup and spray and will allow unimpaired operation of the ASW pumps during the Design Basis Flood event.
d.
The applicant has conservatively determined the wave pressures on the Saltwater Intake Structure and the ventilation stacks associated with the Design Basis Flood event with both breakwaters degraded to O feet MLLW level. The structural ability of the SW Intake Structure and the ventilation stacks to resist impact forces associated with the DBF event 3.V and other design events is discussed in the Section 33 of this SSER.
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The applicant has conservatively determined the best estimate of the frequency of a vessel crossing the degraded breakwater and impacting on the Saltwater Intake Structure for the storm-independent case as
-6 6.7 x 10 per year. The analysis was limited to those types of vessels with a draft shallow enough to cross over the breakwater and displacing more than 250 tons. Vessels displacing less than 250 tons will not inflict significant damage to the Intake Structure.
The staff therefore concludes that the Auxiliary Saltwater pumps would be flood protectdd for events up to and including the " Probable Maximum Tsunami Event" and the " Maximum Credible Wave Event" even if the entire length of both breakwaters were degraded to the level of 0 feet MLLW. Because there is no assurance that the breakwater will not degrade below the level of o fee b NLLWe the staff will requirer and the licensee has agreed to, a technical specification to:
a) monitor the condition of the breakwater, b) implement timely corrective action when limited damage is sustainede and c) identify the limiting condition for operation relative to the 4Hdd+
configuration nf the breakwaters.
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Based on its review and analysis and the implementation of the technical 3
specifications the staff concludes that the plant meets the guidance of Regulatory Guides 1.59r 1.102 and 1.125. The staff further concludes that the plant meets the requirements of General Design Criteria 2 and 10 CFR Part 100r Appendix A with respect to tsunami and wave induced flooding.
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References i ht Lillevang, Omar J., Fredric Raichten, and Jack Cox "The He g 1.
h tically Limiting Effect of Sea Floor Terrain Features and of Hypot e Canyon Extensively Reduced Breakwaters on Wave Action at Diablo i
l Model Sea Water Intake" - Report on a Three-Dimensional Phys ca 982.
Study for Pacific Gas and Electric Company, March 15,1
" Breakwater Damage by Severe Storm Waves and 2.
Wiegeli Robert L.i Tsunami Waves," March Si 1982.
k ters at Seede H. Bolton, " Evaluation of Seismic Stability of Brea wa 3.
1981 (Revised April 6,1982).
Diablo Canyon NPS."
September 22r Interactions Raichten, Fredrice "The Investigation of Wave-Structure 4.
Nu lear for the Cooling Water Intake Structure of the Diablo Canyon Power Plant, December 1982.
and Richard J. Morrise Charles A., Hector Monzon-Despange 5.
Kircherr Intake
" Frequency of Vessel Impact with the Diablo Canyon December 10, 1982.
Structures, i
" Criteria for Selection of Critical Wave Direct ons Lillevang, Omar J.e 6.
November 2r 1982.
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Matsudar E. N., " Wave Effects on the Intake Structure at Diablo Canyon, Units 1 and 2," January 1983.
8.
Ryan, P.J., " Investigation of Seawater Ingestion into the Auxiliary Salt Water Pump Room Due to Splash Runup During the Design Flood Events at Diablo Canyon," Jan'uary 1983.
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