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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML20150F2941988-05-31031 May 1988 Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20155K1391987-12-30030 December 1987 Final Rept MSIV 3-Way Dual Solenoid Valve Failures ML20235F0881987-12-17017 December 1987 Marked-up Draft Seismological Analysis of Bodega Head,Ca ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235G3041987-09-29029 September 1987 Partially Withheld, Preliminary Investigation of Enrico Fermi II Nuclear Power Plant ML20235B3121987-08-31031 August 1987 Comparison of Monticello & Brunswick Recirculation Pump Trip ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20237K8201987-08-26026 August 1987 TVA Employee Concerns Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-2, Review of Nuclear Safety Review Staff Non-Startup Items at Bellefonte ML20237K7691987-08-0606 August 1987 Rev 3 to TVA Employee Concern Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-1, Review of Nuclear Safety Review Staff Restart Items at Browns Ferry ML20236N2591987-07-31031 July 1987 Final Summary Rept of Human Factors Engineering Review for Byron & Braidwood Stations Spds ML20237K7981987-07-28028 July 1987 Rev 1 to TVA Employee Concerns Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-2, Review of Nuclear Safety Review Staff Non-Restart Items at Browns Ferry ML20237K8081987-07-23023 July 1987 Rev 0 to TVA Employee Concern Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-1, Review of Nuclear Safety Review Staff Startup Items at Bellefonte ML18093A1791987-06-19019 June 1987 Installation of Trip-A-Unit Protection Scheme Suppl Info Salem & Hope Creek Generating Stations. ML20214S3081987-05-28028 May 1987 Weekly Status Rept,Assessment of Embedment Plates Status as of 870528 ML20214T2941987-05-27027 May 1987 Comm Ed Final Summary Rept on Human Factors Review for Byron/Braidwood Stations Emergency Response Facilities ML20215K2441987-04-30030 April 1987 Assessment of Embedment Plates Status as of 870430, Weekly Status Rept ML20214E0581987-04-16016 April 1987 Rev 2 to ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations ML17279A1911987-04-0707 April 1987 Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl ML18092B4971987-04-0303 April 1987 S-C-E500-NSE-0675-R-1, Justification for Operation of All Three Units at Artificial Island at Increased Power During Hope Creek-Keeney Line Outage. ML20204J7431987-03-12012 March 1987 Assessment of Embedment Plates Status as of 870308, Weekly Status Rept ML20212K1201987-01-23023 January 1987 Final Design Description,Atws Mitigation Sys Actuation Circuitry ML20210U3761987-01-16016 January 1987 Rev 1 to ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations 1989-08-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18094B3211990-02-28028 February 1990 Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML18094B1471989-10-25025 October 1989 Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML20248G8291989-10-0202 October 1989 Rev 19 to YOQAP-I-A, Operational QA Program ML17347B3821989-09-30030 September 1989 Monthly Operating Repts for Sept 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/891016 Ltr ML19327C0681989-09-30030 September 1989 Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20248D1571989-09-13013 September 1989 Rev 56 to QA Program ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML17347B3341989-08-31031 August 1989 Monthly Operating Repts for Aug 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/890913 Ltr ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML17347B2731989-07-31031 July 1989 Monthly Operating Repts for Jul 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML17347B2741989-06-30030 June 1989 Corrected Monthly Operating Repts for June 1989 for Turkey Point Units 3 & 4 ML17347B1851989-06-30030 June 1989 Monthly Operating Repts for June 1989 for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4.W/890717 Ltr ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML18151A5411989-06-21021 June 1989 Updated Operational QA Program Topical Rept. ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML18101A4931989-06-13013 June 1989 Radiological Emergency Preparedness Exercise Evaluation Rept. ML17345A7241989-06-0909 June 1989 Rev 15 to Topical QA Rept. ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML17345A7501989-05-31031 May 1989 Monthly Operating Repts for May 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML17345A6851989-04-30030 April 1989 Monthly Operating Repts for Apr 1989 for Turkey Point Units 1 & 2 & St Lucie Units 1 & 2.W/890515 Ltr ML17345A7531989-04-30030 April 1989 Corrected Monthly Operating Rept for Apr 1989 for St Lucie Unit 2 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing 1990-02-28
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. QUMMARY OF REPORT i1 h
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, M6teorological Aspects of. Nuclear %eactor; Hazards dt(Bode a Ba by'Dr. James E. Mcdonald,lSenior Physicist d -
t , Institute of Atmospheric, Physics, University gof Arizona M fune; 1964 4 ,. .-
Certain meteorological conditions peculiar to the Bodega Bay area and to the northern California coast have quite adverse implications fo: radiological hazards that could
~
I arise from a major reactor accident.
?
j One extremely adverse meteorological feature for which fairly reliable data are at hand l i is the high frequency of inversions that would act to ponfine radioactive effluents 4
release in any accident The inversion frequency at Oakland, California, averages 70 ,
per cent of all days for the summer months of June to September. At Oakland, for the year as a whole, 40 percent of the days have inversion bases at or below 1500 feet.
c r. y The frequency of low inversions at a coastal site such as Bodega Head is certain to be O. E even greater'than in Oakland,because air reaching Oakland has, in general, been sub'-
- ..gc jected to some overland warming. Furthermore, ocean surface temperatures just
.--v;7
-r - offshore band of upwellingand upwind watersofoff Bodega Head Californi'a, are known increasing local to be among tendencies the stability, toward lowest alo if Inversion studies by U.C.L.A. meteorologists have shown that the intensity of the 90- ' inversion is particularly strong near Bodega and at coastal points northward % Cape Mendocino . Mean summer inversion-layer thickness of about 1500 feet, and mean j
% ~. inversion magnitude (temperature increase from cool base to warm top) of about 1200 i
W4,7~ near Bodega makes the inversion extremly effective as a lid preventing deep mixing of )
l any radioactive effluents from an accidental release.
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#7 With auch high frequency and unusual intensity of low inversions it is difficult to 1 jpgz .
visualize a less desirable locality in which to have a serious reactor accident.
l I
NN iM.j Following the Company's submission of a new design concept to compensate for fault 1
;--m =- movement through the site, the Atomic Energy. Commission's Director of Regulation, I r_1 Mr. Harold L. Price,(letter: May 19, 1964) recentip asked P.G. & E. how it proposes to l modify its design so that "(1) the structure and leak tightness of the containment build '
. s ..
ing would not beimpaired.? (ii) the ability to shut down the reactor and maintain it in
- the shut-down condition would not be imparied? (iii) primary systems would remain intact? and (iv) supply of power to the facility would not be interrupted?" Director i
Price proceeds to still more specific queries about location and safeguards proposed for " vital internal components" and'especially about the emercency cooline system.
N The latter query is directed to a crucial' point, for with the original triple containment barrier potentially reduced (by major seismic accident) to the single barrier of the reactt vessel, the question of reliability of the emergency cooling system required to dispose i
of post-accident fission decay heat assumes major importance. Possibility of a whole series of seismically induced malfunctions in the complex automatic control systems that must swing into operation in event of accident draws attention to the possibility b
of failure of the standby systems design to deliver emergency cooling to the reactor core. Such a failure would insure meltdown of the core, a prerequisite to escape of the volatile fission products. With'the outer two containment barriers breached, core meltdown would leave only the reactor vessel as the sole containment barrier. The further possibility (admitted by PG&E in its estimate of the " maximum credible accident' Mh1.E 8709220564 851217 -
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specified in its 1962 Pr'eliminary Hazards Summary Report) that seismically induced !
failures of other components of the safety system might event'uate in breaching of 1
) that one last barrier returns our attention to the meteorological factors that would govern radiolo'gical exposure hazards in event of such an accident.
,The foregoing remarks have been aimed primarily at drawing attention to the fact that there has been a' substantial drop in claimed integrity of the Bodega reactor as a result of recent geological and seismological findings at the site. The peculiarly adverse meteorological factors associated with the Bodega site assume much more serious proportions in the face of these reductions in claimed integrity.
It should be noted that serious radiological exposures are obtained for an assumed j escape of only 80 megacuries of the total of approximately 200 megacuries of y! volatile fission products, or about one-third of all the volatiles. One-third of the j i volatile fission products accumulated in the Bodega reactor core at equilibrium
! represents, in turn, approximately 6 or 7 per cent of the total fission product
~- inventory in the equilibrium core of Bodega No.1 Reactor. Even that small a i fractional escape of total fission products would produce catastrophic results.
~ The foregoing summary of seismic potential for major accident and of hazard dimen- >
sions should suffice to show that one must, indeed, weigh into the over-all assess-N, ment of desirability of constructing a complex of reactors at Bodega Head the -l 7" question of the adverse meteorological features of the area, for the possibility AJ -
that those features would be brought into play seems much greater now that the pros-i pect of a major release has essumed its recently acquired credibility.
1 c. m Cf The meteorological difficult'ies are compounded by the unusually high persistence g of winds blowing out of the northwest. The marked tendency for northwest winds ;
.O blowing onshore from the Pacific anticyclone means that effluents caught under the gdh inversion lid would tend, in general, to drift towards the populous areas and milk- l f shed areas of'Marin and Sonoma Counties.
l 9.
Furthermore, recent studies carried out in connection with forest-fire meteorology 5 investigations, have clearly established that a well-developed summer sea-breeze r system prevails in the "Petaluma gap", the corridor of low terrain running inland
= from Bodega to the Petaluma and Cotati Valleys. During the daytime hours, marine D'
air penetrates into inland areas beyond Petaluma and Santa Rosa. Past field studies on the extent of inland penetration required to break down inversions in the los Angeles area indicate that it is almost certain that the inversion lid would still be present E' in air currents reaching, say, Petaluma and Shnta Rosa; so a reactor accident that happened to occur between morning and mid-afternoon, during summer months, would almost certainly lead to radiological exposures in those and other inland communities.
g During evening and early morning hours, weak counterblow (land breeze) is to be expeued through the Petaluma gap, but quantitative data on the nighttime land breeze are non-existent. This is a very serious lack of meteorological information. It
' seems probable that weak land-breeze flow would cause radioactive effluents from Bodega to drift a short distance out to sea before being caught in the prevailing i northwesterly flow. Thus any reactor accident that occur ed during the nighttime j hours in the summer half-year is likely to inject effluents into coastwise-drifting '
air heading toward the second principal gap in the coastal ranges, the Golden Gate.
- The fact that stability of the inversion and sub-inversion layers would be even greater at night implies substantially less lateral dispersion for nighttime drift of effluents towards the Golden Gate than for daytime drift of effluents through the Peta- l
; luma gap. It seems entirely possible that effectlye radioactive plume widths of only !
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, j
.-,. ~--<.w. 3, . ,
-m . . g 7 .-v,v,,,-,..., m e.n, w.,.c,w ,- .- m - ---,--m,
babout,1p-15 miles coult .e characteristic of effluents re. )ing the Golden Gate, f'
-{penhaps only half those for Santa Rosa or Petaluma, implying perhaps twice as high concentrations 1,n San Frsncisco) .
I^ Smoke expe~riments carried out at Brookhaven National Laborator'es and elsewhere !
.have established that under the kind of highly stable inversion conditions present j . under summer nighttime condU. ions along the California coast, effluent plumes can 6 l drift for manytens of miles with almost no turbulent mixing or spreading, so high
' plume concentrations could persist to and through the Golden Gste. The monsoonal I inflow of inarine air through the Golden Gate into the San Francisco Bay area is so .
strong as to persist, th6 ugh with reduced intensity, even during nfghttime hours. !
Hence there is high probability that effluents drifting down the coast from Bodega - l
' to the Golden Gate would be mainly swept inland to endanger the large population ,
center of the Eay area. i I
Thus, in summer, pasence of a sea-breeze system in the Petaluma gap is of over- J riding importance in any assessment of radiological hazards of the Bodsga reactor !
site. It is disquieting to find no discussion of this sea" breeze system in the meteor- {
-2 olgical section of the Preliminary Hazards Summcry Report filed by the Pacific Gas 1 I
~~; atd Electric Company as part of the application for a construction permit. Much .
more needs to be known about both the day'ime and the nighttime portions of that I e=-j sea-breeze system before reliable quantitative estimates of radiological hazards may !
M be made; but on the basis of existing knowledge, I regard the meteorological factors j gh. as peculiarly adverse. !
i b -
A reactor accident taking place during the winter half-year would involve rather different meteorological factors than would a suauner accident. In winter, stability
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conditions would generally favor rapid vertical mixing of accidentally released q 7 ,,j radioactive effluents, and wind directions are also more variable. However, even j
.1 ~ in the winter wet season, coastal inversions are relatively common (as contrasted 1
'W
{ egg with other areas of the country), and northwesterly winds are still the prevailing winds . The distinctive featutes of winter weather on the California coast is the j
i A.f occurrence of frequent light rains or drizzles (3 approximately one day in three has l some precipitation near Bodega in winter) implying correspondingly high probability bs of rain-washout of radioactivity. Deposition of radioactivity on the milkshed areas F(9 of Sonoma County, and panicularly of Marin County, would become the most serious !
- r. r :D hazard accompanying a major accident during the wet winter months. Only the still I'
)
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wetter coasts of Oregon and Washington excel the northern California coast in winter with respect to probability of serious rain washout of reactor-accident effluents .
N Note must be taken here of the extremely poor siting of the meteorological tower that has been set up on the Head to gather data on the diffusion climatology of the
- reactor area. This tower lies directly downwind of steeply ascending slopes on the west side of the Head. Steady-state turbulence fields will almost never prevail at this tower location, renderinq application of existing diffusion theories almost h impossible. Furthermore, aerodynamic acceleration of low-level winds sweeping up the slopes of the Head towards the tower is likely to give spuriously favorable indication of intensity of the prevailing field of turbulence. I do not see how re-liable estimates of the turbulent diffusion conditions actually prevailing at stack height can be obtained without erection of additional towers, or else a much higher tower at the present site.
t
- I would stress in conclusion, the pressing need for much more extensive and much more careful investigation of all meteorological factors bearing on Bodega reactor hazards . Inversions, prevailingly northwest winds, sea breezes.and land breezes, rain washout, fog and stratus washout and deposition, and details of diffusion climatology must be much more thoroughly understood before safe estimates of radiological hazards can be made for the Bodega site.
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