Similar Documents at Zion |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 ML20236U6331998-07-24024 July 1998 Safety Evaluation Supporting Amends 179 & 166 to Licenses DPR-39 & DPR-48,respectively ML20236S3281998-07-20020 July 1998 Safety Evaluation Supporting Certified Fuel Handlers Training & Retraining Program ML20198P8361998-01-0909 January 1998 SER Accepting Determination of Zone of Influnce for Coatings in Containment of Plant,Units 1 & 2 ML20198P8721998-01-0909 January 1998 Safety Evaluation Accepting Request for Alternative Insp Requirements for Augmented Exam of Reactor Presure Vessels for Zion Nuclear Power Station,Units 1 & 2 ML20202F0761997-12-0202 December 1997 Safety Evaluation Denying Licensee Proposed Alternative Contained in Request for Relief CR-13,Rev 1,of Removing Only Insulation Classified as Removable.Staff Determined That Submittal Does Not Provide Acceptable Level of Quality ML20132F5111996-12-20020 December 1996 Safety Evaluation Supporting Amends 177 & 164 to Licenses DPR-39 & DPR-48,respectively ML20135D8971996-11-25025 November 1996 Corrected SE Supporting Amends 176 & 163 to Licenses DPR-39 & DPR-48,respectively ML20134P7941996-11-25025 November 1996 Safety Evaluation Supporting Amends 176 & 163 to Licenses DPR-39 & DPR-48,respectively ML20134H6781996-11-12012 November 1996 Safety Evaluation Supporting Amends 175 & 162 to Licenses DPR-39 & DPR-48,respectively ML20134F9851996-11-0606 November 1996 Safety Evaluation Supporting Amends 174 & 161 to Licenses DPR-39 & DPR-48,respectively ML20129H2901996-10-29029 October 1996 Safety Evaluation Supporting Amends 173 & 160 to Licenses DPR-39 & DPR-48,respectively ML20059E2871993-12-30030 December 1993 Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively ML20058G2981993-11-29029 November 1993 Safety Evaluation Supporting Amends 151 & 139 to Licenses DPR-39 & DPR-48 ML20059M7851993-11-15015 November 1993 Safety Evaluation Supporting Amends 150 & 138 to Licenses DPR-39 & DPR-48,respectively ML20059L7511993-11-10010 November 1993 Safety Evaluation Accepting Category 3 Qualification in Lieu of Category 2 for Pressure Monitoring Instrumentation ML20059L6801993-11-0909 November 1993 Safety Evaluation Re Update to Plant Reg Guide 1.97 Parameter Summary Table ML20058E6661993-10-22022 October 1993 Corrected SE Re Revised Fuel Handling Accident Inside Containment.Se Mistakenly Gives Decontamination Factor for Elemental Iodine Value of 100 Instead of 133 ML20059B1961993-10-22022 October 1993 Safety Evaluation Accepting Util 930913 Reanalysis of Fuel Handling Accident Inside Containment ML20059A7211993-10-14014 October 1993 Safety Evaluation Supporting Amends 149 & 137 to Licenses DPR-39 & DPR-48,respectively ML20059C5521993-10-13013 October 1993 Corrected Safety Evaluation Supporting Amends 148 & 136 to Licenses DPR-39 & DPR-48,respectively ML20057F8351993-10-13013 October 1993 Safety Evaluation Supporting Amends 148 & 136 to Licenses DPR-39 & DPR-48,respectively ML20057A2091993-08-31031 August 1993 Safety Evaluation Denying Addl Exemptions from Fire Protection Requirements of 10CFR50,app R.Conclusions Reached When Granting Exemptions in 830307 & 880607 SEs Still Valid ML20056H5001993-08-27027 August 1993 Safety Evaluation Re Fire Protection Open Items from Section 3.2.1 of 780310 Safety Evaluation ML20057B1711993-03-24024 March 1993 Safety Evaluation Granting Relief Requests to Licenses DPR-39 & DPR-48 Re Second 10-yr Interval Inservice Testing Plan for Pumps & Valves ML20056C0501992-06-0909 June 1992 Safety Evaluation Supporting Amends 138 & 127 to Licenses DPR-39 & DPR-48,respectively ML20058D8081990-10-31031 October 1990 Safety Evaluation Supporting Amends 120 & 109 to Licenses DPR-39 & DPR-48,respectively ML20247E7421989-09-0808 September 1989 Safety Evaluation Supporting Amends 118 & 107 to Licenses DPR-39 & DPR-48,respectively ML20245F1631989-08-0101 August 1989 Safety Evaluation Supporting Amends 117 & 106 to Licenses DPR-39 & DPR-48,respectively ML20247P9591989-05-30030 May 1989 Safety Evaluation Supporting Amends 116 & 105 to Licenses DPR-39 & DPR-48,respectively ML20247M7431989-05-22022 May 1989 Safety Evaluation Supporting Util Compliance W/Atws Rule 10CFR50.62 ML20245H8051989-04-27027 April 1989 Safety Evaluation Supporting Amends 115 & 104 to Licenses DPR-39 & DPR-48,respectively ML20244E4141989-04-14014 April 1989 Safety Evaluation Supporting Util post-accident Monitoring Instrumentation Per Reg Guide 1.97 & Generic Ltr 82-33 ML20196B8081988-12-0202 December 1988 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements ML20207K9971988-10-11011 October 1988 SER Supporting Amends 113 & 102 to Licenses DPR-39 & DPR-48, Respectively ML20155G5771988-06-0707 June 1988 Safety Evaluation Recommending That Util 840727 Exemption Request from Sections III.G.2 & III.G.3 of 10CFR50,App R Be Granted.One Exemption Request Determined as Unnecessary ML20154A7781988-04-15015 April 1988 Safety Evaluation Supporting Amends 112 & 110 to Licenses DPR-39 & DPR-48,respectively ML20151M1281988-04-0606 April 1988 Safety Evaluation Supporting Amends 111 & 100 to Licenses DPR-39 & DPR-48,respectively ML20148P4951988-04-0404 April 1988 Safety Evaluation Supporting Amends 110 & 99 to Licenses DPR-39 & DPR-48,respectively ML20150F0601988-03-28028 March 1988 Safety Evaluation Supporting Amends 109 & 98 to Licenses DPR-39 & DPR-48,respectively ML20147B8831988-02-26026 February 1988 SER Re Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Nrc Concludes That Many of 30 Measurements Added to List in WCAP-10962 Not Credible ML20149H5541988-02-0505 February 1988 Safety Evaluation Supporting Amend 108 to License DPR-39 ML20237H5511987-08-17017 August 1987 Safety Evaluation Supporting Amends 107 & 97 to Licenses DPR-39 & DPR-48,respectively ML20236J3961987-07-20020 July 1987 Safety Evaluation Supporting Amends 106 & 96 to Licenses DPR-39 & DPR-48,respectively ML20235E9171987-06-23023 June 1987 Safety Evaluation Supporting Amends 105 & 95 to Licenses DPR-39 & DPR-48,respectively ML20213G6351987-05-0808 May 1987 Safety Evaluation Supporting Amends 104 & 94 to Licenses DPR-39 & DPR-48,respectively ML20215K3831987-05-0707 May 1987 Safety Evaluation Re Util 861229 Submittal Concerning Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61.Reported Values of Copper & Nickel Content Unacceptable ML20205Q9561987-03-26026 March 1987 Safety Evaluation Supporting Amends 103 & 93 to Licenses DPR-39 & DPR-48,respectively ML20205G7221987-03-19019 March 1987 Safety Evaluation Supporting Amends 102 & 92 to Licenses DPR-39 & DPR-48 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 A99026, Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers A99023, Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 A99022, Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With A99021, Monthly Operating Repts for June 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Zion Nuclear Power Station,Units 1 & 2.With A99019, Monthly Operating Repts for May 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations A99016, Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20195H9521999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2 A99013, Monthly Operating Repts for Mar 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results A990101, Monthly Operating Repts for Feb 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with A99002, Monthly Operating Repts for Dec 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Zion Nuclear Power Station,Units 1 & 2.With A98062, Monthly Operating Repts for Nov 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Zion Nuclear Power Station,Units 1 & 2.With ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB A98057, Monthly Operating Repts for Oct 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Zion Nuclear Power Station,Units 1 & 2.With A98052, Monthly Operating Rept for Sept 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Zion Nuclear Power Station,Units 1 & 2.With A98049, Special Rept 304-123-98-001SR:on 980902,valid Failure Rept for 2A EDG Occurred.Cause Unknown.Util Submitted Written Certification of Permanent Cessation of Operations at Zion Station,Units 1 & 21998-09-25025 September 1998 Special Rept 304-123-98-001SR:on 980902,valid Failure Rept for 2A EDG Occurred.Cause Unknown.Util Submitted Written Certification of Permanent Cessation of Operations at Zion Station,Units 1 & 2 ML20195D1221998-08-31031 August 1998 DSAR, for Zion Station A98048, Monthly Operating Repts for Aug 1998 for Zion Station,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Zion Station,Units 1 & 2.With ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept A98042, Monthly Operating Repts for July 1998 for Zion Station,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Zion Station,Units 1 & 2 ML20236U6331998-07-24024 July 1998 Safety Evaluation Supporting Amends 179 & 166 to Licenses DPR-39 & DPR-48,respectively ML20236S3281998-07-20020 July 1998 Safety Evaluation Supporting Certified Fuel Handlers Training & Retraining Program A98041, Monthly Operating Repts for June 1998 for Zion Nuclear Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Zion Nuclear Station,Units 1 & 2 ML20236J7911998-06-12012 June 1998 LER 98-S02-00:on 980517,first Shift Security Officer Reported Being Wounded by Unknown Subject Who Fled Area. Caused by accidental,self-inflicted Gunshot Wound.Removed Officer from Duty & Charged Officer W/Filing False Rept A98039, Monthly Operating Repts for May 1998 for Zion Generating Station,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Zion Generating Station,Units 1 & 2 A98035, Monthly Operating Repts for Apr 1998 for Zion Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Zion Station,Units 1 & 2 A98033, Monthly Operating Repts for Mar 1998 for Zion Station,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Zion Station,Units 1 & 2 A98029, Monthly Operating Repts for Feb 1998 for Zion Station,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Zion Station,Units 1 & 2 A98015, Monthly Operating Repts for Jan 1998 for Zion Station,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Zion Station,Units 1 & 2 ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr ML20198P8361998-01-0909 January 1998 SER Accepting Determination of Zone of Influnce for Coatings in Containment of Plant,Units 1 & 2 ML20198P8721998-01-0909 January 1998 Safety Evaluation Accepting Request for Alternative Insp Requirements for Augmented Exam of Reactor Presure Vessels for Zion Nuclear Power Station,Units 1 & 2 A98034, 1997 Annual 10CFR50.59 Summary Rept1997-12-31031 December 1997 1997 Annual 10CFR50.59 Summary Rept ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept A98004, Monthly Operating Repts for Dec 1997 for Zion Station,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Zion Station,Units 1 & 2 ML20202F1451997-12-0303 December 1997 Independent Investigation Team Rept on Safety Conscious Work Environment at Zion Station ML20202F0761997-12-0202 December 1997 Safety Evaluation Denying Licensee Proposed Alternative Contained in Request for Relief CR-13,Rev 1,of Removing Only Insulation Classified as Removable.Staff Determined That Submittal Does Not Provide Acceptable Level of Quality A97076, Monthly Operating Repts for Nov 1997 for Zion Station,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Zion Station,Units 1 & 2 ML20199J5931997-11-26026 November 1997 SG Insp Results,Fall 1996 Refueling Outage 14 (Z2R14) A97063, Special Rept 295-123-97-002SR:on 971014,failure of 1B EDG Occurred.Exam of Nipple Fractured Surface Revealed Failure Occurred Through Thread Root.Unit 1 Defueled & Unit 2 in Mode 5 Throughout Event1997-11-13013 November 1997 Special Rept 295-123-97-002SR:on 971014,failure of 1B EDG Occurred.Exam of Nipple Fractured Surface Revealed Failure Occurred Through Thread Root.Unit 1 Defueled & Unit 2 in Mode 5 Throughout Event A97069, Monthly Operating Repts for Oct 1997 for Zion Station,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Zion Station,Units 1 & 2 ML20211M0181997-10-0707 October 1997 Special Rept 295-123-97-001SR:on 970904,OA Motor Declared Inoperable Due to Pin Hole Leaks Identified on Pressure Regulating Relief valve,0FP0052.Procedure Was Rewritten to Ensure 0FP0052 Would Maintain Same Pressure When Fully Open A97058, Monthly Operating Repts for Sept 1997 for Zion Generating Station,Units 1 & 21997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Zion Generating Station,Units 1 & 2 ML20210V2401997-09-19019 September 1997 Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual 1999-09-30
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION kY RELATED TO PROTECTION AGAINST i
PRESSURIZED THERMAL SHOCK EVENTS l ZION NUCLEAR POWER STATION, UNIT I DOCKET NO. 50-295 1
FAST NEUTRON FLUENCE ASPECT By letter dated January 17, 1986, the Commonwealth Edison Company, licensee for the Zion Unit 1 plant, submitted information on the material properi.ies and the i
fast neutron fluence (E>1.0 MeV) of the reactor pressure vessel in compliance with the requirements of 10 CFR 50.61 (Reference 1). The Engineering Branch of OPWRL-B
]
reviewed the submitted information and detemined the acceptable values of the material properties and chemical composition (Reference 2). The following 7
evaluation concerns the estimation of the fluence to the inside surface of the i pressure vessel for 32 effective full power years of operation and to the end of license and the corresponding values of the RTPTS*
i The neutron transport calculation was performed by Westinghouse using the bench-
- marked DOT discrete ordinates code. Plant and cycle specific sources were used
- to obtain the exposure due to each fuel cycle. The SAILOR cross section set was used, which is ENDF/8-IV based, with a P 3 scattering approximation.
Results of j l the calculation are within 115% of the measured flux values at the surveillance capsule locations. The fluence calculation methodology is acceptable. In. par-f j
ticular, future low leakage cycles are conservatively estimated. The maximum value occurs at 45' in the azimuthal distribution. For the lower shell
]
circumferential weld the peak values of 1.47 x 101' n/cm2 and 1.79 x 101' n/cm2 i' are applicable. They are based on 25.0 and 32 effective full power years of
! operation respectively and low leakage loadings for cycle 7 and subsequent 1
l cycles. <
The applicable equation for the estimation of RTPTS as specified in 10 CFR 50.61 is:
1 I
i i
1 07/08/86 l ZION FRACTURE TOUGHNESS RQMTS l osoeaccog4 080u14
! PDR ADOCK 09000?9S PDR <
p
~
RTPTS= I + M +(-10 + 470 Cu + 350 Cu Ni) f Where: I = initial RT NDT
= 0'F M = uncertainty margin = 59'F Cu = w/o copper in weld WF70 = 0.35 Ni = w/o nickel in weld WF70 = 0.59 f = peak fluence in units of 1018 n/cm2 = 1,79 Then:
o,27 RTPTS = 59 + (-10 + 470 x 0.35 + 350 x 0.35 x 0.59) x 1,79
= 59 + 226.8 x 1.17 = 59 + 265.4 = 324.4*F which exceeds the applicable criterion of 300*F.
For the end of the current license i.e., 25.8 effective full power years the RT PTS value is:
o,27 RTPTS = 59 + 226.8 x 1.47 = 59 + 251.7 = 310.7'F which also exceeds the 300'F screening criterion.
Therefore, we will require that the licensee submit their plans to satisfy the
. provisions of 10 CFR 50.61.
4 5
l i
i 1
ZION FRACTURE TOUGHNESS RQMTS 2 07/14/86 L
, t References 4
- 1. Letter from G. L. Alexander, Commonwealth Edison Company to H. R. Denton, dated January 17, 1986. .
- 2. Memorandum from C. E. Rossi to J. Norris, " Zion Station Unit 1, Material Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events,10 CFR 50.61,", dated June 24, 1986.
I h 4 l
l l
l ZION FRACTURE TOUGHNESS RQMTS 3 07/14/86 t
l
. 1 MATERIAL PROPERTIES ASPECT The controlling beltline material from the standpoint of PTS susceptibility was identified to be intermediata to icwer shell circumferential weld WF70 (weld wire heat number 721055 The material properties of the controlling material and the associated margin and chemistry factor were:
Utility Submittal Staff Evaluation Cu (copper content, %) = 0.32 0.35 Ni (nickel content, %) = 0.56 0.59 I (Initial RTNDT, F) = 0 M (Margin,"F) ,
= --
59 CF (Chemistry Factor, 'F) = --
226.8 Discussion The controlling material has been properly identified, but the copper and nickel i
contents given for weld wire 72105 are not acceptable. In the staff evaluation, the copper and nickel contents tabulated above were taken from a B&W weld chemistry study,* which reported more than 50 measurements on this weld wire.
! The licensee's submittal is based on a Westinghouse report,** which presented 57 values from the B&W report plus 30 additional values from recent surveillance reports and elsewhere.
l l
l K. E. Moore, A. S. Heller, "B&W 177-FA Reactor Vessel Beltline Weld Chemistry Study," BAW-1799, July 1983.
- E. L. Furchi, S. L. Anderson, K. R. Balkey, V. A. Perone, and M. A. Weaver,
" Zion Units 1 and 2 Reactor Vessel Fluence and RTPTS Evaluations," WCAP10962 December 1985.
A histogram of the copper contents listed for heat 72105 in Table B.1-4 of the licensee's submittal shows that most of tha values added by Westinghouse fall in the range 0.22 - 0.28% copper, whereas most of the data taken from BAW 1799 range from 0.28% upward. Clearly, the values added by Westinghouse constitute a different population of weld wire from heat 72105, or the difference is a con-sequence of the different method used for chemical analysis. The latter is probably the case because most of the values added to the data base by Westinghouse came from two surveillance reports which gave x-ray fluorescence measurements on irradiated broken Charpy bars - a technique for which calibra-tion is more difficult. In addition, three of the added values are from early measurements on weld qualification samples which are now known to be in error on the low side.
The large number of copper measurements result from widespread use of wire heat 72105 in studies of low upper shelf toughness, in the investigation of " atypical weld metal" (BAW10144-A, 1979) and in surveillance programs. Heat 72105 was used with one weld flux to make welds designated WF70, which was used in several vessel welds. It was used with another flux lot to make weld WF209-1, which was used as t'he surveillance weld for several plants. Copper measurements for these two weld designations do not appear to be one homogeneous population, for reasons unknown. Weld flux does not affect the copper content.
Conclusion The primary observation to be made from the studies of welds made from heat 72105 is the broad range of copper contents represented -- for example, 9 of the 87 values are in the range 0.40-0.49% copper. One standard deviation is about 0.07%. In light of these facts, it seems prudent to use the higher average values of copper and nickel content tabulated above. Based on the staff's evaluation, assuming the reported fluence values are correct, Zion 1 will rea-h the screening criterion before the end of licensed life. (The staff's evalua-tion of fluence issues will be forthcoming from L. Lois, Division of pWR Licensing-A.) Hence, the Licensee should be asked to submit an analysis of possible flux reduction programs as required by paragraph 50.61(b)(3).
,