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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20210Q9991997-08-28028 August 1997 Safety Evaluation Concluding That Since 25th Tendon Surveillance on Few Yrs Away,Adequacy of Remaining Prestressing Force Will Be Critical to Verify ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20138H6671996-12-19019 December 1996 Safety Evaluation Accepting Util IPE Submittal in Response to GL 88-20 ML20134D7811996-10-24024 October 1996 Safety Evaluation Supporting Amend 51 to License DPR-73 ML20128L6741996-10-11011 October 1996 Safety Evaluation Accepting Third ten-year Interval for Pump & Valve Inservice Testing Program for Facility ML20128K1981996-10-0808 October 1996 Safety Evaluation Supporting Amend 50 to License DPR-73 ML20059D1771993-12-28028 December 1993 Safety Evaluation Supporting Amend 48 to License DPR-73 ML20062K1041993-12-0606 December 1993 Safety Evaluation Supporting Amend 47 to License DPR-73 ML20058F0311993-11-16016 November 1993 SE Informing That Changes to Pdms Requirements & Commitments List of 930115,does Not Constitute Unreviewed Safety Question,Nor Do They Involve Significant Hazard or an Environmental Impact ML20059K3001993-11-0808 November 1993 Safety Evaluation Supporting Amend 46 to License DPR-73 ML20057A3641993-09-0101 September 1993 SER Denying Licensee 930216 & 0416 Requests for Relief from Certain Requirements of ISI Program ML20056F0171993-08-0505 August 1993 Safety Evaluation Accepting Proposed Changes to Pdms Requirements & Commitments List of 930115 ML20128P7321993-02-19019 February 1993 Safety Evaluation Supporting Amend 171 to License DPR-50 ML20126M2861993-01-0505 January 1993 Safety Evaluation Granting Relief from ISI Post Repair Hydrostatic Schedule Requirements ML20058G1331990-11-0606 November 1990 Safety Evaluation Supporting Amend 39 to License DPR-73 ML20058P4681990-08-0909 August 1990 Safety Evaluation Accepting Changes to Table 4.3-3 of Recovery Operations Plan ML20247L0681989-09-11011 September 1989 Safety Evaluation Supporting Amend 35 to License DPR-73 ML20245J4411989-06-23023 June 1989 Safety Evaluation Supporting Util 850823 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability - On-Line Functional Testing of Reactor Trip Sys ML20247E8141989-05-18018 May 1989 Safety Evaluation Accepting Proposed Changes to Recovery Operations Plan ML20247G4131989-05-15015 May 1989 Safety Evaluation Supporting Amend 34 to License DPR-73 ML20245J1201989-04-27027 April 1989 Safety Evaluation Supporting Amend 149 to License DPR-50 ML20245A6521989-04-12012 April 1989 Safety Evaluation Supporting Amend 33 to License DPR-73 ML20196B3071988-12-0101 December 1988 Safety Evaluation Supporting Approval of Lower Core Support Assembly & Lower Head Defueling ML20153E6861988-08-31031 August 1988 Safety Evaluation Accepting Request for Exemption from Lecture Requirements of 10CFR55.59(c)(2) & for Exceptions to Control Manipulations Required by 10CFR55.59(c)(3)(i), Subsections (a) to (AA) ML20153E8471988-08-30030 August 1988 Safety Evaluation Approving Request for Mod of Recovery Operations Plan Table 4.3.3 ML20195B6991988-05-27027 May 1988 Safety Evaluation Supporting Amend 30 to License DPR-73 ML20155B3151988-05-25025 May 1988 Safety Evaluation Supporting Amend 30 to License DPR-73 ML20151D5611988-03-31031 March 1988 Sser of Util 870917 & 1103 Justifications for Proposals & & Relief Requests Re Pump & Valve Inservice Testing Program Denied in 870319 Ser.Exclusion of Stated Valves Accepted ML20150D5101988-03-18018 March 1988 Safety Evaluation Supporting Util 871027 Submittal Re Reconfiguring Main Steam Line Rupture Detection Sys Bypass Indicating Lamp During Cycle 8 Refueling Outage ML20147D9721988-02-26026 February 1988 Supplemental Safety Evaluation Supporting Util Use of Rochester Instrument Sys Model SC-1302 Isolation Devices,Per NUREG-0737,Suppl 1 ML20147E2491988-01-0808 January 1988 Safety Evaluation Supporting Util 871203 & 28 Requests to Use Core Bore Machine to Dismantle Lower Core Suport Assembly ML20237B1501987-12-10010 December 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components) ML20236T5611987-11-18018 November 1987 SER Accepting Util 831108,850805 & 870529 Responses to Generic Ltr 83-28,Item 2.2.1, Equipment Classification Programs for All Safety-Related Components ML20236M9221987-11-0505 November 1987 Safety Evaluation Supporting Util Proposal Re Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis ML20235S3241987-10-0101 October 1987 Safety Evaluation Approving Util 870724 Request for Staging of Two Radwaste Solidification Liners in Waste Handling & Packaging facility.TMI-2 Svc List Encl ML20237G5301987-08-12012 August 1987 Safety Evaluation of Util Response to Item 2.1 (Part 1) of Generic Ltr 83-28, Equipment Classification (Reactor Trip Sys Components) TMI-1. Util Response Acceptable ML20234B9701987-06-25025 June 1987 Safety Evaluation Supporting Amend 28 to License DPR-73 ML20212Q7341987-04-17017 April 1987 Safety Evaluation Supporting Amend 27 to License DPR-73 ML20206B4131987-04-0303 April 1987 Safety Evaluation Supporting Util 850416 Request for Deletion of Constraint of 20-ft Square Modified Penetrations Between Reactor & Auxiliary/Fuel Handling Bldgs.Expanding of Limit to 40-ft Square Acceptable ML20205C6161987-03-20020 March 1987 Safety Evaluation Re Util 860820 & 1020 Requests for Relief from ASME Code Section XI Requirements for Class 1,2 & 3 Components.Relief Should Be Granted Except for Requests 4 & 7.Insufficient Info Provided for Request 7 1999-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
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SAFETY EVALUATION '
- i. REVIEW OF TWENTIETH YEAR TENDON SURVEILLANCE !
THREE MILE-ISLAND UNIT 1 l
l DOCKET NO. 50-289 >
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1.0 INTRODUCTION
i ,
- The staff has reviewed the Three Mlle Island Unit 1 (TMI-1) toth Year Tendon 4
Surveillance Report submitted on April-7,1995 and supplemented by additional information-as requested by the staff and provided by the licensee, the GPU ,
i Nuclear Corporation, on November 29, 1995. The surveillance was performed in L
accordance with TMI-l Technical Specification (TS) 4.4.2 which requires the '
licensee to perform periodic tendon surveillance on 11 randomly pre-selected i tendons. The surveillance consists of sheathing filler material inspection and testing, tendon w ire inspection and tensile testingtendon grease leakagelift-off check, force tendon measurement, detensioning and retensioning, and grease r,efilling and resealing. The group l
! of Il tendons inspected consists of 3 dome, 5 horizontal and 3 vertical. .This 1- is in com i 1.35 Rev.pliance with the tendon number requirement of Regulatory Guide (RG
- 3. In addition to the 11 tendons ins
- areas were inspected for concrete crack growth.pected, 7 dom I. 2.0' EVALUATION i '
The staff has reviewed the results of the 20th year surveillance of the
! various elements of the post-tensioning system as contained in the report and j in tha licensee's response and clarification to staff's request for additional
," information. The staff found the licensee's tendon surveillance procedure to ;
be generally in conformance with the criteria established in the relevant TS
- - and the guidance contained in RG 1.35 Rev. 3. However, after an independent check of licensn's analysis of the tendon lift-off forces, the staff has-found-that the hoop tendon may go below the minimum required force starting in j the 25th year. This is in contrast to the licensu's conclusion of its '
i analysis that the hoop tendon will not go below the minimum required for the L rest of the 40 year plant-life. Therefore, the staff has reservation about the licensee's a discussed below.pproach and method of determining the tendon force levels as 2.1 Tendon Lift-Off Force
.The licensee has used the average values'_of the tendon lift-off forces instead- '
of individual tendon lift-off forces for each surveillance to study the trend of-the tendon forces for each group of tendons. In addition, the average *
.value for each survelliance is the average of the normalized lift-off forces. -
The use of such a procedure may result in-a trend which is not the trend of '
the actual lift-off forces. Instead of using the average of the normalized tendon forces the individual tendon forces as obtained from the lift-off of the-same group, of tendons should be used in the trend regression analysis.
The bases for such a procedurr tre: (1) the normalization factors (NF) are ENCLOSURE :
Fa' ifE! 74%"=,
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t-determined by the licensee on the basis of a method presented in a paper published in Nuclear Engineerin staff has some reservation licensee for the same thegroup, normalizedo(2)g tendon forces f tendons are not the same as the result of the andasDesign, shown by the October 1 and NFs (3) thebeing regression detemined analysis may on-the basis of subgroups be considered as a form of normalizat of a group of tendons, io process, and the regression line represents the means of the probability distributions of the tendon forces for each of the points of time. Therefore, it is inappropriate to take the avera surveillance for the trend analysis. le of the lift-off forces of eachThe licensee w analysis of the tendon force trend wi hout any averaging and by using the individual lift-off forces. The resu' ts of the re-analysis indicate that the hoop tendon force may go below the milimum required-force at about 26 years after structural integrity test SIT whichindicatesnotendongrouph(avin) its in forces contrast go to below the the original analysis minimum required force for the life of the p1 nt. Based on the data provided by the licensee the staff performed an independent linear regression analysis, by usingalogarithmicscalefortime,andfoundthatthehooptendonforcemay go below tae minimum required force at about 25 years after 51T. The result of the staff's analysis confirms that of the licensee. Since the next tendon surveillance is the 25th year one, it becomes very critical to see if this will be truly the case and to determine what corrective action is to be taken for such an eventuality.
At the staff's request, the licensee provided the force-elongation data as well as a plot of the data for the retensioned tendons. From the plots, as expected..there is a linear relationship for the dome and vertical tendons.
However, for the hoop tendon there is a kink in the slope of the line. The licensee attributed it initially to the compression of the shims with a finite thickness,-the validity of'which was questioned by the staff. It ap inaccurate measurement, most likely in elongation may be the cause, because pears that other data points can-be fitted on the same. slope,line. The force-elongation data on retensioning the detensioned tendon can be used as a check of the overall performance of tendon lift-off tests to see how carefully the surveillance was conducted. From the data provided. it appears that the licensee has conducted the tendon surveillance with reasonable care, despite
. the one inaccurate measurement.
2.2 Grease Volds The grease voids are determined from the difference between the grease removed and the grease added for tendons detensioned and retensioned. The difference should not exceed the 4-gallon limit. In cases where the 4-gallon-limit'is exceeded, an engineering evaluation of the discrepancy is requir6d.- According.
to the licensee. the 4-ga11on limit is derived from RG 1.35, Rev.- 3 and is .
based on 5 percent of net tendon sheathing volume.- It appears that the licensee has calculated the not tendon sheathing volume on the-basis of the average of the lengths.cf all tendons in the containment. The licensee used >
the average value of gallons of grease used for all the surveillances since 5 the-fifth year surveillance for.each group of tendons.as the criterion. For ,
each surveillance, the average of the additional grease used to fill the sheathings of the tendons inspected is used. The use of such averages does
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! not meet the intent of the RG 1.35 Rev. 3. The criterion of additional grease i
should be based on the 5 percent of the not volume of the sheathing of each
, individual tendon. For vertical and hoop tendons the limit for each sheathing expressed in gallons thould '>e the same,since each of the vertical and hoop tendons has respectively the same length. However, since the tendon lengths vary for the done tendons from the upper part to the lower I
done, the limits in gallons will vary with the lengths of tendons. part of the For cases when the added grease volume is less than that removed, it should not be treated ss presently by the licensee as a reduction of the additional grease for the 3endon grou). For such a condition, the licensee should provide an explanation as to-wiy less grease needs to be added. In spite of the deficie:icies in the licensee's procedure in analyzing the data. there appears to be little loss of grease discovered in the 20th year surveillance.
However, for future surveillances the licensee's method of analyzing the data should be modified to meet the intent of RG.1.35. Rev. 3 as discussed above.
The grease voids should be considered for each individual tendons inspected, if the licensee's intent is to assess the average grease voids for each group of tendons, a regression analysis of the leakage data for that group of tendons appears to be more appropriate. However, the basic concern of grease voids is that, with the presence of the voids, the tendon wires may not be protected against corrosion. Unless the wires withdrawn for inspection and testing show signs of corrosion, the need for such an analysis appears to be unnecessary. Even in such cases it will be more assuring to have additional tendons detensioned and wires withdrawn and inspected than to perform the analysis. Another concern is that missing grease may indicate grease leakage into concrete which may reduce the concrete strength. To reach such a condition, the leakage must be widespread and most likely there will be grease stains on the containment surface.
2.3 Anchorage Assembly and Tendon Wire The licensee inspected and measured the anchorhead threads to assure proper thread engagement during the lift-off, detensioning and retensioning. The anchorage components consisting of anchorhead, busing, shims, buttonheads and bearing plate were inspected for corrosion and cracks. Only minor surface corrosion and slight pitting were found on some of the components. There was no. evidence of cracking on any of the components.- With the exception of one wire in one tendon, no wires were found to be protruding or broken. The results of wire inspection and testing indicated that-the ultimate strength exceeded 240 ksi and the elongation at failure exceeded 4 percent in all sam >1es tested. Based on.the-information provided, we can conclude that the anciorage components and the tendon wires are in good condition.
In addition to the anchorage assembly and tendon wire, the concrete around the bearing plate was also inspected. No cracks greater than 0.010 inch were
.found for-the tendons inspected except around the two ends of a done tendon-wher(cracks as long as 4 inches and .020 inch wide were found. This is one
' of the- seven done teedons chosen to study the crack growth of the concrete around their ends. The licensee evaluated the crack growth and found it to be' acceptatie..
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3.0 CONCLUSION
Based on the review prestress in the hoo,)as described above, the staff concludes that the loss of tendon is more than predicted and it may reduce the hoep tendon force below tie minimum required force at about 25 years after the Sil.
Otherwise the overall condition of the containment tendon system is found to be satisfactory. Since the 25th year tendon surveillance is only a few years away, it will be critical to verify the adequacy of the remaining prestressing force. If it is found to be inadequate, corrective actions should be planned and taken by the licensee. The licensee should inform the staff of such finding and the planned action. The licensee should modify its procedure in assessing the grease voids for future grease inspections as discussed in this Safety Evaluation.
Principal Contributor: Chen P. Tan '
Date: August 28, 1997 i
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