ML20199A925

Rev 1 to ESR 97-00034, Engineering Evaluation B213R1 Core Shroud Insps

ML20199A925
Person / Time
Site:	Brunswick
Issue date:	10/31/1997
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20199A911	List: BSEP-97-0484, Forwards Rev 1 to ESR 97-00034, Engineering Evaluations B213R1 Core Shroud Insps. Util Will Keep NRC Advised of Any Significant Changes Resulting from Review,However,None Expected ML20199A925
References
ESR-97-00034, ESR-97-00034-R01, ESR-97-34, ESR-97-34-R1, NUDOCS 9711180152
Download: ML20199A925 (106)

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{{#Wiki_filter:. Carolina Power & Light Company ESR 97-00034 Brunswick Nuclear Plant - Unit 2 Revision 1 Engineering Evaluation Page n ESR 97-00034, REVISION 1 ENGINEERING EVALUAT!ON B213R1 CORE SHROUD INSPECTIONS NSSS - REACTOR SYSTEMS BRUNSWICK ENGINEERING SUPPORT SECTION NUCLEAR ENGINEERING DEPARTMENT CAROLINA POWER AND LIGHT COMPANY OCTOBER 1997 L l SAFETY RELATED O4 {[d** Erd!! y

ICcrolins Pow 1r & Ught Compsny ' ESR 97-00034. I Brunswick Nuclear Plant Unit 2 . Revision 1-Engineering Evaluation. Page'2 List of Effective Pages t e Page Number _ Revision = Page Number-Revision - ESR Cover (2 pages) 1 27 1

1 1

28-0-- 2 29 0 3 1 30 0 4 1 31, 0 5 1-6 1 - Attachment A 1 7 1 Attachment B 0 (pp.1 -8,10-30) 8~ 1 Attachment B, p. 9 1 g 3 Attachment C 0 10 0 Attachment D 0 33 3 Attachment E O 12. 1 Attachment F 0 13 1 14-1 15 0 16 1 17-1 .18 1 19 1-20 1 21 -1 22-1 l 23-1; I 24 -- 1 _ 1 b 26 0 I. l ,,4., .. ~ , _ _ _ _ _ _.... -. _ _. ~., - - -

am' +,.--> A 44,J-=1--f_.4.1-+- -.., s_ A,, 4: fr de w =.4si.cw.,_(.i.W,. a.i pise'-gri.J h i s- - ESR 97 00034 CtroliniPowtr & Ught Cornpxny . Brunswick Nuclear Plant.'t) nit 2. Revision 1-Engineering Evaluation Pago 3. t Table of Contents Page No. 3 4 ~ ESR Cover Sheets (2) Eva l u atio n C ove r Pa g e............................................................................................... L i s t of E ffect ive P a g e s.................................................................................................. Ta b le o f C o n te n t s................................................................................................................ ; 3 - 1.0 -Purpose............................................................................. ........................ 4 - 2.0 C o n cl u s io n................................................................... ....................... 4

3. 0 '

B a ck g ro u nd...................................,............................ .......................4 4.0 R e fe re n ce s................................................................ ....................6 5.0 lnspection Summary..................... .....................8 6.0 De s ig n I n p u t s..................................................................... ................11 7.0 Structural Evaluation Summary............................................ ....................12 8.0 S h ro u d F l u e n ce S u m m a ry..................................................................................... 9.0 R e a clo r Wa te r C he mist ry....................................................................................... 10.0 R e i n s pe ct io n I nie rva l s..................................................................................... 2 7 - 11,0 S a fe t y A n a ly s i s.................................................................................................. Figums 1 Core Shroud Inspection Coverage for 8213R1 (Rollout Dwg.)...............................10 2 8213 R 1 Shroud Evaluation Flow Chart................................................................. 15 3 Comparison of Weld H4 (North) Cruk Depths (2D)................................................. 20 3a - Comparison of Wdd _H4 (North) Crack Depths (3D) w/o 8211R1 Data.................... 21 4 Comparison of Weld H4 (South) Crack Depths (2D)........................,................... 22 4a Compa. 'on of Weld H4 (South) Crack Depths (3D) w/o B211R1 Data................... 23 5 Flue n ce J ra p h for a ll We Id s............................................................................ 2 5 6 Flue nce G ra p h io r Weld H4................................................................................. 2 6 Attachments A Core Shroud Inspection Plan. Unit 2_ B213R1 Outage, September 1997...... 7 pages B . An alysis Inp uts/Outp uts....................................................................... 3 0 pa g es C - DLL Software Program Benchmark........................................................... 8 pages ~D G E I ns pectio n Data..................................................................................... 20 p a g e s E Lcalc S pre ad sheets................................................................................ 7 pa g e s F Cycle 12 Hydrogen Injection Graphs....................................................... 2 pages --y.34 r-

Carolina Power & Light Cornpany ; ESR 97 00034 Brunswick Nuclear Plant - Unit 2 Revision 1 Engineering Evaluation 'Page 4 1.0 PUf1 POSE . This ESR-Evaluation is required. as part of Carolina Power andL Light Company's commitment to USNRC Generic Letter 94-03 ?Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors." As such, this evaluation provides the following: Documentation of the inspections performed on the Core Shroud during B213R1. e I e A basis for the continued use of the BNP2 Core Shroud for at least one additional operating cycle in the as-found condition without any. operational changes or restrictions. This is accomplished by a review of the core shroud structural capacity to the criteria established by the BWRVIP (references 4.6,4.7) and approved by the Nuclear Regulatory Commission.

• A basis for the determination of future shroud inspection scope and analysis methodologies.

2.0 CONCLUSION

S The BNP2 core shroud can safely perform its design functions in its present and e predicted condition for at least one additional fuel cycle without any operational changes or restrictions. All repoited cracking is typical IGSCC located in the heat affected zone of the e welds; a

3.0 BACKGROUND

in October,1990, RICSIL 054 reported cracking near the circumferential seam weld at the core beltline area of the shroud in a GE BWR/4 located outside the United States. Based on recommendations contained in RICSIL 054, the BNP Unit 2 shroud was inspected during the 1991 refueling outage. No cracks were identified.- The Unit 1 shroud was inspected in July,1993, and a near 360* circumferential crack was confirmed on the inside diameter of.the Top Guide Support Ring, at the weld to the shroud mid-section. The video tapes of the Unit 2 shroud IWI were re-examined based on the early July Unit 1 findings. Three smallindications were noted. Unit 2 tapes were again examined in late September. of 1993 based on lessons leamed on Unit 1. One additional small indication was noted. Although this additional indication was bounded by assumptions in the original evaluation, it was recognized that the quality of the 1991 video tapes was insufficierit to identify all of the types of cracks being confirmed on Unit 1. Engineering evaluation EER 93-0536 was issued to assess Unit 1 shroud structuralintegrity and justify continued operation of Unit 2 until a detailed inspection could be performed during the Spring,1994 RFO (B211R1). L .,e -... ~.., ~,,.,.., .. ~ --,+

Carolins Power & Light Company EsR 97-00034 - Brunswick Nuclear Plant - Unit 2 Revision 1 Engineering Evaluation Page S i The Unit 2 B211R1 shroud inspections were evaluated in engineering evaluation EER 94-0077. The evaluation concluded that structural integrity of the core shroud would be ~ maintained, with full FSAR safety margins, for at least the next 600 days of hot operation,- and for welds H1, H4, and H5, for at least 1200 days of hot operation based on analysis of the inspection results. Additionally, welds H2 and H3 were permanently repaired during B211R1 by the installation of-12 brackets 30 degrees apart about the outside circumference of the shroud. The B212R1 BNP2 shroud evaluation, ESR 96-00154, concluded that the Core Shroud could safely operate in the as-found condition for at least one fuel cycle without any operational changes or restrictions. All indications were IGSCC related. The B213R1 inspection scope was initially submitted to the NRC on June 12, 1997. Subsequently, the B213R1 inspection plan was revised to address questions and comments received from the NRC. Revision 1 of the inspection plan is included in this ESR as Attachment A. I +l y s w.+. .-e -w,.--. .4 wi. y ai~% --w ..~. .-e. n

Ccrolina Power & Light Company ESR 97-00034 Brunswick Nuclear Plant - Unit 2 Revision 1 Engineering Evaluation Page 6

4.0 REFERENCES

4.1 U.S. Nuclear Regulatory Commission Generic Letter, GL 94 03 "Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors," dated July 25,1994 4.2 U.S. Nuclear Regulatory Commission Letter to Mr. R. A. Anderson of Carolina Power and Light Company dated January 3, 1995 " Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors, Brunswick Steam Electric Plant, Units 1 and 2 (TAC NOS. M90084 and M90085)" including Enclosure 1 " Safety Evaluation for Unit 1" and Enclosure 2 " Safety Evaluation for Unit 2" 4.3 Engineering Evaluation Report, EER 94-0077, " Evaluation of Unit 2 Core Shroud Indications and Operability Assessment," Revision 0 dated 06/04/94 4.4 Engineering Evaluation Report, EER 93-0536, " Evaluation of Unit 1 Core Shroud Indications and Operability Assessment of Unit 1 and 2," Revision 2 dated 03/13/94 4.5 Engineering Service Requeet, ESR 95-00765, " Unit 1 Core Shrot.d Reinspection Evaluation," Revision 1 dated 05/15/95 4.6 BWR Vessel and internal Project, BWRVIP 01, "BWR Core Shmud Inspection and Flaw Evaluation Guide!ines," Revision 2 dated October 1996 4.7 BWR tessel and internals Project, BWRVIP-20, "BV R Core Shroud Distributed Ligament Length ComputerProgram," Version 2.1 dated December 1996 4.8 BWRVIP Inspection Committee document " Reactor Pressure Vessel and /ntemals - Examination Guidelines (BWRVIP-03),"TR-105696 dated September 1995 4.9 Structural Integrity Associates document RAM-94-092/ SIR-94-029, " Addendum to the Brunswick Unit 1 Screening Criteria," dated April 6,1994. 4.10 CP&L Brunswick Nuclear Plant - Plant Operating Manual-Volume X - Period Test - OPT-90.1, "In-Vessel Visual Examinations," Rev 20, dated 9/25/97 4.11 U.S. Nuclear Regulatory Commission Letter to Mr. J.T. Beckham, Chairman BWRVIP, dated June 16,1995 " Evaluation of BWR Com Shroud Inspection and Evaluation Guidelines, GENE-523-113-0894, Revision 1, dated March 1995, and BWRVIP Core Shroud NDE Uncertainty & Procedure Standard," dated November 22,1994 4.12 GE Document GENE-811-00682-1 Revision 1,

• Brunswick Nuclear Plant - Unit 2 -

Shroud Examination Plan," dated 2/2/96

Ccrolins Power & Light Company ESR 97-0o034 Brunswick Nuclear Plant - Unit 2 Revision 1 Enginecting Evaluation Page 7 4.13 Supplement 2 Report to GPT-90.1 "GE BNP B213R1 Inspection Summary," dated October 1997 4.14 Engineering Evaluation Report, ESR 96-00154, " Evaluation of Unit 2 Core _ Shroud Indications and Operability Assessment," Revision 0 dated 03/08/96 (8212R1) 4.15 Engineering Evaluation Report, ESR 96-00160, " Evaluation of Unit 1 Core Shroud Indications and Operability Assessment " Revision 0 dated 10/31/96 (8111R11 4.16 GE Nuclear Energy Document GENE-523-A028-0495, " Brunswick Units 1 and 2, and Hatch Units 1 and 2 Shivud Safety Assessment," Rev. 0 dated Dec 20,1996. 4.17 CP&L Calculation 1B21-1008, " Evaluation of Core Shroud Seismic Loads," Rev. O dated Dec 10,1993. 4 16 CP&L Calculation DB21-1012, " Calculation of Core Shroud Horizontal Wold Stresses," Rev. O dated Sept. 15,1997. 4.19 CP&L Calculation 1821-0049, " Application of GENE-523-123-0993, " Evaluation and Screening Criteria for the Brunswick 1 Shroud Indications to the Unit 1 Indications / Crack for BNP U1 Reactor Core Shroud Crack Investigation," Rev. O dated Nov 17,1993. 4.20 BWR Core Shroud Evaluation Report No. SL-4942 Rev. O, " Load Definition Guiceline," dated November 11,1994. 4.21 BWR Vessels and Internal Project, BWRVIP-07, " Guidelines for Reinspection of BWR Core Shrouds," dated February 1996

Carolina Power & l.ight Company ESR 97 00034 Brunswick Nuclear Plant Unit 2 Revision 1 l Engineering Evaluation Page 8 5.0 INSPECTION

SUMMARY

A copy of the CP&L 8213R1 shroud inspection plan which was submitted to the U.S. Nuclear Regulatory Commission is included in this report as Attachment A. Table 5.1 provides the B213R1 shroud inspection summary. Weld inspection % of Weld % of Comment ID Method Length Examined Examined Weld Length this Outage Flawed H1 No This weld was not it, aded in the B213R1 Outage inspection N/A N/A Scope. See ESR 96-00154 for previous performed inspection results. H2 No Shroud weld H2 has been permanently repaired by inspection' N/A N/A the addition of bolte'l clamps during 0211R1, performed j H3 No Shroud weld H3 has been permanently repaired by j inspection N/A N/A the addition of bolted clamps during B211R1. performed Two (2) 20" sections, one on the north side and one on the south side, which were previously examined in B211R1 and B212R1, These areas H4 Ultrasonic See bee were inspected to assess crack depth growth. comment comment Results indicated no detectable crack depth growth since B21161 within the uncertainty band of the UT measurements. This is consistent with 1 industry data on similar indications. Also, crack growth predictor models run last cycle using actual BNP water chemistry data (which is representative of the 12"' cycle run) indicated no measurable growth, as observed. 100 % of the accessible weld could not be 1.5 % HS Ultrasonic 0.0 accomplished during B213R1 due to tooling issues. No indications were noted. H6a No See Reference 4.14 for the previous inspection inspection 'N/A N/A

results, performed -

Carolina Power & Light Company ESR 97 00034 Brunswick Nuc/ ear P/ ant Unit 2 Revision 1 Engineerino Evaluation Page 9 ibio 5.1 - E h13R1 Shr< l l Wold Inspection % of Wold % of Comment ID Method Length Examined Examined Weld Length this Outage Flawed An additional 9.5% of the weld was inspectedf H6b Ultrasonic 73.0 84.3 this outage, and results indicate an increase ofl 3.4% in cracking of examined length, f I H7 See Reference 4.14 for the previous inspectior: N N/A N/A results. inspections performed H8 No BWRVIP develophg inspection tools / techniques. inspection N/A N/A j performed l HD No Wold H9 data obtained during inspection of RPV N/A inspections N/A Beltline "K" weld. Last inspected during B212R1 performed outage with no indications found. j i Shroud No BWRVIP developing inspection tools / techniques. Support inspection N/A N/A Legs performed Clamps VT-1 N/A N/A Three clamps inspected this outogo (azimuths 15, VT-3 45, & 225): no anomalies found. 1 l 1 i i 1 a 4 j

de 8, (., A.) U GE NuclewEnergy hff Brunswick Nuclear Power P. ant - Unit 2 {f gq ~s: Core Shroud Rollout Drawina } }, ;; ' n & ;j!* ma mw m m u m mmm m m m m m mm mm m mm m m m,,em a a o a ur a = n a a,e a,z 1 i i i i i i i i i i i i l 1 I I i I I i i I I I I I I I I I I I I l 'l l' 79 Ya sh7m a aa a aa n Te aa a ae ea a a a as aa rs e a e a Tf7 gg $g a v. n. V V Q- { g ] g [ Q { { g g g H2 Stroutt Annuth (Degees) mammmmmmmmmmmmmmmmmmmmmmmm,,am e a e e e a a n a am LIIIIIIIIIIIIIIIIIIIIIIIIIl IIIIIIIII1 F ssrert h-hN h h h H3 2ns) l2c,e L.,_'... !,2,e H4 3,f l 'S e sf

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.,i i,,, r,, r-- s HS 1 !we M nel _m e 34un.. % ;i--..- - = H6A _sme!

lin,

,2el H6B !we \\ H7 Leoend I. I Shroud Regions Examined Using Tri-Modal Search Unit m E - Flaw Locations ,y3 3 6' Figure 1 ag -a w o o+ 1 .1

- Carolin: Power & Light Company ESR 97-00034 Brunswick Nuclear Plant Unit 2 Revision 1 Engineering Evaluation Page ll OO - 6.0 DES!GN INPUTS The design inputs associated with this evaluation can be found in the references of Section 4.0, and the actual inspection data received from GE in Attachment D Table 6.1 below is a summary of some of the key inputs. Table 6.1 sam;m d@l*ADesiso #!autinergsAsegnptionswsumumma throud Parameter WeM Hi H4 HS H8A H88 ' M7 Comments / References Geometry: A.FP-50553 SNt 1 Rev A 1 Wood Elev from vessel rero on i 388 375, 317.375 219 250 183 250 179 250 127.188 0 FP45357 Rev 0 Shroud Mean Radius On > 94 00 88 00 88 00 88 00 88 00 84 75 Sheoud was Thichnees on ) 1 500 1.500 '1 500 1 500 1 500 1 500 ,$k33Ajdvels: SL 4942.Pey 0 load Dermann ownssane" NU Primov Membrane fosn f50 234 210 61/ 594 603

ptryses per Calculation N/U Pnmerv Bendma foot 483 1006 1814 2162 2204 2946

ce21 tot 2, Rev o Emeracnew Prn fosh 257 244 221 629 606' 617 Erne'agv Pb foso 637 1340 2434 2905 2960 3989 FauNed Primaev Membrane uso 818 844 821 1315 1292 1330 r

FouNed Primary Bert@na foso 641 1375 2500 3110 3176 4432 Fkut Strese f3Srn for 304ss) fose 50700 50700 50700. 50700 50700 50700 Nm = 16 9 ksi $afetv Factora: .. Por UFSAR Sec 3 9 5 2.t Normel/UowI 2 250 2 250 2 250 2 250 2 250 2 250 g BWRv: Pet Rev 2 r.mernency 1 500 1 500 1500 1 500 1 500 1 50_0 Fjtylled i125 1 125 1 125l 1.125 1.125 1125 Methodoloav innuta , Smylpet Rev 2 Cract Depth Ury'taetv f

• In i N/A N/A N/A N/A 0.106 N'A SWRVIP47 Feb '96 Crark Orru th Ra'e On Ihr )

5 00E-O' 5 00E-05 5 00E-05 5 00E-05 5 00E 05 5 00E@ . BMV1P43 Proximav Ceteria (7t) On i 30 30 30 30 30 30 iU (iengm) a $cluded m the GE especten mults Days Per Run Cvele 600 600 600 600 600 600 Proximg considered sier CO and thcortamty Hours Per Run Cvele 14400 14400 14400 14400 14400 14400 As inacasons pensusersJ thnmali except Heb Evoluaton Period (days) 2400 2400 2400 1800 600 1800 Flows teko compressinn Y Y Y Y Y Y pcgsorated m Ot.L Program j Fluence Vaiue at End of Life (proi) 12BE+18 5 86E+20 2 24E+20' 162E+18 8 82E +17 2 28E+14 .a?etEFpy Mswh rs+us) Accentance Crtteria: .BWRviP-20 (DLL Pmo'am) - Memched Lioament Lealc on ) M 159 166 190 215 215 224 . s:R 94429 e) Met Crack Oppth hw 360 flaw On ) 1463 1 451 1 429 1 398 1 398 1 372 per omvip c5 sectma 4 5 a

-.~ y Carolina Pow:t & Light Comp:ny ESR 97 oOO34 Brunswick Nuclear Plant Unit 2 - Revision 1 Engineering Evaluation - Page 12 - 7.0 - STRUCTURAL EVALUATION

SUMMARY

Core Shroud Evaluation Conservatisms/ Assumptions Assumed all areas uninspected are fully cracked through-wall and no credit was taken e - in analysis for these areas. Used 5x f 0

• in/hr crack growth rate in lieu of measured orpredicted DNP crack growth rates.

(Inspection results from the Unit 1 H5 and Unit 2 H4 welds showed no measurable crack depth growth.) Used maximum depths for reported flaws for entire length of flaw in lieu of actual e depths vs. length (profile) of flaws. (Applies for length evaluations only.) - UT consistently oversized the reported length on all flaws, e e Assumed 100% capacity factor for analysis. Assumed a 600 day cycle length for the next cycle. (548 days is predicted.) Applied UT uncertainty for depth on all flaws where specific depth limit load analysis e was run. Applied UT uncertainty for length as required. -e. Applied the Section XI proximity criteria for adjacent cracks. 2 Used the criteria described in BWRVIP-07 (Feb'96) for calculation of inspection e intervals on a weldby weld basis. Safety Factors The analyses contained in this engineering evaluation used safety factors consistent with Section 3.9.5 " Reactor Pressure Vessel Intemals" of the BSEP Updated FSAR which specifies safety factors of 2.25 for normal / upset,1.5 for emergency, and 1.125 for faulted - conditions. Weld Stresses The stress levels for welds H1 through H7 have been revised per reference 4.18 (see Table 6.1 for new values). The new stresses incorporate new reactor internal pressure differentials for GE-13 fuel under power uprate conditions, along with BNP specific shroud component weights, using the guidance of reference 4.20. Each weld has been evaluated for the new stresses. There was no significant change in th'e results. See Table 7.1 for more details. Weld H1 No inspection of weld H1 was performed during the B213R1 outage. The previous !nspection data was re-analyzed for the new weld stresses and shown to be acceptable until the next evaluation / inspection period.

~ .Csrolins Power & Light Cornpany EsR 97-00034 i Brunswick Nuclear Plant Unit 2 Revision 1 Engineering Evaluation Page 13

Weld H4 Two 20" areas were inspected for this weld as they were for the previous two outages. This weld is being scrutinized specifically for crack depth growth characteristics. H4 was chosen

~ because.of its elevation on the shroud, which places it in the highest fluence zone of all horizontal welds. One 20" area is on the north side of the shroud centered approximately on azimuth 137*. The other area is on the south side centered approximately on azimuth 257*. Two graphs for each weld have been developed which show the inspection results available to date. Considering the depth uncertainty of the UT technique used (10.106" per ref, 4.8), no measurable crack growth has been detected since inspections began in B211R1 (1994). Weld H5 The B213R1 inspection plan for this weld was to inspect 100% of the accessible regions. This was not accomplished due to tooling problems.- The upper and associated lower scans were obtained for 125.8 degrees The remaining accessible region was interrogated - from the lower side only for a length of 175.2 degrees. However, a cae sided scan is capable of fully interrogating 3 of the 4 HAZs. Therefore, it is appropriate to consider the one sided scan as at least 75% of the length examined. As a result, the total effective l length scanned is computed as follows (see Figure 2 and Attachment D): l Accessible weld length = (171.3 - 13.30) + (341,1 - 198.1) = 301.0" Accessible weld length = 83.6% of total weld length. Considering 75% of 175.2, the effective examination length = 131.4 4 Therefore, the total effective length of accessible weld inspected is: 125.8+ 131.4 = 257.2*, which is 71.4% of the total weld length, and 85.5% of the accessible weld. No relevant indications were seen in the regions inspected. The indications noted during the VT examination in 1994 were deemed to be geometric indications associated with the weld itself and not associated with typical IGSCC indiJations. 'Although 71.4% of the total weld length was fully L1rpected, the ligament length determination for H5 only took credit for the two sections (encompassing 125.8*) that were scanned from both -~1e upper side and the lower side of the weld. A detailed limit load l analysis was then performed which, in addition to the segments inspected from both sides, also took credit for the portions inspected from the lower side. Since a lower side scan can L fully interrogate three HAZs and the fourth HAZ for crack depths 20.30", the portions -inspected from the lower side only (totaling 175.2*) were assumed to have a uniform 0.30" crack depth. This is considered to be very conservative in light of the assumed high crack - depth growth rate and the fact that no relevant indications were observed in the examination of-71.4% of the total weld length for H5. 1

Ctrolina Power & Light Cornpany ESR 97-ooo34 Brunswick Nuclear Plant - Unit 2 Revision 1 Engineering Evaluation Page 14 Weld H6a No inspection of weld H6a was performed during the B213R1 outese. The previcus inspection data was re-analyzed for the new weld stresses and shown to be ecceptable until the next evaluation / inspection period per the requirements of ref. 4.21. Weld H6b 100% of the accessible areas of H6b were inspected this outage. Improved operator techniques have increased coverage by 5.9%. A plant specific analysis was performed on this weld due to its high ratio of crack length to length inspected. The results of the analysis shows that the weld is good, as is, for at least one additional operating cycle. The crack depth data from this inspection is in the process of being compared to the data collected from the B212R1 outage. The preliminary conclusion is similar to that of H4. The inspection plan for this outage included the use of a " Phased Array" technique on weld H6b. This technique was not implerNnted because of tooling problems encountered prior to and during the outage. The scans performed on H6b used the same technique as used during the B212R1 outage (last outage). The inspection process and data for this outage were witnessed by representatives of the Electric Power Research Institute (EPRI) NDE Center. They concurred with the analysis methodology used to obtain the depth and length results of the 1997 data. The 1906 data is being sent to the EPRI NDE Center for review to investigate the apparent different s in depth of indications. Weld H7 No inspection of weld H7 was performed during the B213R1 outage. The previous inspection data was re-analyzed for the new weld stresses and shown to be acceptable until the next evaluation / inspection period in accordance with ref. 4.21.

Carolina Power & Ught Comp:ny ESR 97-00034 Brunswick Nuclear Plant - Unit 2 Revision O Engineering Evaluation Page 15 r%V Inspection Strategy for Category C Plants per Figure 5, BWRVIP-07 (2/96) Status of BNP Unit 2, Pout B213RI Outage Haeoline inepections are oosspists forall' Welds. E@M7 ! If 100Kyrsoesssihie-regiolihipes boon u

inspnoi(d. HI L H7-1f kI

( ' Mji' - 1 Evaluationi No s S883Efted75. 11(6 - gg l litEl#R hffhd OMG LMIEC lll 111 813 38 5 3/96 Il212RI IM y,, 17 114 78 0 33 1 6H Il211RI 115 = 115 71.4 00 9:97 11213RI Il6a = Il6a - 79 0 $.3 3<96 il212R1 If 117 (Case-Speciftcf, i17 73 6 10 9 396 11212RI InsMiionInleeval:

wan

' O"* ' Descemine Cracking SN Yes ininspected Region; $y. No iktermi_neinspection Intetral'per Figure 6: Interval Next inspecton nf BWRVIP 07 ~ V Lut) Dele / Outage til 17 N 99 = ..Untermine Inpacction 114 5.2 amn N 99 innsrval portable 11 ils - 10 03,05 of BWRVIP.07.c 136*

• 80 03 03 117 80 03 03

( Figure 2

~ I - Carolina Power & Light Company EsR 97-ooo34 Brunswick Nuclear Plant - Unit 2 Revision 1 Engineering Evaluation Page 16 Full Thickness Llgarneft Evaluation Methodolony This ESR utilizes the Distributed Ligament Length (DLL) program primarily as a means to illustrate end of evaluation period safety factors. BWRVIP-07 criteria is used to establish projected reinspection intervals based on maximum combined stresses and % cracking for welds H1, H4, H5, H6a, and H7 (see Table 10.2). With the exception of the H6b weld (site specific partial thickness evaluation), DLL output is provided only to maintain consistency with past evaluation methodulogy, it should be noted that a revision to the DLL program to allow flawn to take compression has resulted in a significant increase in the calculated safety factors as contpared to the version of DLL used for previous evaluations. Step 1 - Collect information The full thickness ligament data is extracted from the verified GE inspection summacv sheets and input into a spreadsheet. All uninspected regions as well as partial thickness ligaments are assumed fully cracked. The following spreadsheet variables were also input for each weld location evaluated: Variable Comment Shroud thickness (tn) 1.50" (No credit taken for any fillet welds ) Shroud outside diameter 189.5"; H1 177.5"; H4, HS, H6a, H6b 171.0"; H7 Crack Growth Rate 5x10

• in/hr TotalInspection Uncertainty Reference 4.8. See spreadsheets (Attachment B) and/or Table 7.1 for specific values used.

Evaluation Period Used at least 2 cycles of crack growth for all full (1 fuel cycle assumed to be 600 days) thickness ligament evaluations. Lcalc (for Normallupset, Emergency and Faulted) Reference 4.9. See Attachment E spreadsheet outputs for values. 4 From this information the sp'readsheet calculates the weld L,n,n value, the total full thickness ligament length at the end of the evaluation period and the full thickness ligament starting and stopping azimuths. Crack growth, inspection uncertainty and crack proximity are considered in determining end of evaluation period full thickness ligament length. Step 2 - Determine if Limit Load Analysis is Required The total full thickness ligament length at-the 'end of the evaluation period (L ) is compared to L n. If L was greater than Lon, then the we!d was considered structurally qualified for continued service for at least one fuel cycle, if L was less than Lon, then a detailed limit load analysis using the DLL computer program (reference 4.7) is performed.

' Ctrolina Power & Light Cornpany ESR 97-00034 Brunswick Nuclear Plant Unit 2 Revision 1 Engineering Evaluation Page 17 Step 3 - Perform DLL analysis End of evaluation period full thickness ligament data is input into the DLL computer program along with other required variables. See the DLL computer run outputs contained in Attachment B. Shroud stress values are obtained from reference 4.18. Step 4 - Determine if Weld is Structurally Qualified if the required UFSAR safety margins are met, the weld is considered structurally qualified for continued service fr at least one fuel cycle. If the required safety margins are not met, - then the process (Steps 1 - 4 ) is repeated with iteration on evaluation period down to 600 days. If a weld can not be structurally qualified by the full thickness ligament length method for the specified minimum evaluation period, then the partial thickness ligament analysis method is used. Partial Thickness Liaament Evaluation Methodoloav (Welds H5 and H6b) Step 1 - Collect Information The partial thickness ligament depth data is extracted from the verified GE inspection summary sheets and input into a spreadsheet. All uninspected regions are assumed fully cracked. The spreadsheet calculates the new ligament lengths at the end of the evaluation period (600 days). Additionally, the partial thickness ligament starting and stopping azimuths are calculated. Crack growth (5x10 in/hr) and inspection uncertainty (0.106") were considered in the determination of the end of evaluation period ligament depth. Step 2 - Perform DLL analysis End of evaluation period partial thickness ligament depth data is input into the DLL computer program along with the other required variables. See the DLL computer run output for welds H5 and H6b. Shroud stress values are obtained from reference 4.18. It should be noted that the DLL analysis for weld H5 was only performed as a partial thickness ligament evaluation to provide a more realistic assessment of end of evaluation period safety factors by takina credit for the scan data from the lower side of the weld. See the discussion on page 13 for additional details on evaluation of H5. Step 3 - Determine if Weld is Structurally Qualified. If the required safety margins are met, the weld is considered structurally qualified for continued service for at least one additional fuel cycle. 1 n,

' Carolins Poiver & Light Company ESR 97-00034 Brunswick Nuclear Plant ? Unit 2 Revision 1 Engineering Evaluation Page 18 . Table 7.1 - Evaluation Summary - Shroud Circumferential Welds ia Eve 6ueuen . Evaluation -. Analysis Summary /Results [ . Wold Evolustion Inspeceon 10 - N. -. ___ 8 'J -. r, . Period Method i/'i (in) -(days), v m _____ H1' 23.1 %U 0.0 2400 "' Lon '"

• Acceptable for Cont:nued Operation
• Weld H1 is not a safety significant weld 83,3%L (length)

Satisfied

• All cracks assumed through-wall (B212R1)

/

• Uninspected regions assumed ftlly cracked
• Based on conservative evaluations (ESR 96-00154) that were performed on the deepest flaw found from the upper and lower examination, the safety factors 4

based on the upper data were greater than 3 times those for the lower data, therefore the lower exam data was used for the structural analysis. H4' 78.0 % 0.372 2400 L,

• Acceptable for Continued Operation
• UT insp'ection data from s1211R1 (B211R1)

(Icngth) Satisfied

• All cracks assumed through wall
• Uninspected regions assumed fully cracked HS-71.4 %

N/A 600 Limit Load

• Acceptable for Continued Operatiori (3213R1)

(length) Analysis

• No relevant indic6tions with 71.4% of total weld length inspected
• Assumes a uniform crack depth on the upper side to be 0.30" per UT limits for lower side exam data (see page 13)

{

• Uninspected regions assumad fully cracked 1H6aJ 79.0 %

0.0 1800 "' L*

• Acceptable for Continued Operation All cracks assumed through-wall

. (8212RI) Dength) Satisfied

• Uninspected regions assumed fully cracked

-.-fH6b1 84.3 % 0.108 000 Limit Load

• Acceptable for Continued Operation (B213R1) l'iepth)

Analysis

• Partialligaments analyzed i

(H7f * ' 75.6% 0.0 1800'" L*

• Acceptable for Continued Operation (821?R1)

(length) Satisfied

• All cracks assumed through wall Uninspected regions assumed fully cracked a

H9 --

.98% g No indcations requinng engineenng evaluation were reported. No analysts required for we6d H9 a ( l See next page for notes L 1 .-.w w <w.

Ccrolio e Pow:r & Light Cornpiny ESR 97-00034 Brunsw,hk Nuclear Plant Unit 2 Revision 1 Engineerag Evaluation Page 19 Notes to i nble 7.1 (1) Evaluation Percentage = The percentage of total weld circumference on which the strtctural evaluation is based. Remaining percentage is assumed fully cracked. For all welds, the remaining percentage is the uninspected percentage. (2) Inspection uncertainty from Reference 4.8. (Welds H1, H6a, H6b, H7 ; UT Demo 16; Scan Type 2A; Surface = ID/Near; Length transducer = 45' Shear; Depth transducer = 60* Longitudinal.) Weld H6b was structurally qualified by taking credit for partial ligament thickness. Therefore, the uncertainty was applied 5 the depth measurements where partial ligament credit was taken. (3) Circumferential shroud welds H1, H4, H6a, and H7 were not inspected during the B213R1 outage. (Two sections of H4 were reinspected for crack depth growth during B213R1.) The inspection data from the B211R1 and 8212R1 outages were used in the structural evaluation. See Attachment B for evaluation periods used in the current analysis. (4) Lon = Minimum required ligament length for limit load single ligament analysis = L, + (2 x Crack Growth for Evaluation Period) t Inspection Uncertainty. Since L,n at the end of the m evaluation period is satisfied (L. > Lon), a detailed limit load analysis is not required to show structural acceptance. A limit load analysis was performed for these welds in order to determine the safety factors used in this report. (5) Circumferential shroud welds H5 and H6b were analyzed using partialligament thickness. For H6b, measured thickness data was reduced to account for growth and uncertainty. For H5, a uniform crack depth of 0.30" was assumed for lower side only exam data (where one of the upper side HAZs could not be fully interrogated), which was further reduced to account for crack growth and uncertainty. The crack growth calculation used a run time of ? 600 days (1 fuel cycle). Actual projected length for fuel cycle 13 is 548 days. 1

O O O ste r-3 ib'2 % u-Brunswick B213R1 Shroud Weld H4 (North) f!j Crack Depth Comparison of B213R1, B212R1 & B211R1 Data g-- 3 79 130 gg 1.40 "4 1 30 120 1,10 1 00 E[ ! B21sai o.t. i / r 1----- -$ o 7a _/ I f_ 0,,, ._ _k _/ I '/lA I g g i

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I'd A

. xM _I I \\\\! 0,, ,, L JM / L sm q,jro 4 yi e222ai o.t. - 131 40 132.60 133.80 135 00 13620 137.40 138 60 139 80 141.00 142.20 143.40 144 60 145 80 Azimuth Position (deg.) B212R1 Data - -8211R1 Data 8213R1 Data Figure 3 J*Yo e., 8

• i

. O m $. t i

1 e e e =y9 T !=ar .t. ?% mg*n Brunswick B213R1 Shroud Weld H4 (North) {g; Crack Depth Comparison of B213R1 & B212R1 Data y=g ~ ,so/ i El -~ 1 40 130 / im w i..o / l 8 ,x ( E,, (f j s213a1 oata j s B om / A B212R1 Data I k d 010 ia / '\\ l 1 o. 3 a3a / LE \\ .Il a. a iA la y o.., / Un' \\NL .N M M\\ J M l / [(f '\\ w lLT i J Y n l'1 1 ~ o,, li % Ar ' Y' 1' VUl 4. 1 o, T \\A// 1 LWR O H o,o oTafe"ing",I Ide'ie11' ins ";;" "i"bi)"!b Vaa"ia= ?b'" ""' l Azimuth Position (deg) m B212R1 Data a B213R1 Data Figure 3a G

n a"U*3$

b 6 ='. 8 5 ? J g

O O O. s E 2 =kI 3'k l Brunswick B213R1 Shroud Weld H4 (South) [@$' Crack Depth Comparison of B213R1, B212R1, & B211R1 Data 7 p-1= Ef, 2.5 4-tM ,2a B211R1 Data [ 1 10 i 8212ai m i \\ 1 ^ g a,0, \\

7. s21= = l m

= s L_f s 30. 4 , Mq ! g_ _ _ _, i i 5,l /T{ T gf gg ],5, 1N_.i f f l. I i kll h/ Ill at v i i - 1 3 g g g-0. r I ip O

I

}'! _ta 0. g -- Q L g'V) 0 20 j [ P l. I \\ Tl. ! \\ / li_ h 240 36 241 40 242 30 243 50 244 40 246 05 24710 250 25

• 251 45 252.30 253 25 254 45 256 50 Azrnuth Poseon (dog) l B213R1

- -8211R1 B212R1 i Figure 4 ' 5x $=ag a8o N _. E - m..m. m - a v. v

O O O g in o .ae r ,T R}!g- ) m E l, sg t.,,n. Brunswick B213R1 Shroud Weld H4 (South) &3e = = 5t Crack Depth Comparison of B213R1 & B212R1 Data 79 . f 4. - ~ I Mk t so 1 40 1" B212R1 Daes -- \\ 'i 8213R1 Data; g 1 to 1 00 \\ / 7 oa . 80 ~ 7 g q l A s sn E .r w A a c oo y l yg g y ? o so -~, ~ ~~~ ~, %g g ~f A aa 1 1 .fi ~{- V i -% A l ";,/ ) d...................... v...... '. L...... L M/ 2.,. m. m 2.e. 2.z,. m, m. m, Azimutn Poodion (dog) l mB213R1 m B212R1 l l i j. ??8 l i SEg l MS l w Vak-

'Corolina Power & Light Cornpany ESR 97-00034 Brunswick Nuclear Plant - Unit 2 Revision 1 . Engineering Evaluation Page 24 8.0 SHROUD FLUENCE

SUMMARY

Based on current industry evaluation guidelines, in order to ensure structural integrity, a linear elastic fracture mechanics analysis (LEFM) should be performed when the total neutron fluence accumulation at any shroud circumferential weld reachts 3x102 n/cm, 2 2 E>1MeV. No BNP2 shroud weld will reach the fluence threshold level (3x10 ' n/cm', E>1McV) for LEFM analysis during the next fuel cycle. The only weld expected to reach this. threshold level during the current operating license of BNP2 is H4. Figure 5 shows the peak neutron fluence levels expected for each shroud weld at 29.3 EFPY. These projections are based on the flux data supplied by Westinghouse specifically for Brunswick - based on CP&L supplied information of Core power distributions including fuel assembly burnups and relative axial distributions of both fuel burnup and core void fractions for each of the first eleven fuel cycles utilized at Brunswick Unit 2. An alternate method of accounting for high fluence areas is to assume the areas of the weld that have exceeded the threshold fluence are fully cracked. This method was used for the qualification of H4, even though H4 will not reach the LEFM fluence threshold until after 8214R1. Figure 6 shows a plan view of the fluence shape. The most significant peaks occur at approximately 45*,135*,225*, and 315*. For the H4 weld, a zone extending 15* on either side of the peak azimuth was assumed fully cracked. As shown in Figure 6, the computed primary LEFM affected zones are 23.14 wide at the end of plant life. Thus, 30 is conservative. H4 is projected to reach the fluence threshold in January, 2001. The secondary fluence peaks for H4 are projected to reach the LEFM threshold in March,2011. This method is considered to be conservative based on the fact that no credit is taken for the areas that have exceeded the threshold and the existing evidence that the threshold 2 itself is considerably higher (8.0E+20n/cm ), based on testing of material properties that 4 have experienced higher fluence levels (see ref. 4.21). 9.0 REACTOR WATER CHEMISTRY The graphs contained in Attachment F show the hydrogen water (HWC) chemistry data for f the Unit 2 operating cycle 12. This information is provided to document HWC injection flow rate, a parameter that is known to affect the crack growth rate for IGSCC phenomena. y 9 -<-ns

,. _ _ - -. ~. _.. -.... _ _ -... -..... -. - Carolins Powsr & Light Company ESR 97-00034 Brunswick Nucl:tr Plznt - Unit 2 Ravision 1 Engineering Evaluation Page 26 O [ Peak Shroud Fluence g 29.3 EFPYl Fluence (Ncm-2, E>1.0 MeV) Trnes 1E+18 10000000E.18 100 200 300 400 500 600 700 LEFM Threshoki 2 ) (3E+20 Ncm 2) H1 f i I f O -^ 1 c R H5 l t l H68l i ( 1 I h f g, t n } e ID Fluence e Fluence g Mean Radsus l t 1 l m oo Fiuenc. i-Figure 5 L ,_4

O O O

• 70 9

.V "= a l i 4 .4- &Rm m o mq N ~ BNP H4 Weld -Shroud inside Radius Fluence vs. Time a.? > - a4 c wm E@@n ' l ~N

• ud 9

6E+20 h i [j 23.14 deg LEFM zone [ at 29.3 EFPY ~ N.. / / .,.., f N ,.{xe. - s N / s.. 3E+ J / g.' ,3( s ',f., 10.19 deg / '\\, [' ' t LEFM zone / 'N 1 '} '-{. ) f, .?f- ,j- ~ I' f.f,?/) Of-f '*., [ (. jd v 'q.^4j j _ secondary sur zone r e \\,: / .C v. y ~ crosses LEFM \\.- threshold Mar. 2011 t f :.. /'3 ,7 / ,/ ./ ~ ,/ \\

---

.. B215R1 Ruence l

/ %._ d,/ - _ _._ a3 em noene. './'/ LEFM Threshold Primary fux zone crosses LEFM threshold Jan 2001 I E! x Figure 6 ., y e =< O--- %3 p D OA

Carolin2 Power & Light Cornpany ESR 97-00034 Brunswick Nuclear Plant - Unit 2 Rivision 1 . Engineering Evaluation Page 27 ,9O 10.0 REINSPECTION INTERVALS Table 10.1 below sumrnarizes the_ data that was used to compute inspection intervals in Table 10.2 for the subject Core Shroud welds associated with Unit 2. Table 10.1 Wold Data 'andjnspostion Status fof the Bamswick.UnN 2 Core Shroud as.'odet08lthaim mese n DATA 1 uma n DE*=_^TIONj N1 ! M1 I He l H8 l' HBa Heb I M7 Commes.ts PWled bwarID - OD un/bw ID un/bw OD - fD beerID - ID BehlL9[P9 Min 5ptOdhlkLlMel3feld jepath f%) 10 3 23.1 78.0 71.4 79 0 84.3 75.8 as of B213R1 andpagt9@m Pyqqfig[bsp,qtp(jygA[qyn(gggk,d_,, 38.5 36 33 1 00 51 73 0 10 9 IncludogLngpejo.ALingedegt)L fadedtensleyAI2ntifD1 (Ksn 1.5 1.5 24 34 .44

15. _

58 famtmedsna19m_Ishbil. l'W80/91 ptMYff0Z.12/991.If>t_1_ lyt #31 37 TBD 57 10 8 SpeytSc 8 in.Jefpohttoavse(sh Dates [last#wpectenlexdudro pattutal MML _%9e sS4 Sf92_. _ 190 _ JEDI._. 198 Qveas,t9afte9(pedtaGAukteolders) 149Q.__.24JXt 2400 ego 1800 soo 1190 Dett PID94EmptflGO.pqfjWRVIP47 _1))99 TBD 1%._.p(QZ._ _204 1 Cvele 3/QL, TBD = Ig.Dgjetecngtgq_ Oia-nrw to reachana tr~-etad irie i B214R1 J214R1 B214R1 B218R1 B218R1 B214R1 B218R1 Table 10.2 was derived using the BWRVIP-07 " Guidelines for Reinspection of BWR Core Shrouds (Feb. '96) (ref. 4.21). O it snouid be noted 1het toe BwRvie-07 docement oes recen119 been reviewed bv tne NRC. An SE was issued with comments to be resolved. The information contained in Table 10.2 is subject to change based on the results of the Safety Evaluation comment resolution. OG

C1rolin's Power & Light Compzny ESR 97 00034 l - Brunswick Nuclear PI:nt - Unit 2 Rsvision 0 Engineering Evaluation Page 2.8 O l Table 10.2 . Core Shroud Reinspection intervals for Category C Plants I cracking % l (vrs.) l (vrs ) l (vrs.) l (yrs ) l (vrs.) l (yrs.) (yrs ) l (vrs.) l (vrs.) l l 0 l 10 0 l 10.0 l 10.0 l 10.0 l 10.0 1 10.0 10.0 1 10.0 l 10.0 l l l l >0 to 10 l 8.0 1 8.0 I 8.0 l 8.0 l 8.0 I s.0 8.0 8.0 l 8.0 l l- >10 to 20 l 8.0 8.0 l 8.0 l 8.0 l 8.0 l 8.0 8.0 8.0 1 8.0 l-l >20 to 25 l 60 60 l 6.0 l 6,0 l 60 l 6.0 6.0 6.0 l 6.0 l I >25 to 30 l 60 60 l 60 l 6.0 l 6.0 l 60 60 6.0 l 6.0 l l >30 to 35 l 5.8 5.7 l 5.5 l 5.3 l 5.2 l 4.9 4.9 4.6 l 4.5 l l >35 to 40 l 3.8 3.7 l 3.5 l 3.3 l 3.2 l 2.9 2.9 2.6 l 2.5 l -l >40 l Specific Specific l Soccific l Specific l Specific l Specific Specific Specific l Specific l Core Shroud Reinspection inAervals for Category C Plants OM' l Crackino % I (vts ) l (vrsl (vrs ) l (vrs ) l (vrs.) I (vrs.) l (vts.) l (vrO l (vrs ) ll I O -l 10 0 l 10.0 10 0 l 10.0 l 10.0 l 10,0 l 10 0 l 10,0 l 10 0 R l 50 to 10 l C.0 l 80 8.0 l 80 l 8.0 l 80 l 80 l 8.0 l 8.0 l l >10 to 20 l' 80 l 8.0 80 l 8.0 l 7.7 l 7.1 l 7.0 l 6.1 l 6.0 l l >20 to 25 l 6.0 l 60 60 l 60 l 60 l 60 l 60 l 6.0 l 6.0 l l >25 to 30 l~ 6.0 l 6.0 6.0 I 6.0 l 5.7 l 4.8 l 4.7 l 3.6 l 3.4 l l >30 to 35 l 5.6 l 5.4 5.2 l 4.9 l 4.6 l 4.0 l 3.9 l 3.0 l 2.9 l [ >35 to 40 l 3.7 l 3.5 3.3 l 3.0 l 2.9 l 2G l 2.6 l 2.2 l 2.1 ll l_ >40 l Specific l Specific Specific l Specific l Specific l Specific l Specific l Specific l Specific l Table 10.3 Summary of Wald Safety Factors at the End of Evaluation (ref. Attachment B) Load Case \\\\ Weld No. H1 H4 HS H6a H6b H7 Normal Upset 21.29 15.30 16.51 17.85 10.86 10.14 Emergency 17.47 11.99 12.59 13.93 8.53 7.81 Faulted 10.46 8.41 9.91 11.11 6.79 6.23

k ESR 97 00034 Rev,0 Page 29 l ATTACHMENT B s s Guideline for 10 CFR $0.69 Safety Evaluations j 11.0 SAFETY ANALYSIS r ATTACHMENT 1 i . Page 1 of 5 i 10 CFR 80,69 Safety Evaluation ScieenPage 1 of.L ACTfVITV NO. EOR of 4 034 REV. 0 [ 1. DOE 8 THE AC TMTY REQUWtt A CHANGE TO THE OPERATWO LICENSE OR TECHNICAL. SPECIFICATION? l)Yt8 {AjNO f Senes(Tf 4e ($44ggin3 nggrina f valuellen which Gw _. the structural rf* _1, of the Reacter Core throud bened on me 3 6 l inecedens certurmed dwina the 9? ort outane No chvocal onent memcatons or caeroponer reeMirsas evenwered as e reevet of thes t $84 Therefore. tNs ISR does twd recure e che'ee lo the noseoten konge or toencel epocAcetm foote: If Yes, and the etope of the ocevity le limited to e T6chnacel Speelmeetionf0perating Licono change, then composte 6vetten es of thee form, and procoes por procedure. If the scope of the utivity le not lemsted to e Tech. er OL change, in edenson to processing e imA Spec, or change requee* tonUnve the screening protese. W No, continue the screen 6ng procoes. 2. IS THE ACTMiY (UMY DOuteDED SV A PREVIOUSLY PERFORIAEO 10 CFR 9e.99 SAFETY EVALUAflON7 (AjYES ()NO Evoluetten No, The enggLegent 18CFR 80 H Sofstr Leglyejlen33g!!agigt JL814 7 sowieggjiant.ggetIGLgghgigs wptt.le8erett694 le one fved cycle, The conclyteone from ESft $g0!44 shour that the reentred setetv marmine are mes% !PqgLgne addigspnet fuel cries icycle 01 Therefore me artyegtgjelglE.. - tre concede od Sounens ? _^^^^ r_ e senerte selogy i Ottttte!!Pnigp!!rgvg weeg s Nurse wesEpit!I9flyJhtjnf.R. OO in 1984

• hroud Crocouna Genorte Safetrhment"M84z e

NF-A10FP47R Revepsyyn,gvot 994. A Seep esent opetsfic speseement wee provtqleti m ressorse to Generte Lemor 8443 i Note: If Yes, ettech a copy or provide document nummer for regiovel capeldetty of the provnove8y performed it CFR 80.H Ssfety Eveive on end compiele Section e of th:a form. W No, conunce the screenene procees. 3. DOES THE ACTMTV IAAKE CHANGES TO THE FACILITY AS DESCRIBED W THE SAR? [ j YES [ J NO Beste: List SAR loomellec.ione reviewed: e 4. DOES THE ACIMTV RAAkt CHANGES TO PROCEDURES AS DESCRISED W THE SAR? (jYES (JNO Seele: List SAR home/Soctione reviewed: 8 DOES THE ACTMTV INVOLVE A TESI Oft EXPERieAENT NOT DESCRIGED W THE SARt (]VES [JNO Boo 6e: List SAR Pomettnet6ons reviewed: } NOTE: if any guestion a through 6 le enowered YES, then mere Soit6on e6 Not Apphcoats (4A) and comp 6ete Untevtowed Safety Quesp.wi Determinet6an otherwooe complete Section es. 6. DISCIPLWE PMWT NARAE S3 NATURE ist QSR: Structural i Larry Yemme i Nef se Date: 10/1997 Other QSR: i f Dete; - Other QSR: i t. Date: l N.l.[h oeio: if /., and QSR: Msmaim ! 64Aa r. Owe = ARech e u,uonei.h.eten needet f . ) 10 CFR 50 59 - Rev. 5 Page 13 of 37 OAl 109 Rev,9 Page 25 of 54 .--y, -r#-v-

• y-

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i ESR 97 00034 Rev. O Page 30 -[ ATTACHMENT C Page 1 of 2 l hem Classmcation Form DOCUMENT NO. ' ESR 97 00034 REV. NO. O mM t 1. Does this item (including temporary changes to the faciltty or procedures as [] [X] desenbod in the UFSAR) require a revision to the UFSAR? (See Section 5.0 of 0Al 109 for instruction). 2, Does this item involve a change to the Off Site Dose Calculation Manual? (If - yes, see Section 5.0 of 0Al 109 for instruction.) II IX} 3. Does this stem constitute a change to the Process Control Program? (if yes, see Section 5.0 of 0Al 109 for instruction.) () lX] 4. ...ss this item involve a major change to a Radwaste Treatment System? (if yes, see Section 5.0 of 0Al.109 for instruction.) [] [X] 5. Does this item involve a change to the Technical Specification Equipment List? (If yes, process the change in accordance with CRCl-Os 'i. For further l} IXl 1s% instruction see Section 5.0 of 0Al 109.) i 6. Does this item impact the NPDES Permit or a "significant environmental impact"? (Use the guidance contained in Attachment A to make this II IXI determination. If yes, see Section 5.0 of OAl 109 for instruction ) 7. Does this item involve a change to a previously accepted; i Ib I a. Quality Assurance Program b. Security Plan (including Training, Qualification, and Contingency Plans)? X' c. Emergency Plan? 'X' i (if yes, see Section 5.0 of OAl 109 for instruction and complete a 10 CFR 50.54 evaluation using Attachment D.) 8. Does the item involve a change to the following Fire Protection Program Documents: OPlo-01; OPLP-01.1; OPLP-01.2; or OPLP-01.57 [] [X] (if yes, s >e Section 5.0 of OAl 109 for instruction ) I P b I OAl109 Rev.9 Page 50 of 54 f 1 n.~.=. u ~ _ _ _.._,.. _ _. _.u _.-,__ _ ___. _ n._. _ _

. - - - =. ESR 97 00034 Rev. O Page fl m' ATTACHMENT C Page 2 of 2 item Classification Form DOCUMENT NO. ESR 97-00034 REV.NO. 0 YES ELQ 1. Does this change require a revision to the improved Technical Specification. [] [X) including associated bases or the Technical Requirements Manual? (if yes, see Section 5.0 of 0Al 109 for instruction.) References; identify specific references used for any "Yes" answer, t% i l OAl109 Rev 9 Page 51 of 54 l l l l l, .. ~ .. J

Cerchns Power A L/cht Comp:nv ESR 97 00034 R:v. O Brunswick Nucle:r ft:nt. Unit 2 Att:chmsnt A [ngineering (vHu* tion P:01 l Brunswick Steam Electric Plant, Unit No. 2 Core Shroud Inspection Plan Revision 1 Outage B213R1 Prepared by: Phil Gore John Langdon Blane Wilton October 8,1997 WNL Date: /0 7 9 7 Recommended byf it o b Date: /0kb 7 Approved by: i (

Cctriins Pow:t & Light Cornpent ESR 91 ooo34 Rn o Brunswick NucMr Pt:nt Unit 2 Att: chm:nt A Engineering Ev:lu: tion Paae 2 HRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 CORE SHROUD INSPECTION PLAN REVISION 1 OUTAGE B213R1

SUMMARY

OF INSPECTIONS The scope of core shroud reinspections for the Brimswick Steam Electric Plant (BSEP), Unit No. 2 is based on several factors. Results of previous inspections performed on both BSEP, Unit No. I and BSEP, Unit No. 2, as well as results within the industry, are key inputs into the inspection plan. Follow-up actions and commitments established from the last inspection are also included in the determination of the inspection scope. Guidance on shroud inspections and flaw evaluation, contained in the Dolling Water Reactor Vessel Intemals Program (BWRVIP) documents BWRVIP 01, " Core Shroud Inspection and Evaluation Guidelines," and BWRVIP-07, " Core Shroud Reinspection Guidelines," is also used. Based on the previous inspection results, inspections of welds H1, H6A, H7 and H9 are not planned. Since welds 112 and 113 have been structurally replaced with clamps, these welds no longer require inspection. However, three of the twelve repair clamps for welds H2/H3 will be visually inspected. The B211R1 ultrasonic :esting (UT) inspection results for weld H4 demonstrated that the weld does not require re inspection until the B214R1 outage. However, based on CP&L's internal program to monitor growth rates on core shroud welds, two 20 inch long areas of weld H4 will be inspected, using UT, during B213RI. Weld H5 will be re-inspected, using UT, since the B211R1 inspection was performed using only visual testing (VT) methods on both the inside and outside weld surfaces. Weld H6B will be re inspected using UT for changes in the crack lengths and/or depths. No inspections of weld H8 or the shroud support legs are planned since the BWRVIP has not completed development of the inspection and evaluation guidelines, and inspection tooling and techniques, that will work on the BSEP type shroud, have not been fully developed. UNIT 2 CORE SIIROUI) REINSPECTIT i PLAN 4 Weld H1 was inspected using VT at four (4; wations (i.e.,11 percent of the circumference) on the outside surface, during the B211R1 outap, with no indications noted. During the B212R1 outage,100 percent of the accessible area was inspected using UT from the outside surface. This included 30.9 percent of the upper weld sur face area, of which 2.7 percent of the weld length examined had circumferential cracking. The upper weld surface has significant UT tool access limitations due to the shroud head bolt lugs, the guide rod brackets, and the core spray piping. The lower weld surface area was inspected on 83.3 percent of the surface area, with 32.1 percent of the inspected weld length having circumferential cracking. The lower weld surface area UT

. ~ -.. - - I Ccts' ins Powcr & Ught Comptny ESR 9100034 Rsv. 0 l Bruns wick Nucim Ptnt. Unir 2 Attachmsnt A Engin:ering Evclus.io,n Paos 3 } tool access is limited due to the location of the guide rod brackets and the core spray piping. Analysis of the weld showed that no inspectien was necessary during the B213R1 outage. Welds H2 and H3 were structurally replaced with twelve clamps during the B211R1 outage. Therefore, no inspection of these welds is required. Although BWRVIP-07 only requires Inspection of 25 percent of the repair clamps each outage, CP&L inspected four (4) of the clamps using VT techniques during the B212R1 outage, with no mdications roted. Three (3) a'iditional clamps will be inspected using VT during this outage, bringing the total repair clamps that will l have been inspected to seven (7). Weld H4 was inspected using UT in 100 percent of the accessible areas during the B211R1 outage, obtaining coverage of 78.8 percent of the total weld with circumferential cracking found in 26.1 percent of the areas inspected. The guide rod brackets, core spray piping, and jet pump riser brace arms prevented access to some areas of the weld. Although analysis showed the weld was qualified to operate for 1800 days (i.e., until the B214R1 outage), CP&L elected to monitor the circumferential crack growth rates at two locations with UT dur:ng the B212R1 outage. No growth outside the UT technique uncertainty factors was detected. CPtL plans to use UT to inspect these same two areas for circumferential crack length and depth growth during the B213R1 outage. i An attempt to inspect the H5 weld using UT was made during the B211RI outage, but was aborted due to significant access limitations from thejet pumps and associated components for the UT tool. The UT inspections were replaced with VT inspections, where 100 percent of the inside weld surfaces and 30.6 percent of the outside weld surfaces were inspected. Circumferential cracking was fotmd on 13.6 percent of the inside weld surfaces and 6.8 percent of the outside weld surfaces. The : lose proximity of thejet pumps to the core shroud outside surfaces prevented 100 percent inspection of the outside surfaces using VT. Since analysis showed the weld was structurally sound to operate for 1400 days (i.e., until the B213R1 outage), no inspections were perfonned during the B212R1 outage. CP&L plans to use UT to inspect the H5 weld during the B213R1 outage to gain additional coverage and determine the depth of the cracking. The coverage for this weld is projected to be greater than 70 percent, with the guide rod brackets, core spray piping, and jet pump riser brace arms preventing access to some areas. . Weld H6A was inspected on 6 percent of the outside surface during the B211R1 outage using VT, with one,1.5 inch long circumferential crack found. During the B212R1 outage, this weld - was inspected in 100 percent of the accessible areas using UT, which resulted in 79 percent of the total weld being inspected. Circumferential cracking was found in 5.3 percent of the inspected area. Analysis determined the weld does not require re-inspection during B21JRI. Weld H68 was inspected on 6 percent of the outside weld surface during the B211R1 outage using VT, with no circumferential cracking found. During the B212R1 outage, this weld was - inspected in 100 percent of the accessible areas using UT, which resulted in 78.4 percent of the total weld being inspected. Circumferential cracking was found in 69.6 percent of the inspected area. Analysis determined the weld required re inspection during B213RI. For the B213R1 UT inspection, the Ele'ctric Power Research Institute Non Destmetive Examination Center was

Ccrolins Powy & Light Comp:ny ESR 91.oo034 Rsv. O Crunswick Nucleu PI:nt Unit 2 Attschmsnt A Engineering Evtlustion Pros 4 l f I contracted to develop a phased array UT technique. The technique will enable CP&L to obtain i more refined data on the lengths and depths of the circumferential cracking in this weld. It is capected that at least the same coverage will be obtained as was obtained during the B212R1 outage.- Weld H7 was inspected on 6 percent of the outside weld surface during the B211R1 outage using VT, with no circumferential cracking found. During the B212R1 outage, this weld was inspected in 100 percent of the accessible areas using UT, which resulted in 75.6 percent of the total weld being inspected. Circumferential cracking was found in 10.9 percent of the inspected ares. Analysis determined the weld does not need to be re inspected until the B215R1 outage, so no inspections are planned for the B213R1 outage. No inspections have been performed, or are planned during the B213R1 outage, for the H8 weld. This weld presents significant accessibility challenges since the upper side of the weld is very restricted due to the jet pump diffusers, core spray piping, and guide rod brackets. The lower side of this weld has even more restrictive access due to thejet pump baffle plate and the need to disassemble fuel cells for access from the bottom head region. Additionally, the BWRVIP has not completed development of the inspection and evaluation guidelines, nor have inspection techniques and tooling been completely developed. While some inspection tooling is available, it will not work at BSEP due to the clamps installed around the H2 and H3 welds. When the BWRVIP completes these guidelines, and inspection tooling and techniques are available, CP&L plans to inspect this weld consistent with BWRVIP guidance. Although not currently required in the BWRVIP guidelines, CP&L inspected the H9 weld during the B212R1 outage. Since the H9 weld is directly attached to the reactor pressure vessel (RPV) shell to bottom head weld, CP&L qualified a UT technique to inspect the H9 weld in conjunction with the RPV shell to-bottom head weld The inspection coverage was 99 percent of the weld, with no indications noted. Since no indications were noted during the B212RI inspections, no inspections are planned for the B213R1 outage. The BWRVIP has not completed inspection and evaluation guidelines for the shroud support legs and other areas below the core plate. Additionally, equipment and techniques have not been developed for these areas. When these guidelines and inspection tooling and techniques are available, these areas will be inspected consistent with BWRVIP guidance. t A summary of the inspection history and plans for each weld, and for the clamps, is described in Table 1. During the course of the inspections, unanticipated interferences may be encountered - that will require changes to this plan. These situations will be evaluated as they arise. INSPECTION SCOPE EXPANSION Additional areas of the shroud welds will be inspected if crack growths are unusually higher than predicted. The UT uncertainty has been determined in qualification testing by the inspection vendor, and meets the BWRVIP guidelines, t [ n .. _,, _ ~ - -..... _.. - _ _

C:r: lins Power & Light Comp:ny ES;197-00034 R:v. O Brunswick Nuclear Plant. Unit 2 Att chment A Engineering Evtluition P:ge $ if any unusual findings are connrmed upon inspection of the three clamps, the remaining clamps will be inspected. EVALUATION An engineering evaluation of the inspection results wil' be performed using the flaw evaluation guidance of the BWRVIP-01 and BWRVIP-07 documents. No significant changes from the last inspection results are expected. D 3 O ,_,,..r- ._.. ~.. .m, _r ,.m ...-,,.-.y

i p=3 s[n L TABLEI $[ i j. Unit 2 Refueling Outage 12 (B213RI) Core Shroud Reinspection Ig& F di REINSPECTION [ d{

• I WELD LASTINSPECTION RESULTS METIIOD*

B213R1 INSPECTION PLANS AND COMMENTS [> l HI Outage B212RI - UT of 100 percent of the None planned Analysis concluded that no inspections were needed h'. n accessible inside diameter and outside diameter this outage. Suflicient structural margins exist, and any y areas. anticipated growth of indications will not impact i structural margins. i H2 NA N/A Replaced by clamps during the B211R1 outage. s H3 NA N/A Replaced by clamps during the 3211R1 outage. I I H4 Outage B212R1 - UT at two 20 inch areas for UT UT inspection of the same two 20 inch areas is planned i crack depth growth determination. No growth this outage as part of a BSEP intemal program to l outside the correction factors for the UT l monitor crack growth. The next inspection, per technique was detected. BWRVIP Guidelines, is scheduled for the B214RI outage. r l H5 Outage B212R1 - None performed. UT Analysis ofinspections following the B211RI outage ( concluded that no inspections were required until this outage. Plan to inspect 100 percent ofaccessible areas l which is projected to be in excess of 70 percent of the l total weld. H6A Outage B212R1 - UT 100 percent of accessible None planned Analysis concluded that no inspections were required i f areas which resulted in 79 percent of the total this outage. weld being inspected. Found circumferential

=

cracking in 5.3 percent of examined weld length. O k8 i s8 9-

!s' I

7 1 e2o i i

?F0 12 8 ? !. E TABLEI J"2 Unit 2 Refueling Outage 12 (B213RI) Core Shroud Reinspection E!$ fN REINSPECTION [% WELD-LASTINSPECTION RESULTS METHOD

• B213R1 INSPECTION PLANS AND COMMENTS 7p E4 H6B Outage B212RI - UT 100 percent of accessible UT Analysis concluded that inspection was required this y

areas which resulted in 78.4 percent of weld outage. Plan to inspect 100 percent of accessible areas length being inspected. Circumferential cracking with phased array UT technique to refine cracking was found in 69.6 percent ofinspected weld lengths and depths. Total weld coverage is expected to length. be at least that obtained during the B212R1 outage. 37 Outage B212R1 - UT 100 percent of accessible None planned Analysis of the B212R1 outage data concluded that no areas resulting in 75.6 percent of the tctal weld inspections were required this outage. Sufficient length being examined. Circumferentiil cracking structural margin exists and any anticipated growth of was found in 10.9 percent ofinspected weld indications will not impact structural margins. length. HS None None planned Awaiting BWRVIP development of inspection tools / techniques. H9 Outage B212R1 - UT 100 percent of accessible None planned Not scheduled for inspection this outage. Sufficient areas. 99 percent of weld length examined with structural 'nargin exists. Any anticipated growth of no flaws noted. indicat:ans will not impact structural margins. Shroud - Not inspected. Nene planned BWRVIP developing inspection tools / techniques. support legs y e Y >0 5 sa n ,2x Page 2 a :; 4>0

?" s$2 e a 2 3 p I[* ? TABLE 1 y*, Unit 2 Refueling Outage 12 (B213RI) Core Shroud Reinspection h,_,4 REINSPECflON WELD LASTINSPECTION RESULTS METIIOD' B213R1 INSPECTION PLANS AND COMMENTS 7& E4 i Shroud Outage B212R1 - VT of 4 different installed VT Inspect 3 clamps for general appearance, missing parts, 44 clamps clamps. and integrity of tack welds. Will bring the total clamps ?- inspected to 7 of the 12 total installed. ~ Non-oestructive examination methods to be qualified in accordance with "BWRVIP Reactor Pressure Vessel and Internals Examination Guidelines" issued by the BWRVIP. t l I i r d .i i i i 3 S 18 Er o 9 *,, 2~!} 2' Page 3 5 >o w...., _..,.... .,., ~.. ,,,,.._,,_n_.,... . ~ =,,

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C rolino Pow:r & Ught Company ESR 97 00034 Rsv. 0 Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 2 til:Honnaluanet Good for 1890Aays from March 1996 125 0 8095E+08 19441. 26 86 -> ACCEPTABLE 130 0 7 70$E+08 18504. 2559 -> ACCEPTABLE Fdename DLL8-18-97 For 135 0 7.613E+08 10264. 25 29 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 140 0 7 R79E+08 17483 24 19 ->ACCEPTAELE (09/19/96) 145 0 6 968E+08 16735 23,17 -> ACCEPTABLE DATE OF THIS ANALYSIS 09/17/1997 150 0 6 988E*08 16783-23 24 -> ACCEPTABLE 155 0 6 560E+08 15756. 21 84 -> ACCEPTABLE

SUMMARY

OF INPUTS-160 0 6 766E+08 16250. 22 51 > ACCEPTABLE 165 0 6 607E+08 15868 21 99 -> ACCEPTABLE Tetle. H1 Rev'd New WU Loads & Safe *y Factor 170 0 6 662E+08 10000. 22 17 -> ACCEPTABLE 1.0 deg. (COARSE) 175 0 6620E+08 15898 22 03 -> ACCEPTABLE Angle increment = 64mbrano Stress, Pm = 250. psi 180 0 6 395E+08 15358 21 29 -> ACCEPTABLE 483 psi 185 0 6 487E+08 15580. 21 60 -> ACCEPTABLE Benden9 Stress. Pb = 2 25 190 0 6 493E+08 15594. 21 62 -> ACCEPTABLE Safeiy Factor, SF = = 94 00 inches 195 0 6 421E+08 15421. 21 38 -> ACCEPTABLE Mean Radius, Rm = 1500 inches 200 0 6 682E+08 16047. 22 23 -> ACCEPTABLE Wall Thickness, t Stree intensity, Sm = 16900 psi 205 0 6.792E+08 16313. 22 60 ' ACCEPTABLE Fluence = 1.28E+18 n/cm^2 (at end of heensed hfe) 210 0 6 955E+08 16703 23 13 -> ACCEPTABLE (Thus, LEF M evaluation not apphcable) 215 0 7.169E+08 17216. 23 83 -> ACCEPTABLE 220 0 7 431E+08 17648 24 69 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 225 0 7.536E +08 18100. 25 03 -> ACCEPTABLE l

v. IlON ldeg ]

[deg) Dnches) 230 0 7.961E +08 19120. 26 43 -> ACCEPTABLE I 235 0 8 287E+08 19901. 2749 -> ACCEPTABLE i 1 78 0 79 9 1 500 240 0 8604E*08 20663 28 53 -> ACCEPTABLE 2 92 5 94 5 1 500 2450 C 911E+08 21400. 29 54 -> ACCEPT ABLE 3 104 0 106 0 1.500 250 0 9 204E+08 22105 30 50 -> ACCEPTABLE 4 111 3 113 3 1.500 255 0 9 583E+08 23015 31.74 -> ACCEPTABLE 5 119 8 125 4 1 500 260 0 9 671E+08 23226 32 03 -> ACCEPTABLE 6 150 1 164 3 1 500 265 0 100$E+09 24142. 33 28 ->ACGEPTABLE 7 199 7 202 3 1 500 270 0 1043E+0V 25060 34 53 -> ACCEPTABLE "GN 8 209 4 213 8 1 500 275 0 1055E+09 25335. 34 90 -> ACCEPTABLE 'f 9 233 7 238 3 1 500 280 0 1094E+09 26279 36 19 -> ACCEPTABLE 10 256 2 2878 1 500 285 0 1.134 E+09 27229 37 49 -> ACCEPTABLE 11 310 1 343 7 1.500 290 0 1.149E+09 27589 37.98 -> ACCEPTABLE f 295 0 1.190E +09 28574. 39 32 -> ACCEPTABLE 300 0 1231E+09 29566. 40 68 -> ACCEPTABLE L 8MIT LCAD RESULTS 305 0 1258E+09 30213 41 56 -> ACCEPTABLE 310 0 1291E+09 31004. 42 64 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESUI TS ASSUME THAT 315 0 1330E+09 21934. 43 91 -> ACCEPTABLE THE FLAWS TAF COMPRESSION 320 0 1.352E+09 32461. 44 63 -> ACCEPTABLE 325 0 1379E+09 33112 45 51 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1.403E+09 33707. 46 33 -> ACCEPTABLE (deg) On-tbs) [ps#) FACTOR RESULT 335 0 1426E+09 34245 47.06 -> ACCEPTABLE 340 0 1446E+09 34728. 47.72 -> ACCEPTABLE 00 1498E+09 35987. 49 44 > ACCEPTABLE 345 0 1471 E +09 35329 48 54 -> ACCEPTABLE 50 1502E+09 36081. 49 M > ACCEPTABLE 350 0 1478E+09 35484 48 75 > ACCEPTABLE 10 0 1502E+09 36006. 49 54 -> ACCEPTABLE 355 0 1490E+09 35785 49 16 > ACCEPTABLE 15 0 1497E +09 35942. 49 38 > ACCEPTABLE 20 0 1478E +09 35507, 48 75 -> ACCEPTABLE ACCEPTABLE! 25 0 1464E +09 35648 48 97 -> ACCEPTABLE MINIMUM SAFETY FACTOR = 2129 AT 180 0 DEGREES 30 0 1452E+09 34877, 47 92 -> ACCEPTABLE 35 0 1455E+09 34936 48 00 -> ACCEPTABLE 40 0 1426E +09 34258 47 08 -> ACCEPTABLE 45 0 1414E +09 33948 4665 -> ACCEPTABLE 50 0 1.387E+09 33306 45 78 > ACCEPTABLE $5 0 1.356E+09 32572. 44 78 -> ACCEPTABLE 60 0 1322E+09 31761, 43 67 -> ACCEPTABLE 65 0 1.286E+09 30886. 42 48 -> ACCEPTABLE 70 0 1238E+09 29725 40 89 > ACCEPTABLE 75 0 1208E+09 29019 39 93 -> ACCEPTABLE 80 0 1,169E +09 28085. 38 66 ->/ CCEPTABL E 85 0 1 121E+09 26920 37 07 -> ACCEPTABLE 90 0 1080E+09 25940 35 73 -> ACCEPTABLE 95 0 1037E*09 24915 34 33 -> ACCEPTABLE 100 0 9 842E+08 23636. 32 59 > ACCEPTABLE 1050 9 320E+08 22383 30 88 > ACCEPTABLE 110 0 9116E+08 21892. 30 21 -> ACCEPTABLE 115 0 S S45E +08 21242. 29 32 > ACCEPTABLE 120 0 8 508E+08 20432 28 22 >ACCtPTABLE

C:rolina Pow:r & Light Company ESR 97 00034 rov. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation PagB 3 H1-EmelgtDsyJ90d for_1MO days from Marsh _in6 125 0 8 095E+08 19441. 22 03 > ACCEPTABLE 130 0 7.70$E +08 18504 20 99 ->ACCEPTADLE Fdename DLL8-18-97 For 135 0 7 613E+08 18284 20 74 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION. REV. 21 140 0 7.279E+08 17483 1964 -> ACCEPTABLE (09/19/96) 145 0 6 968E+08 16735 19 01 ->ACCEPTADLE DATE OF THIS ANALYSIS: 09/30/1997 150 0 6 988E+08 16783 19 06 -> ACCEPTABLE 155 0 6 560E+08 15756. 17 91 ->ACCEAPLE 1UMMARY OF INPUTS 160 0 6 766E+08 16231 18 46 ->ACCEPTAt it 165 0 6 607E+08 15868. 18 04 ->ACCEPTABLJ i.............s... Tatie HI Rev'd-New Eme*g Loads & Safety Facto 170 0 6 662E+08 16000 18 18 ->ACCEt TABLE 10 deg (COARSE) 175 0 6 620E+08 15898. 18 07 -> ACCEPTABLE Angie anctement = Membrane Stre:s, Pm = 257. psi 180 0 6 395E+08 15358. 17 47 -> ACCEPTABLE 637. psi 185 0 6 487E+08 15580 17.71 -> ACCE PTADLE Bending Stress. Pb = = 1 50 190 0 6 493E+08 15594. 17.73 -> ACCEPTABLE Safety Factor, SF Mean Radeus, Rm = 94 00 inches 195 0 6 421E+08 15421. 1754 ->ACCEPTADLE Wall Thekness, t = 1.500 inches 2000 ti 682E+08 16047, 18 24 -> ACCEPTABLE Stress intensity, Sm.16900 psi 2050 6 792E+08 16313 18$3 -> ACCEPTABLE Fluence = 128E+18 n/cm^2 (at end of hcensed too) 210 0 6955E+08 16703 18 97 -> ACCEPTABLE (Thus, LEFM evalustson not opphcable) 215 0 7.169E+08 17216. 19 55 ->ACCEPTADLE 220 0 7.431 E +08 17848 2025 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 225 0 7 536E+08 18100 20 53 -> ACCEPTABLE 230 0 7 961E+08 19120 21 67 -> ACCEPTABLE REGION [deg ) [deg ) [ inches) 233 0 8 287E+08 19901. 22 55 -> ACCEPTABLE 1 76 0 79 9 1.500 240 0 8504E+08 20063 23 40 -> ACCEPTABLE 2 92 5 94 5 1 500 245 0 8 911E+08 21400. 24 22 -> ACCEPTABLE 3 104 0 106 0 1 500 250 0 9204E+08 22105 2501 -> ACCEPTABLE 4 111.3 11J 3 1 500 255 0 9 $83E+08 23015-26 03 -> ACCEPTABLE 5 1198 125 4 1 500 260 0 9 671E+08 23226. 26 27 -> ACCEPTABLE 6 1501 164 3 1 500 265 0 1.00$E+09 24142 27 29 > ACCEPTABLE 7 199 7 202 3 1 500 270 0 1043F+09 25060 2832

• ACCEPTABLE 8

209 4 213 8 1 500 275 0 1.055E +09 25335. 28 63 -> ACCEPTABLE 9 233 7 238 3 1 500 280 0 1094E+09 26279 29 68 -> ACCEPTABLE 10 2562 2878 1 500 285 0 1.134E+09 27229 30 74 ->ACCEPTADLE 11 310 1 343 7 1 500 290 0 1.149E+09 27589. 31,15 -> ACCEPTABLE 295 0 1.190E+09 28574. 32 25 > ACCEPTABLE 300 0 1231E+09 29566 33 36 ->ACCEPTADLE LIMIT LOAD RESULTS. 305 0 1258E+09 30213. 34 C8 -> ACCEPTABLE 310 0 1291E+09 31004 34 97 -> ACCEPTABLE NOTE. THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1330E+09 31934 36 01 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1352E+09 32481. 36 60 -> ACCEPTABLE 325 0 1.379E+09 33112. 37 33 -> ACCEPTABLE ALPHA MOMENT Pb' SAFELY 330 0 1403E+ 09 33707. 37 99 > ACCEPTABLE [deg] [in-hs) (psi] FACTOR RESULT 335 0 1.426E +09 34245. 38 59 -> ACCEPTABLE 340 0 1446E +09 34728 39 13 -> ACCEPTABLE 00 1498E +09 35957 40 54 ->ACCEOTABLE 345 0 1471E *09 35329 39 61 -> ACCEPTABLE 50 1502E *09 36081. 40 65 -> ACCEPTABLE 350 0 1478E+09 35484 39 98 -> ACCEPTABLE 10 0 1502E+09 36066 40 63 -> ACCEPTABLE 355 0 1.490E +09 35785 40 32 ->ACCEPTABL E 15 0 1497E+09 35942. 40 49 -> ACCEPTABLE 20 0 1478E+09 35507 40 00 -> ACCEPTABLE ACCEPTABLEf 25 0 1484E

• 09 35648 40 16 ->ACCEFTABLE MINIMUM SAFETY FACTOR = 17 47 AT 180 0 DEGREES.

30 0 1452E +09 34877. 39 30 > ACCEPTABLE 35 0 1455E+09 34h36 39 37 ->ACCEPTADLE 40 0 1426E+09 34258 38 61 -> ACCEPTABLE 45 0 1414E +09 33948 38 26 -> ACCEPTABLE 50 0 1387E+09 33306 37 54 > ACCEPTABLE %50 1356E+09 32572. 36 72 -> ACCEPTABLE 60 0 1322E+09 31761. 3581 > ACCEPTABLE 65 0 1286E+09 30886 34 84 >ACCEPTOLE 70 0 1238E+09 29725 3354 > ACCEPTABLE 75 0 1208E+09 29019 32 75 -> ACCEPTABLE S00 1.169E +09 28085 31.70 > ACCEPTABLE 85 0 1 121E+09 26920 30 40 ->ACCE PTABL E 9C 0 1080E+09 25940 29 30 -> ACCEPTABLE 95 0 1037E+09 24915 28 16 -> ACCEPTABLE 100 0 9 842E +08 23836 26 73 > ACCEPTABLE 105 0 9 320E+08 22383 25 32 -> ACCEPTABLE 110 0 9116E+08 21892 24 78 -> ACCEPTABLE 115 0 8 845F.+08 21242 24 05 >ACCF PTABLE 120 0 8 508E+08 20432 23 14 > ACCEPTABLE

__ _ ~ _. _. _ _ _ _ i ) ' Ccrolina Powcr & Light Company ESR 97 00034 Rev. 0 Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering Evaluation Page 4 i Hi FaulteLQood for.130n dawn fremDarch itM 125 0 7 833E+08 18812, 13 45 -> ACCEPTABLE 130 0 7 435E+08 17855 12 60 -> ACCEPTABLE F4ename DLL818 97 For 135 0 7.061E +08 16959 12,18 ->A::CEPTABLE DLL CASTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 140 0 6 998E+08 16806 17 06 -> ACCEPTABLE (09/1996) 145 0 6 5ME+08 15812 1140 -> ACCEPTABLE DATE OF THIS ANALYSIS. 09/30/1997 150 0 6 407E+08 15388 11.11 -> ACCEPTABLE 155 0 6167E+08 14811 10 71 -> ACCEPTABLE

SUMMARY

OF INPUTS-160 0 6= 172E +08 14822. 10 72 -> ACCEPTABLE 165 0 6 305E+08 15143. 10 94 -> ACCEPTABLE Tale H1 Rev'd. New Fauned Loade & Sakty Fac 170 0 6 258E+08 16029 10 86 -> ACCEPTABLE 10 oog (COARSE) 175 0 6 014E+08

14444, 10 46 -> ACCEPTABLE An94e increment

= Membrane Stress, Pm = 818. pel 180 0 6097E*05 14643 10 60 -> ACCEPTABLE 185 0 6 092E+0a 14630- 10 59 -> ACCEPTABLE Bending Stress. Pb o 641. poi seesty Factor, SF a f.13 190 0 6194E+08 14877. 10 76 -> ACCEPTABLE Mean Re$us, Rm = 94 00 inches id$ 0 6116E+08 14688 10 63 -> ACCEPTABLE 1500 inches 200 0 6 276E48 15072. 10 89 -> ACCEPTABLE { . Web Thdness, t = - 205 0 6 386E+08 15337 11.07 -> ACCEPTABLE Stroos intensey, Sm a 16900 ps) Fluence = 128E+18 n/un*2 (a1 end of konsed life) 210 0 6 549E+08 15728 11 34 -> ACCEPTABLE 215 0 6 762E+08 18241. 11.69 -> ACCEPTABLE (Thus, LEF M evolueton not appkable) 220 0 7.025f +08 16872. 12.12 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 225 0 7.232E+08 17369 12 47 -> ACCEPTABLE 230 0 7.561E+08 18159 13 01 -> ACCEPTABLE i REOlON (dog) ldeg ) [ inches) 235 0 7 687E*06 18941. 13 54 -> ACCEPTABLE g _ 73 o yg 9 3 $00 240 0 8 204E+08_ 19702. 14 06 -> ACCEPTABLE 2 92 5 94 5 1 500 245 0 8 511E*08 20439 14 57 -> ACCEPTABLE 3 104 0 106 0 1.500 250 0 8 804E+08 21145. 15 05 -> ACCEPTABLE 4 111.3 113 3 1 500 255 0 8 991E*08 215P3 15 36 -> ACCEPTABLE 5 119 8 125 4 1 500 260 0 9.380E +08 22526 16 00 -> ACCEPTABLE 6 150 1 164 3 1 500 265 0 9 769E+08 23460. 16 64 -> ACCEPTABLE 7 199 7 202 3 1 500 270 0 9878E+08 23723. 16 82 -> ACCEPTABLE 8 209 4 213 8 1.500 275 0 1028E+09 24680. 17.48 -> ACCEPTABLE 9 233 7 238 3 1.500 280 0 1068E+09 25643 18 14 -> ACCEPTABLE 10 256 2 287 8 1 500 285 0 1082E+09 25986. 18 37 -> ACCEPTABLE 11 310.1 343 7 1 500 290 0 1.124E +09 26983 19 06 -> ACCEPTABLE 2950 1.165E +09 27980 19 74 -> ACCEPTABLE 300 0 1.184E +09 28428. 20 04 > ACCEPTABLE LIM:T LOAD RESULTS. 3050 1226E+09 29452. 20 75 > ACCEPTABLE 310 0 1259E+09 30243 21 29 -> ACCEPTABLE ....c.............. NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1290E+09 30983 21 80 > ACCEPTABLE THE FLAWS TAKE COMPRES$10N 320 0 1.319E+09 31686 22 28 -> ACCEPTABLE 325 0 1346E +09 32337. 22 72 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1379E+09 33118 23 26 -> ACCEPTABLE [de9) (in-lbs) (psi) _ FACTOR RESULT 335 0 1393E+09 33455 23 19 -> ACCEPTABLE 340 0 1413E+09 33924. 23 81 ->ACCE PTABl.E 00 1463E+09 35143 24 65 > ACCEPTABLE 345 0 1429E+09 34325 24 09 > ACCEPTABLE 50 14670+09 35237. 24 71 > ACCEPTABLE 350 0 1452E+09 34864 24 46 -> ACCEPTABLE 10 0 1467E+09 ' 35222. 24 70 > ACCEPTABLE 355 0 1455E+09 34942< 24 51 ->ACCEPTA3LE -15 0 1461E +09 35099 - 24 62 -> ACCEPTABLE 20 0 1452E+09 34868 24 46 > ACCEPTABLE ACCEPTABLE! 25 0 1430E +09 34341. 24 10 -> ACCEPTABLE MINIMUM SAFETY FACTOR 10 46 AT 175 0 DEGREES 30 0 1424E+09 34210. 24 01 -> ACCEPTABLE 35 0 1398E+09 33574 23 57 > ACCEPTABLE 40 0 1398E+09 33576 23 57 -> ACCEPTABLE 45 0 13760+09 33042. 23 21 -> ACCEPTABLE 50 0 1349E+09 32400. 22 77 >ACCEPTA9LE 55 0 - 1.319E+00 ' 31678 22 27 --> ACCEPTABLE 60 0 : 1.267E+09 - - 30423 2141 - -> ACCEPTABLE 65 0 1249E+09 30005 21.13 -> ACCEPTABLE 70 0 1.210E+09 - 29070 20 49 > ACCEPTABLE 75 0 1.163E+09 27936 19 71 -> ACCEPTABLE 80 0 1 124E+09 26998. 19 07

• ACCEPTABLE -

85 0 1093E+09 26253 18 55 > ACCEPT ABL E 90 0 1043E *09 25046 17.73 > ACCEPTABLE 95 0 1000E+09 24021. 17 02 -> ACCEPTABLE ~ 100 0 9 565E+08 22971. 16 31 -> ACCEPTABLE 105 0 8 955E+03 21507. 15 30 ->ACCEPTAPLE. 110 0 8847E*08 21247. 15 12 -> ACCE PT ABLE 115 0 8 319E+08 19980. 14 25 -> ACCEPTABLE 120 0 8162E +08 19601. 14 00 -> ACCEPTABLE

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m4_ a _._- 1u __.-4_ Ccrolina Power & Light Company ESR 97-00034 Rcy O Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering Evaluation Page 6 tiidgrmal UpttLGnodigt2400Anya from June igg ( 140 0 8 650E+08 23704. 19 30 -> ACCEPTABLE 145 0 8 877E+08 24326 19 81 -> ACCE PT ABLE Faename DLL818-97 For 150 0 8 942E+08 24504. 19 95 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 155 0 9187E+08 25175. 20 49 -> ACCEPTABLE (09/19/96) 160 0 9 287E+08 25450 20 71 -> ACCEPTABLE DATE OF THIS ANALYSIS' 09/30/1997 165 0 9 637E+08 26408 21 49 -> ACCEPTABLE 170 0 9 732E+08 26669-21.70 -> ACCEPTABLE $UMMARY Or !NPUTS 175 0 9 815E+08 26890 21 88 -> ACCEPTABLE 180 0 100$E+09 27553 22 41 -> ACCEPTABLE s.e...... Tale H4 t#U. New Loads & Safety Factor will 185 0 1018E+09 27888 22 68 -> ACCEPTABLE 10 dog (COARSE) 190 0 1.027E +09 28139 22 88 ->ACCEP'ABLE Angie inuement Membrano Stress. Pm. 234 psi 105 0 1033E+09 28305. 23 02 -> ACCEPTABLE i Bending Stress, Pb = 1000 pel 200 0 103aE+09 28383 23 08 -> ACCEPTABLE 2 2a 205 0 1.035E+09 28374, 23 07 -> ACCEPTABLE Safety Factor, SF = . 88 00 inches 210 0 1.041 E+09 28520 23 19 -> ACCEPTABLE Mean Radius, Rm Wall ThKAness, t. 1.500 inches 215 0 1010E*09 27933. 22 72 -> ACCEPTABLE Stress intensity, Sm 16900 psj 220 0 1032E+09 28289 23 00 -> ACCEPTABLE Flune = 126E+20 n/cm 2 225 0 1017E+09 27881. 22 67 -> ACCEPTABLE a (peak value of evaluated region at 8215R1) 230 0 1.018E +09 27909 22 70 -> ACCEPTABLE (Thus, LEFM evaluston not appicable) 235 0 9 942E+08 27245 22.18 -> ACCEPTABLE ] 240 0 9 942E+08 27245. 22 18 -> ACCEPTABLE THETA 1 THE'TA2 THICKNESS 245 0 9 939E+08 27235 22 15 -> ACCEPTABLE l REClON (deg ) [deg ) bnches) 250 0 9 710E+08 26607. 21 65 -> ACCEPTABLE 255 0 9 780E+08 26799 21 80 ->ACCEPTADLE 1 60 0 91 2 1 500 260 0 9 687E+08 20545 21 60 -> ACCEPTABLE l 2 115 4 120 0 1.500 265 0 9 582E+08 26257. 21 38 -> ACCEPTABLE l 3 150 0 1720 1 500 270 0 9 466E +08 25938 21 11 -> ACCEPTABLE 4 202 4 200 4 1 500 275 0 9 339E+08 25592 20 83 > ACCEPTABLE 2003 273 5 1 500 280 0 9203E+08 25219 2053 -> ACCEPTABLE 6 2779 297 1 1.500 285 0 0059E+08 24824 20 21 > ACCEPTABLE 7 3345 3385 1 500 290 0 8 692E+08 23819 19 40 > ACCEPTABLE 295 0 8 663E+08 23738 19 33 -> ACCEPTABLE 300 0 8 728E+08 23918 19 48 -> ACCEPTABLE LIMIT LOAD RESULTS 305 0 8 $71E+08 23487. 19 13 -> ACCEPTABLE 310 0 8 418E+08 230G8. 18 79 > ACCEPTABLE NOTE: THE F OLLOV ING limit LOAD RESULTS AOSUME THAT 315 0 8 522E+08 23351 19 02 -> ACCEPTABLE THE FLAWS TA'I COMPRESSION 320 0 8 3795+08 22959. 18 70 -> ACCEPTABLE 325 0 8 234E+08 22563 18 38 -> ACCEPTABLE ALPHA 60 MENT Pb' SAFETY 330w d 353E+08 22888 1865 -> ACCEPTABLE (de9) Dn Ibs) [ psi) FACTOR RESULT 335 0 8199E+08 22469 18 31 -> ACCEPTABLE 340 0 8118E+08 22244. 18 13 > ACCEPTABLE 00 7 629E+08 20904 17 05 -> ACCEPTABLE 345 0 8 018E+08 21972 17 91 -> ACCEPTABLE 50 7 502E+08 20558 16 77 -> ACCEPTABLE 350 0 7 902E+b8 21653 17 65 > ACCEPTABLE 10 0 7 46SE+08 20460 16 69 -> ACCEPTABLE 355 0 7.769E +08 21290 17.36 -> ACCEPTABLE 15 0 7.175E +08 19661. 16 04 -> ACCEPTABLE 20 0 7154E+08 19603 16 00 -> ACCEPTABLE ACCEPTABLE! 25 0 6 893E+08 18890 15 42 -> ACCEPTABLE MINIMUM SAFETY FACTOR = 15 30 AT 35 0 DEGREES 30 0 6 840E+08 18744 15 30 -> ACCEPTABLE 35 0 6 839E +08 18741. 15 30 -> ACCEPTABLE 40 0 7135E+08 19551 15 96 > ACCEPTABLE 45 0 7.113E +08 19491. 15 91 > ACCEPTABLE 50 0 7 099E+08 13453 15 88 > ACCEPTABLE 55 0 7 263E+08 19902 18 24 -> ACCEPTABLE 60 0 7 334E+08 20097. 1640 > ACCEPTABLE 65 0 7.498E+08 20547 16 76 -> ACCEPTABLE 70 0 7 576E+08 20761. 10 93 -> ACCEPTABLE 75 0 - 7 647E+08 20955 17 09 -> ACCEPTABLE 80 0 7 627E+08 20900. 17.04 -> ACCEPTABLE 85 0 7.783E+08 21328 17 39 -> ACCEPTABLE 90 0 7 847F +08 21502. 17 53 -> ACCEPTABLE 95 0 7 728E+08 21177, 17 27 -> ACCEPTABLE 100 0 7 874E*08 21576 17 59 -> ACCEPTABLE 105 0 8 023E+08 21956 17,92 > ACCEPTABLE 110 0 7 937E+08 21750 17 73 -> ACCEPTABLE 115 0 8109E +08 22220 18 11 > ACCEPTABLE 1200' 8290E+08 22717. 1851 -> ACCEPTABLE 125 0 8259E+08 ?2632 18 44 -> ACCEPTABLE 130 0 8 538E*08 23396 19 06 -> ACCEPTABLE 1350 8 590E+08 23539 19 17 -> ACCEPTABLE

Ccrolina Pow:r & Light Company ESR 97 00034 Rev. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 7 H4-EmergencyJpod for 24QgiayajmaduntRM 140 0 8650E+08 23704 15 12 -> ACCEPTABLE 145 0 8 877E+08 24326 15 51 > ACCEPTABLE Faename DLL616 97 For 150 0 8 942E+08 24504 15 62 -> ACCEPTABLE OLL DIETRIDUTED LIGAMENT LENGTH EVALUATION, REV. 21 155 0 9187E+08 25175 16 05 -> ACCEPTABLE (09/19/96) 160 0 9 287E+08 25450 16 22 -> ACCEPTABLE DA1E OF THIS ANALYSIS 09/30/1997 165 0 9 637E +08 26408 1683 -> ACCEPTABLE 170 0 9 732E+08 20669 18 99 -> ACCEPTABLE GUMMARY OF INPUTS-175 0 9 815E+08 26896 17 13 -> ACCEPTABLE 180 0 1005E+09 27553 17.55 -> ACCEPTABLE Tale H4 Emer9ency. New Loads & Safet) Factor 185 0 1018E+09 27L38 17.76 -> ACCEPTABLE 10 deg (COARSE) 190 0 1027E+09 28139 17 92 -> ACCEPTABLE Angle anuement Membrane Stress, Pm. 244 psi 1950 1033E +09 28305. 18 02 -> ACCEPTABLE Bending Stress. Pb. 1340 psi 200 0 1.036E +09 28383 18 07 -> ACCEPTABLE = 1 50 20$ 0 1.035E+09 28374. 18 07 -> ACCEPTABLE Safety Factor, SF Mean Ra$us, Rm 8800 inches 210 0 1.041E+09 28520 18 18 -> ACCEPTABLE . 1500 inches 215 0 1019E+09 27933 1r19 ->ACCEPTADLE WaN Thekness, t Stress intensty, Sm = 16900 pas 220 0 1032E+09 28289. 18 01 -> ACCEPTABLE Flurice e126E* 20 n/un*2 225 0 1.017E+09 27881. 17.76 -> ACCEPTABLE (peak value of evaluaP,egion at B215R1) 230 0 1.018E+09 27909. 17.77 -> ACCEPTABLE 235 0 9 942E+08 27245. 17.35 -> ACCEPTABLE (Thus, LEFM evaluation not appleabr 240 0 9 942E+0m 27245 17.35 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 245 0 9 939E+08 27235 17.35 -> ACCEPTABLE REGION ldeg ) (deg ) Dnches) 250 0 9 710E+08 26607. 18 95 -> ACCEPTABLE 255 0 9.780E+08 26799 17.07 -> ACCEPTABLE 1 60 0 91 2 1 500 260 0 9 687E+08 26545 16 91 -> ACCEPTABLE 2 115 4 120 0 1 500 265 0 9 582E+08 26257. 16 73 -> ACCEPTABLE 3 150 0 172 9 1 500 270 0 9 466E+08 25938, 16 53 -> ACCEPTABLE 4 202 4 206 4 1 500 275 0 9 339E+08 25592. 18 31 -> ACCEPTABLE 5 206 3 273 5 1 500 280 0 9 203E+08 25219 16 08 ->ACCEPTADLE 6 277 9 297.1 1.500 285 0 9 05DE+08 24824. 15 83 -> ACCEPTABLE 7 334 5 338 5 1.500 290 0 8 692E+08 23819. 15.19 -> ACCEPTABLE p 295 0 8 663E+08 23738. 15 14 -> ACCEPTABLE 300 0 8.728E+08 23918 15 25 -> ACCEPTABLE LIMIT LOAD RESULTS 305.0 8 571E+08 23487, 14 98 -> ACCEPTABLE 310 0 8 418E+08 23068 14 72 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 3 8 522E+08 23351. 14 90 > ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 8 379E+08 22959 14 65 ->ACCEPTADLE 325 0 8 234E+08 22563 14 40 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 8 353E+08 22888-14 60 > ACCEPTABLE (dog) [Mbs) [ psi) FACTOR RESULT 335 0 8199E+08 22469 14 34 > ACCEPTABLE 340 0 8118E+08 22244. 14 20 -> ACCEPTABLE 00 7 629E+08 20904 13 35 -> ACCEPTABLE 345 0 8 018E+08 21972. 14 03 ->ACCEPTABLF $0 7.502E *08 20558. 13 13 > ACCEPTABLE 350 0 7 902E+08 21653 13 82 -> ACCEPTABLE 10 0 7466E+08 20460 13 07 > ACCEPTABLE 3550 7.769E +08 21290. 13 59 -> ACCEPTABLE 15 0 7175E+08 19661. 12 57 -> ACCEPTABLE 20 0 7154E+08 19G03 12.53 -> ACCEPTABLE ACCEPTABLE! 25 0 6 893E+08 18890 12 08 -> ACCEPTABLE MINIMUM SAFETY FACTOR = 1199 AT 35 0 DEGREES 30 0 6 640E+08 18744 11 99 ->ACCEPTADLE 35 0 6 839E+08 18741. 11 99 -> ACCEPTABLE 40 0 7.135E+08 19551. 12 50 -> ACCEPTABLE 45 0 7.113E+08 19491. 12 46 -> ACCEPTABLE 50 0 7 099E+08 19453 12 44 > ACCEPTABLE $5 0 7 263E+08 19902. 12 72 > ACCEPTABLE 60 0 7 334E+08 20097. 12 84 -> ACCEPTABLE 65 0 7 498E+08 20547. 13 13 > ACCEPTABLE 70 0 7 576E+08 20761. 13 26 -> ACCEPTABLE 75 0 7 647E+08 20955 13 38 > ACCEPTABLE 80 0 7 627E+08 20900 13 35 -> ACCEPTABLE 85 0 7,783E +08 21328. 13 62 -> ACCEPTABLE 90 0 7 847E+08 21502. 13 73 > ACCEPTABLE 95 0 7 728E+08 21177 13 52 -> ACCEPTABLE 100 0 7.874E+08 21576 13 78 > ACCEPTABLE 105 0 8 023E+08 21986 14 03 > ACCEPTABLE 110 0 7 937E+08 21750 13 89 -> ACCEPTABLE 115 0 8109E +08 22220 14 18 > ACCEPTABLE 120 0 8290E+08 22717. 14 50 -> ACCEPTABLE 125 0 8 259E+08 22632 14 44 -> ACCEPTABLE 130 0 8 538E+08 23396 14 92 -> ACCEPTABLE 135 0 8 590E+08 23539 15 01 > ACCEPTABLE

Ccrolins Pow:r & l.ight Compcny ESR 97 00034 Rev. O B?unswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 8 l H4f aulted. Good for 2400 days from June 1994 140 0 8 413E+08 23055 10 77 -> ACCEPTABLE r 145 0 8 474E+08 23221. 1084 -> ACCEPTABLE Filename DLL818 97 For 150 0 8 699E+08 23837. 11 12 -> ACCEPTABLE i OLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 155 0 8 697E+08 23831. 11.12 -> ACCEPTABLE l (09/19/96) 160 0 9 037E+08 24765. 11.54 -> ACCEPTABLE OATE OF THIS AMALYSIS. 09/30/1997 165 0 9128E+08 25013. 11.65 -> ACCEPTABLE 170 0 9 211E+08 25241. 11.78 -> ACCEPTABLE

SUMMARY

OF INPUTS: 175 0 9 $50E+08 26170. 12 17 -> ACCEPTABLE 180.0 9 700E+08 26582. 12 38 -> ACCEPTABLE 185 0 9 823E+08 23917. 12 51 -> ACCEPTABLE Tstie' H4 Fauhed. New l pads & Safety Factor w 190 0 9 915E+08 27169. 12.62 -> ACCEPTABLE 1.0 deg (COARSE) An91o increment 195 0 9 975E+08 27334. 12.70 -> ACCEPTABLE Membrane Stress, Pm. 844. pal Bendin9 Stress Pb. 1375. psi 200 0 1.000E+09 27413 12.73 -> ACCEPTABLE = 1.13 205 0 1.000E+09 27403. 12.73 -> ACCEPTABLE Safety Factor, SF Mean Redeus, Rm 8800nnches 210 0 9 883E+08 27082. 12 58 -> ACCEPTABLE l . 1.500 inches 215 0 9.845E+08 26977. 12 54 ->ACCI:P1ABLE Wat Th6ckness,1 220 0 0 890E+08 27101. 12 59 ->ACCEPTxBLE Streno intensty, Sm = 16900 pW Fluence 126E+20 n/cm 2 225 0 9.661E+08 26474. 12.31 ->ACCEPTA BLE a (peak value of evaluated region at B215R1) 230 0 9 684E+08 26536 12 34 ->ACCEPTA3LE (Thus, LEFM evaluation not apr'ecable) 235 0 9 697E+08 26571. 12 35 ->ACCEPTAEi,E 240 0 9 461E+08 25925, 12 00 ->ACCEPTABLC l THETA 1 THETA 2 THICKNESS 245 0 9 471E+08 25953. 12 08 -> ACCEPTABLE 250 0 9 402E+08 25763. 11 99 -> ACCEPTABLE f REGION ldeg ] [deg ] [ inches] 255 0 9 J22E+08 25544. 11.89.-> ACCEPTABLE 1 60 0 91.2 150ri 260 0 9.229E+08 25289. 11.78 -> ACCEPTABLE 2 115 4 120 0 1.500 265 0 9.124E+08 25001. 11 65 -> ACCEPTABLE 3 150 0 172.0 1 500 270 0 9 007E+08 24883. 11,50 -> ACCEPTABLE 4 202 4 206 4 1,500 275 0 8 881E+08 24336. 11.35 -> ACCEPTABLE 5 286 3 273$ l500 280 0 8 745E+08 23963, 11.18 -> ACCEPTABLE 6 277 9 297.1 1 500 285 0 8 601E+08 23568. 11 00 -> ACCEPTABLE 7 334 5 -338 5 1.500 290 0 8387E+08 22982. 10 74 -> ACCEPTABLE 295 0 8 429E+08 23099. 10 79 -> ACCEPTABLE 300 0 8 251E+0B 22611. 10 57 -> ACCEPTABLE LIMIT LOAD RESULTS: 305 0 8 081E+08 22143. 10.36 -> ACCEPTABLE 310 0 8.168E+08 22383 10 47 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 8012E+08 21956. 10 27 -> ACCEPTABLE THE FLAWS TAKU COMPRESSION 320 0 7 857E+08 21532. 10 08 -> ACCEPTABLE 325 0 7.969E+08 21837, 10 22 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 7.815E+08 216 a 10 03 -> ACCEPTABLE [de9] On-ibs) [ psi) FACTOR RESULT 335 0 7.838E +08 21479 10 06 -> ACCEPTABLE 3d0 0 7.756E+08 21254. 9 96 -> ACCEPTABLE 00 7.266E+08 19910 9 35 -> ACCEPTABLE 345 0 7 657E+08 20982. 9 84 -> ACCEPTABLE 50 6 961E+08 19075 8 98 ->ACCF.PTABLE 350 0 7.540E+08 20663. 9 69 -> ACCEPTABLE 10 0 6 936E+08 19006. 8 95 > ACCEPTABLE 155 0 7.408E+08 20300. 9 53 -> ACCEPTABLE 15 0 6 914E+08 18946. 8 92 -> ACCEPTABLE 20 0 8 640E+08 18197. 8 58 ->ACCEP TABLE ACCEPTABLE! 25 0 6 641E+08 18199 8 58 -> ACCEPTABLE MINIMUM SAFETY FACTOR = 8 41 AT 35 0 DEGREES-- 30 0 6 503E+08 17621. 8 41 -> ACCEPTABLE 35 0 6 502E+08 17818 8 41 -> ACCEPTABLE 40 0 6626E+08 18156. 8 56 > ACCEPTABLE 45 0 6 592E+08 18064.. 8 52 > ACCEPTABLE 50 0 8 834E+08 18728 8 82 > ACCEPTABLE $5 0 6 908E+08 18931. 8 91 -> ACCEPTABLE 60 0 6 809E+08 18659 8 79 > ACCEPTABLE 65 0 6 981E+08 19130 9 00 > ACCEPTABLE 70 0 7 059E+08 19344. 9 10 -> ACCEPTABLE 75 0 7.130E+00 19538. 9 19' ~> ACCEPTABLE 80 0 7.194 E+08 19713 9 26 -> ACCEPTABLE 85 0 7,344 E+08 20125 9 45 -> ACCEPTABLE 90 0 7.318E +08 20054 9 42 -> ACCEPTABLE 95 0 7.487E+08 20462. 9 60 > ACCEPTABLE 100 0 7 360E+04 20169 9 47 > ACCEPTABLE 105 0 7 522E+08 20613 9 67 > ACCT:PTABLE i 110 0 7 691E+08 21077c 9 88 ->ACCEP7ABLE 115 0 7 627E+08 20900. 9 SO -> ACCEPTABLE 12C0 7 822E*08 21436 -10 04 > ACCEPTABLE i 125 0 7 951E+08 21788 10 20 -> ACCEPTABLE 130 0 8 080E+08 22141. 10 36 -> ACCEPTABLE 1350 8 205E+08 22484 10 51 ->ACC,EPTABLE

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C:rolina Pow:r & Light Comp:ny ESR 97-00034 Rcv. O Brunswick NucIcar Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 10 85:Mormal Usnt, Good for 600 days from Sept 1992 155 0 1659E+09 45471, 22 57 -> ACCEPTABLE 160 0 1658E+09 45432. 22 55 > ACCEPTABLE Filename DLLS 18-97 For 165 0 1629E+09 44626 22 15 -> ACCEPTABLE OLL DISTRIBUTED LIGAMENT LENGTH EVALUATION. REV. 21 170 0 1611E+09 44133 21 91 -> ACCEPTABLE (094 9/96) 175 0 1590E+09 43560. 21 63 -> ACCEPTABLE DATE OF THIS ANALYSIS. 10/06/1997 180 0 1.566E+09 42914. 21 31 -> ACCEPTABLE 185 0 1.540E+09 42198 20 95 -> ACCEPTABLE

SUMMARY

OF INPUTS: 190 0 1511E+09 41418. 2057 -> ACCEPTABLE 195 0 1.481 E+09 40580 20 15 -> ACCEPTABLE Title H5 N/U B211 data W/New Loads & Safety Fa 200 0 1447E +09 39644. 19 69 -> ACCEPTABLE 2050 1419E+09 38897 19 32 -> ACCEPTABLE 10 deg (COARSE) Angle increment = Membrane Stress, Pm = 210 psi 210 0 1.391 E+09 38109 18 93 -> ACCEPTABLE 215 0 1.345E+09 36860 18 32 -> ACCEPTABLE Bendog Stress, Pb 1914. psi = 2 25 220 0 1.316E +09 36052. 17 92 ->ACCEPTABL E Safety Fador, SF Mean Radeus, Rm = 88 00 inct, 225 0 1.287E+09 35274-17 53 -> ACCEPTABLE Wall Thickness,1 = 1500 mch 230 0 1260E+09 34517. 17.16 -> ACCEPTABLE 235 0 1238E+09 33929 16 87 -> ACCEPTABLE Stress intensty, Sm = 16900 t.si Fluence = 2 24E+20 n/cm 2i end of hcensed hfe) 240 0 1.223E+09 33514. 16 66 -> ACCEPTABLE a 245 0 1214E+09 33275 16 54 -> ACCEPTABLE (Thus, LEFM evaluation not apphcabt 250 0 1.212E +09 33216 1651 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 255 0 1216E+09 33335 16 57 -> ACCEPTABLE 260 0 1.227E +09 33632. 16 72 -> ACCEPTABLE REGION [deg) [deg) [ inches) 265 0 1.234E+09 33824 16 82 > ACCEPTABLE 1 13 8 80 2 1.500 270 0 1,255E +09 34382. 17 09 -> ACCEPTABLE 2 80 2 170 2 0480 275 0 1.278E+09 35016 17.40 -> ACCE PT ABLE 3 197 4 233 8 0 480 280 0 1.303E+09 35718 17.75 -> ACCEPTABLE 4 233 8 291.4 1 500 285 0 1.331E +09 36474 18 12 -> ACCEPTABLE 5 291.4 340 2 0 480 290 0 1360E+09 37280. 18 52 -> ACCEPTABLE 295 0 1.391E+09 38125 18 94 -> ACCEPTABLE 300 0 1426E+09 39078. 19 41 -> ACCEPTABLE LIMli LOAD RESULTS 305 0 1.456E +09 39880. 19 81 > ACCEPTABLE 310 0 1478E+09 40511. 20.12 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1512E+09 41442. 20 58 > ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1529E+09 41893 20 80 > ACCEPTABLE 325 0 1.541 E+09 42241. 20 97 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1565E +09 42894. 21 30 -> ACCEPTABLE ldeg) [in-lbs) [pss) FACTOR RESULT 335 0 1.564E+09 42856. 21.28 > ACCEPTABLE 340 0 1.572E+09 43066. 21.38 ->ACC(!PTABLE 00 1.5%E +09 43727. 21 71 -> ACCEPTABLE 345 0 1579E+09 43256 21 48 -> ACCEPTABLE 50 1601E+09 4'561. 21 77 -> ACCEPTABLE 350 0 1585E+09 43428 21.56 > ACCEPTABLE 10 0 1605E+09 43988. 21 84 -> ACCEPTABLE 355 0 1.590EG9 43584 21 64 -> ACCEPTABLE 15 0 1610E+09 44110 21 90 -> ACCEPTABLE 20 0 1614E +09 44231. 21 96 > ACCEPTABLE ACCEPTABLE! MINIMUM SAFETY FACTOR = 16 51 AT 250 0 25 0 1625E+09 44518 22 10 -> ACCEPTABLE DEGREES. 30 0 1631E+09 44693 22 19 -> ACCEPTABLE 35 0 1622E+09 44451. 22 07 -> ACCEPTABLE 40 0 1625E+09 44531 22 11 > ACCEPTABLE 45 0 1622E *09 44436 22 06 -> ACCEPTABLE 50 0 1 6.'0E +09 44401. 22 04 -> ACCEPTABLE 55 0 1620E+09 44393 22 04 -> ACCEPTABLE 60 0 1621E+09 44413 22 05 > ACCEPTABLE 65 0 1629E+09 44628 22 15 -> ACCEPTABLE 70 0 1629E+09 44633 22if -> ACCEPTABLE 75 0 1624E+09 44500 22 0s -> ACCEPTABLE 80 0 1625E+09 44516 22 10 > ACCEPTABLE 85 0 1626E+09 44560 22.12 -> ACCEPTABLE 90 0 1629E+09 28 22 15 -> ACCEPTABLE 95 0 1632E+09 44719 22 20 > ACCEPTABLE 100 0 1636E+09 44827. 22 25 -> ACCEPTABLE 105 0 1640E+09 44950 22 31 -> ACCEPTABLE 110 0 1645E+09 45085. 22 38 -> ACCEPTABLE 115 0 - 1650E+09 45226 22 45 -> ACCEPTABLE 120 0 1656E+09 45369 22 52 -> ACCEPTABLE i 125 0 1661E+09 45512. 22 59 -> ACCEPTABLE l 130 0 1666E +09 45648. 22 66 > ACCEPTABLE 135 0 1670E*09 45773 22 72 -> ACCEPTABLE 140 0 1661E +09 45515 22 59 -> ACCEPTABLE 145 0 1673E+09 45850 22.76 > ACCEPTABLE 150 0 1671E+09 45778 22 72 > ACCEPTABLE

Ccrolina Pow:t & Light Company ESR 97 00034 Rnv. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 11 / H0 Emergency, Gngdigdpg_ days from Sept 1997 155 0 1659E +09 45471 17 21 -> ACCEPTABLE 160 0 1658E+09 45432. 17.19 -> ACCEPTABLE F61ename DLLS.18-97 For 165 0 1629E+09 44626 16 89 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVAltJATION, REV. 21 1O O 1.611E+09 44133 16 71 -> ACCEPTABLE (09/19/96) 175 0 1590E+09 43560 16 49 -> ACCEPTABLE DATE OF THIS ANALYSIS-10/06/1997 180 0 M56E+09 42914 16 25 -> ACCEPTABLE 185 0 1440E+09 42198 15 98 -> ACCEPTABLE

SUMMARY

OF INPUTS 190 0 1511E +09 41418. 15 68 -> ACCEPTABLE 195 0 1481E+09 40580 15 37 -> ACCEPTABLE Title-HS Emerg B211 & D213 data W/New Loads a 200 0 1.447E+09 39644 1502 -> ACCEPTABLE 10 de9 (COARSE) 205 0 1419E+09 38897. 14 73 -> ACCEPTABLE Angle increment Membrane Stress, Pm. 221 psi 210 0 1391E+09 38109 14 44 -> ACCEPTABLE Bendn9 Stress Pb = 2434 psi 215 0 1.345E+09 36860. 13 97 -> ACCEPTABLE 1.50 220 0 1316E+09 36052. 13 66 ->ACCEPTADLE Safety F actor, SF = 88 00 inches 225 0 1287E+09 35274. 13 37 -> ACCEPTABLE Mean Radius, Rm = 1.500 inches 230 0 1260E+09 34517. 13 08 -> ACCEPTABLE Wallihickness.1 = Stress intensity, Sm = 16900 psi 235 0 1238E+09 33929 12.86 -> ACCEPTABLE Fksence = 2 24E+20 n/cm'2 (at end of licensed hfe) 240 0 1.223E +09 33514. 12.71 -> ACCEPTABLE (Thus. LEFM evaluation not apphcable) 245 0 1.214 E +09 33275 12 62 -> ACCEPTABLE 250 0 1.212E+09 33216. 12 59 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 2550 1216E+09 33335 12 64 -> ACCEPTABLE REGION (deg ) (deg j (inches) 260 0 1227E+09 33632. 12 75 -> ACCEPTABLE 265 0 1.234E+09 33824 12 82 ->ACCEPTADLE 1 13 1, 60 2 1 500 270 0 125bE+09 34382. 13 03 -> ACCEPTABLE 2 80 2 170 2 0 480 2750 1278E+09 35016 13 27 -> ACCEPTABLE 3 1974 233 8 0 480 280 0 1.303E+09 35716. 1354 -> ACCEPTABLE 4 233 8 291 4 1.500 285 0 1,331 E+09 36474 13 82 -> ACCEPTABLE 5 291 4 340 2 0 480 290 0 1360E+09 37280 14 12 -> ACCEPTABLE 295 0 1391E+09 38125 14 44 ->ACCEPTADLE 300 0 1.426E + 09 39078 14 40 -> ACCEPTABLE LIMIT LOAD RESULTS. 305 0 1.456E +09 39886= 15 11 -> ACCEPTABLE A, 310 0 1478E+09 40511. 15 34 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1512E+09 41442. 15 69 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1529E+09 41093 1566 -> ACCEPTABLE 325 0 1541E+09 42241 15 99 ->ACCEPTADLE ALPHA MOMENT Pb' SAFETY 330 0 1.565E+09 42894. 16 24 -> ACCEPTABLE ldeg] (m Ibs) (psi) FACTOR RESULT 335 0 1.564E+09 42856 16 22 -> ACCEPTABLE 340 0 1.572E+09 43066 16 30 -> ACCEPTABLE 00 1.596E +09 43727. 1655 -> ACCEPTABLE 345 0 1579E+09 43256 16 38 -> ACCEPTABLE 50 1601E +09 43861. 16 60 ->ACCEP7ADLE 350 0 1.585E+09 43428 16 44 -> ACCEPTABLE 10 0 1605E+09 43988 16 65 >ACCEPTADLE 355 0 1590E+09 43584. 16 50 -> ACCEPTABLE 15 0 1610E+09 44110 16 70 -> ACCEPTABLE 20 0 1614E+09 44231 16 74 -> ACCEPTABLE ACCEPTABLE! MINIMUM SAFETY FACTOR = 12 59 AT 250 0 25 0 1625E+09 44518 16 85 -> ACCEPTABLE DEGREES. 30 0 1631E+09 44693 16 92 -> ACCEPTABLE 35 0 1.622E +09 44451. 16 83 ->ACCEPTADLE 40 0 1625E+09 44531 16 56 -> ACCEPTABLE 45 0 1622E +09 44436 16 82 > ACCEPTABLE 50 0 1620E+09 44401. 16 81 -> ACCEPTABLE 55 0 1620E +09 44393. 16 80 -> ACCEPTABLE 60 0 1621E+09 44413 16 81 > ACCEPTABLE 65 0 1829E+09 44628 16 89 -> ACCEPTABLE 70 0 1829E+09 44633 16 89 > ACCEPTABLE 75 0 1624E+09 44500 16 84 -> ACCEPTABLE 80 0 1625E+09 44516 16 85 -> ACCEPTABLE 85 0 1626E+09 44560. 16 87 -> ACCEPTABLE 90 0 1629E+09 44628 1689 > ACCEPTABLE 95 0 1632E+0A 44719 16 93 > ACCEPTABLE 100 0 1636E+09 44827. 16 97 -> ACCEPTABLE 1050 1640E+09 44950 17 01 -> ACCEPTABLE 110 0 1645E+09 45085. 17 06 -> ACCEPTABLE 115 0 1650E+09 45226 17.12 > ACCEPTABLE 120 0 1656E+09 45369 17 17 -> ACCEPTABLE i 125 0 1661E+09 45512. 17 23 -> ACCEPTABLE 130 0 1666E+09. 45G:". 17.28 -> ACCEPTABLE 135 0 1670E+09 45773 17.32 -> ACCEPTABLE 140 0 1661E +09 45515 17 23 > ACCEPTABLE 145 0 1673E+09 45850 17 35 -> ACCEPTABLE 150 0 1671E *09 45778 17.33 > ACCEPTABLE M

Cuolina Pow:r & Light Company ESR 97 00034 nov. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 12 H5 Faulteddood for 609_ days from Sept 1997 155 0 1630E+09 44674 13 46 -> ACCEPTABLE 160 0 1627E+09 44580. 13 43 -> ACCEPTABLE Falename DLL818-97 For 165 0 1=612E+09 44169 13 31 -> ACCEPTABLE DLL DISTRIDUTED LK1 AMENT LENGTH EVALUATION, REV 21 170 0 1.594E +09 43675. 13 16 -> ACCEPTABLE (09/19/96) 175 0 1573E+09 43103. 12 99 -> ACCEPTABLE DATE OF THIS ANALYSIS 1WO6/1997 180 0 1549E+09 42456. 12 80 -> ACCEPTABLE 185 0 1.523E+09 41740. 12 59 -> ACCEPTABLE

SUMMARY

OF INPUT & 190 0 1495E+09 40960 12 36 -> ACCEPTABLE 195 0 1464E+09 40122, 12 11 -> ACCEPTABLE .......+......... Tt6e: H5 Faulted B211 & B213 data W/New loads 200 0 142BE+09 39138 11 82 -> ACCEPTABLE 10 deg (COARSE) 205 0 1402E+09 38414. 11.60 -> ACCEPTABLE Angle 6ncremerd = Membrane Stress, Pm = 821. psi 210 0 1357E+09 37180 11.24 -> ACCEPTABLE Dending Stress. Pb = 2560. psi 215 0 1.329E +09 36414. 11 01 -> ACCEPTABLE 1.13 220 0 1300E+09 35632. 10 78 -> ACCEPTABLE Safety Factor, SF = Mean Radius, Rm = 88 00 h.ches 225 0 1.267E+09 34728. 1051 -> ACCEPTABLE Well TNcAness, t = 1 500 inches 230 0 1240E+09 3J971. 10.2P -> ACCEPTABLE Stress intensity, Sm = 16900 psi 235 0 1218E+09 33382. 10 12 > ACCEPTABLE Fluence = 2 24E+20 n/cm*2 (at end of heensed hfe) 240 0 1.203E+09 32967. 9 99 -> ACCEPTABLE (Thus, LEFM evolust60n not apphcaNe) 245 0 1.194E +09 32729. 9 92 -> ACCEPTABLE 250 0 1.192E+09 32670. 9 91 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 255 0 1.197E +09 32789 9 94 -> ACCEPTABLE REGJON [deg ] (deg ) [inchenj 200 0 1.207E +09 33086. 10 03 -> ACCEPTABLE '65 0 1.217E+09 33355. 10 11 -> ACCEPTABLE 1 13 8 80 2 1 500 270 0 1237E+09 33899 10 27 -> ACCEPTABLE 2 80 2 170 2 0 480 275 0 1260E+09 34519. 10 45 -> ACCEPTABLE 3 197 4 233 8 0 480 280 0 1.285E+09 35205 10 66 > ACCEPTABLE 4 2338 291 4 1 500 285 0 1312E+09 35950. 10 88 -> ACCEPTABLE 291 4 340 2 0 480 290 0 1341E+09 36743-11.11 -> ACCEPTABLE 295 0 1.371E+09 37574, 11.36 -> ACCEPTABLE 300 0 1394E+09 3'1193 11 54 -> ACCEPTABLE LIMIT LOAD RESULTS: 305 0 1.427E

• 09 39107. 11 81 -> ACCEPTABLE 310 0 1.464E+09 40117.

12.11 ->ACCEPTADLE ....m.............. NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1483E+09 40645. 12 26 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1499E+09 41078. 12 39 -> ACCEPTABLE 325 0 1526E+09 41829 12 61 ->ACCEPTADLE ALPHA MOMENT Pb' SAFETY 330 0 1535E+09 42061. 12.68 -> ACCEPTABLE [deg) [in-lbs) [ psi) FACTOR RESULT 335 0 1.54?E +09 42256. 12.74 -> ACCEPTABLE 340 0 1550E+09 42479 12 81 -> ACCEPTABLE 00 1576E+09 43192 13 02 -eACCEPTABLE 345 0 1658E+09 42682 12 87 -> ACCEPTABLE 50 1582E *09 43339 13 06 -> ACCEPTABLE 350 0 1564E+09 42866. 12 92 -> ACCEPTABLE 10 0 1.587E+09 43480 13 10 -> ACCEPTABLE 355 0 1570E+09 43035. 12 97 ->ACCFATABLE 15 0 159?E+09 43616. 13 14 > ACCEPTABLE 20 0 1597E+09 43751. 13 18 > ACCEPTABLE ACCEPTADLE! MINIMUM SAFETY FACTOR = 9 91 AT 250 0 25 0 1610E+09 44111. 13 29 > ACCEPTABLE DEGREES 30 0 1603E +09 43917. 13 23 -> ACCEPTABLE 35 0 1609E +09 44082 13 28 > ACCEPTABLE 40 0 1613E+09 44190 13 31 -> ACCEPT ADLE 45 0 1608E+09 44072 13 28 ->ACCEPTADLE 50 0 1608E+09 44052 13 27 > ACCEPTABLE $5 0 t608E+09 44059 13 27 ->ACCEPTADLE 60 0 1609E+09 44095 13 28 >ACCEPTADLE 65 0 1610E+09 44132 13 30 -> ACCEPTABLE 70 0 1611E+09 44136 13 30 > ACCEPTABLE 75 0 1612E+09 44179. 13 31 -> ACCEPTABLE 80 0 1612E+09 44180 13 31 ->ACCEPTADL E 85 0 1613E+09 44208 13 32 -> ACCEPTABLE 90 0 -1615E+09 44261. 13 33 > ACCEPTABLE 95 0 1818E +09 44337 13 36 -> ACCEPTABLE 100 0 1621E+09 44430 13 38 > ACCEPTABLE i 105 0 1625E+09 44539 13 42 > ACCEPTABLE 110 0 1630E+09 44659 13 45 -> ACCEPTABLE 115 0 1618E+09 44330 13 35 > ACCEPTABLE 120 0 1$22E+09 44446 13 39 > ACCEPTABLE 125 0 1626E+09 41b 13 42 > ACCEPTABLE 130 0 1630E+09 4466 13 45 -> ACCEPTABLE 135 0 1634E+09 44766 13 48 > ACCEPTABLE 140 0 1644E+09 45040 1356 > ACCEPTABLE 145 0 1637E+09 44865 13 51 > ACCEPTABLE l 150 0 1642E+09 44999 13 55 >ACCEPTABi.E l l l

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Ccrolina Pow:r & Light Company ESR 97 00034 Rev. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation y Page 14_ ) l}Q-N/U. Good for 1800 days from March 199) 150 0 1923E+09 5269T. 19 34 -> ACCEPTABLE 155 0 1932E*09 52945 19 43 -> ACCEPTABLE Fdename DLL816-97 For 160 0 1937E+09 53078 1947 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 165 0 1951E+09 53449 19 61 ->A CCEPTABLE (09/19/96) 170 0 1947E+09 53363 19 58 -> ACCEPTABLE DATE OF THIS ANALYSIS- 097,snp7 1750 1951E +09 53473 19 62 --> ACCEPTABLE 180 0 1952E+09 53491. 19 62 -> ACCEPTABLE

SUMMARY

OF INPUTS 185 0 1944E+09 53277. 1955 -> ACCEPTABLE 190 0 1947E+09 53346. 19 57 -> ACCEPTABLE Title H6a N/U W/New Loads & Safety Factors 1950 1945E +09 53292 19 55 -> ACCEPTABLE 10 deg (COARSE) 200 0 1927E+09 52813 19 38 -> ACCEPTABLE Angie 6ncrement Memtsane Stress, Pm. 594 pti 2050 1921E+09 52647. 19 32 -> ACCEPTABLE Bondag Stress. Pb = 2162. pal 210 0 1896E+09 $1950. 19 07 -> ACCEPTABLE 2 25 2150 1877E+09 51441. 1888 -> ACCEPTABLE Safety Factor, SF = Mean Radeus, Rm 88 00 inches 220 0 1848E+09 50642. 18 59 -> ACCEPTABLE Wall Thickness, t 1500 inches 2250 1828E+09 50091. 18 39 -> ACCEPTABLE 230 0 1811E+09 4962d-18 22 -> ACCEPTABLE Stress intensity, Sm = 18900 pst Fluence = 162E+18 n/cm^2 (at end of licensed hfe) 235 0 1.797E+09 49255. 18 09 -> ACCEPTABLE (Thus, LEFM evaluation not apolecable) 240 0 1.787E+09 48976 17 99 -> ACCEPTABLE 245 0 1.786E+09 48948. 17.98 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 250 0 1.782E+09 48819 17 93 -> ACCEPTABLE 255 0 1776E+09 48662. 17.87 -> ACCEPTABLE REGION [deg ) ldeg] Dnches] 260 0 1.774E+09 48601. 17 85 -> ACCEPTABLE 1 19 0 75 4 1 500 265 0 1775E+09 48635 17 86 -> ACCEPTABLE 2 88 2 143 3 1 500 270 0 1.780E+09 48756. 17 91 -> ACCEPTABLE 3 148 9 156 8 1.500 275 0 1.784E+09 48897. 17 96 -> ACCEPTABLE 4 197.2 223 4 1 500 250 0 1.795E +09 49100 18 06 -> ACCEPTABLE 227 8 260 9 1 500 285 0 1.797E +09 49249 18 09 -> ACCEPTABLE 8 267 0 336 7 1500 290 0 1805E+09 49459 18 16 -> ACCEPTABLE 295 0 1816E+09 49766 18 27 -> ACCEPTABLE 300 0 1831E+09 50167. 18 42 -> ACCEPTABLE LIMIT LOAD RESULTS 30$ 0 1.849E +09 50661. 18 60 -> ACCEPTABLE 310 0 1870E+09 51241. 18 81 -> ACCEPTABLE NOTE-THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1.894E+09 51906 19 05 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1921E+09 52649 19 32 -> ACCEPTABLE 325 0 1952E+09 53482. 19 62 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1973E+09 54060 19 83 > ACCEPTABLE (deQ] (n-lbs] [psil FACTOR RESULT 335 0 1990E+09 54519 20 00 -> ACCEPTABLE 34v. 2 013E+09 55171. 20 23 -> ACCEPTABLE OO 2 032t:+09 55683 20 42 > ACCEPTABLE 345 0 2 022E+ 09 55400 20 32 -> ACCEPTABLE 50 2 033E+09 55700 20 43 > ACCEPTABLE 350 0 2 029E+09 55603 20 39 -> ACCEPTABLE 10 0 2 033E+09 55705 1043 > ACCEPTABLE 3550 2 031E+09 55651 20 41 ->ACCEPTAPI.E 15 0 2 017E+09 55271. 20 27 -> ACCEPTABLE 20 0 2 008E+09 55034 20 18 -> ACCEPTABLE ACCEPTABLE! 25 0 1995E+09 54669 20 05 -> ACCEPTABLE MINIMUM SAFETY FACTOR = 17 85 AT 260 0 DEGREES. 30 0 1969E +09 53953 19 79 -> ACCE PTABLE 35 0 1946E +09 53331. 19 57 > ACCEPTABLE 40 0 1925E+09 52757 19 36 -> ACCEPTABLE 45 0 1907E+09 52256 19 18 -> ACCEPTABLE 50 0 1891E +09 51829 19 02 -> ACCEPTABLE 55 0 1879E+09 51482. 18 90 -> ACCEPTABLE 60 0 1874 E+09 51353. 1885 -> ACCEPTABLE 65 0 1859E+09 50954. 18 70 > ACCEPTABLE 70 0 1842E+09 50466. 18 53 > ACCEPTABLE 75 0 1830E+09 50137. 18 41 -> ACCEPTABLE 80 0 1818E + 09 49811. 18 29 -> ACCEPTABLE 85 0 1809E+09 49574 18 20 ->ACCEPTABL E 90 0 1804E+09 49429 18 15 > ACCEPTABLE 95 0 1802E+09 49375 18 13 -> ACCEPTABLE 100 0 1806E+09 49476 18 17 > ACCEPTABLE 105 0 1805E+09 4S:65 18 16 -> ACCEPTABLE 110 0 1808E+09 49531. 18 19 > ACCEPTABLE 115 0 1813E+09 49694 18 25 -> ACCEPTABLE 120 0 1823E +09 49952. 18 34 > ACCEPTABLE 125 0 1836E+09 50304 18 47 > ACCEPTABLE 130 0 1848E +09 50647. 18 59 -> ACCEPTABLE 135 0 1865E +09 51104. 18 76 > ACCEPTABLE 140 0 t885E+09 51643 18 95 -> ACCEPTABLE 145 0 1900E +09 52076 19 11 -> ACCEPTABLE

Caiolin2 Pow:r & Light Company ESR 97 00034 Rzv. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page 15 N, Bla Emergency Good fgfjl0Q4ays from MarctL111g 150 0 1923E+09 52697. 15 09 -> ACCEPTABLE 155 0 1972E+09 52945 15 16 ->ACCEPTABM Foeeame DLL81847 For 160 0 1937E+09 53078 15 20 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 155 0 1951E +09 53449 15 30 -> ACCEPTABLE '70 0 1947E+09 53363 15 28 -> ACCEPTABLE (09/19/96) DATE OF THl3 ANALYSIS 09/30/1997 1750 1951E+09 53473 15 31 -> ACCEPTABLE 180 0 1952E+09 53491. 15.31 -> ACCEPTABLE

SUMMARY

OF INPUTS 185 0 1944E+09 53277. 15 25 -> ACCEPTABLE 190 0 1.947E +09 53346. 15 27 -> ACCEPTABLE 195 0 t 945E+09 53292 15 26 -> ACCEPTABLE Title H6a Emer9ency W/New Loads & Safety Facto 10 de9 (COARSE) 200 0 1917E+09 52818. 15 12 -> ACCEPTABLE Angle merement Membrane 1 tress. Pm. 829 pti 205 0 1921E +09 52647. 15 08 -> ACCEPTABLE 210 0 1896E+09 51950 14 88 -> ACCEPTABLE Dending St. :ss. Pb = 2905 ps! = 1 50 215 0 1.877E+09 51441. 14 73 -> ACCEPTABLE Safety Fad t, $F Mean Rad 61. Rm 88 00 triches 220 0 1848E+09 50642. 14.51 ->ACCEPTATLE WaH Thickness, t = 1500 mebes 225 0 1828E+09 50091. 14v5 -> ACCEPTABLE 230 0 1811E+09 49628. 14 22 ->ACCEPTADLE Stress intensity Sm = 16900 psi Fluerce 162E+18 n/cm*2 (at end of hcensed hfe) 235 0 1.797E+09 49255 14 12 -> ACCEPTABLE 240 0 1.78 7E+ 09 48978. 14 04 -> ACCEPTABLE (Thus, LEFM evaluaton not apphcable) 245 0 1.786E+09 48948. 14 03 -> ACCEPTABLE THETA 1 THETA 2 THICKNESS 250 0 1.782E +09 48819 13 99 -> ACCEPTABLE 255 0 1.776E +09 48662. 13 95 > ACCEPTABLE REGION [deg ) ldeg ) [6nches) 260 0 1.7'4 E +09 48601. 13 93 > ACCEPTABLE 1 19 0 75 4 1 500 2650 i,775E+09 48635 13 94 >ACCEPTADLE 2 88 2 143 3 1 500 270 0 1.78CE +09 48766 13 98 > ACCEPTABLE 3 146 9 158 8 1 500 275 0 1.784E+09 48897, 14 01 > ACCEPTABLE 4 197.2 223 4 1.500 280 0 1.795E+09 49180 14 09 -3 ACCEPTABLE 5 227 8 260 9 1 500 285 0 1.797E+09 49249 14.11 > ACCEPTABLE 6 267.0 336 7 1500 290 0 1805E+09 49459. 14 17 > ACCEPTABLE 295 0 1816E+09 49766 14 26 > ACCEPTABLE 300 0 18316:+09 50167. 14.37 >ACCEPTADLE LIMIT LOAD RESULTS 3050 1.849E+09 50661. 1451 - >ACCEPTADLE 310 0 1870E+09 51241. 14 68 -> ACCEPTABLE NOTE THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1894E+09 51906. 14 87 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1921E+09 5264V 15 08 -> ACCEPTABLE 325 0 1952E+09 53482. 15 31 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1.973E +09 54060 15 47 -> ACCEPTABLE [de9] [o sbs] [ psi] FACTOR RESULT 335 0 1990E+09 54519 15 60 ->ACCEPTADLE 340 ') 2 013E+09 55171. 15 79 -> ACCEPTABLE 00 2 032E+09 55683 15 93 ->ACCEPTADLE 345 0 2 022E+09 55400. 15 85 -> ACCEPTABLE 50 2 033E+09 $5700- 15 94 > ACCEPTABLE 350 0 2 029E+09 $5603. 15 91 ->ACCtiPTADLE 10 0 2 033E+09 55705 15 94 -> ACCEPTABLE 355 0 2 031E+09 55651, 15 93 -> ACCEPTABLE 15 0 2 017E+09 55271 15 82 -> ACCE PT ABL E 20 0 2 008E+09 55034 15 75 ->ACCEPTADLE ACCEPTABLE! 25 0 1995E+09 54669 15 65 -> ACCEPTABLE MINIMUM SAFETY FACTOR.13 93 AT 260 0 DEGREES. 30 0 1969E +09 53953 15 44 > ACCEPTABLE 35 0 1946E+09 53331 15 27 > ACCEPTABLE 40 0 1925E+09 52757. 15 11 -> ACCEPTABLE 45 0 1907E409 52256 14 96 ->ACCEPTADLE 50 0 1891C+ 39 51829 14 84 > ACCEPTABLE 55 0 1879E+09 51482. 14 75 -> ACCEPTABLE 60 0 1874E+09 51353 14 71 ->ACCEPTADLE 65 0 1859E+09 50E54. 14 60 -> ACCEPTABLE 70 0 1842E +09 50466 14 46 >ACCEPTADLE 75 0 1830E+09 50137. 14 37 -> ACCEPTABLE 80 0 1818E +09 49811. 14 27 -> ACCEPTABLE 85 0 1809E+09 49574 14 21 ->ACCEPTADLE 90 0 1804E+09 49429 14 16 -> ACCEPTABLE 95 0 1802E +09 49375 14 15 ->ACCEPTADLE 100 0 1806E+09 43476 14 18 >ACCEPTADLE 105 0 180$E *09 49465 14 17 > ACCEPTABLE 110 0 1808E +09 49531. 14 19 > ACCEPTABLE 115 0 t813E+09 49694 14 24 -> ACCEPTABLE 120 0 1823E +09 49952 14 31 -> ACCEPTABLE +I 125 0 1836E +09 50304 14 41 > ACCEPTABLE 130 0 1848E +09 50647 14 51 -> ACCEPTABLE 135 0 1865E+09 51104. 14 64 -> ACCEPTABLE 140 0 1885E+09 51643 14 79 -> ACCEPTABLE 145 0 1900E +09 52076 14 91 ->ACCEPTADL E

Ccrolina Pow:r & Light Company ESR 97 00034 Rcy. O Brunswick Nuclear Plant - Unit 2 AYTACHMENT B Engineering Evaluation Page 16 1 HitiguntdJood for 1300 days fro 0Warch 19H 150 0 1901E+09 52101. 12 07 -> ACCEPTABLE 155 0 1908E+09 52294 12 11 -> ACCEPTABLE Fuename. DLL818 97 For 160 0 1924E+09 52732 12 21 -> ACCEPTABLE DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION. REV 21 165 0 1.924E+09 52717. 12 21 -> ACCEPTABLE (09/19/96) 170 0 1914E+09 5:448 12 15 -> ACCEPTABLE DATE OF THIS ANALYSIS' 09/30/1997 175 0 1913E+09 52433 t215 -> ACCEPTABLE 180 0 1914E+09 52451, 12 15 -> ACCEPTABLE

SUMMARY

OF INPUTS 185 0 1930E+09 52895 12 25 -> ACCEPTABLE 190 0 1920E +09 $2623 12 19 -> ACCEPTABLE Title H6a Faulted Whew Loads & Safety Factors 195 0 1920E+09 $2623 12.19 -> ACCEPTABLE 10 deg (COARSE) 200 0 1916E+09 52504 12,16 -> ACCEPTABLE Angni, inctement = Membrane Stress. Pm = 1315 pal 2050 1899E +09 52042 12 06 -> ACCEPTABLE Bendin9 Sttess. Pb = 3110 psi 210 0 1.885E+09 51663 11 97 > ACCEPTABLE . 1.13 215 0 1.858E +09 50909. 11.80 -> ACCEPTABLE Safety Factor, SF Mean Radius, Rm = 88 00 inches 220 0 1835E+09 50294. 11 66 > ACCEPTABLE Wall Thickness, t 1500 mches 225 0 1815E+09 49743. 1154 > ACCEPTABLE Stress intensty, Sm 16900 psi J30 0 1798E+09 49280 11.43 -> ACCEPTABLE Fluencs 162E* 18 rvem*2 (at end of licensed isfe) 235 0 1.785E+09 48907, 11 35 -> ACCEPTABLE (Thus LEFM evaluaSon not applecable) 240 0 1775E+09 48628, 11 29 -> ACCEPTABLE i 245 0 1.767E+09 484C7. 11.24 ->ACCFPTABLE THETA 1 THETA 2 THICKNESS 250 0 1.754C+09 48067. 11.16 -> ACCEPTABLE 255 0 1.748E+09 47910. 11.12 -> ACCEPTABLE REGION lde9 ) (deg) pnches; 260 0 1.746E+09 47849 11.11 -> ACCEPTABLE 1 19 0 75 4 1 500 265 0 1.747E+09 47883. 11.12 > ACCEPTABLE 2 88 2 143 3 1500 270 0 1.752E+09 48014 11.15 -> ACCEPTABLE 3 148 9 156 6 1.500 275 0 1.760E+09 482391 11 20 -> ACCEPTABLE 4 197.2 223 4 1.500 280 0 1776E+09 4B676 11.30 -> ACCEPTABLE 221 6 200 9 1 500 285 0 1.786E+09 48939 11.36 -> ACCEPTABLE 8 267.0 336 7 1 500 290 0 1794E+09 49149. 11 40 -> ACCEPTABLE 295 0 180$E+09 49455 11 47 -> ACCEPTABLE 300 0 1819E+09 49857, 11 56 -> ACCEPTABLE LIMIT LOAD RESULTS 305 0 1837E+09 50350. 11 68 > ACCEPTABLE 310 0 1859E+09 50931. 11 81 > ACCEPTABLE NOTE THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1883E+09 51595. 11.96 ->ACCEPTADLE THE FLAWS TAKE COMPRESSION 320 0 1910E+09 52338 12.12 -> ACCEPTABLE 325 0 1933E*09 52969 12 27 -> ACCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1952E +09 53491. 12 39 -> ACCEPTABLE [deg) (n-ibs) [ psi) FACTOR RESULT 335 0 1978E+09 54213. 12 55 > ACCEPTABLE 340 0 1990E+09 5m7 12 62 -> ACCEPTABLE 345 0 19%E+09 54695. 12 66 -> ACCEPTABLE OO 2 014E+09 55189 12.77 -> ACCEPTABLE 50 2 006E+09 54977. 12 72 -> ACCEPTABLE 350 0 2 011E+09 55118 12 75 -> ACCEPTABLE 10 0 2 008E+00 55035 12.73 > ACCEPTABLE 355 0 2 013E+09 55157. 12.76 -> ACCEPTABLE 15 0 2 006E+09 54957. 12 72 -> ACCEPT ABL E 20 0 1987E+09 54447. 12 60 -> ACCEPTABLE ACCEPTABLE! 25 0 1976E+09 54138 12 53 -> ACCEPTABLE MINIMUM SAFETY FACTOR.11.11 AT 260 0 CEGREES 30 0 1960E+09 $3709 1743 -> ACCEPTABLE 35 0 1935E+09 $3021. 12 28 -> ACCEPTABLE 40 0 1914E+09 52447. 12 15 -> ACCEPTABLE 45 0 1896E+09 51945 12 04 -> ACCEPTABLE 50 0 1.880E+09 51519 11 94 -> ACCE PTABLE 55 0 1667E +09 51172 11 86 > ACCEPTABLE 60 0 1860E +09 50981. 11 82 > ACCEPTABLE 65 0 1842E+09 50470 11.70 -> ACCEPTABLE 70 0 1832E+09 50202. 11 64 ->ACCFPTABLE 75 0 1817E+09 49789 11 55 -> ACCEPTABLE 80 0 1.805E +09 49463 11 48 -> ACCEPTABLE $5 0 1 796E+09 49226 11 42 -> ACCEPTABLE 90 0 1791E+09 49081. 11 39 -> ACCEPTABLE 95 0 1.789E+09 49027. 11.38 > ACCEPTABLE 100 0 1.787E +09 48973 11 36 >ACCEPTABL E 105 0 1.782E+09 48825 11 33 > ACCEPTABLE 110 0 1784E +09 48891. 11 35 > ACCEPTABLE 115 0 1.790E+09 49054 11 38 > ACCEPTABLE ) 120 0 1800E +09 49312. 11 44 > ACCEPTABLE 125 0 1.812E *09 49664 11 52 > ACCEPTABLE 130 0 1836E +09 50317. 11 67 > ACCEPTABLE 135 0 1853E*09 50774 1177 -> ACCEPTABLE 140 0 1866E +09 51130 11 85 -> ACCEPTABLE 145 0 1890E+09 51798 12 00 > ACCEPTABLE

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Ctrolin2 Pow:r & Light Comp:ny ESR 97-00034 Rev. 0 -- Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering Evaluation Page 18 g 140 0 1.871E+09 55264. 15.74 -> ACCEPTABLE 145 0 1.908E+09 $6359. 16.05 -> ACCEPTABLE F4ename DLLS 18 97.For 150 0 1928E+09 56959. 16.22 > ACCEPTABLE DLL DtSTRIBUTED LIGAMENT LENGTH EVALUATION REV. 2.1 155 0 1956E+09 57791. 1645 -> ACCEPTABLE (09/HW96) 1604 1.970E+09 58210. 16 57 -> ACCEPTABLE DATE OF THIS ANALYSIS. 09/30/1997 165 0 1.979E+09 58474. 16 65 -> ACCEPTABLE 170 0 1.994E+09 58905 16 77 > ACCEPTABLE

SUMMARY

OF INPUTS: 175 0 _1.996E+09 58969, 16 79 -> ACCEPTABLE 180 0 1.990E+09 58784, 16.73 > ACCEPTABLE . m.. m....... Title. H7 Norm 4I/ Upset w/Rev'd Stresses & Sadot 185.0 1.980E+09 58493. 16 65 ->ACCEPTA3LE 190.0 - 1.962E+09 57980. 16.51 -> ACCEPTABLE 1.0 dog (COARSE 3 Angieincrement. Memtwane Stress. Pm = 603. psi 1950 1.935E+09 5T169. 1628 ->ACCEPTAdLE 8enden9 Ftress. Pb = 2946. psi 200 0 1.914E+09 56544. 16.10 -> ACCEPTABLE 2 25 205 0 1.879E+09 - 55515. 15 81 -> ACCEPTABLE Safety Fat tor, SF Mean Radius. Rm - = 84.75 inches 210 0 1.831E+09 54099. 15 41 -> ACCEPTABLE Wa8 Thestness, t = 1.500 inches 215 0 1.790E+09 52879. 15.07 -> ACCEPTABLE 220 0 1.739E+09 51364. 14 64 -> ACCEPTABLE Stress intens4y, Sm = 16900. poi Fluence = 2 28E+14 nkie2 (at en! of licensed hio) 225.0 1.695E+09 50067. 14.28 -> ACCEPTABLE 230.0 1.638E+09 48385. 13 80 -> ACCEPTABLE (Thus, LEFM evaluation not appleable) - 235 0 1.586E+09 46865. 13.38 -> ACCEPTABLE THETA 1 THETA 2 THICKNE'SS 240 0 1.533E+09 45288. 12 93 -> ACCEPTABLE 245 0 1.483E+09 43813 12 52 -> ACCEPTABLE REGION [de,g ] [deg ) [ inches) 250 0 1.437E+09 42452.. 12.13 -> ACCEPTABLE 1 17.3 152 4 1.500 255 0 1.395E+09 41214. 11.78 -> ACCEPTABLE 2 197.5 200 0 1.500 260 0 1.358E 09 40110 11.47 -> ACCEPTABLE 3 215 0 220.7 1.503 265 0 1.325E+09 39148 11.20 -> ACCEPTABLE 4 229 2 235.2 1.500 270 0 1.283E+09 37904. 10 85 -> ACCEPTABLE 5 258 7 290 7 1.500 275 0 1257E+09 37131. 10 63. -> ACCEPTABLE 6 295 2 3C3 8 1.500 280 0 1.240E+09 36636. 10 49 -> ACCEPTABLE 7 309.2 322.2 1.G)0 285.0 1.218E+09 35971. 10.31 -> ACCEPTABLE 8 325.7 330.7 1.500 290 0 1.20$E+09 35589. 10.20 -> ACCEPTABLE 295 0 1.197E+09 35372. 10.14 -> ACCEPTABLE 300 0 1.207E+09 35659. 10.22 -> ACCEPTABLE LIMIT LOAD RESULTS: 305 0 1.20E+09 35555. 10.19 -> ACCEPTABLE 310 0 1.201E+09 35469. 10.16 > ACCEPTABLE .... m........ m. NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1.213E+09 35829. 10 27 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION. 320.0 1.210E+09 35756. 10.24 -> ACCEPTABLE 325.0 1.207E+09 35668. 10.22 ->ALCEPTABLE ALPHA MOMENT Pb' SAFETY 330 0 1.221E+09 36070..10.33 -> ACCEPTABLE [deg] [in-lbs) [ psi) FACTOR RESULT 335 0 1.217E +09 35960. 10.30 -> ACCEPTABLE 340 0 1219E+09 36015. 10.32 -> ACCEPTABLE 00 1.260E+09 37212. 10 66 > ACCEPTABLE 345.0 1224E+09 36161. 10.36 -> ACCEPTABLE 50 1278E+09 37758. 10.81 > ACCEPTABLE 350 0 1.232E+09 36410. 10.43 -> ACCEPTABLE 10.0 1.300E +09 38497. 10 99 -> ACCEPTABLE 355 0 1.244E+09 36761. 10 53 -> ACCEPTABLE 15 0 1.323E+09 39092. 11.18 -> ACCEPTABLE 20 0 1.351E+09 39919 11.42 -> ACCEPTABLE ACCEPTABLE! 25 0 1.361E+09 40209 11.50 -> ACCEPTABLE MINIMUM SAFETY FACTOR = 10.14 AT 295.0 DEGREES. 30 0 1.386E+09 40952. 11.71 -> ACCEPTABLE 35 0 1.409E+09 41641 11.90 -> ACCEPTABLE 40 0 1.4172+09 41M8 11 96 -> ACCEPTABLE 45 0 1437E+09 - 42470 12.14 > ACCEPTABLE 50 0 1458E+09 43090. 12.31 -> ACCEPTABLE 55 0 1.466E+09 - 43320. 12.38 ->CCEPTABLE 60 0 1486E+09 43891. 12.54 -> ACCEPTABLE 65.0 1.503E+09 44392. 12.68 > ACCEPTABLE 70 0 .524E+09 45021. 12 86 -> ACCEPTABLE 75 0 1534E+09 45324-12 94 ->ACCEPTADLE 80 0-1.558E+09. 46042. 13.14 ->ACCEPTABlei 85 0 1.581E+09 46712. 13 33 > ACCEPTABLE 90 0 1.593E+09 47059 1343 -> ACCEPTABLE 95 0 1612E+09 47628 13 59 -> ACCEPTABLE 100 0 1.630E+09 48155 --13.74 ->ACCEPTADLE 105 0 1.651E+09 48737, 13 02 > ACCEPTABLE 110 0 1.676E+09 49518 14.12 -> ACCEPTABLE 115 0 1.704E+09 50344 14 36 -> ACCEPTABLE 120 0 1.735E+09 51257. 14 61 >ACCEPTADLE ?25 0 1.769E+09 52251, 14 8') ->ACCEIRABLE 130 0 1.803P09 ' 53281.-- 15.18 -> ACCEPTABLE 135 0 1835E 09 54224. 15 45- > ACCEPTABLE

Ccrolina Power & Light Company ESR 97-00034 Rev. O Bruwtwick Nuclear Plant - Unit 2 ATTACHMENT B Engincoring Evaluation Page 19 q HZ:Etntinency. Good foL12Q04ays from March 1996 140 0 1811E+09 55264 12 13 ->ACCEPTADLE 145 0 1.908E+09 56359 12 37 -> ACCEPTABLE Filename DLL8-18-97 For 150 0 1928E+09 56959 12 50 > ACCEPTABLE DLL DISTRIBUTEC LIGAMENT LENGTH EVALUATION. REV 21 155 0 1956E+09 57791. 12 68 ->ACCEPTADLE (09/10/96) 160 0 1970E+09 58210 12.77 -> ACCEPTABLE DATE OF THIS ANALYSIS: 09/30/1997 165 0 1979E +09 58474 12 83 >ACCEPTADLE 170 0 1994E +09 58905 12 92 -.>ACCEPTADLE

SUMMARY

OF INPUTS-175 0 1996E+09 58969. 12 94 ->ACCEPTADLE 180 0 1990E+09 58784 12 90 -> ACCEPTABLE Title H7 Erner9ency w/ReVd Stresses & Safety F 185 0 1.980E +09 58493 12 83 ->ACCEPTADLE 1.0 deg (COARSE) 190 0 1.962E +09 57980 12 72 -> ACCEPTABLE Angle increment = Memtwane Stress, Pm = 617. psi 195 0 1935E +09 57169 12 55 ->ACCEPTADLE Dending Stress. Pb = 3989 psi 200 0 1914E+09 56544 12 41 -> ACCEPTABLE = 1 50 205 0 1879E+09 55515 12 19 -> ACCEPTABLE Safety Factor, SF Mean Radius, Rm = 84 75 inches 210 0 1.831 E+09 54099 11.88 ->ACCEPTADLE a '. 500 inches 215 0 1,790E +09 52879 11 61 ->ACCEPTADLE Wan Thackness, t Stress intensty, Sm = 16900 psi 220 0 1.739E +09 51364 11 29 -> ACCEPTABLE 225 0 1.695E +09 50067. 11.00 >ACCEPTADLE Fluence a 2 28E+14 n/cm^2 (at end of k:ensed hfe) (Thus, LEFM evaluation not appicable) 230 0 5 638E+09 48385 10 64 -> ACCEPTABLE 2350 1.586E+09 46865 10 31 -> ACCEPTABLE THETA THETA 2 THICKNESS 240 0 1533E +09 45288 9 97 > ACCEPTABLE REGION [deg ] [deg ] [ inches) 245 0 1.483E +09 43813 9 65 ->ACCEPTADLE 250 0 1437E +09 42452. 9 35 -> ACCEPTABLE 1 17.3 152 4 1 500 255 0 1395E+09 41214 9 08 > ACCEPTABLE 2 197.5 200 0 1 500 260 0 1.358E+09 40110 8 84 >ACCEPTADLE 3 215 0 220 7 1 500 265 0 1.325E+09 39148. 8 63 >ACCEPTADLE 4 229 2 235 2 1 500 270 0 1.283E+09 37904 8 36 >ACCEPTADLE 5 258 7 290 7 1500 275 0 1257E+09 37131, 8 20 > ACCEPTABLE 6 295 2 305 8 1 500 280 0 1.240E+09 36636 9 09 >ACCEPTADLE 7 309 2 322 2 1 500 285 0 1.218E+09 35971. 7 94 ->ACCEPTADLE p 325 7 330 7 1 500 290 0 1.205E+09 35589 7 86 -> ACCEPTABLE 295 0 1.197E +09 35372 7 81 > ACCEPTABLE 300 0 1.207E *09 35659 7.88 -> ACCEPTABLE LIMIT l %D RESULTS 305 0 1.203E +09 35555 7 85 -> ACCEPTABLE 310.0 1201E+09 35469 7.83 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1213E+09 35829 7 91 > ACCEPTABLE THE FLAWS TAKE COMPRESSION 320 0 1210E+09 35756 7 90 > ACCEPTABLE 325 0 1207E *09 35668 7.88 >ACCEPTfDLE ALPHA MOMENT Ptf SAFETY 330 0 1221E+09 36070 7 97 >ACCEPTADLE (dog] [o ibs) [psil FACTOR RESULT 335 0 1217E+09 35960 7 94 > ACCEPTABLE 340 0 1219E+09 36015 7 G5 > ACCEPTABLE 345 0 1224E +09

36181, 79? -> ACCEPTABLE OO 1 260E+09 37212.

8 21 ->ACCEPTABLt; 50 1278E+09 37758 8 33 > ACCEPTABLE 350 0 1.232E+09 36410 8 04 > ACCEPTABLE 10 0 1300E +09 38397. 8 47 -> ACCEPTABLE 355 0 1244E+09 36761. 8 12 > ACCEPTABLE 15 0 1323E +09 39092 8 62 -- 3CCEPTABLE 20 0 1351E+09 39919 8 80 >ACCFPTABLE ACCEPTABLES 25 0 13615 +09 40209 8 86 ->ACCEPTADLE MINIMUM SAFETY FACTOR = 7 81 AT 295 0 DEGREES 30 0 1.386E +09 40952 9 02 >ACCEPTABL E 35 0 1409E*09 41642 9 17 -> ACCEPTABLE 40 0 ? 417E+09 41858 9 22 > '.CCEPT ABL E 45 0 1637E+09 42470 9 35 >ACCEPTADLE 50 0 1458E +09 43090 9 49 -> ACCEPTABLE 55 0 1466E+09 43320 9 54 -> ACCEPTABLE 60 0 1486E+09 43891. 9 66 > ACCEPTABLE 65 0 1503E*09 44392-9 71 -> ACCEPTABLE 70 0 1524E +09 45021 9 91 -> ACCEPTABLE 75 0 1534E+09 45329 9 98 > ACCEPTABLE 80 0 1558E +09 46042 10 13 >ACCEPTADLE 85 0 1581E+09 46712 10 28 ->ACCEPTADLE l 90 0 1%93E+09 47059 10 35 >ACCEPTADLE 95 0 1812E+09 47628 10 47 > ACCEPTABLE 100 0 1630E +09 48155 10 59 -> ACCEPTABLE 105 0 1651E+09 48i87. 10 73 > ACCEPTABLE 110 0 1676E+09 49518 to 88 > ACCEPTABLE ^ 115 0 1704E +09 50344 11 06 > ACCEPTABLE 120 0 1735E *09 51257. 1126 -> ACCEPTABLE 125 0 1 769E +09 52251. 11 48 -> ACCEPTABLE 130 0 1803E +09 5328: 11 70 >ACCJFTABLE 135 0 1835E *09 54224 11 91 -> ACCEPTABLE l l

Ccrolino Power & Light Company ESR 97-00034 Rov. O Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering Evaluation Page 20 m H7-Faulted. Good for 1200 days from March 193g 140 0 1.862E +09 55015. 9 78 -> ACCEPTABLE 145 0 1.890E+09 55837, 9 92 -> ACCEPTABLE Fnename DLL8-18-97 For 150 0 1919E+09 56682 10.07 -> ACCEPTABLE DLL C3TRIBUTED LIGAMENT LENGTH EVALUATION, REV. 21 155 0 1936E+09 57194. 10 16 -> ACCEPTABLE (09/19/96) 160 3 1946E+09 57559. 10.22 -> ACCEPTABLE DATE OF THIS ANALYSIS 09/30/1997 165 0 1967E+09 58128. 10.32 ' ACCEPTABLE 170 0 1.974E +09 58321. 10 35 -> ACCEPTABLE

SUMMARY

OF INPUTS 1750 1.967E+09 58120. 10 32 -> ACCEPTABLE 180 0 1.973E+09 58299. 10 35 > ACCEPTABLE Title ~ H7 Faulted w/Rev'd Stresses & Safety Fac 185 0 1.963E+09 58008 10.30 -> ACCEPTABLE 10 deg (COARSE) 190 0 1.942E+09 57374. 10 19 -> ACCEPTABLE Angie increment = Membrkne Stress. Pm = 1330. psi 195 0 1.923E+09 56828. 10 09 -> ACCEPTABLE Bendog Stress, Pb = 4432. psi 200 0 1.891E+09 55884. 9 93 -> ACCEPTABLE 1.13 205 0 1.857E+09 54855 9 75 -> ACCEPTABLE Safety Factor, SF rp 75 inches 210 0 1.820E+09 53785 9.57 -> ACCEPTABLE Mean Radius, Rm = = 1.bW mches 215 0 1.773E+09 52390. 9 32 -> ACCEPTABLE Wall Thackness, t Stress intensity, Sm = 16900. psi 220 0 1.728E+09 51059, 9 09 -> ACCEPTABLE Fluence 2.28E+14 n/cm 2 (at end of hcensed hfe) 2250 1.673E +09 49415 8 81 -> ACCEPTABLE a (Thus, LEFM evaluation not apphcable) 230 0 1.614E+09 47679 8 51 - >ACCEP'"ABLE 235 0 1.553E+09 45895 8 20 > ACCEPTABLE THETA 1 THETA 2 THICKNESS 240 0 1.500E+09 44318 7 92 -> ACCEPTABLE REGION [deg) [$.9 ) [ inches) 245 0 1.450E+09 42843. 7.67 -> ACCEPTABLE S00 1.404E+C9 41482. 7.43 -> ACCEPTABLE 1 17.3 152 4 1 500 255 0 1.362E+09 40244 7.22 -> ACCEPTABLE 2 197.5 200 0 1.500 260 0 1.325E+00 39140. 7.02 -> ACCEPTABLE 3 215 0 220 7 1.500 265 0 1.296E+05, 38300. R88 -> ACCEPTABLE 4 229 2 235 2 1 500 270 0 1.266E+09 37393. 6 72 -> ACCEPTABLE 5 258 7 290 7 1 500 275 0 1239E+04 36619 6 59 -> ACCEPTABLE 6 295 2 305 8 1.500 280 0 1.227E+09 36250. 6 52 -> ACCEPTABLE 7 309 2 322.2 1.500 285 0 1.200E+09 35442. 6 38 -> ACCEPTABLE 8 325 7 330 7 1.500 290 0 1.187E+09 35060. 6 32 -> ACCEPTABLE 'm 295 0 t184E+09 34973 6 30 -> ACCEPTABLE \\ 300 0 1.171E+09 34584. 6 23 -> ACCEPTABLE LIMIT LOAD RESULTS 305 0 1.175E+09 34718. 6 26 -> ACCEPTABLE 310 0 1.186E+09 35032. 6 31 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 315 0 1.182E+09 34917. 6.29 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION 320.0 1.178E+09 34795. 6.27 ->ACCEP' ABLE 325.0 1.190E+09 35169. 6 33 ->ACCEPTA BLE ALPHA MOMENT Pb' SAFETY 330 0 1.186E+09 35038. 6 31 > ACCEPTABLE [deg) [in-lbs] [ psi] FACTOR RESULT 335 0 1.181E+09 34881. 6 28 -> ACCEPTABLE 340 0 1.194E+09 35291. 6.36 -> ACCEPTABLE OO 1235E+09 36488 6 56 ->ACCEOTABLE 345 0 1.199E +09 35436 6 38 -> ACCEPTABLE 50 1254E+09 37034 6 66 -> ACCEPTABLE 350 0 1.208E+09 35686 6 42 > ACCEPTABLE 10 0 1275E+09 37673. 6.77 ->AOCEPTABLE 355 0 1.220E+09 36037. 6 49 -> ACCEPTABLE 15 0 1.287E +09 38021. 6 83 > ACCEPTABLE 20 0 1316E+09 38894 6 98 -> ACCEPTABLE ACCEPTABLE' 25 0 1.344E+09 39714 7.12 -> ACCEPTABLE MINIMUM SAFETY FACTOR a 6 23 AT 300 0 DEGREES. 30 0 1.354E+09 39999 7.17 -> ACCEPTABLE 35 0 1379E+09 40738 7.30 -> ACCEPTABLE 40 0 1402E +09 41425 7.42 -> ACCEPTABLE 45 0 1.409E+09 41642 7 46 > ACCEPTABLE 50 0 1431E+09 42288 7.57 -> ACCEPTABLE 55 0 1453E+09 42938. 7.68 -> ACCEPTABLE 60 0 1461 E +09 43168. 7.72 -> ACCEPTABLE 65 0 1486E+09 43916. 7.85 -> ACCEPTABLE 70 0 1.501 E+09 44352. 7 93 -> ACCEPTABLE 75 0 1519E+09 44889 8 02 -> ACCEPTABLE 80 0 1.537E +09 45400. 8 11 -> ACCEPTABLE 85 0 1.561E+09 46125. 8 24 -> ACCEPTABLE 90 0 1584E+09 46786. 8 35 -> ACCEPTABLE 95 0 1.595E+09 47125 8 41 -> ACCEPTABLE 100 0 1619E+09 47826 8 53 > ACCEPTABLE 105 0 1640E+09 #4457. 8 64 -> ACCEPTABLE 110 0 1665E+09 49189 8.77 -> ACCEPTABLE 1150 1.693E+09 50014 8 91 -> ACCEPTABLE 120 0 1.724E+09 50928 9 07 -> ACCEPTABLE 125 0 1.757E +09 51922. 9 24 >ACCEPTAE;E 130 0 1 787E+09 52806 9 40 -> ACCEPTABLE 135 0 1825E *09 53913 9 59 > ACCEPTABLE

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3 [80ZO8 68C80 89L _._..y8 c Cmkw, [ 7 Cracted] _j, _ i l j X ri e $2 68; $3. 79 i 0 Bi Cracked: i Cracked i j ti f 05 69hf 06. 79((0 8((Cracmed] L _[ _ Cracked [ i j j d i e3 i r r2 68 f 73. r9 { #4. 7~~~I~ f 2819 f f 9'~r9 ~~08 Crac6ea i i Crocked. j i i 15I Crechei ~7 Craches i l { i h gg 7 ,j 7 c,,, j i I~ _ g

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~0 8 7~CrackedI I T Creciei [~ I { l r 15 Crocked' I i Cascsed i ~ [ I i7 ~f 50 69 ~ df>8 {;~2 4I~Osched I t i Cracie8 I L s$f f 8 I~~) # 70224 ~ 2 F s97204 79 277.86 " 11.0 " 3313 I 20~ T 2r3 38 279 77 9 9Y' ~ 2874} L'21587~~215li2114i ~ 95] bNo . Yes 7 653 iIll f 205 3; 8 SJ j vos Yes 2138' 219Y T~ 21 M' 22128 ~222 80, 24i Crocked ~ ~ T~ ' I Crocked l 225 83i b8i Crocked L~ Y Cueeses G [ 22' T 2253i23 1[ 230 89 C 23320p_33L 247j 36 l 23i.~3i 232.7' 2.2) Ljf 7e]s g~ 25-. 236 I'I~238 26 24 k._ C'*c"**l ?' ~ t Crocked: C C'*c h ** Crocked. I l , 24 s. 79i~242 29 ' O 8! - 24f30 ~24583i 39F ~ ~383] p 438 M 4I4[~ Nckes 'i ll No - No~ j 5 26 ~250 38 350 88? ~~~ O'^8 ? Csacked' ? V C i ( G27 ~ ~28W252 40 ~253 20T 1"2 Cracked I Cracked 29^Dj5d.23 258 76i 39 ~ 383 [~,_255 f 272 7{ 17 Oi ( No i 258T 2.51 L 261.(4 ],[30 267.28 27320 { ] 85[ 6442' _No No ]~251))Q7] j 3t_ V292 40{g 293.20 ~31 p _ked.54) 'C277g 278.34_1.7j 27d 74 2M 76; No Nc, y } 22 12. Croc y

Cracked, 33 ' ~I~ 300. 7' 8 I303 8s T7 7i 706f 56il4~303 3I~3 31 vu y'es~

Q ~ 16i W 36f M 34 T305 32I373 2dFI2 2i-~3836i P305.8 r

31) 7; 10 8' I'~ Ves 3058~

312.7 ~~ DS T, Leement tenpin gaf.I _7 3 ? EZ4482Jl~332 *E3* s t tim E*-t YesM t_33).h4o 8] l I v240 D 4r2s Na Es.src 134.9 eof Laz. Length tant-88 4 sece eof usament Lang:!: ( a eri a detMed last koed eneften is remdred IDLLsemputer arnerateL Notts g3 (1) boernent Data from 8212R1GE Emomenet on Summary o iest r ,,,4 (2) Crack growth is appbed et each ered of $garvent ( 31 Calcutenon fos End it Evahaenen bgament Date recludes uncertaw-M d apphcatise. O (41 Days to Fusy Cracked - days tA Eosmer4 rength is more tactueEv - uncertarity + ASME crack romunrty nJet for each ngameria. g >O O O ($1 High Flus Zone - seus or minus 15 deg%,.e from munuthe45,135. 225 and 315 (se 3060 etc3 cn Wold H6b vvse not seach LEFM threshoed levei for notaron..;,..; :n.:(3:10 201witten current operatng scense. to I W gO 471 Ideg - 1.54898 in O (81 urunspected negions assumed fuity cracked. As cracks assumed throughwas gy 19) icase - wunsmura neeered bearnent hmeth for hawt toad concerns reto ence StructurW kitegnty esport $m 94 029 Rev. O h3 41 01 Lnun = Lcalc + 2tCrack Growth m Ewasvat on Penod) + Totd inspection Uncertancy 7o (1 11 Revised Wood stresses voere mcorperseed dunns 8213R1 outage These steesses are vetlected above (Ref. case 0821 1012) -e 03 O 10/11/97 H68 g2,333 9 wg4

C:rolin2 Pow:r 8t Light Comptny; ESR 97 00034 Rsv. 0 ' Brunswick Nuclear Plant - Unit 2 ATTACHMENT B- ' Engineering Evaluation Page-22 q Heb-N/U. Good for too days from Sept 1997 7 y 3 p gs4g 56 56 57.4 58 0 0.560 F4eneme: DLL6-18-97.For 57 58 0 50.1 ' O490 DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 2.1 58 - 59 1 61.7 1.500 (06/1W96) 59 61.7 62 8 '0450 DATE OF THIS ANALYSIS: 10/08/1997 61 63.9 65 6 ~ 0.370 60 62.8 63,9 1.500

SUMMARY

OF INPUTS: 62 65.6 66 7 0.530 63 66.7 67.4 0 440 - Titie Wood H6b N/U 8213R1 ONE CYCLE 64 67.4 68.7 0 420 Angie increment 1.0 dog. (COARSE) 65 68.7 70.0 0,420 = Membrene Stroes. Pm = 594. poi ~ 66 70 0 70.2 0.520 Bendmg Strees, PD = 2204. poi 67 70.2 70 2-0.510 Safety Fector, SF = 2.25-68 70 2 72.2 0 450 Moon Redeus, Rm = 88 00 inches 69 72 2 72.8 0.340 = 1.500 trw2we Wes Thenees, t 70 72 8 73 5 0 370 Stress intensay, Sm = 18900 pel 71 73 5 74 1 0 620 Fluence . = 8 82E+17 n/cm*2 (ct end of IKenned ide) 72 74.1 748 0440 - (Thus, LEFM ovoluebon not app 4ebie) 73 74.8 75 4 0 480 74 75 4 76.7 0570 THETA 1 -THETA 2 THICKNESS 75 76.7 77.4 0.480 ' REGION [de9 ) (d*9 ]. (bches) 76 77.4 - 78.0 0.550 77 78 0 78 7 0510 1 12.7 13 4 0 620 73 73 7 7g 3 0.440 2 13 4 14 0 0 490 79 79.3 80.0 0 500 3 14 0 14 6 0 570 80 80 0 80.6 0 540 4 14 6 15 3 0.500 81 80 6 81.3 0.520 5 15.3 15 9 0 450 82 81.3 - 83.7 1.500 6 15.9 16 6 0 120 83 83.7 84 8 0 630 7 16 6 17.2 0 440 84 84 8 85 4 0.530 8 17.2 17.9 0.540 85 85 4 86 1 0.500 9 17.9 18 5 0430 86 86.1 - 86 7 0.510 10 18,5 19 2 0 490 87 86.7 87.4 0.540 11 19 2 19 8 0 170 88 87.4 88 0 0.480 h. 12 19.8 20 5 0.420 89 88 0 88.7 0613 13 20.5 21.1 0.080 90 88.7 89 3 0.500 14 21.1 21,8 0240 91 89.3 90 0 0 420 15 21 8 22 4 0.320 92 90.0 91.5 0 530 16 22.4 24 4 0.320 93 91 5 92 2 0.620 17 24 4 25 0 0 450 94 92.2 92.8 0620 18 25 0 25.7 0.110 95 92 8 93 5 0.570 1c 25 7-26.3 0 460 96 93 5 94.1 0 480 20 26.3 27 0 0.590 tr, 94 1 94 8 0 440 21 27.0 27.6 0 420 98 94 8 95 4 0 440 22 27.6 28.3 0.240 99 95 4 96.1 0.610 23 28 3 28 9 0230 100 96.1 96 7 0.410 24 28 9 29 5 0 220 101 96.7 97.4 0.200 25 29 5 30 2 0 440 102 97.4 98 0 0.430 26 30 2 30 9 0550 103 98 0 98.7 0.430 27 30.9 31.5 0 5t0 104 98 7 99.3 0 470 28 31.5 - 32 2 0450 - 105 99.3 99.6 0 270 29 32.2 32.8 - 0.310 106 99 6 100 2 0.310 30 32 8 33 5 0 420 ~107 100 2 100 9 0470 31 33 5 34.1 0.410 108 100 9 101.5' O410 32 34 1 34 8 = 0 490 109 101.5 102.2 0 600 33 34 8 - 35.4 0 290 110 102.2 102 8 0 580 34 35 4 36 1 - 0 510 111 102 8 104 1 0 410 35 36.1 36.7 0550 112 104 1 105.4 0 550 36 36 7 37.4 0620 113 105 4 106 1 0.580 37 37.4 38 0 0 490 114 106.1 108.7 0580 38 38 0 .38.7 0 470 115 108.7 109 3 0 620 39 38.7 39 3 0 620 116 109.3 110 0 0.500 40 39 3 40 0 0 620 117 110 0 111.5 0.580 41 40 6 43.0 1.500 118 111.5 112.2 0 510 - 42 43 0 44 1 0 530 4 119 112.2 112.8 0 510 43 44.1 45 4 0560 120 112.8 113 5 0620 44 454 46.7-0560' 121 113 5 114 1 0 620 45. 46 7 47,4 0 620 122 114 1 114 8 0 460 -46 47.4 48 0 - 0610 123 114 8 116 7 0 410 47 48 0 48 7 0590 124 116.7 117.4 0 560 48: 48 7 49 3 0 440 125 117,4 118 0 0 420 49 49 3 50 0 0 210 126 118 0 118 7 0.580 50 50 0 50 9 0 580 127 118 7 119 3 0 520 51 50.9 51 5 '0440 128 119 3 120 4 0580 52 51 5 52 6 - 0400 129 120 4 121.7 1.500 53 52.6 55 6 1 500 - 130 121 7 122.8 0 430

Cerolino Pow:r & Light Comp:ny ESR 97-00034 R5v. O Brunswick Nuclear Plant Unit 2 ATTACHMENT B Engineering Evaluation Page~ 23 1 131 122 8 123 5 0 $10 208 227.4 228 0 0 410 132 123 5 124 1 0 470 209 228 0 228.7 0 410 133 124.1 124 8 bi% 210 228 7 229 3 0 #10 134 124 8 125 4 0 4h 1 211 229 3 230 6 0 620 135 125 4 126 1 0 42 J 212 230 6 231.5 0 620 136 126.1 126 7 01Ju 213 231.5 232 2 0 620 137 126.7 127,4 0 380 214 232 2 232.8 0620 138 127.4 128 0 0 400 215 232 8 233 5 0 590 139 1280 128 7 0$60 216 233 5 234.1 0 050 140 128 7 129 3 0 560 217 234.1 234 8 0.140 141 129 3 130 0 0 620 218 234 8 235.4 0 000 142 130 0 130 6 0 040 219 235 4 236.1 0.180 143 130 6 31.5 0620 220-236 1 236.7 0 000 144 131.5 132.2 0 530 221 236 7 237.S 0.140 145 132 2 132 8 0550 222 237.6 238.3 0.620 148 132.8 133$ 0.580 223 238.3 238.9 0 440 147 133 5 134.1 0 400 224 238 9 240.2 0 520 148 134.1 134 8 0 520 225 240.2 241.5 1450 149 134 d 135 4 0620 226 241 5 242.2 L240 150 135 4 136 1 0 550 227 242.2 242.8 0.,19 0 151 136 1 136 7 0 530 228 242.8 243 5 04% 152 136 7 137.4 0 460 229 243 5 244.1 0.110 153 137.4 1380 0 490 230 244.1 244 8 0.270 154 138 0-138 7 0 410 231 244 8 245 4 0 420 155 138 7 140 6 0450 232 245.4 2484 0.590 156 140 6 141.5 0 440 233 246 4 247.0 0 440 157 141.5 144.1 0 400 234 247.0 247.6 0.620 158 144 1 144 8 0 580 235 247.6 248 3 0 620 159 144 8 146.1 0 530 236 248.3 249 6 0 620 160 146.1 146 7 0560 237 2496 250.2 0 350 161 146 7 148 0 0 540 238 250.2 250.9 0 550 162 1480 148 7 0 450 239 250 9 251.5 0.530 163 148 7 149 3 0 440 240 251.5 252.2 0.370 164 149 3 150 0 0 600 241 252 2 252 8 0.130 165 150.0 1506 0 570 242 252.8 2535 0 430 166 1506 151 5 0 550 243 253.5 254.1 0 560 167 151.5 152.2 0 340 244 254 1 2548 0 470 168 152.2 152 8 0 460 245 254 S 255 4 0 510 169 152.8 153 5 0 130 24S 255.4 256,1 0.560 170 1535 154 1 0.370 247 256 1 257.6 0.560 171 154 1 156.1 0.400 248 257.6 2590 1.500 172 156 1 156.7 0.160 249 2590 261.1 0.490 173 156.7 157.4 0590 250 261.1 276 3 1 500 174 157 4 158 0 0 450 251 276.3 2778 0 440 175 1580 158 7 0 420 252 277.8 280 1 1.500 176 158 7 159 3 0.520 253 280.1 280 9 0620 177 159 3 160 0 0.380 254 280 9 2815 0 480 178 160.0 160 6 0.550 255 281.5 282 2 0 460 179 160 6 161.5 0 610 256 282 2 283.5 0.500 180 161.5 162 8 0600 257 283.5 284.1 0 620 181 162.8 163 5 0 600 258 284.1 284 8 0 490 182 163'; 164 1 0.550 259 284 8 285.4 0 420 183 164 1 166.1 0.540 260 285 4 286 1 0.400 184 166,1 166 7 0 470 261 286 1 286 7 0 420 185 166 7 167.4 0 340 262 286 7 287 4 0=10 186 167.4 168 0 0 450 263 287.4 289 3 0 50C 187 168 0 168 7 0 320 264 289 3 290 0 0 500 188 168 7 169 4 0 520 265 290 0 290 6 0 460 189 169 4 170 0 0.540 266 290 6 291.5 0 590 190 170 0 171.1 0 $20 267 291.5 292.2 0.430 191 171 1 194 6 1.500 268 292 2 292 8 0110 192 1946 195.8 0 450 269 292.8 293.5 0 460 193 195 8 196 4 0 430 270 2935 294 1 0 480 194 196 4 197.0 0 540 271 294.1 294 8 0 460 195 197.0 197.7 0 530 272 294 8 295 4 0 490 196 197.7 198 3 0470 273 295 4 296.1 0 550 197 198 3 199 0 0 490 274 296 1 296 7 0630 198 199 0 199 6 0550 275 296 7 297 4 0 440 199 199 6 200.3 0$10 276 297.4 298 0 0 470 200 200 3 200 9 0510 2 77 298 0 298 7 0560 201' 200 9 20 t.6 0 500 278 298 7 299 3 0 540 -232 201 6 202 7 0 400 279 299.3 300 0 0 010 203 202 7 210 4 1.500 280 300 0 302.2 0 610 204 210 4 211 5 0 480 2o1 302.2 303 3 0 610 205 211 5 212.6 0560 282 303 3 315 5 1.500 206 212 6 226 3 1 500 283 315 5 316 6 0.500 207 226 3 227 4 0 200 284 316 6 317.3 0 580

C rolin3 Pow:r & Light Company ESR 97-00034 Rev. O Brunswick Nuclear Plant - Unit 2 ATTACHMENT (3 Engineering Evaluation Page 24 ? 285 317.3 317.9 0350 165 0 1.167E+09 31980, 11.64 -> ACCEPTABLE 286 317.9 318 6 0 620 170 0 1.187E +09 32537, 11 84 -> ACCEPTABLE 287 318 6 319 2 0 600 175 0 1.220E+09 33442. 12.16 -> ACCEPTABLE 288 319 2 319 9 0 510 160 0 1.227E+09 33633. 12 23 -> ACCEPTABLE 289 319 9 320 5 0 490 185 0 1.276E+09 34957. 12.71 -> ACCEPTABLE 290 3205 321 2 0.360 190 0 1.305E+09 35748. 12 99 -> ACCEPTABLE 291 321 2 322.7 0 $20 195 0 1.335E+09 36573. 13 28 -> ACCEPTABLE 292 322.7 323 4 0 630 200.0 1.364E+09 37385. 13.57 -> ACCEPTABLE 293 323 4 324 0 0 520 205 0 1.382E+09 37881, 13.75 ~5 ACCEPTABLE 294 324 0 324 7 0 490 210 0 1.414E+09 38757. 14 06 > ACCEPTABLE 295 324 7 325 3 0 080 215 0 1.439E+09 39445. 14 31 -> ACCEPTABLE 29ti 325 3 326 0 0 220 220 0 1.450E+09 39730. 14 41 -> ACCEPTABLE 297 326 0 326 6 0 450 225.0 1.467E+09 40195. 14.58 -> ACCEPTABLE 298 326 6 327.3 0.440 230 0 1.488E+09 40765. 14.78 -> ACCEPTABLE 299 327.3 327.9 0 020 235 0 1.501E+09 41121. 14 91 -> ACCEPTABLE 300 327.9 328 6 0 430 240 0 1.514E+09 41494. 15 04 -> ACCEPTABLE 301 328 6 329 2 0 100 245 0 1530E+09 41922. 15 20 -> ACCEPTABLE - 302 329 2 329 9 0 460 250.0 1.556E+09 42631. 15 45 > ACCEPTABLE 303 329 9 3305 0 $20 2550 1.576E+09 43178. 15 64 -> ACCEPTABLE 304 330 5 331.2 0 560 260 0 1.595E+09 43712. 15 83 -> ACCEPTABLE 305 331.2 332.2 0 430 265.0 1.609E+09 44096 15 97 -> ACCEPTABLE 306 332.2 332 8 0 440 270 0 1.629E+09 44642. 16.17 -> ACCEPTABLE 307 332 8 333 5 0 620 275.0 1.629E+09 44641. 16.17 - ACCEPTABLE 308 333 5 334.1 0 470 280.0 1.665E+09 45627. 1652 -> ACCEPTABLE 309 334.1 334 8 0 290 285 0 1.681E+09 46062. 16 67 -> ACCEPTABLE 310 334 8 336.1 0 600 290.0 1691E+09 46327. 16.77 -> ACCEPTABLE 311 336 1 336.7 0390 295.0 1.709E+09 46841. 16 95 ->ACCEPTAFLE 312 336.7 337.4 0 140 300 0 1.724E+09 47239 17.10 ->ACCEPTABL E 313 337.4 338 0 0 340 305.0 1.735E+09 47537. 17.20 -> ACCEPTABLE 314 338 0 338 7 0 430 310 0 1.741 E+09 47717. 17.27 > ACCEPTABLE 315 338 7 340 0 0 450 315 0 1.736E+09 47580. 17.22 -> ACCEPTABLE 316 340 0 340 6 0 490 320.0 1.746E+09 47855. 17.32 -> ACCEPTABLE 317 340 6 341.3 0 520 325 0 1.740E+09 47677. 17.25 -> ACCEPTABLE 318 341.3 341.9 0 070 330.0 1.728E+09 47353. 17.14 -> ACCEPTABLE Q 335 0 1.716E+09 47022. 17.02 -> ACCEPTABLE 340 0 1.707E+09 46786. 16 93 -> ACCEPTABLE LIMIT LOAD RESULTS-345.0 1.675E+09 45894. 16 61 -> ACCEPTABLE ....=====*========= 350 0 1.655E+09 45350. 16 42 > ACCEPTABLE NOTE. THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 355.0 1.630E+09 44662. 16.17 >ACCEPTAKE THE FLAWS TAKE COMPRESSION ACCEPTABLE! MINIMUM SAFETY FACTOR = 10.86 AT 140 0 ALPHA MOMENT Pb' SAFETY DEGREES. [deg) [m-ibs) (pse] FACTOR RESULT 00 1603E+09 43925. 15 91 -> ACCEPTABLE 50 1.573E+09 43091. 15$1 -> ACCEPTABLE 10 0 1.529E+09 41902 15.19 > ACCEPTABLE 15 0 1.507E+09 41307, 14 9C -> ACCEPTABLE 20.0 1.472E+09 40342. 14 63 ->ACCEPTASLE 25 0 1435E+09 39322. 14 27 -> ACCEPTABLE 30 0 1.3%E +09 38257. 13 89 -> ACCEPTABLE 35 0 1.379E+09 37785 13 72 -> ACCEPTABLE 40 0 1.353E+09 37085. 13 47 -> ACCEPTABLE 45 0 1328E +09 36379 13 21 -> ACCEPTABLE 50 0 1296E+09 35512. 12 90 -> ACCEPTABLE 55 0 1274E+09 34901. 12.69 > ACCEPTABLE 60 0 1259E+09 34507. 12 54 -> ACCEPTABLE 65 0 1242E+09 34032. 12.38 -> ACCEPTABLE 70 0 1.215E+09 33301. 12.11 -> ACCEPTABLE 75.0 1.197E+09 32798. 11.93 > ACCEPTABLE 80 0 1.183E +09 32418. 11.80 -> ACCEPTABLE 85 0 1.107E+09 31980. 11 64 -> ACCEPTABLE 90 0 1.16 TE+09 31972 11.64 > ACCEPTABLE 05 0 1.156E+09 31669 11.53 -> ACCEPTABLE 100.0 1.141E*09 31276. 11.39 u ACCEPTABLE 105 0 1.130E+09 30952. 11.27 -> ACCEPTABLE 110 0 1.120E+09 30692. 11.18 -> ACCEPTABLE 115.0 1,114E+09 30516 11.12 -> ACCEPTABLE 120 0 1.114E+09 3G540. 11.13 -> ACCEPTABLE 125 0 1097E+09 30051. 10 95 -> ACCEPTABLE 130.0 1088E+09 29819 10 87 -> ACCEPTABLE 135 0 1.088E+09 298t2 10 87 ->ACCEPTAE'.E 140 0 1.088E+09 29803. 10 86 ->ACCEP7A3LE 145 0 1 110E +09 30422. 11.08 -> ACCEPTABLE 150 0 1,121E+09 30709 11 19 -> ACCEPTABLE 1550 1.134E+09 31068 11 32 -> ACCEPTABLE 160 0 1.144E+09 31493 11.47 -> ACCEPTABLE

C:rolin3 Pow:r 8r Ught Comp:ny ESR 97 00034 Rav. 0-Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering Evaluation Page 25 HEt:fmergency. Good for 600 days from Sept 1997 55 56 7 57.4 0430 56 57.4 58 0 0 560 Filename-DLL8-18-97 For 57 58 0. 59 1.0490 DLL OtSTRIBUTED LIGAMENT LENGTH EVALUATION, REV. 2,1 58

- 59 1 61 7 1.500 (0WIW96) 59 61.7 62 8 0 450 DATE OF THIS ANALYSIS: 10/08/1997 60 62 8 63.9 0 370 61 63 9 65 6 1.500

SUMMARY

OF INPUIS-62 - 65 6 06 7 0530-63 66.7-67.4 0 440 Title. Wood H8b EMERGENCY B213R1 ONE CYCLE 64 67.4 68 7 0 420 1.0 dog (COARSE). 65 68 7 70 0 0 420

Angle increment Membrane Stress, Pm. 606. pet 66 70 0 70 2 0 $20 Stroes, Pb. 2960. pas 67 70 2 70 2 0.510 1.50 68 70 2 72.2 0 450 Safety ecsor, GF a

Moon Redeve, Mm '

• 88 00 inches -

69 72.2 72 8 0.340 Was Thaneos, t 1.500inchee 70 72.8 73 5 0.370 71 73 5 74.1 0 ft20 Strese Intenemy Sm = 16900 pel Fluence 8 826+17 n/cm 2 (et end of licensed ine) 72 74 1 74.8 0 440 a (Thus, LEFM ovaluation not applicable) 73 74 8 75 4 0 480 74 75 4 76.7 0570 THETA 1 THETA 2 THICKNESS 75 76.7 77.4 0 480 ' REGION [deg ) - (dog ] [mches) 76 77.4 78 0 0 550 77 7a0 78 7 0510 1 12,7 13 4 0 820 78 78 7 79.3 0 440 2 13 4 14 0 0 490 79 79 3 80 0 0 500 3 = 14 0 14 6 0 570 80 80 0 80 6 0 540 4 14 6 15 3 0.500 81 80 6 81.3 0 520 5 15 3 15 9 0 450 82 81.3 83.7 1 500 8 15 9 16 6 0.120 83 83 7 ~84,8 0630 7 16 6 17.2 0 440 84 84 8 85 4 0530 8 17.2 17.9. 0 540 85 85 4 86.1 0.500 9 17.9 18.5 0 430 86 ' 86 1 86 7 0510 10 18.5 19 2 0 490 87 86.7 87.4 0540 11 19 2 f 98 0170 88 87.4 88 0 0 480 12 19 8 10.5 0 420 89 88 0 88 7 0610 13 20.5 21.1 0 080 90 88.7 89 3 0 500 14 21.1. 21.8 0.240 98 89 3 90 0 0 420 15 21 8 22 4 0320 92 90.0 91.5 0 530 16 22.4 24.4 0 320 93 91.5 92.2 0620 17 24.4 25 0 0 450 94 92.2 92.8 0.620 18 25 0 25.7 0 110 95 92 8 93 5 0.570 19 25.7 28.3 0 480 96 93 5 94.1 0.480 20 26.3 27.0 0 590 97 94.1 94 8 0 440 21 27.0-27.6 0 420 98 94 6 95 4 0 440 22 - 27.6 .28 3 0 240 99 95 4 96 1 0 610 23 28 3 28 9 0.230 100 96.1 96.7 0 410 24 28 9 29 5 0220 101 96.7 97.4 0 200 25 29 5, 30 2 0 440 102 97.4 08 0 0 430 26 30.2 JO 9 0 550 103 98 0 98 7 0 430 27 . 30.9 31.5 0510 104 98.7 99.3 0 470 28 31.5-32.2 0 450 105 99.3 99 6 0 270 29 32.2 32 8 0 310 106 99 6 100 2 0.310 30 32.8 33 5 0420 107 100.2 100 9 0470 31 33 5 34 1 0 410 108 100.9 101.5 0.410 32 34 1 34 8 0490 109 101 5 102.2 0 600 33 34 8 35 4 0 290 110 102.2 102 8 0 580 M 35 4 36.1 0 510 111 102 8 104.1 0 410 35 36.1 36 7 - 0550 112 -104.1 105 4 0.550 . 36 36 7 37.4 0 620 113 105 4 1061 0 580 37

37 4 38 0 0 490..

114 106.1 108.7 0.580 38 38 0 33 7 0470 115 108.7 109 3 0 623 39 38.7 ^ 39 3 0 620 116 109 3 110 0 0 500 40 - 39 3 40.6 ~0620 117 110 0 111,5 0 580 41 40 6 43 0 1.500 -110 111.5 112.2 0.510 42 43.0 44.1' 0 530 119 112.2 112 8 0510 43 - 44 1 45 4 ' 0 560 - 120. 112.8 113.5 0 620 44 45 4 46 7 0560 121 113 5 114.1 0620 45 46 7-47.4 0620 122 114.1 1148 0460 46- - 47 4 48 0 0 610 123 114 8 116.7 0 410 47 48 0 48 7 0100 124 116 7 117 4 0 MO 48 = 48 7 49 3 0 440 125 117 4 118 0 0 420 - 49 49 3 50 0 0 210 126 118.0 118 7 0580 50 l 50 0 50 9 - 0 580 127 118 7 119.3 0 520 '51- . 50 9 51 2 0 440 128 119 3 120 4 0.580 52. 51.5 52 6 - 0400 129 120 4 121.7 1.500 53 52 6-55.6 < 1.500 130 121.7 122.8. O430 54 55 6 56 7 0540 131 122 8 - 123 5 0.510

CcroliniPow:r & Light Comp:n) ESR 97-00034 Rsv. O Brunswick Nuclear Plant - Unit 2 ATTACHMENT B - Engineering Evaluation Page 26 9 132 123.5 124.1 0470 209 228.0 228.7 0 410 133: 124.1 124 8 0450 210 228.7 229 3 0 410 134 -124 8 125 4 0 490 211 229.3 2306 0 620 -135 125 4 126.1 0 420 212-230 6-231.5 0 620 136 126.1 1267 0133 213 231.5 ' 232 2 0.620 137 126.7 127.4 0.380 214. 232.2 2328 0620 138 127.4 - 128 0 - 0 400 215 232 8 233 5 0.590 139 128 0 1287 0 $60 - 216 2335 234.1 0.050 140 128.7 129 3 0 560 217 234 1 234 8 0.140 141 129 3 -130 0 0620 218 234 8 235.4 0 000 142 130 0 130 6 0.040 219 235e 236.1 0.180 143 130 6 131.5 0 620 220 236.1 - 236.7 0.000 144 131.5 132.2 0 530 221 236.7 237.6 0.140 145 132 2 132.8 0.550 222 237.6 238.3 3.620 146 132.8 133.5 0.580 223 238 3 238.9 0440 147 133 5 134.1 0.400 -224 238.9 240.2 0 520 148 134.1 134 8 - 0 520 225 240 2 241.5 0.450 149-134 8 135 4 0 620 226 241.5 242.2 0.240 150 135 4 136.1 0.550 227 242.2 242.8 0.090 151 136.1 - 136.7 0 530 228 242.8 243 5 0.450 152 136.7 137A 0 460 229 243 5 244.1 0.110 153 137.4 138 0 0 490 230 244.1 244.8 0.270 -154 1380 138 7 0.410 231 - 244 8 245 4 0 420 155 138.7 1406 0.450 232 245 4 246.4 0.590 156 1406 141.5 0 440 233 246 4 247.0 0 440 -157 141.5 144.1 0 400 234 247.0 247.6 0 620 158 144.1 144.8 0.580 235 247.6 248.3 0.620 159 -144.8 146.1 0.530 - 236 248.3 249.6 0.620 160 146.1 146.7 0 560 237 249 6 250.2 0.550 161 146.7 148 0 0.540 238-250.2 250.9 0.550 182 148.0 148.7 0 450 239 250 9 251.5 0.530 163 148.7 149 3 0.440 240 251.5 252.2 0.370 164-149.3 150.0 0.600 241 252J 252.8 0.130 165 150.0 150.6 0 570 242 252.8 253.5 0.430 186 150 6 151.5 0 550 243 ?53 5 254.1 0.560 167 151.5 152.2 1340 244 254.1 254 8 0.470 168 152.2 152 8 0 460 245 254.8 255 4 0 510 169 152.8 153.5 0 130 246 255 4 256.1 0.e60 170 153 5 1C4.1 0 370 247 256.1 257.6 0 560 171 154.1 156.1 0 400 248 257.6 259.0 1.500 172 156.1 156.7 0.160 249 259.0 261.1 0.490 173 156.7 157.4 0 590 250 261.1 276.3 1.500 174 137.4 158 0 0.450 251 276.3 277.8 0 440 175 158.0 158.7 0 420 252 277.8 280.1 1.500 176 158.7 '59 3 0 520 253 280 1 280.9 0620 177 159 3 160 0 0.380 254 280.9 281.5 0 480 178 160 0 160 6 0.550 255 281.5 282.2 0 460-179 16R8 161.5 0 610 256 282.2 283 5 0.580 180 161.5 162.8 0 600 257 283 5 284 1 0.620 181 1623 163 5 0 600 258 284.1 284.8 0 490 182 163 5 164.1 0 550 259 284 8 285 4 0 420 183 164.1 166 1 0 540 260 285 4 286.1 0 400 184 166.1 166 7 0 470 261 286.1 286.7 0.420 185 166.7 167A 0.340 262 286.7 287.4 0.410 186 167.4 168 0 0 450 263 287 4 289 3 0 500 187 1680 168.7 0.320 264 289 3 200 0 0.500-186 168.7 169 4 0 520 265 290 0 290 6 0460 189 169 4 170 0 0540 266 290 6 291.5 0.590 190 1?J.0 171.1 0520 267 291.5 292.2 0 430 191 171.1 194 6 1 500 268 292.2 292.8 0.110 192 194 6 1956 0.450 269 292.8 293.5 0.460 193 -195.8 196 4 0 430 270 293.5 294.1 0 480 194 196 4 197.0 0 540 271 294.1 294 8 0 460 195 197.0 197.7 0.530 272 294 8 295.4 0.490 196 197.7 196.3 0 470 273 295 4 296.1 0.550 197 198.3 199 0 0 490 274 296.1 296 7 0630 198 199 0 199 6 0.550 - 275 296.7 297 4 0 440 199 199 6 200 3 0510 276 297.4 298 0 0.470 200-200.3 200.9 0.510 277 298.0 298 7 0.560 201 200 9 201 6 0.500 278 290.7 299.3 0.540 202-201.6 202.7 0 400 279 299 3 300 0 0.610 / 203 202.7. 210.4 1.500. 280 300.0 302.2 0.610 204 210 4 211.5 0.480 281 302.2 303 3-0610 205 211.5 212.6 0 560 282 303.3 315 5 1.500 206 .-212 6 226 3 1.500 283 315 5 316 6 0.500 207-226.3 227 4 0.200 284 316 6 317.3 0580 208 227.4 2280 0410 285 317.3 317.9 - 0550 - ~. -.

Ccrolina Pow:r & l.ight Company ESR 97-00034 Ray. O Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering hvaluation Page 27 O 286 317 9 318 6 0 620 170 0 1.187E+09 32537. 9 29 -> ACCEPTABLE 287 318 6 319 2 0600 175 0 1.194E+09 32718. 9 34 -> ACCEPTABLE 288 319 2 319 9 0$10 180 0 1.227E+09 33633. 9 60 > ACCEPTABLE 289 319 9 3205 0490 185 0 1.276E+09 34957. 9 97 -> ACCEPTABLE 290 320 5 321 2 0 360 190 0 130$E+09 35748 10.19 -> ACCEPTABLE 291 321.2 322 7 0 520 1950 1.335E+09 36573. 10 43 -> ACCEPTABLE 292 322 7 323 4 0630 200 0 1.164E+09 37385 10 65 -> ACCEPTABLE 293 323 4 ~ 324 0 0 $20 205 0 1.382E+09 37881. 10.79 -> ACCEPTABLE 294 324 0 324 7 0490 210 0 1.414E +09 38757. 11.04 -> ACCEPTABLE 295 324 7 325 3 0 080 215 0 1439E+09 39445 11.23 -> ACCEPTABLE 296 325 3 326 0 0 220 220 0 1.450E+09 39730. 11.31 -> ACCEPTABLE 297 326 0 326 6 0 450 225 0 1.467E +09 40195. 11.44 ->ACCEPTABt.E 298 326 6 327.3 0 440 230 0 1.488E+09 40765. 11 60 -> ACCEPTABLE 299 327.3 32t9 0 020 235 0 1.501E+09 41121. 11.70 -> ACCEPTABLE 300 327.9 328 6 0 430 240 0 1.514E+09 41494. 11.31 -> ACCEPTABLE 301 328 6 329 2 0.100 245 0 1.530E+09 41922. 11,93 -> ACCEPTABLE 302 329 2 329 9 0.400 250 0 1.556E+09 42631, 12.12 -> ACCEPTABLE 303 329 9 330 5 0 520 255 0 1.576E+09 43178. 12.28 -> ACCEPTABLE 304 3305 331 2 0 560 260 0 1.595E+09 437?2. 12 43 -> ACCEPTABLE 305 331.2 332 2 0 430 265 0 1.609E+09 44096-12.54 -> ACCEPTABLE 306 332 2 332 8 0 440 270 0 1.629E+09 44642. 12 64 -> ACCEPTABLE 307 332.8 333 5 0620 275 0 1.629E+09 44641. 12.69 > ACCEPTABLE 308 3335 334 1 0.470 280 0 1.649E+09 45178. 12.84 -> ACCEPTABLE 309 334 1 334 8 0 290 285 0 1.681 E+09 46062. 13 09 -> ACCEPTABLE 310 334.8 336.1 0 600 290 0 1.691E+09 46327. 13.16 ->ACCEPTABL E 311 336,1 336 7 0 390 295 0 1.709E+09 46841. 13.31 -> ACCEPTABLE 312 336.7 337.4 0 140 300 0 1.724E+09 47239. 13 42 -> ACCEPTABLE 313 337.4 338 0 0 340 3050 1.735E+09 47517. 1350 -> ACCEPTABLE 314 338 0 338 7 0 430 310 0 1.741E+09 47717. 13 55 -> ACCEPTABLE 315 338 7 340 0 0 450 315 0 1.736E+09 47580 13 51 -> ACCEPTABLE 316 340 0 340 6 0 490 320 0 1.746E+09 47855-13 59 -> ACCEPTABLE 317 3406 341 3 0520 3250 1.740E+09 47677. 13 54 -> ACCEPTABLE 318 34t.3 341.9 0 070 330.0 1.728E+09 47353. 13 45 -> ACCEPTABLE 335 0 1.716E+ 09 47022. 13.36 -> ACCEPTABLE Q 340 0 1.707E+09 46786. 13 29 -> ACCEPTABLE LIMIT LOAD RESULTS: 345 0 1.675E+09 45894. 13 04 -> ACCEPTABLE ............====== 350 0 1.655E+09 45350 12.89 ->ACCEPTABLC. NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 355 0 1.630E+09 44662 12.69 -> ACCEPTABLE THE FLAWS TAKE COMPRESSION = ACCEPTABLE! MINIMUM SAFETY FACTOR = 8 53 AT 140 0 ALPHA MOMENT Ptr SAFETY DEGREES. (deg) [mes) [ psi) FACTOR RESULT 00 1603E+09 43925 12 49 -> ACCEPTABLE 50 1.573E*09 43091. 12 25 ->ACCEPTADLE 10 0 1529E+09 41902 11 92 > ACCEPTABLE 15 0 1.507E+09 41307. 11.75 > ACCEPTABLE 20 0 1472E+09 40342. 11 48 -> ACCEPTABLE 25 0 1435E+09 39322 11 20 > ACCEPTABLE 30 0 1396E+09 38257. 10 90 -> ACCEPTABLE 55 0 1379E+09 37785 10 77 > ACCEPTABLE 40 0 1353E+09 37085 10 57 -> ACCEPTABLE 45 0 1328E+09 36379-10 37 > ACCEPTABLE 50 0 1.296E +09 35512. 10 13 -> ACCEPTABLE 55 0 1274E+09 34901. 9 96 > ACCEPTABLE 60 0 1259E+09 34507. 9 85 -> ACCEPTABLE 65 0 1242E+09 34032. 9 71 -> ACCEPTABLE 70 0 1.215E+09 33301. 9 51 -> ACCEPTABLE 75 0 1.197E+09 32798 9 37 -> ACCEPTABLE 80 0 1.183E +09 32418 9 26 ->ACCE PTABLE 85 0 1.187E+09 31980. 9 14 > ACCEPTABLE 90 0 1.167E+09 31972. 9.14 > ACCEPTABLE 95 0 1.156E+09 31669 9 05 -> ACCEPTABLE 100 0 1 141E+09 31276. 8 94 -> ACCEPTABLE 105 0 1 130E+09 30952. 8 85 -> ACCEPTABLE 110 0 1 120E+09 30692. 8 78 >ACCEPTARLE 115 0 1,114E+09 30516 8.73 -> ACCEPTABLE 120 0 1,114E+09 30540. 8 73 ->ACCEP TABLE 125 0 1097E+09 30051. 8 60 -> ACCEPTABLE 130 0 1088E+09 29819. 8 53 -> ACCEPTABLE 135 0 1.088E+09 29812. 8.53 -> ACCEPTABLE 140 0 1088E+09 29603. 8 53 > ACCEPTABLE l .1450 1.110E+09 30422. 8 70 -> ACCEPTABLE 150 0 1,121E+09 30709 8 78 -> ACCEPTABLE 155 0 1,114E+09 31068. 8 88 -> ACCEPTABLE l 160 0 1.149E+09 31493-9 00 > ACCEPTABLE l 165 0 1,167E+09 31980. 9 14 > ACCEPTABLE I l ~

1 C:rolins Pow:r & Light Compzny: ESR 9500034 Rsv. O Brunswick Nuclear Plant - Unit 2 - ATTACHMENT B Engineering Evaluation - Page 28 19lt:Emdied.jemLfgLGG9.,,dgra from Sent 1997 '55 56.7 57.4 - 0.430 56 57.4 58 0 0.560 Filename' DLL8-18-97.For 57 58 0 59.1 0 490 DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION, REV, 2.1 58 59.1 61.7 1.500 (00/11W96) 59 61.7 62.8 0450 DATE OF THIS ANALYSIS: 1048/196,7 60 62.8 63 9 0.370 61 63.9 65.6 1.500 -

SUMMARY

OF thPUTS: 62 65.6 86.7 0.530 63 06 7 67.4 0 440

Title:

Wold H8b FAULTED 8213R1 ONE CYCLE 64 67.4 68.7 0.420 6 = 1.0 - (COARSE) 65 68.7 70.0 0.420 An9 e increment Membrane Stress Pm = 129. psi 66 70.0 70.2 0.520 Stress, Pb = 3176. pel 57 70 2 70.2 0.510 = 1.13 68 70.2 72.2 0 450 actor, SF Mean Radeus, Rm = 8800 inches-69 72.2 72.8 0.340 Wou Thk* ness, t = 1.500 inches 70 72.8 73.5 0.370 Strees Intens4y, Sm = 16900. psi 71 73.5 74.1 0.620 Fluence = 8 82E+17 n/cm^2 (at end of heensed ide) 72 74.1 74.8 0 440 (Thus, LEFM ovaluebon not appbcable) 73 74 8 75.4 0 480 74 75 4 76.7 0.570 THETA 1 THETA 2 THICKNESS 75 76.7 77.4 0 480 REGION ldeg ) [deg ) Dnches) 76 77.4 78.0 0.553 77 78 0 78.7 0510 1 12.7 13 4 0620 78 78.7 79.3 0.440 2 13 4 14 0 0,490 79 79.3 80 0 0.500 3 14 0 14 6 0.570 80 80 0 80 6 0.540 4 14 6 15.3 0A00 81 80.6 81.3 0.520 5 15.3 15 9 0 450 82 81.3 83.7 1.500 6 15 9 16 6 0 120 83 83.7 84 8 0.630 7 16 6-17.2 0 440 84 84.8 85.4 0.530 8 17.2 17.9 0 540 85 85 4 86.1 0.500 9 17.9 18 5 0 430 86 86.1 86.7 0.510 10 18 5 19.2 0.490 87 86.7 87.4 0.540 11 19 2 19 8 0.170 88 87.4 88.0 0.480 O 12 19 8 20.5 0.420 89 S80 88.7 0.610 13 20.5 21.1 0 080 90 88.7 89.3 0.500 14 21 1 21.8 0 240 91 89 3 90.0 0.420 15 21.8 22.4 0 320 92 90.0 91.5 0.530 16 22.4 24 4 0700 93 91.5 92.2 0 620 17 24 4 25 0 0 450 94 92.2 92.8 0.620 18 25 0 25.7 0.110 95 92.8 93.5 0.570 19 25.7 20 3 0.460 96 93.5 94.1 0 480 20 26.3 27.0 0.590 97 94.1 94 8 0.440 21 27.0 27.6 0 420 98 94.0 95 4 0 440 22 27.6 28 3.0240 99 95 4 96.1 0 610 23 28.3 28=9 0230 100 96.1 96.7 0 410 24 24 9 29 5 0220 101 96.7 97.4 0.200 25 29 5 30.2 0.440 102 97.4 98.0 0.430 26 30 2 30.9 0550 103 98 0 98.7 0.430 27 30.9 - 31.3 0510 104 98.7 99 3 0 470 28 31.5 32 2 0 450 105 99.3 99.6 0.270 29 32.2 32.8 0 310 106 99 6 100.2 0.310 30 32 8 33.5 0 420 107 100.2 100.9 0 470 31 33 5 R1 0 410 108 100.9 101.5 0.410 32 34.1 34.8 0 490 109 101.5 102.2 0.600 33 34 8 35 4 0.290 110 102.* 102.8 0.580 34 35 4 36 1 0 510 111 102.8 104.1 0.410 35 36.1 36.7 0550 112 104.1 105.4 0.550 36 36.7 37.4 0.620 113 105 4 106.1 0.580 37 37 4 38 0 - 0490 114 106.1 108.7 0.580 38 38 0 38 7 0 470 115 108.7 109.3 0 620 39 38.7 39 3 0 620 116 109.3 110.0 0.500 40 39 3 - 40 ' 0 620 117 110 0 111.5 0.580 41 40 6 43 0 - 1.500 118 111.5 112.2 0.510 42 43 0 44.1 0.530 119 112.2 112 8 0510 l. 43 - 44.1 45.4 0.560 120 112.8 '113.5 0620 l - 44 45 4 46.7 0.560 121 113.5 114.1 0.620 45 45.7 ' 47,4 - 0620 122 114.1 114.8 0.460 46 47.4 48 0 0 610 123 114 8 116.7 0 410 47 - - 48.0 48,7 0 590 124 116.7 117.4 0.560 l 48 48.7 49.3 0 440-125 117.4 118 0 0.420 l 49 49.3 50 0 0.210 - 126 1180 118.7 0.580 l 50 50 0 - 50 9 0.580 127 118.7 119.3 0.520 51 50.9 51.5 0 440 128 119.3 120 4 0 580 i 52 51 5 52.6 0 400 129 120 4 121.7 1.500 53 52.6 55 6 1.500 130 121.7 122.8 0.430 I '54 55 6 56.7-0 540 131 122.8 123.5 0.510

Ccrolin2 Pow:r D Light Comp:ny ESR 97-00034 R;v. O Brunswick Nuclear Plant - Unit 2 ATTACHMENT B ' Engineering Evaluation Page 29 O I 132 123.5 124 1 0 470 209 228.0 228 7 0 410 133 124.1 124 8 0 450 210 228.7 229.3 0 410 134 124 8 125 4 0 490 211-229.3 230 6 0620 135 125 4 126 1 0 420 212 230 6 231.5 0 620 136 126.1 126.7 0.130 213 231.5 232.2 0.620 137 126.7 127.4 0.380 214 232.2 232.8 0620 138 127.4 128 0 0 400 215 232C 233 5 0.590 139 128 0 - 128.7 0 560 216 233.5 234.1 0.050 140 128 7 129 3 0 560 217 234.1 2348 0.140 141 129.3 130 0 0 620 218 234 8 235 4 0.000 142 130.0 130 6 0 040 219 235 4 2?d.1 0 180 143 130 6 131.5 0.620 220 236.1 236.7 0.000 144 131.5 132.2 0 530 221 236.7 237.6 0.140 145 132.2 1328 0550 222 237.6 238.3 0.620 146 132.8 133.5 0 580 223 2384 238 9 0.440 147 133.5 134.1 0 400 224 238.9 240 2 0.520 148 114.1 134 8 0.520 225 250.2 241.5 0 450 149 134 8 1354 0.620 226 241.5 242 2 0.240 150 135 4 136.1 0.550 227 242.2 242.8 0.090 151 136.1 136.7 0 530 228 242.8 243.5 0.450 152 136.7 137.4 0 460 229 243.5 244.1 0.110 153 137.4 138 0 0 490 230 - 244.1 244.8 0.270 154 1380 138.7 0 410 23 244.8 245 4 0.420 155 138.7 140 6 0 450 232 245 4 246 4 0.590 156 140 6 141.5 0 440 233 246.4 247.0 0 440 157 141.5 144.1 0 400 234 247.0 247.6 0 620 158 144.1 144 8 0.580 235 247.6 248.3 0 620 159 144 8 146 1 0 530 236 248.3 249 6 0.620 160 146.1 146.7 0.560 237 249 6 250 2 0.550 161 146 7 148 0 0 540 238 250.2 250.9 0.550 162 148 0 148.7 ' O.450 239 250.9 251.5 0 530 163 148.7 149 3 0 440 240 251.5 252.2 0.370 164 149.3 150 0 0 600 241 252.2 252.8 0.130 165 150.0 1506 0.570 242 252.8 253.5 0430 Q 166 150.6 151.5 0.550 243 253.5 254.1 0 560 167 151.5 152.2 0 340 244 254.1 254.8 0470 168 152.2 152 8 0 460 245 254.8 255.4 0.510 169 152.8 153.5 0 130 246 255 4 256.1 0.560 170 153.5 154.1 0.370 247 256.1 257.6 0.560 171 154 1 156.1 0 400 248 257.6 259 0 1.500 172 156.1 156.7 R160 249 259 0 261.1 0.490 173 156.7 157.4 0.590 250 261,1 276.3 1.5GO 174 157.4 158 0 0.450 251 276.3 277.8 0.440 175 1580 158 7 0 420 252 277.8 280.1 1.500 176 158.7 159 3 0 520 253 280.1 280.9 0.620 177 159 3 160 0 0.380 254 280.9 281.5 0 480 178 160 0 160.6 0.550 255 281.5 282.2 0.460 179 1606 161.5 0610 256 282.2 283.5 0 **L 180 161.5 162.8 0600 257 283.5 284.1 0.620 181 162 8 163 5 0.600 258 284.1 284 8 0 490 182 163 5 164.1 0 550 259 2848 285 4 0.420 183 164 1 166.1 0.540 260 285 4 286.1 0 400 184 166.1 166 7 0 470 261 286.1 286.7 0.420 185 166.7 167.4 0.340 262 286.7 287.4 0.410 186 167.4 168 0 0 450 263 287.4 289.3 0.500 187 1680 1687 0 320 264 289.3 290 0 0 500 188 168.7 169 4 0 520 265 290 0 290.6 0 460 189 169 4 170 0 0 540 266 290 6 291.5 0.590 190 170 0 171.1 0 520 267 291.5 292.2 0 430 191 171.1 194 6 1.500 268 292.2 292.8 0.110 192 194 6 195 8 0 450 269 292.8 293.5 0.460 193 195 8 196.4 0,430 270 293 5 294.1 0 480 194 196 4 197 0 0 540 271 294.1 294 8 0460 195 197.0 197.7 0530 272 294 8 295 4 0.490 196 197.7 198.3 0 470 273 295 4 296.1 0.550 197 198.3 1(90 0 490 274 296.1 206.7 0.630 198 199 0 199 6 0 550 275 296.7 U74 0 440 199 1996 200.3 0510 276 297.4 298.0 0.470 200 200 3 200 9 0510 277 298.0 298.7 0560 201 200.9 201.6 0500 278 2981 299.3 0.540 202 201.6 202.7 C400 279 299 3 300.0 0.610 203 202 7 210 4 1.500 280 300 0 302.2 0.610 204 210 4 211.5 0 480 281 302.2 303.3 0 610 205 211.5 212 6 .0560 282 303.3 315.5 1.500 '206 212 6 226 3 1.500 283 315.5 316 6 0 500 207 226.3 227.4 0 200 284 316.6 317.3 0 580 208 227 4 228 0 0 410 285 317.3 317.9 0550

~ Cuolins Pow:r & Light Company ESR 97-00034 R0v. O Brunswick Nuclear Plant - Unit 2 ATTACHMENT B Engineering Evaluation Page 30 m ) 286 317.9 318 6 0 620 170 0 1.161 E+09 31813. 7.41 -> ACCEPTABLE 287 318 6 319.2 0 600 175.0 1.167E+09 31979. 7.45 -> ACCEPTABLE 288 319.2 319 9 0 510 180 0 1205E+09 33032. 7 68 > ACCEPTABLE 289 319 9 320 5 0 490 185 0 1.234E+09 33804. 7.85 > ACCEPTABLE 290 320 5 321 2 0 360 190 0 1273E+09 34872 8 09 -> ACCEPTABLE 291 321.2 322 7 0 $20 195.0 1303E+09 35695. 8.28 -> ACCEPTABLE 292 322.7 323 4 0 630 200 0 1.336E+09 36613. 8 48 -> ACCEPTABLE 293 323.4 324 0 0.520 205.0 1.355E+09 37117. 8 60 -> ACCEPTABLE 294 324 0 324 7 0 490 210 0 1.386E+09 37973. 8 79 > ACCEPTABLE 295 324 7 325 3 0 080 215 0 1.411 E+09 38674. 8 95 > ACCEPTABLE 296 325.3 326 0 0 220 220.0 1.422E +09 38960. 9 01 -> ACCEPTABLE 297 326 0 326 6 0 450 225 0 1.450E+09 39724. 9.18 -> ACCEPTABLE 298 326 6 327.3 0 440 230 0 1.452E+09 39778. 9.19 -> ACCEPTABLE 299 327.3 327.9 0 020 235.0 1.483E+09 40643. 9 39 > ACCEPTABLE 300 327.9 328 6 0430 240 0 1.498E+09 41039. 9.47 -> ACCEPTABLE 301 328 6 329 2 0 100 245 0 1.513E+09 41474. 9 57 -> ACCEPTABLE 302 329 2 329 9 0 460 250 0 1.536E+09 42085. 9 71 -> ACCEPTABLE 303 329 9 330 5 0 520 255 0 1.548E+09 42423. 9.78 > ACCEPTABLE 304 330.5 331.2 0 560 260.0 1.568E+09 42974 9 91 -> ACCEPTABLE 305 331.2 332 2 0430 265.0 1.574E+09 43137. 9 94 -> ACCEPTABLE 306 332 2 332 8 0 440 270 0 1.597E+09 43764. 10 08 > ACCEPTABLE 307 332 8 3335 0.620 275.0 1.608E+09 44061. 10 15 -> ACCEPTABLE 308 333.5 334.1 0 470 280 0 1632E+09 44708. 10.30 -> ACCEPTABLE 309 334 1 334 8 0290 285 0 1.648E+09 45164. 1040 > ACCEPTABLE 310 334 8 336.1 0 600 290 0 1.660E+09 45499. 10.47 -> ACCEPTABLE 311 336 1 336 7 0 390 295 0 1.683E+09 46108. 10 M -> ACCEPTABLE 31/ 336.7 337 4 0.140 300.0 1.699E+09 46551, 10.71 -> ACCEPTABLE 313 337.4 338 0 0 340 305.0 1.709E+09 46829. 10.77 > ACCEPTABLE 314 338 0 338 7 0 430 310 0 1.716E+09 47018. 10.81 -> ACCEPTABLE 315 338 7 340 0 0 450 315 0 1.712E+09 46919 10 79 -> ACCEPTABLE 316 340 0 340 6 0 490 320 0 1.722E+09 47191. 10 85 -> ACCEPTABLE 317 340 6 341.3 0.520 325 0 1.715E +09 47000. 10 81 -> ACCEPTABLE 318 341.3 341.9 0 070 330 0 1.703E+09 46671. 10 73 -> ACCEPTABLE 335 0 1690E+09 46321. 10 66 -> ACCEPTABLE Q 340 0 1.680E+09 46039. 10 59 -> ACCEPTABLE LIMIT LOAD RESULTS: 345 0 1660E+09 45489. 10 47 -> ACCEPTABLE

=

u=========== 350.0 1.626E+09 44556. 10 26 -> ACCEPTABLE NOTE: THE FOLLOWING LIMIT LOAD RESULTS ASSUME THAT 355 0 1.602E+09 43905. 10.12 > ACCEPTABLE THC FLAWS TAKE COMPRESSION. ACCEPTABLE! MINIMUM SAFETY FACTOR = 6 79 AT 135 0 ALPHA MOMENT Pb' SAFETY DEGREES. [deg] [in-lbs) [ psi] FACTOR RESULT 00 1,573E+09 43106. 9 94 -> ACCEPTABLE 50 1542E +09 42262. 9 75 -> ACCEPTABLE 10 0 1.510E+09 41382. 9 55 -> ACCEPTABLE 15 0 1.476E+09 40456. 9 34 > ACCEPTABLE 20 0 1440E +09 39466. 9 12 -> ACCEPTABLE 25 0 1.417E+09 38830. 8 98 > ACCEPTABLE 30 0 1.378E +09 37758 8 74 -> ACCEPTABLE 35 0 1342E+09 36762, 8 52 > ACCEPTABLE 40 0 1314E+09 36009 8 35 -> ACCEPTABLE 45 0 1.287E+09 35279 8 19 -> ACCEPTABLE %0 1276E+09 34958. 8 11 > ACCEPTABLE 55 0 1.257E+09 34451 8 00 > ACCEPTABLE 60 0 1.219E+09 33409 7.77 -> ACCEPTABLE 65 0 1200E+09 32886. 7.65 -> ACCEPTABLE 70 0 1.180E+09 32338 7 53 -> ACCEPTABLE 75 0 1.175E+09 32192 7.49 > ACCEPTABLE 80.0 1.161E+09 31803. 7.41 -> ACCEPTABLE 85 0 1.145E+09 31372, 7.31 -> ACCEPTABLE 90 0 1,131E+09 30981. 7.22 -> ACCEPTABLE 95 0 1.121 E+09 30717. 7.16 -> ACCEPTABLE 100 0 1.124E+09 30789. 7.18 > ACCEPTABLE 1050 1.113E+09 30504 7.12 -> ACCEPTABLE 110 0 1.101E+09 30178 7 04 -> ACCEPTABLE 1150 1077E+09 29524. 6 90 > ACCEPTABLE 120 0 1 OG8E+09 29268. 6 84 -> ACCEPTABLE 125 0 1.074E+09 29442. 6 88 -> ACCEPTABLE 130 0 106( E+09 29051. 6 79 -> ACCEPTABLE 135 0 1060ti+09 29044. 6.79 -> ACCEPTABLE 140 0 1065E+09 2v172. 6 82 -> ACCEPTABLE 145 0 1.087E+09 29785. 6% -> ACCEPTABLE 150 0 1.098E +09 30094 7 02 > ACCEPTABLE 155 0 1099E+09 30111. 7.03 -> ACCEPTABLE 160 0 1.113E +09 30498. 7.11 > ACCEPTABLE 165 0 1.141E +09 31256. 7 28 -> ACCEPTABLE

C~rolina Pow:r & Light Comp:ny. ESR 97-00034 R v. O Brun: wick Nucle:r PI:nt - Unit 2 Attachm:nt C - Engineering Evaluation Page 1 n Distributed Ligament Length (DLL) Computer Program Benchmark of Version 2.1 (e (As Modified by CP&L) This attachment contains the listings of the input files that were used to benchmark this program. Th: input files have been verified as being identical to the sample files supplied with BWRVIP-20. The output files listed herein have been verified against the output files supplied with B%% VIP-20. The " modification" to this software program by CP&L is also shown in this Attachment by comparing the source codes of version 2.1 with the modified version of 2.1 by CP&L. I

C:rolin2 Pow:r & Light Comp:ny ESR 97-00034 Rev. O Brunswick Nuclear PI:nt - Unit 2 Att chm:nt C Engineering Evaluation Page 2 m DLL Semple Problem #1 38.9,49.3,.98 1 49.3,52.3,1.50 1000 52.3,150.1,.90 2000 150.1,230.9,1.50 2.80 230.9,231.5,1.23 99.00 231.5,239.0,1.50 2.00-239.0,248.3,1.22 14400. 248.5,259.0,1.50 Se21 259.0,260.4,1.28 150 260.4,288.6,1.50 5 288.6,295.2,1.17 0,7.5,2.00 295.2,305.4,1.50 R2.5,97.5,2.00 305.4,306.9,1,16 172.5,187.5,2.00 306.9,319.8,1.50 262.5,277.5,2.00 319.8,329.4,1.14 '352.5,360.0,2.00 329.4,360.0,1.50 DLL Sample Problem #2 0 DLL Sample Problem #4 500 1 ? 1500 920 1.40 1180 100.00 1.40 1.50 94.00 16900. 1.50 0 14400. I Se20 0,360,0.06 150 10 0,26.4,1.50 32.1,38.9,1.50 DLL Sample Problem #3 49.3,52.3.1.50 1 150.1,230.9,1.50 920 231.5,239.0,1.50 1180 248.5.259.0,1.50 1.40 260.4,288.6,1.50 94.00 295.2,305.4,1.50 1.50 306.9.319.8,1.50 14400. 329.4,360.0,1.50 Se20 150 19 0,26.4.1.50 26.4,32.1,0.97 32.1,38.9,1.50

C:rolin2 Pow:r & Light Comptny ESR 97-00034 Rcv. O Brunswick Nucl:sr Pl:nt. Unit 2 Attechm:mt C Engineering Evaluation Page 3 l Feenerae DLL8-IS 87 For 2950 7.366t + 08 11982. 4 32 - n A CCFFTAttt A-DLL delta 19VTED tsGAMENT LINQTH tvALUATION. AtV< 21 300 0 7.3828 + 08 11954. 4 32 -> ACCtPTA8tt 109/18'98) 306 0 7.354E + 08 11948 4 32 - > ACCtPT ASLt Daft 08 TMit ANALVl#8 08/28/1997 310 0 7.3588 + 08 91948 4 32 -> ACCEPTA8LE 316 0 7 368t +% 19948 4 32 - > ACCEPTA8Lt $UMMARY OF INPUTS-- 320 0 7 358t + 08 11948 4 32 -> ACCEPT ASLE 325 0 7.3564 + 08

11848, 4 32 - > ACCEPT ASLE.

Trise DLt sempae Preeson 81 330 0 7 3488 + 08 11932 4.31 -> ACCEPTA8tt 0 1 4et iFINti 335 0 7.3938 + 08 12006. 4 34 ' -> ACCEPTAkt Angse meeomern Mea 8vene Stress. Pm. 1000 pu 340 0 74094+08 12031. 4 34 -> ACCEPTABLE 2000.po 346.0 7 430t + 08 12008-4 36 -> ACCEPTASLt 8eaeng Setess. PD 2 80 350.0 7 4818 +08 12144 4 38 - > ACCEPTAkt Sa'eff Factor. SF = Meen Re*us. Am . 99 00 anches 385.0 7.6068 + 04

• 2189 4 40 - > ACCEPT A8LE wet Thekness. t. 2 000 anches Stress insenssty. 6m = 14400.pm ACCEPTAktt MINIMUM SAFETY F ACTOR. 4 31 AT 330 0 DEORIES.

Fbetue . 6Of+28necm*2 7oughnees, Ese 1to O t**m'0 $ LtFM RESULTS: THETA 1 TMtiA2 THICK NESS htGaON leet 5 (deg $ 1*tAeol N0ft: THE FOLLOwiNG LIFM IVALUAitON TRIAT5 PART.THROUGH WALL I OO FS 2 000 FLAWS A5 THROUGH WALL 2 82 5 87 8 2.000 Thus, the fcoomine flows were assumed 3 172 8 187 5 2 000 4 202 S 277 6 2 000 FLAW START END LtNGTH LENGTH DEPTM S 352 8 360 0 2000 No toes) 14egl ideo I incN tecN 1 7.5 82.6 76.0 129 69 2 00 LIM *T LOAD Rt3ULTS 2 97.5 172 5 75 0 128 59 2.00 3 '187.6 282.5 750 12959 2 00 NOTt: THE FOLL0 wino limit LOAO mtSULTS ASStist THAT 4 277.6 362 6 75 0 129 59 2 00 THE PLAWS TAtt COMPRESS 80N ALPHA MOMENT Ptr SAftTY Amowebae Stress intenest( Factor. EictSF = 13 8 he'mch'0 6 toegl (m-abel invl FACTOA RESULT 00 7 614t + 04 12202 4 40 -> ACCEPTAkt $ PACING Linen K 50 7.6088 + 08 12189 4 40 - > ACCEPT ASLA w (m I tecN ihm.ml RtSULT 10 0 7 485t + 08 12t48 4 JS - >ACCEPTA8tt 18 0 7 4444 + 04 12089 4 18 - >ACCEPTA8LE For space between News n 2. Ill 51 129$9 1489 NOT 20 0 74234+08 120F 4. 4 35 - 3ACCEPTAkt ACCEPT A8Lil 26 0 7.3444 + 04 11982 4 32 - > ACCEPT A8tt For space Derween news 2& 3 til $1 129 69 144 8 NOT 30 0 7 3628 + 08 1104 4.32 - >ACCEPTAkt ACCEPT A 8tti 35 0 7 Slet

• 08 t1948 4.32

- >ACCEPTASLE For space between powe 3& 4. Ill $1 129 69 144 9 NOT ,h 40 0 7.388t + 08 11948 4 32 -- > ACCEPTA8LE ACCEPTAkt!

1. 50 7.398t + 08 11948 4 32 - >ACCEPTA8tf Per sease between pews 46 1: 138 61 129 69 146 9 NOT 50 0 7.358t + 08 11948 4 32 - > ACCEPT ASLE ACCEPTA8Lff 56 0 7.318f

• 04 11948 4 32 - > ACCEPT A8Lt 60 0 7 3444 + De 11932 4 31 - >ACCEPTASLt LMITING E = 148 9 ks'mch*0 8. NOT ACCEPT A8Lil 86 0 7 3938 + *)G 12004 4 34

.-2 ACCEPTASLE Try comewnmg unaccepteone news 4 eerun 70 0 7 409t + 08 12031. 4 34 - > ACCtPTASLE 74 0 7 4304 + 04 12088 4 36 - >ACCEPTA8Lt 80 0 7 48 t t + J8 12148 4 38 - > ACCEPT ABLE 89.0 7.608E + 08 12189-4 40 ~. > ACCEPTABLE 90 0 7 614t + 08 12202. 4 40 - >ACCEPTA8tf 96 0 7 606t + 08 12183 4 40 - >ACCEPTA8tf 100 0 7 481t + 08 12144 4 34 - > ACCEPT A8LE 106 0 7 444E + 08 12089 4 38 - >ACCEPTA8Lt t90 7.423t + 04 120&4 4 35 - > ACCEPTABLE 114 0 7 3668 + 08

11982, 4 32 - >ACCEPTA8tt 120 0 7 382t + 08 11954 4.31

- > ACCEPT A8LE 125 0 7.368t + 08 11948 4 32 - > ACCEPTA8tt t 30.0 7 3181 + 08 11948 4 32 - > ACCEPTABLE 139 0 7.368t + 04 19948 4 32 - >ACCEPTA8 t 140.0 7 358t

• 08 19948 4 32 - > ACCEPT ABLE 145 0 7 368t + 08 11948 4 32 - >ACCEPTA8tt 150 0 7.348t + 04 11932 4 31 -- > ACCEPT Akt ill 0 7 3938 + 04 12006 4 34 -- > ACCEPTABLE 140 0 7409E+04 12011.

4 34 - >ACCEPTA8tt 185 0 7 43M + 08 13064 4 36 - > ACCEPTABLE 170,3 7 delt + 08 12148 4 38 - > ACCEPT A8LE 176 0 7.506t + 08 12189. 4 40 -> ACCEPTABLE 180.0 7514t+08 12202. 4 40 -.DACCAPTA8LE 189 0 7 lost + 08 12189 4 40 - > ACCEPTA8tf 190 0 7,48 t v 6 08 12148 4 34 - >ACCEPTA8tt 1960 7 444t + 08 17089 4 38 - >ACCtPTA8tt 200 0 7 423t + 04 12064 4 36 - >ACCEPTA8tt 206 0 7 34et +08 11942 4 32 - > ACCEPTAett 210 0 7,362t +08 11954 4 32 - > ACCEPTABLE 216 0 7.318t +08 81948. 4.32 - > ACCEPT A8tt 220 0 7 3684 608 19948. 4.32 - >ACCIPTAgts 219 0 7 3 Set +08 19948 4 32 - >ACCtPTA8(t 230 0 7 3648 +08 11648. 4 32 - > ACCEPTA8Lt 236 0 7.3584 + 04 11948. 4 32 -> ACCEPTA8Lt 240 0 - 7.348f 9 08.I1932 4 31 - > ACCEPTntt 248 0 7 3934 +08 12006 4 34 - > ACCE PT A8tt 250 0 7 4094 + 08 12031. 4.34 -> ACCtPTAkt 256 0 7 431;+ 08 12006 4 36 - > ACCf P'Atti = 260 0 7 44 t t + 08 12148 4 38 - > ACCEPT A8LE 288.0 7 5088 + 08 92189. 4 40 - >ACCEPTA8tt 270 0 PStat*0s 12202 4 40 - > ACCtPT ASLt 275 0 7 5068 tot 12189 - 4 40 - >ACCtPTA8(t 200 0 7 481 t + 08 12148 4 38 - >ACCEPTA8Lt 285 0 7 444f A08 - 13049 4 36 - >ACCEPTA8Lt 290 0 7 4236 +04 12064 4 39 - > ACCEPTABLE

C:rolina Pow:r & Light Company-ESR 97-00034 Rev. O Brunswick Nucle:r PI:nt. Unit 2 Attachment C Engineering Evaluation Page 4 Feename. 0LLD 18 97 For 315 0 1.241t*08 2634. 1 57 - > ACCEPT ABLE ~O DLL DelTR8UTfD LIGAMENT LFNOTH (VALUATION. Afy. 21 320 0 12415 + 08 2834 1 57 - > ACCEPT A8LE 409/18'981 325 0 1.241t+08 2834 1 57 -> ACCEPTA8tt . Daft OF THt$ ANALY&t08/28/1997 330 0 1.241I + 08 2634. 1 57 -> ACCEPTABLE 325 0 1.2415 + 08 2834. 1 57 - > ACCEPT ABLt

SUMMARY

OF INPL175 340.0 1.2418 + 08 2034. 1 57 - > ACCEPT ABLE 345.0 1.241t + 08 2634. 1 57 - > ACCEPT ABLE Twte. OLL SemPee Pe+84.m a2 350 0 f.241t + 08 2634 1 57 -> ACCEPT A8tt 10 8e8 tCOAR$tt all 0 1.241t + 08 2634. 1 87 -> ACCEPTABLE Angae kwrement Merr4. ene Stroes. Pm. 600 pe4 1500.po ACCEPTABLit MINIMUM EAFETY FACTOR. t 57 AT 10 0 Dt0 REEL. tendme Spose. Pt Eefety f actor 88 1.40 M*en Remus, fu . 1C J 00 esches We4 Thtknees, t. 1600 esches Spose intenemy, Sm. 16300- pas Feuence 0 CE + 00 n/cm*2 (Thus LIFM ovedvecen not ePphcatwel THETAt THETA 2 T>aCKNi$$ RE/ DON laeg i loot I imchi al 1 0.0 380 0 0 060 LIMff LOAD RtSULTS: fe0TI: THE FOLLOWeNG LIMIT LOA 0 RESU.TS ASSUME THAT THE FLAwl T AKE COMPRES$80N ALPHA MOMENT PD' SAFETY loest inibal Ipeal FACTOR RESULT 00 1.24 tt + 08 2834 f.5 7 - > ACCEPT Aett 60 1.241t + 08 2834 I SF - > ACCEPTABLE 10 0 1.24 t t + 08 2634 1 67 c > ACCEPTABLE $5 0 1.241t + 08 2834 4 87 - > ACCEPT Aett 20 0 1.J41E

• 04 2834 1 57 - > ACCEPTABLE 26 0 1.24tt+08 2834
• 87

--.m ACCEPT A2Lt 30 0 1.24 t t + 08 2634 1 57 - > ACCEPT ABLE 36 0 1.241t+08 2634 1 87 - >ACCEPTApti 40.0 1.24tt+08 2834. 1 57 - -> ACCEPTA8Lt 45 0 124tt*08 2634 1 87 -> ACCEPTABLE 60 0 124 t t + 08 2034 1 57 - > ACCEPTA8Lil 65 0 1.24 9 t

• 08 2834-i t? - > ACCEPT A8Lt h

60 0 1.241t + 08 2834 1 67 -- > ACCEPT ABLE 85 0 1.241t

• 04 2834 1 87 - > ACCEPT ASLt 70 0 1.24 t t + 08 2434.

1 57 - > ACCEPT A8tt 75 0 1.241f 4 08 2034 1 87 -> ACCEPTABLE 80 0 1.241 t + 08 2634 1.57 - > ACCEPTAett 48 0 1241t+08 2834 1 57 -> ACCEPTABLt 90 0 1.241t+08 26M 1 67 -> ACCEPTABLE 95 0 1.2 4 t t + 08 2834 1.67 - > ACCEPT Aett 100 0 124 t t + 08 2834 1 67 -> ACCEPTA8tt 1060 1.241t + 08 2634 1.67 - > ACCEPT ABLE 110 0 1.2415+08 28M 1 57 - > ACCEPTAstt 195 0 124 tt + 08 2634 1 87 - > ACCEPTABLE 120 0 1.2418 + 08 28M 1 67 - > ACCEPTABLE 125.0 1.24t t + 08 2834 1 87 - > ACCEPTABLE 130 0 1.241t+08 2634 1 87 - > ACCEPTABLE 136 0 1.24tt+08 2634-1 57 -> ACCEPTABLE 140 0 1.241t + 04 26M 1 67 - > ACCEPT ABLE 145 0 1.2415 + 04 2834 1 57 - > ACCEPTABLt 150 0 1.241E

• 04 2634 1 67 -> ACCEPTABLE t lP.0 1.241t+08 2634 1 57 -- > ACCEPT A BLE 180 0 1.24 t t + 08 2634 1.87

-> ACCEPTA8tt 165 0 1.24 t t + 08 2834 1.67 -- > ACCEPT A8Lt 170 0 1.241t + 08 2634 1.67 - > ACCEPTA$LE 178 0 124tt+08 28M 1 47 -> ACCEPTABLE 180 0 124lt + 08 2034 1.97 - > ACCEPTA8tt t al o 1.24t t + 08 2834 1 57 - >ACCEPTA$Lt 190 0 1.241E+08 2614 1 87 - > ACCEPT A 8(t 1950 1.24 t t + 04 2634 1 $7 - > ACCEPTangt 200.0 t 241t + 04 2634. 1,67 - > ACCEPT A.t 20S 0 1.24 tt

• 08 2634 1.57

- > ACCEPTABLE 210 0 1.24tt + 08 2434 1 57 - >ACCEPTA8tt 216 0 1241 t + 04 2434 1 67 - >ACCEPTAsti 220 0 1241t

• 08 2634 1 47 -> ACCEPTASLE 228 0 1.241t+08 2534 1 57 -> ACCEPfatti 230.0 124 ?t + 08 2634 i t? -> ACCEPTA8Lt 235 0 1.241t+08 2434-1.57

-> ACCEPTABLE 240 0 1.2 41E +08 2631 1.57 -> ACCEPTA8tt 245 0 1.24 t t + 08 2634 1.57 - > ACCEPTABLE 260.0 1.241t + 08

2634, 1 57 - > ACCEPTA8tt

. 254 0 114 t t

• De 2834 1.67

-> ACCEPTABLE 200 0 1.24 t t + 08 2834. t 67 -> ACCfPf ABLE 288 0 1241t

• 08 2034 1.57

- > ACCEPTABLE 270 0 1241t+08 2634. 1.67 - > aCCtPT A RLt 275 0 1241t+08 2834. 1,87 - > ACCEPTABLE 280 0 1.24tt + 04 2634 1 47 - > ACCEPT ABLE 256 0 1.241E + 08 2834-1 47 - > ACCE PT A8L t 290 0 1.241E + 04 2034 l.57 -> ACCEPTA8Lt 294 0 1.24 tt +08 2034 1 67 -> ACCEPTABLE 300 0 124tt+08 2834. 1 67 - > ACCEPTABLE 306 0 124tt+08 28M 1.47 - > ACCEPTABLE 310 0 1.241t+08 2434. t 17 - > AcctPT Aatt

C rolina Pow:r & Light Company ESR 97-00034 Rzv. O Brunswick Nucl::r PI:nt. Unit 2 Atttchmsnt C Engineering Evaluation Page S

• eenemo OLLS 16 97 For 224 0 1 9491 + 09 44797 22 72 - >ACCEPTA8tt OL1 Ol$m8MED LIGAMENT LENGTH (VALUATtON. RtV. 2.1 230 0 1 Sept + 09

47287, 22 to - > ACCEPTABLE 80 9/1 919 86 2350 1.990E + 09 47796 23 20 ---> ACCEPTABLE Daft OF T>eS ANALYSIS-04/26/1997 240 0 2 012t + 09 48322 23 45 - > ACCEPTABLE 245 0 2 034E + 09 4884S-23 70 - > ACCEPTABLE

SUMMARY

OF INPUTS 250 0 2.0684 + 09 49383. 23 95 +-> ACCEPTABLt 255 0 2.077t + 09 49893. 24.20 s ACCEPTABLE T' te. OLL Semspe Preinem F3 260 0 2 09M + 09 50406. 24 44 -> ACCEPTA8LE a 0.1 deg i FINE I 266 0 211 M + 09 50808. 24.47 -> ACCEPTABLE Anese merement Membrene Stress. Pm. 920. pad 270 0 2.13M + 09 51359 24 89 - > ACCEPTA$tt tent >ng Strese. PD 1180 Pm 27b 0 2.157t + 09 51807. 25 11 - > ACCEPTABLE Se'ety Factor, SF e 1 40 280.0 2.1744 + 09 52218. 25.30 -> ACCEPTABLE Mean kshus. lh . 94 00 mches 288 0 2.190E + 09 52597. 25.44 -> ACCEPTABLE was Thetnees. t. 1500 inches 290.0 2.2044 + 09 52945. 25 44 - > ACCEPTA8Lt Sevese intensety, $m. 14400. pee 296 0 2.218E + 09 53224. 28 78 -> ACCEPTA8LE FNonce 5 OE + 20 ntcen*2 300.0 2.227f + 09 53483. 25 91 -> ACCEPTA8LE Tenghnese. Eic . 150.0 ts'oc0 5 30S 0 2.236E + 09 53695. 28 01 -> ACCEPTABLE 310.0 2.243E +09 53847. 26 09 -> ACCEPTA8LE THETA 1 THETA 2 T>eCENESS 318.0 2.2498 + 09 54008. 26.16 -> ACCEPTABLE Iw JION ldeg l foeg l Imcheel 320 0 2.282t + 09 54091. 28 20 -> ACCEPTABLE 325.0 2.253t + 09 54117. 28 21 - > ACCEPT ABLE 1 00 26 4 1.500 330.0 2.262f + 09 54085. 24.19 -> ACCEPTABLE 2 20 4 32 1 0.970 336 0 2.249t + 09 54018. 26.16 - > ACCEPTABLE 3 32.1 34 9 1.600 340 0 2.244t + 09 63945. 28 13 -> ACCEPT A8tt 4 38 9 49 3 0 980 345 0 2.2431 + 09 53840. 28.10 -> ACCEPTABLE 6 49.3 52 3 1.500 350 0 2.241t + 09 63822. 20 07 - > ACCEPT ABLE 8 $2 3 150.1 0.900 35$ 0 2 239E + 09 53773. 26 04 - > ACCEPTA8tt 7 150 1 2309 1.600 8 2300 231.1 1.230 ACCEPTABLES M.MMUM SAFETY FACTOR = 2167 AT 185 0 9 231 5 239 0 1 SCO OtGRitS. 10 239 0 244 5 1.220 11 248 5 259 0 1.500 12 269 0 260 4 1.280 LEFM RESULTS: 13 260 4 298 8 1.500 14 288 8 295 2 1.170 NOTE: THE FOLL0wlNG LIFM EVALUATION TREATS PART.THROUGH 16 299 2 306 4 1.500 WALL 15 305 4 308 9 1.180 FLAW $ AS THROUGe+ WALL 17 308 9 3198 1.500 Thus, the fonowing news were assumed 18 3198 329 4 1 140 19 329 4 360 0 1 500 FLAW START ENO LINGTH LTNOTH OEPTH No. toeg5 IdegJ toep t McN McN LWIT LOAO nfSULTS. 1 26 4 32.1 5.7 9.35 1.50 2 34 9 49 3 10 4 17.06 1.50 gPh N071: THE FOLL0 wing Lwff LOAD RESULTS ASSUME THAT 3 52.3 160.1 97.0 f t'3 48 1.50 THE PLAWS TARE COMPRES$f0N. 4 230 9 231.4 00 0.98 1.60 S 239.0 244 6 9.6 16.S$ 1 50 ALPHA MOMENT "D' SAFETY 6 259 0 280.4 1.4 2.30 1.50 ldeel len.lbel Ipast FACTOR RESULT 7 238 8 295.2 8.8 to 83 1.50 8 306 4 300 9 1.5 2 44 1.50

0. 0 2237E+09 53732 29 02 - > ACCEPTABLE 9 319 8 329 4 96 15 75 1.50 60 2 236E + 09 53700 26 01 -> ACCEPTABLE 10 0 2 235t

• 09 S3678-28.00

- >ACCEPTA8Lt IS 0 2.2365 + 09 53664. 28 99 - >ACCEPTA8tt Asowetwa Serese Intenesty Feeton, Eac/SF = 107.1 tm' inch *0 $ 20 0 2.234t + 09 S1660 26 99 - > ACCEPTABLE 25 0 2.2344 + 09 53662. 26 99 -> ACCEPTA8Lt 30 0 2.2 34t + 08 43642. 21 98 - > ACCEPT ABLE SPACING tmas E 31.0 2.23Ji + 09 63625. 2$.97 - > ACCEPTABLE w ton.) McN ska.ina RESULT 40 0 2 232t +09 834G1. 29.94 -> ACCtPfl.8tE 45 0 2 2296 +09

63537, 25 93 - > ACCEPTABLE For space between news 1&

2. 28.22 17 08 14 3 - 80.0 2.227E

• 09 63473.

25 90 -> ACCEPTA8LE >ACCEPTA8tf 55.0 2 222f + 09 83348. 25 85 - > ACCEPT A8LE For space between news 2& 3. 18S 37 160 45 312 9 NOT 60 0 2 216t +09 53231. 25 79 -> ACCEPT A$tt ACCEPTA8(11 SS O 2 20M + 09 53052 25.70 -> ACCEPTABLE For space between news 3& 4 293 01 180 45 97.1 - 70 0 2.200t + 09 62843 26 00 - > ACCEPT ARE > ACCEPTABLE 75 0 2.1898 + 09 62570. 2847 -

• ACCLPTABLE For space between flaws 4&

27.89 15 59 13.1 - 80 0 2176t + 09 52264. 25.33 - > ACCEPT ABLE > ACCEP'ABLt SS 0 21638 + 09 61936. 25.17 - 2ACCEPTASLE For space between fleet 6& 6. 32 91 15 $$ 12 4 - 90 0 2.147t + 09

51571, 25 00 -> ACCEPT A9LE

>ACCEPTA8LE SS 0 2.131 f + 09 61173 24 81 -> ACC2PTABLE For soere between news 6& 7-57.09 10 83 92 - 100 0 2114t +09 50787. 24 81 +. - > ACCE*TA8LE >ACCEPTA8LE 106 0 2.095E + 09 50325. 24 40 -> ACCEPTA8(E For space between news 7& 8. 27.66 10.83 97 - 110 0 2 077t + 09 49882. 24 19 - > A CCf PT A BLE > ACCEPTA8Lt 115 0 2.0671 + 09 4940e 23 97 -> ACCEPTA8LE For space netween news 8& 9-36.91 15.75 12 2 - 120 0 2.036t + 09

44940, 23.74

- >ACCEPTASLt > ACCEPTABLE 1250 2.0t 7 + 09 48435. 23.60 -> ACCEPTABLE For space between flaws 9& 1: 109 26 15.75 11.3 - 130.0 1995E + 03 47913 23 25 - > ACCEPT 48tf >ACCEPTA8LE 135 0 1974t + 09 47402 23 01 - > ACCEPT A 8LE 140 0 1.913t + 09 44894. 22 77 - 2ACCEPTASLt LMITING 1 = 312 9 km' inch *0 6 N0 6 'CCEPTABLE1 144 0 19334 + 09 46418 22.64 -> ACCEPT A8LE Try comteng unacceptath news & rerun. 160.0 1.9184 + 09 44004. 22.34 - >ACCEPTA8(E ISS O 1.90lt+09 45647. 22.17 - > ACCEPTABLE 160 0 1887t+09 45324. 22.02 - > ACCEPT ABLE 185 0 1.8788 + 09 4S051. 21 89 - > ACCEPTA8tt 170 0 1847t + 09 44433 2179 - > ACCEPTABLE 1750 18ect + 09 44481. 21.71 - > ACCEP 7ABLE 180.0 1857t + 09 44597. 21 67 -> ACCEPTABLE i 10S 0 18988 + 09 44581. 21 67 - > ACCf PT A8tt t 190.0 1.858t + 09 44633 21.69 -> ACCEPT ABLE l 1950 te43t+09 44763. 21.7S -> ACCEPTASLt l 200 0 18 71E + 09 A4941. 21 84 - > ACCEPT ABLE 205 0 1882E+09 49194. 21 94 - - > ACCtPTA8LE l 21C.0 1 8958, 09 45510 22.11 - > ACCEPT 48tf - 211.0 1.9118 09 45868. 22.29 -> ACCEPT A8tt 320 0 1929E

• 09 44322.

22 $0 - > ACCEPT A8tt j

C:rolin2 Pow:r & Light Comp:ny ESR D7 00034 R:v. O Brunswick Nucl::r Plant. Unit 2 Attachm:nt C Engineering Evaluation Page 6 Feeaame DLLS 16 97 For 210 0 1.132f + 09 27179 13 38 - > ACCEPT Asti A Ott OsSTRittFTED Ls0 AMENT LINGTH (VALUATION, MEY. 21 215 0 1.16M + 09

20077, 13 wt

- > ACCEPTABLE tot /19% 220 0 1.200t + 09 29019 14 28 -> ACCEPTA8LE Daft OF T>at ANALY$15 08/26/1997 225 0 1.253E + 09 30090. 14 77 -> ACCEPTABLE 230 0 1.301t

• 09 31239.

19 31 -> ACotPTABLE

SUMMARY

OF INPUTS 2350 1.364E

• 09 32620-15 92 - >AOCEPTABLE 240 0 14128 + 09. 33915.

16 S9 -> ACCEPT ABLE T1 tie. OLL Sampas PeeMem 84 248 0 1.47 IE

• 09 35314.

17.26 - > ACCEPTA8LE 0.1 eeg I FINil 250 0 1.431t + 09 34779. 17.95 -> ACCEPTABLE Angse meras.ent Eembrane Stress, Pm = 920 pel 258 0 1 5941+09 34289 18 47 -> ACCEPTABLE 11% Pe6 260 0 1.655E + 09 39740. 19 34 - > ACCEPTABLE 8endent 5 areas. Pt = 1.40 265 0 1.712E + 09 41125 20 02 - > ACCtPTA8(t Safety Factor, SF S4 00 inches 270.0 1.767t + 09 42444. 20.65 - > ACCEPT ABLE MeanRedbs. h = waa fwckness.1 -. 1500 inches 2750 1.81M + 09 43687. 21.24 - > ACCEPTABLE Strese tntenoty. Sm. 14400 pel 280.0 1.866t + 09 44812. 21.78 - > ACCEPT ABLt Fbence 5 Of + 20 nicm*2 295 0 1.910E + 09

45963, 22 28 - > ACCEPT ABLE 160 0 kse*m*0 6 290.0 1.94M + 09 44818 2L73 -> ACCEPTA8LE Tevghnees. us 296 0 1.984( + 09 47643 23.13 - > ACCEPTABLE THETAl THETA 2 THICENiss 500 0 2 016t + 09 48395 23 44 -> ACCEPTAett MG80N l des I ideg i lechsel 305 0 2 041t + 09 49018.

23 78 -> ACCEPTA".E 310 0 2.06 H + 09 49456. 2399 -> ACCEPTA8LE 1 00 26 4 1.600 315.0 2.071t + 09 49744 24 13 - > ACCEPTA8LE 2 32 1 34 3 1.800 320 0 2 078e +09 49306. 24.20 -> ACCEPTABLE 3-49 3 52 3 1 500 325 0 2,081E + 09 49978. 24.24 -> ACCEPT 8 BLE 4 180 1 230 9 1 400 330 0 2 07M +09 49938 24 22 - > ACCEPTABLE S 231 4 239 0 1.500 335 0 2 073t + 09 49776. 24 14 -> ACCEPTABLE 4 248 6 259 0 1 500 340 0 2 062E +09 49621. 24.02 -> ACCEPT ABLE 7 280 4 284 4 1.600 345 0 2.0515 + 09

49247, 2389 - > ACCEPTABLE 8

296 2 306 4 1.600 350 0 2 041E + 09 49011. 23 78 -> ACCEPTABLE A 306 9 319 8 1.500 255 0 2.033f +09 44815 23 68 - > ACCEPT ABLE 10 323 4 360 0 1 500 ACCEMA8tEt MIN. MUM SAFETY FACTOR. 12.20 AT 185 0 OtontES LNtf LOAD RESULTS-N0ft: THE Pottow1NG LMit tuAD MESULT3 ASSUMt THAT LIFM RESULTS: THE FLAWS TAtt COMPMt$$40N NOTE THE F0ttowiNG LEFM EVALUATION TREAT 5 PART.THROUGH ALPHA MOMENT an' SAFifY WALL Ide91 inveel lomi FACTOR RISULT FLAW 5 AS THROUGH WALL. Thus, the following news were esmoded-00 2 026t + 09 dis 441 23 41 -> ACCEPTA8LE SO 2 022t + 09 48660-23 58 - >ACCIPTA8LE FLAW START ENO LENGTH LENGTH DEFa N 10 0 2 0196 +09 48482. 23 52 - > ACCEPT A BLE No. Ideg) (deg) (deg.) (mch) tinctg h 16 0 2 01 M + 09 44458 2361 -> ACCEPTASLE 20 0 2 Olet + 09 48443 2352 -> ACCEPT ABLE 1 26 4 32.1 57 3 35 1.60 25 0 2 018E +09 44406. 23 48 - > ACCEPT ABLE 2 79 9 49 3 to 4 17 06 1.80 30 0 2 016E + 09 48309. 23 48 -> ACCEPTABLE 3 52 3 150,1 97 8 160 46 1.60 35 0 2 012t +06 48313 23 44 - >ACCEPTASLE 4 2M9 231.5 04 0 99 1.60 40 0 2 004t +09 44168 23 38 - > ACCEPT A 9it 5 2390 2488 99 il 59 1 60 45 0 1997E+09

47837, 23 28 - >ACCtPTASLE 6 259 0 260 4 14 2 30 1.50 50 0 1986E+09 47649 23 15

- > ACCEPTA8Lt 7 288 8 295 2 66 to 83 1 60 ll 0 1969E + 09 47295 22.96 - > ACCEPTA BLE B 305 4 306 9 15 2 46 1.50 80 0 1949E + 09 46804 22.73 -> ACCEPTABLE 9 319 8 329 4 96 15.75 1 50 856 0 19264+09 44244. 22 44 - > ACCEPTABLE 70 0 18978 +09 46588. 22 14 - >ACCEPTA8tt 76 0 18654 + 04 44793. 21.77 -2 ACCEPTABLE Anowetpe Stress b.veasety Factor, Esc /SF = 107.1 kes*mch*0 6 to 0 18308 + 09 43944. 21.37 -> ACCEPTABLE 85 0 1.7904 + 09 42992. 20 91 - > ACCEPTABLE WO O 1,748E + 09 41976 20 43 -- > ACCEPT ASLt SPACING tmas A 95 0 1.700t +09 40426 19 88 - > ACCEMA$tt W ImI tech) (km.we MESULT 100 0 1647t*0* 39582. 19 27 - > ACCEPTABLE 106 0 1 590t + 09 35193 12 63 - > ACCEPT ABLt For space between news 1& 2-28.22 17 06 14 3 - 110 0 18 33t + 09 34418. 17 97 -> ACCEPTABLE > ACCEPTABLE 115 0 1.473t+09 35369 17 28 -- > ACCEPTABLE For space Derween Rowe 2& 3 165 37 160 46 312.9 NOT 120 0 1412E + 09 33918 16 59 - > ACCEPTABLE ACCEPTA8Lil 125 0 1.3558 + 09 32561. 15 N - > ACCEPTABLE For space between news 3& A. 293 01 140 45 97.1 - 130 0 1.302t + 09 3 t 281. 15.33 - > ACCEPT ABLE > ACCEPTABLE 2 135 0 12544 +09 30114 14 78 -> ACCEPTABLE For space betwem flaws 4& 5: 27 89 til 59 13.1 - 140 0 1.210E+09

29065, 14 26 -> ACCEPT A8it

> ACCEPT A8LE 145 0 1 171E + 09

28131, 1383 - >ACCEPTABLt For space between Maws t&

6. 32 81 15 69 12.4 - 150 0 1.13M +09 27221. 13 40 - > ACCEPT ABLE > ACCEPTABLE Ill 0 1.101E + 09 26452. - 13 03 - > ACCEPTABLE For space between flaws t & 7: 57.09 1083 92 - 160 0 1.076t+09 25842. 12.74 - >ACCEPTA8Lt > ACCEPTABLE 165 0 1066E +09 25350. 1261 - > ACCEPT ASLE For space between Maws 7& 8 27.56 10 83 97 - 170 0 1.042t + 09 25018 12.35 - > ACCEPT ABLE > ACCEPTA8Lt 175 0 10344 + 09 24812. 12 26 -> ACCEPTABLt For space between news 8& 9' 36 91 15 75 12.2 - 180 0 1.028t + 09 24497 12 20 -> ACCEPT ABLE > ACCEPTABLE 199 0 1.02SE + 09 24491. 12.20 -> ACCEPTABLE For soace between news 9& 1-109 28 il 75 11.3 - 190 0 1.035t+09

24488, 12 28 -> ACCEPTABLE

> ACCEPTABLE 195 0 1.049t + 09 21197.- 12 44 - > ACCEPTANT 200 0 1070E + 09 25704. 12.68 - > ACCEPT ABLE timmNG E = 312 9 ks'ech'0.5. NOT ACCEPTABLtl 206 0 1097f +09 24353. 1299 -> ACCEPTASLt Try comteng unaneovanee news & rerun.

Ccrolina Pow r & Light Comp:ny ESn 97 00034 Rzy. O Brunswick Nact::r PI:nt - Unit 2 Attcchment C Engineering Evaluation Page 7 ,m Comparing files DLL.FOR and d118-1~1.for 1

• • • • • • DLL.FOR C***=============================.

=========================** C*** PROGRAM: DLL.FOR, REV. 2.1 C*** +++++++++++++++++++++++++++++++ C*** Distributed Ligament Length (DLL) Evaluation Program

• • • • • • dl18-1-1.for C***===========,==============================s-e,-=========**

C*** PROGRAM: UpdatedDLL.FOR, REV. 2.1 C*** ++++++++++++++++++++++++++++++ + C*** Dist ributed Ligament Length (DLL) Evaluation Program .+....

• • • • • • DLL.FOR C***

C***========================================================**

• • • • • • dl18-1-1.for C***

C*** C*** 02/19/97 CMM (CPL) Increased # of uncracked C*** ligaments allowed to 360. C*** g C*** 8/26/97 WBW (CPL) Added Run Filename to C*** output file listing. C*** Increased # of uncracked C*** ligaments allowed to 400. C*** Increased # of angles for C*** fine moah run to 4000. C*** C*** C***========================================================** 499eee l l

C:rolin3 Pow:r & l.ight Comp:ny ESR 97-00034 R:;v. O Brunswick Nucl:tr PI:nt - Unit 2 Attcchm::nt C Engineering Evaluation Page 8

• • • • • • DLL.FOR f,,

CHARACTER *6 MESH DIMENS1')N THETA 1 ( 75), THETA 2 (75), THICK (75), CRACK ( 75 ) DIMENSION CRK_ANG1 (73), CRK,ANG2 (75) _ DIMENSION TH(3600), ANGLE (36w, IFLG (3600) DIMENSION PB_ PRIME (77), SAFE (77)

• • • • • • d118-1-1.for CHARACTER *6 MESH DIMENSION THETA 1 (4 00), THETA 2 (4 00), THICK (400), CRACK (400)

DIMENSION CRK_ANG1(100),CRK_ANG2(100) DIMENSION TH(4000), ANGLE (4000),IFLG(4000) DIMENSION PB_ PRIME (77), SAFE (77)

• • • • • • DLL,FOR WRITE (*,1) REVISION 1 FORMAT

(//,5X,'**********************************************', /,5X,'** PROGRAM "DLL" REV: ',A15,' /,5X,'** Distributed Ligament Length Analysia /,5X,'****************'******************************') C***

• • • • • • d118-1-1.for WRITE (*,1) REVISION 1 FORMAT

(//,5X,'***********************************************', 4I* /,5X,'** PROGRAM "DLL* REV: ' A15,' /,5X,'** CP&L Version - Updated through 8/18/97 /,5X,'** Distributed Ligament Length Analysis /,5X,'***********************************************') C***

• • • • • • DLL.FOR DO 16 I=1,N IF (IFLAG.EQ.

1) THEN READ (08,*) THETA 1 (I), THETA 2 (I), THICK (I)

• • • • • • d118.1-1.for DO 16 I-1,N IF (IFLAG.EQ.

1) THEN READ (08,*) THETA 1(I), THETA 2(I),THICE(I)

• • • • • • DLL.FOR WRITE (*,17) RdVISION,IMONTH,IDAY,IYEAR, TITLE,INCR, MESH 17 FORMAT (2X,'DLL: DISTRIBUTED LICAMENT LENGTH EVALUATION,',

,A15,/,2X,'DATE OF THIS ANALYSIS: ,12.2, REV.

• =4***

d118-1-1.for WRITE (*,17) REVISION,IMONTH,IDAY,IYEAR, TITLE,INCR, MESH 17 FORMAT (2X,' Filename: DLL8-18-97.For',/,2X, &'DLL DISTRIBUTED LIGAMENT LENGTH EVALUATION,', ,A15,/,2X,'DATE OF THIS ANALYSIS: ,I2.2, L' REV.

ESR 97-00034 Rev. O Attachment D Page i es . REPORT NO.:. EXAMINATION

SUMMARY

SHEET GE Nuclear Energy R c3n -s PROJECT:._Bmnswick Nuclear Plant PROCEDUREt_ CE.ut.503 REV:._fL_. FRR: MA

• ^

B213R1-7g3 SYSTEM: SHROUD ASSEMBLY WELDS MA REV: MA FRR: 'MA MA WELD NO.: H4 MA - MA REV: N/A FRR: _ MA CONFIGURATION! PLATE TO PLATE MA EMMINER: f tovd LEVEL: _Jf O MT O PT N UT O VT EXAMINER: P. Johnson LEVEL: In 3 CIRCUMFERENTIAL EXAMINER: o. uwe LEVEL: 11 0 LONGfTUDINAL O OTHER MA DATA SHEET NO.(S): 0-117 o.1in n-12s CAL SHEET NO.(S): c.124 c.12s c.12e c.127 c.12n c.12e Dunng the automated ultrasonc examination of the referenced weld, eight (8) indications associated with IGSCC/1ASCC were recorded by tne Smart 2000 System utilizing a TRI-MOOAL search unrt contaitung a 45' Shear (S),60' Refracted Longetidinal(RL), and 00 creepmg wave (OOCR) search unsts. The referenced indications are pre-existing flaws recorded during the 1994 and 1996 Shroud inspections. Re-examination of'hese flaws were performed for comparative anahsis. The parameters for these mdications are on the following page b The 45' S recorded ins;de and outside surface weld crown geometry and non-relevant indications along with the indications referenced The 60* RL recorded inside surface weld crown geometry and non relevant mdications along with the indications referenced. The OOCR recorded shear component to inside surface geometry and non-relevant indications along with the indca . referenced ladications 1,2, 3,4. 5. 6. 7, and 6 were evaluated and compared to 1994 and 1996 results showing httle evidence of growth. I Circumferential(L) dimensions were recorded in angular units. The conversion factor for linear units es 1.55 inches per degree. This exammation was Imted to the areas scanned for the purpose of flaw growtn evaluacott The areas scanned were from 123 2' to 151.10' and 233 2' to 271.1* for a total of 65 8'(18.3%) Previous data was revwwed pnor to this summary. h \\ ~~*IA7 c~ b-I I 0(. oCf"9 7 L Q40.gA m- ,sde or oc 4 s swer um oars amuew caru noe; _t_ on: to _.,, _~.

. ESR 97-00034 Rev. 0 ' Attachment D Page 2 l 1 D- ~ GE Nuclear Energy - a,,w -, a Core Shroud WeldH4 Indication Data. Teent seen Longe EuanMed(Deg) 68.80 TNchneee (M) 1.90 TeeniSean Lange Enembed(In) 101.92 CJrounderence (MJ 957.00 hchoe perDegree 1.06 T-.-.. of10%f Leppt Enembed 10.3 a ~ _ of Enamened *6%medlenge newed 40.3 Tone!MewedLengeh (M) -80.28 re-. of Toeal WaldLange Mewed 9.0 TotalMewed Lange (Deg) 32A8 %d Start End Lerneth Lange Dep6 Dep* Persent heelneing Depdat.enge No. AJMuush Aafmum Adesum h Afew.h Aadmum T7vuwe# Surflece Trenedecer, - 1 127.11' 130.12' 3.01' 4.88 0.51 120.4T' 34.00 lomoet 00* L 2 130.57' 138.84* 7.37' 12.34 0.03 131.7F - 42.00 lomest 00' L 3 140.1r.142.9r 2.ge* 4.43 0.87 141.02' 08.00 IOMoor 80' L 4 240.18' 244.03' 3.Br 8.01 0.71 242.3r 47,33 IONoet 80* L 5 245.or 290.30' S.2s' 8.15 0.73 247.TP 40.87 IONoet 80* L 248.1$* 48 87 IOMost er L 248.78' 48.87 IONoet 60* L 8' 290.42* 252.23* 1.81' 2.80 0.72 261.02' 48.00 (OMeet 80' L T 2M 83* 200.90* $ ST' 8 00 0.88 290.30* 48.33 ID Heer $r L 250.40' 48.33 IOMeet 80* L _ ~-,, 4 288 $r 287.4r 1.80* 2.79 0.43 288.74' 28ST IDHeat er L Indicaelone Othmugh 03 were detected with the search unote on me upper side of me wekt, looking dowrt toward me wood Indcatione 04 through 08 were detected win the search unite att the lower side of the wekt, looking up toward the weld (Nase: Insaceston as wee not reported in the 1996 date liecause it was not withm the eron that wee scanned) 1 Armee Not Enemoned by All,3 Transducers: 294.20* Total Degreee Not Exer.t..;.od 4 0.00* to 123 20* 123.20' 151.10* to 233.2r 82.10* 271.10* fo 340.00* 86.90* EsadeneWon of Lleifeocons Limeendone: Cornperieon Evolvedon 19ti to 1908 Addeponal Conwnente: There le the r'- ^ *'::i of showMg ladcation dote poettiene, within the etnovo parametere, i shot entend Mio erees shown above as stof enemined TNe le due to me degree poedefone of me Mdv+ahrer eeneducere endeMn me Tri-ecodel Search (Mit pechage, . The eneminadon anarch unden have countercdeckwise o#asse of; Leedng Center TranNng(referencedI6edonepoeroon) LookMg U,n Search (Met: er s - er L OOct 0.se 0.00 .o.81 Loodning Dowre Search Unit: Doct 80* L 48* S 0 81 0.00 4.55 ^ D tofQqp: GA W..

'} Brunswick Nuclear Power Plant-Fall 1997 Core Shroud Examination Prolact-1HDE7. Flaw IndicaTon Position and Through-Wall Measurements - Weld H4 Indicadon $1 Indicauon s2 indicadon 63 Indicadon 04 Azymen Flow Doge Azimum Faen Depen Azanuth. Flaw Depm Arunuth Flaw Depet Azenum Few Depm Ammam Flow Depen (pagrees) Onches) (Degrees) Onches) (0,grees) ; Onches) (Degrees) Onches) (Cy -.) Orc.-.) T _-) Orches) 127.11* 0 00 130 57* 0 00 133 88* O.37

• 3704*

0 05 140.12' O.00 240.15' O.OO t 27.26' O 22 130 72* O 12 134 04* O 34 137.19' O 05 140 27* O 05 240.30* O 00 127.41' O 3d 130 87* O25 134 16' O 32 137.34' O 09 140 42' O 05 240 45' O.00 127.56' 024 131 02-0 15 134 33' O 47 137.49' O 12 140 57' O.34 240 60* O 00 - 127.71* O 50 131.17* O 28 134 48' O 36 137 64* O 07 14077 ~ 0.46 2875* O 00 127 86* O 32 131 32* O 43 134 63-0 37 137.79* O 06 140 87* O.69 240.87* O.46 128 02* 0 05 131.48* 0 37 134 78* 0 39 137.94* O.10 141.07 0.87 241.02* O.46 128.17' O.19 131 63* O.36 134 83* O 59 138 09* O 11 141.17* O.47 241.17' O 05 128 32' O 44 131. 7B* O 63 135 09* O 32 138 24' O 08 141.32* O.70 - 241.3T O 05 128.47' O.51 131.93* 0.34 135 24' 0 48 138 39' 0 05 141.48' O.47 241.48' O.34 128 62* O 39 132.08* O 32 135 39' O 33 138 54' O 00 141.63* O.45 241.63* O 05 128 77* O 24 13223* O 29 135 54* O 38 141.78* O 59 241.78* O 05 128 92* O.27 132.38' O 16 135 69* 0 39 141.93* 0 44 241.93* O.15 129 07* O.22 132.53* O 27 135 84* 0 49 142.08* 0 56 242.08* O.13 129 22' O 05 132 68* O 34 135 99* O 42 14223' O.55 242.23' O SO 129 37' O 15 132 83* O 47 136 14' O 32 142.38' O 42 242.38' O.71 129 52' O 05 132 98* O 28 136 29* O 05 142.53' O.41 242.53* O 65 g 129 67* O 05 133.13* O 43 136 44* O 05 y2 142 68* O 32 242.68* O 52 N 129 82* O 05 133 28* O27 136 $9' O 05 142 83* O.18 242.83* O 40 129 97* O 05 133 48' O 30 136 74* O 07 142 98* O 00 242.98* O 35 130.12*- 0.00 13373* O 40 136 89* O 05 243.13' O 24 o 24328* O.16 8 243.43' O.18 243.58' O.33 y 243.73* O.20 Q 243.88* O 07 244 03* 0 00 C Length 3.01-Length 7 97* Length 2.86* Lenglh 3 88* Man Depm 0 51 Mu Depth c 83 uma Depth 0 87 Men ospeh 0.7s E a ?. O 3 (hh) e: CA 6 g q c_, 10/6/t? Page 6 of 2 O l

) Brunswick Nuclear Power Plant - Fall 1997 Core Shroud Examination Protect - 1HDE7 Flaw Indication Position and Through-Wall Measurements - Weld H4 Indication sS IndscaUon 86 Indication 07 AzumAh riew Oope Wm flow Depm hunuth flew Ospm Azunum Flow Oopth ArumAh Flow Depth Arenum FiewDepm indVcetion OS cegrees) Onches) (Decrees) Onches) (Desroes) Onches) (O=erees) Onct=s) (Degrees) Onches) t _) cr.c ) 245 09' O.OO 248.54' O 70 250 42' O 00 254 63' O.OO 255.24' O.11 26558' O.OO 245.24' O.05 248 70* 0 72 250 57* O 22 254 78* O.14 258.39* 0 28 265 84* 0 00 245.39' O12 248 85* O $5 250.72* O 61 254 93* O.14 258.54' O.12 265.99* O 13 245 54* O.05 249 00* O 67 25087* O J2 25EO9* O 67 258.69* O 31 266.29' O 16 ' 245 69* O.18 24915' O 73 251 02* O 72 255 24' O 66 258 85* O 14 266.44' O.34 245 84* O.21 249.30* O 72 251.17' O 71 255 39' O 61 259 00* O 23 266.59' O 22 245.99* O.47 24945' O.72 251.32* 0 71 255 54* 0 65 25915' O 19 266.74* O.43 246.14* 0 61 249 60* 0 68 251 46* 0 68 255 69* 0 62 259.30* 0 68 266 89* O.42 246.29-0.56 249 75* O.73 251 63* 0 67 255 84* 0 60 259 45' 0 68 267.04* 0 10 246 44* O.56 249 90* O 45 251 78* O 58 255 99* O 62 259 60* O SO 267.19* O 00 246.59' O.55 250 05* O.17 251 93* 0 49 256 14* 0 48 259 75* 0 37 267.34' 0 00 246 74* O 65 250 20* O 15 252 08* O 17 256 29' O.50 259 90* O.14 267.49* O 00 246 89* O 38 250 35' O 00 252 23' O 00 256 44' O 45 260.05* O.25 247 04* 0 71 256 59' 0 46 260.20* O.12 247.19' O 72 256 74* O 13 260.35' O 00 24734* 0 63 256 89-010 260.50* 0 00 247.49' O.43 257 04* 0 10 m 247.64* O 45 CA 257.19' O 10 247.79* O.73 N 257.34' O 18 247.94* O.72 257.49* 0 14 y'O 248.09* O.72 257 64* O.19 6 248 24* O 72 257.79* O15 248 39' O.71 257.94* O 48 y 258 09' O 24 N Length 526* Length 18t* h Length 587* Max Depth O 73 Mas Depth 0 72 Length 1 An* Mas Depth 0 68 g o Men Depth 0 43 l E o a. C IDfLY o CyL, L% gg

wlsh, Page b of 2.0 4;

ESR 97-00034 Rev. 0. Attachment D Page 5 .,m IQ) EXAMINATION

SUMMARY

SHEET f EPO3T NO.; GE Nuclear Energy n.aso .] PROJECT:_ BrunswiChBuClear Ptant PROCEDUREJE.tJT so3 REV:_ E... FRR: N/A B213R1 N/A N/A SYSTEM: _ SHROUD ASSEMBLY WELDS WELD NO.: H5 ~ - N/A MA N/A REVN FRR: _NA CONFIGURATION: Pt. ATE TO PLATE N/A EXAMINER: f Lavd LEVEL: It O MT O PT S UT O vi EXAMINERi-P Johnson LEVEL: ill S CIRCUMFERENTIAL EXAMINER: R. Paasknweki LEVEL: l' O LONGITUDINAL 0 OTHER N/A DATA SHEET NO.(S): 011e n 120 o-121. 0 in CAL.9HEET NO.(S): c tso c.131 c-132 c 133 c.134 c-iss mam124 0-12s n-127-o-128. D 129 Ounng the automated ultrasonic examination of the referenced weld, no indications associated with IGSCC/LASCC were recorded by the Smart 2000 System utikring a TRI-MOOAL search unit containing a 45' Shear (S),60* Refracted Longstdinal(RL), and 00 creeping wave (OOCR) wave search units. The 45' S recorded insde and outsde surface weld crown geometry and non-relevant indications The 60* RL recorded insde surface weld crown geometry and non-relevant indications h-The OOCR recorded shear component to insde surface geome',ry and non-re'evant indcations. Circumferential(L) danenseons were recorded in angular un4s The converson factor for hnear units is 155 incnes per degree. The examination area that was interrogated by all angles was 13 30* to 1713* and 1981* to 341.1* for a total of 301.0* (83 6%) from the lower sde of the weld; and from 13 3* to 81.1* and 233 3* to 291.3* for a total of 125 8'(34 9%) from the upper sde of the weld. Previous data was reviewed pnot to this summary %LQ%6 sc ,cyn 8e = wn ~n c " ~ ~ ~ ~ "" y/n w sues.ev.,' um on _L. or. 21 _...... . d amm can e.ce:

ESR 97-00034 Rev, O Attachment D Page 6 0,. Brunswick Unit 2 ~ GE Nuclear Energy Shroud UT Examination Shroud Weld H5 Scan Coverage / A h f 3 h / -/ _v_ t g ini A F 4 e v 3 / in i 1] 4 b9 \\ !k / d' v / "m " ~m" w A l v l bub (lYh, I-4 as Page 2,_ of d f y acau

ESR 97 00034 Rev. O Attachment D Page 7 Brunswick Unit 2 - Weld H5 Scan Plan m B213R1 FOR LOOKING DOWN AND LOOKING UP EXAM WITH TRIMODAL PROBE (180 deg. to 360 deg.) Lug Posmon Toot Leading Leed.ng Cereer Corner Trades Trashng totat Angie Lug Ammuth Set,p Aamuth Start End Start End Start End Scan Start Scanned overtsp (dog) (dog) (degl (deg) (deg) (dog) (degi (degl (dog) (deg) (deg) (deg) g 19 185.00 OBSTRUCTION DUE TO DOWNCOMER 20 d5.00 21 205.00 +2.40.207.40 198.1 212.1 197.5 211.5 196.9 210.9 0.00 14.00 0.00 22 215.00 -2.40 212.60 206.3 217.3 205.7 216.7 205.1 216.1 3.00 11.00 5.80 23 225.00 2.40 222.60 216.3 227.3 215.7 226.7 215.1 226.1 3.00 11.00 1.00 24 235.00 2.40 232.60 226.3 237.3 225.7 236.7 225.1 236.1 3.00 11.00 1.00 25 245.00 -2.40 242.60 236.3 247.3 235.7 246.7 235.1 246.1 3.00 11.00 1.00 ' 26 255.00 2,40 252.60 246.3 257.3 245.7 256.7 245.1 256.1 3.00 11.00 1.00 27 265.00 -2.40 262.00 256.3 267.3 255.7 266.7 255.1 266.1 3.00 11.00 1.00 b 28 275.00 -2.40 272.60 266.3 277.3 265.7 276.7 265.1 276.1 3.00 11.00 1.00 29 285.00 -2.40 282.60 276.3 287.3 275.7 286.7 275.1 286.1 3.00 11.00 1.00 30 295.00 -2.40 292.60 286 3 297.3 285.7 296.7 285.1 296.1 3.00 11.00 1.00 31 305 00 -2.40 302.60 296.3 307.3 295.7 306.7 295.1 306.1 3.00 11.00 1.00 32 315.00 -2.40 312.60 306.3 317.3 305.7 316.7 305.1 316.1 3.00 11.00 1.00 33 325.00 -2.40 322.60 316.3 327.3 315.7 326.7 315.1 326.1 3.00 11.00 1.00 34 335.00 -2.40 332.60 326.3 340.3 325.7 339.7 325.1 339.1 3,00 14.00 1.00 35 345.00 OBSTRUCTION DUE TO DOWNCOMER 36 355.00 0 50 uwemum overteo on each end of scan (deg) 19 86 Totni Camage Travet (dog) -2A0 Scanner OWest for CW Cyt. Posmoned on CCW sade of CCW Lug (dog) NEGA TNE 8 2.4 Scanner OWiet for CCW Cyt Poseoned on CW suse of CW Lug (dog) POSITNE 8 0 56 HS Leedeng Transducer OWset from Center Lme (d*g) POSITIVE 8 0 00 HS Center (CW) Transducer Onset from Cermer uno (deg) POSITNE8 OR NULL - 4 56 H$ Trading Transducer Oeset from Center Lme (dog) NEGATNE8 OR NULL 1 55 inches per degree 0 64 Degrees per mch (Note: 'deg' urves topr sera degrees on shroudl (Note ' Scan Starf ra referenced from the paysacai nmd of rnoton on the tool 0 65 Inden increment (deg) ,,. 4 <M Nea b w I U g;.p Ge A

ESR 97 00034 Rev. O Attachment D Page 8 t Brunswick Unit 2 - Weld H5 Scan Plan A B213R1 7on LOONNG DOWN AND LOOKING UP FXAM WITH TRMODAL PROSE (0 deg. to 180 deg.) _ l Lu, ces.o., 10 to n, t.o.no Ce=, C.nio, tr..n, tr n. raiei an,, Lue Amme setup Aamusi stort End stort End seert End seen saari ecenned oven p (M fees) (due) (doel (deel (dem) (des) (dea) (des) 1 5.00 (doel (dea) JM l 00GTRUCTION DUE TO DOWNCOMER 2 15.00 3 25.00 2.40 22.60 13.3 - 27.3 12.7 26.7 12.1 26.1 0.00 14.00 0.00 i 4 35.00 ~.2.40 32.60 26.3 37.3 25.7 ~ 16.7 25.1 36.1 3.00 11.00 1.00 5 45.00 2,40 42.60 36.3 47.3 35.7 46.7 35.1 46.1 3.00 11.00 1.00 ~ 6 55.00 2.40 52.60 48.3 57.3 4D7 $6.7 45.1 56.1 3.00 11.00 1.00 7 65.00 -2,40 62.60 56.3 67.3 55.7 66.7 55.1 66.1 3.00 11.00 1.00 s 8 75 00 -2.40 72.60 64.3 77.3 65.7 76.7 65.1-76T 3.00 11.00 1.00 l n E 9 b.00 2.40 82.60 76.3 87.3 75.7 86.7 75.1 86.1 3.00 11.00 1.00 10 95.00 2.43 92.60 86.3 97.3 05.7 96.7 85.1 95.1 3.00 11.00 1.00 f 11 105.00 2.40 102.60 96.3 10T.3 95.7 106.7 95.1 106.1 3.00 11.00 1.00 ~ 12 115.00 2.40 112.60 106.3 11T.3 103.7 II6.7 105.1 116.1 3.00 11.00 1.00 13 125.00 2.40 122.60 116.3 127.3 115.7 126.7 115.1 126.1 3.00 11.00 1.00 i 14 135.00 -2.40 132.60 126.3 137.3 125.7 136.7 125.1 136.1 3.00 11 00 1.00 ~ 15 145.00 2.40 142.60 136.3 147.3 135.7 146.7 135.1 146.1 30. 11,00 1.00 4 16 155 00 2.40 152.60 146.3 157.3 145.7 156.7 145.1 156.1 3.00 11.00 1.00 17 165.00 -2,40 162.60 156.3 I66.6 155.7 166.0 155.1 165.4 3.00 10.30 1.00 18 175.00 k l OBSTRUCTION DUE TO DOWNCOMER 0 so. naeumum emetop on oech end of scari(dog) 19 as Teest comoge Tr<vot (dog) 2 40 Soonner Opeet ist CW Cyt. Peee>ned on CCW emes of CCW Lug (dog) NEGAT1VE s 2.40 Scannot Opeet sur CCW Cyt Pos.oned on CW esde of CW Lug toeg) POSITIVE S 0 St H6 Looeng Treneducer OWest Itom Centet LN (deq) FOGITIVE8 0 DD HS Center (CW) Treneducer Onnet from Coneet Line (dog) POSITIVES OR NULL 4 Se HS Tredeg Treneducet Opset from Center Lme (dog) NEGATTVE8 OR NULL 1.S6 - Inches per degree 0 ed. Depeespermch . ' dog unes represer* degreet on throudl

' Scan Stest es referenced from the physacal hmt of anoton on the toot -

0 06 Indes encreenent (dog) -t y. (2pesh+ u .p ~ " + - i.I, /c, 1 . _,. _..,.,.. _,. _. _.., _. ~,,.

0 ae n.,a=,en.ru Core Shroud Weld H5 - Tyolcal Geometric Indication Details The indications depicted below are illustrative of the nonrelevant indications which were detected during the examination of this weld. The source of the indications is the contour of the ID surface of the component eld. 1.611" --- OD 0 60 L-Wave

c. -

m 3.61" J nt:l: $; 1.50 in. / / ,h (h ~- ,.4/ Top Bottom Sid ID >-t?.arLL."12.flEEl r v. 73,e es y, ,e' .v1 se. 44. M Jdsh M AM_ S ~,.., m w.,. c, u, sm. uum ax ,s w , azz t - a Yn! 99.%] l vi ,37 ss1' 5 n aYl 37 68] 7ae as -6 es t 1/1 12 Fat in O, at h d3Am (3 3 % lsig y Page f of 2I -v -n

ESR 97-00034 Rev. O Att chment D Pege80 f (J EXAMINATION

SUMMARY

SHEET REPORT NO.: GE Nuclear Energy amL_. i m PROJECT:_BrunswiclLNudea _Elant PROCEDURE:._GEllL5M REVL fL FRR:.$A, B213B1 2 SYSTEM:. SHROMQASSEMBLY WELDS .MA REV: NIA FRR: N/A _MA WELD NO.:_B68 _sA -MA REVL.NIA FRR: _NlA i CONFIGURATION:_ CORE SUPPORT RING TO Pt. ATE 16tA t MA EXAMINER: J t* LEVEL: 'l D MT O PT G UT O vi EXAMINER:,,fLfasakestaki LEVEL: if S C!RCUMrJ.RENTIAL FXAMINER: =** LEVEL:. MA-s O LONGITU0iNAL O OTHER MA DATA SHEET NO.(S):.cdoo.Dantodo2.Daos CAL SHEET NO.(S):.cm3 c nan c. net _Da04. D 105. D 108 D IQT Dunng the automated unrasonc exammation of the referenced weld, forty frve (45)indicatens associated with IGSCC/lASCC were recorded by the Smart 2000 System utking a TRt4400AL search unit containing a 45' Shear (S). 60* Refracted Longitudinal (RL), and 00 creeping wave (ODCR) wave search units The parameters for these indications are on the following pages The 45' S recorded msde surfa:e weld crown geometry, acoustic mterface and non-relevan, mocations along with the mdications referenced The 60* RL recorded maide surface weld crown geometry, acounte mterface and non relevant indcatens along with the indications referenced The ODCR recorded non-relevant indications and shear component to mside surface geometry sleng with the edcations referenced Cucumferential(L) demonsions were recorded in angular units The conversion factor for imear units as 15* mches per degree This exammaton was limited to the areas scanned due to obstructens from the guide pins and core spray downcomers. The esaminaten area that was eterrogated by all angies was 303 4'(84 3%),56 6' (t 5 7%) was not exammed due to the above referenced obstructons b Frevious data was reviewed pnot to this summary i <tmem. s w!,k, C C & h:,w num Qd.4%4 ar,eNo cm i se.e,ev: m et m, 4 a==newtw cara l e.oe: L or: n,,,,,,,,,,

ESR 97-00034 Rev. O Atttchment 7 PageO 9 i GE Nuclear Energy i t f ) Core Shroud Weld H6B Indication Data I i i TeaW seen Langst Eranear(peg) 303.40 TMo4nees(ht) 1.80 i reset seen tengst nenmedim)- 40s.93 chaussairense(m) 887.00 I haltee perDepos 1.88 Persensspo et gnquW Langst Eweenteed K3 Persendsys et Eramshed Witsw Langst newed - 13.0 TeeWMewed *.engWe(limJ _ 343.08 enroemese at reevwswtange Mswes 41.8 resernewestengst toeg) 221.48 -) hed. - Seert and -tengst. tengst DepWt Depe Perceni haddesbeg DepetengWe A80. Aatusust Aslusugt Aalseum he. 40er.4. Asbusse T3trwouf Sentece Fhmeestseer 1~ It M 22.4r 9.fr 18.00 0.80 30.or 30.33 10Meer er L 2 M 37' 34.13' - 9.Fe* 18.12 0.87 28.Or 37.4T IOMeer er L 3 34.Tr 40.01' 8.tr _ 9.03 0.30 - 34.7F 26.00 00Meer er L j 4-42.tr 44.78' 1.98' 3.02 0.14 43.48' 9.33 IDMeer 40' L i 8 44.Tr 40.0P 1.2r 2.00 0.11 48.4r T.33 IDWeer er L S 40.0T' 80.01' 4.84* 7.03 0.47 49.31' 31.33 IOMeer GO' L i T 90.01' 52.1r 1.8P 2.43 0.27 $1.83' 18.00 IDMeer 40' L 8 SS.dr 88.4T' 3.28' $.03 0.24 84.7 7 10.00 IDMeer 80* L 9 42.1r 43 M 1.30* 2.01 0.30 42.83* 20.00 ilJMeer 40' L it 88.or EOF 2.00* 4.03 0.28 8T.3P 16.47 10 Meer GO' L i O 11 ' te.Or 69.31' 1.2r 2.00 0.25 KSP 10.07 IDMoor 40' L 12 00.31' 70.8r 1.8r 2.48 0.23 70.24' 18.33 10Meer GO' L 13 71.83* 70.0T* 4M T.03 0.34 72.1r 22.4F IDMeer 40' L 14 70.07' te M 4.82* T.4T 0.23 78.tT' 18.33 IDMeer 40' L } 18 43 M 90.01' T.13' 11.04 0.28 09.31' 10.6? 10Meer 40' L 16 90.41' 183 M 12.8P 19.93 0.48 90.72' 32.00 IDMeer 40* L 17 183 M 1 M 70' 1.30' 2.01 0.12 104.1r - 8.00 10Meer GO' L -it 144.TP - 1R7F 1.94* 3.00 0.00 104.42' 8.00 10 Moor 30' L f 19 1 ROP 110.01' 2.89' 4.01 0.18 100.31' 12.00 10Meer GO' L 20 110.80' 118 M 4.8r T.02 0.28 114.78*- 17.33 10Meer GO' L 21 110.0T' - 119.90' 3.89* 4.03 0.28 117.3P 10.67 10Meer 40' L 22 121.8r 139.31' 1T.78* - 27.84 0.43 129.90' 4 LOO IDMeer 40' L 23 139.tr 14L18' ' 2.2r 3.44 0.28 141.83* 18.07 IOMeer P/ L i 24 143 M 148.42' 1.Sc 3.00 0.14 144.7r 9.33 ID Meer er L i 28 144 M _ 147.37' '1.98' 3.02 0.13 144.72* 8.87 10Meer 40' L i 26 - 14T 3P 184.78' 7.41' 11.48 0.88 18163* 30.47 10 Moor 40' L 27 1K4r 101.8r - 4.11' 9.48 0.81 1K0P 34.00 IDMeer er L i at 14L8r thir 1.30* 2.01 0.13 183 M 8.87 10Meer tr L 29 198 M - 171 M SM ~' 9.08 0.38 1 EOF 23.33 10Meer to' L 1 at 1Mer 300,9F 8.4r ' 10.44 0.24 1K78* - 10.00 IOMeer GO' L v 31 - 300.tr 202.Or 1.94* 3.02 0.28 301 M 14.6T 10Mee6 Or L I 32_ 210 M 21Lir 1.94* 3.00 0.30 210 M 13.33 IDMeer er L ' 33 238M - 238.4P 3.2r 5.03 0.47 - 228.7F 31.33 10Meer er L 34 238.4P 230.01' 1M 3.00 0.06 229.11' 3.33 10 Meer 00* L 38' 23L1r - 24T.tr 16 M 23.98 0.78 2 ROP 50.00 IOMeer GO* L "38 248.94* 2K7F 7.7r 12.08 0.88 282.18' 38.67 10Meer er L I 37 s 200.31' -1461' 1.30' 2.01 0.19 - 200 M 1147 IOMeer GO' L - 30 270.0P - 2T7.37' : -.1.30' 2.01 0.23 276.7F - 18.33 IOMeer er L

30 279.90*.

20143* 2.4P 4.48 - 0.22 281.8r 14.47 10Meer 80* L i I ,-_a .. _ _ _._ _._. _ _ ~,,,,,,..,,,,. ; -.. -, ~, - - = _ ~. - -.

ESR 97 00034 Rev. O Attachment D Pege[?; f 9 GE Nuclear Energy - w Core Shroud Weld H6B Indication Data i 40 182.83' 288.02' 5.19' 8.04 0.27 285.# t' 18.00 IDWeet 60' L 41 288.8T' 201.20' 2.80' 4.01 0.22 300.90' 14.4T IDWeet 80* L 42 201.30' 300.61* 9.38' 1A.48 0.87 29110' 38.00 10 Meet GO' L 43 301.53' 302.83' 1.30' 2.01 0.0T 302.18* 4.87-lDWeer 80* L 44 318.3r 338.42' 20.10' 3f.t3 0.04 327.27' 44.00 10Meer GO' L 44 338.4r 341.20' 5.84' 9.05 0.00 341.20' 40.00 'rWNoor 00* L i M Amecealens were sfefected wtWe me search un#s on me Jower aMe of me wofd, JooWeg up toweJ me weld. Armes Not nemmed by M 3 Transducers-s0.00 toner Depoon not samoned 0.00 to 13.30 13.30 211.10 to 106.70 24.00 34f.30 to 300.00 10.T0 uptanee6en of LJmitadens: LJm6enatens: Core Spray Downcomern, Gutene pins, LMung Lugs andInstrumentadon L)nes f\\ AnHnenat Commente: There le me pesetMNy of showing Ind6cadon date postatens, wteMn me above paremeners, nhet ensamt ones areas showrt above as not examined. This is due to the degree poeldens or me indfvfdual tronaducers wWsMn me Tit-Adodef Search Un#pacAage. The examinaden search unks have counterclockwise oWsets of: Leedrng Center TroIIMg (referenced for doen postoon) LooMng (48 Search UnN: 45* S 60'L OOct 0.54 0.00 4.81 LooMnq Down Search LMIt: ODCt 60*L 45' S 0.41 0.00 4.58 thN CFL LAIL - rp Page 3 of 75 ~; ig t e [ ~.- -.

y w e) ) 1 Brunswick Unit 2 - Shroud Wcld H68 - 0* to 90* Comparison Data 1996 to 1997 t Thru-wall Rollout Map l 1.40 I 01996 Data 5 1997 Data 7 1 f l c 1.00-I e t l 0.80 k l 0.60 O ] 0.0* 6.4* a2.9* 19.4* 25.9* 32.4* 38.9* 45.4* 51.9* 58.4* 64.9* 71.4* 77.9* 84.4* 90.9* j Circumferential Location in Degrees from Vessel *0* y {} {[ t * - 1.55 inctwo or. 00 of stroud g c 4 ,t cpu w se oc. Page 4 of 25 to),[q7 t s 5 'd 4

Y '} ) i \\ Brunswick Unit 2 - Shroud Weld H68 - 90' to 180* i Comparison Data 1996 to 1997 Thru-wallRollout Map ? 1.40-i 1 01996 Data [ 1.20-51997 Data E 5 1 J 1.00-O h i E Area Not o 0.80-m Scanned in 1996 k f [i i 0.60-A i l i V N ! 2 0.40-c

• 90.2*

96.7* 103.2* 109.7* 116 2* 122. <

• 129.2* 135.7* 142.2* 148.7* 155.2* 161.7* 168.2* 174.7* 1 Circumferential Location in Degrees from Vessel *0*

(

r

] 1* = 155 h:hes on OD of Shroud i I 6 1 CPbLGL c;

• lN41 bI Page 5 of 25 g,

i

r ') ) Brunswick Unit 2 - Shroud Weld H68 - 180* to 270* Comparison Data 1996 to 1997 Thru-wallRollout Map 1.40-O $ 996 Dat.t 1.20 E 1997 Data T E l uj 1.00-9 Ey 0.80-c 6 0.60-l jf a f n IAA . 1,, 0. 4 i 4 i 180.0* 186.5* 193.0* 199.5* 206.0* 212.5* 219.0* 225.5* 232.0* 238.5* 245.0* 251.5* 258.0* 2 i, Circumferential Location in Degrees from Vessel *0* E ! n t 1* = 1.55 inches on OD of Stroud. 3 ! "3 j L apen ,q., gy sac

g.,e - 2s q!

v Vp . ) i r I f Brunswick Unit 2 - Shroud Weld H68 - 270* to 360* Comparison Data 19% to 1997 I Thru-wallRollout Map 4 I 1.40-j 01996 Data i j 1.20 -- a 1997 Data f 5 j c 1.00 i e e j o 0.80-5 ) O60-I I kfi k k. I A k i 0. P 270 4* 276.9* 283.4* 289.8* 296.3* 302.8* 309.3* 315.8* 322.3' 328.8* 335.3* 341.a* 348.3* 354.8* 361.3* I Circumferential Location in Degrees from Vessel *0* M iI 1* = 1.55 inches ort 00 of Shroud 3 t I el I de2> @Grac.tSN > t l CPU 4 2! 1! top /q'i p.g. 7 of 2s i or t i

3 ) i s Brunswkk Nuclear Power Plant - Fall 1997 Core Shr~Jd Ex;;-Eki Proiect - 1HDET h t 1 Flaw IrnNcatiott Posnion and Through-WaH neoasurerneens - WeM N8B sneceton 81 In6ceton # 2 Inecaton s 3 Ineeston s 4 5% e S Inemonen s 6 trinc.a.n s 7 ym go,g, Anguesen Fine Ousen Aarnust Fine Depot Ft Dosst Flame Oussi T-- mE. FameOsam mesmesse Fiam,omys, i ^ gem, y see tems ) ~M sees ) M same I W9 88ee1 M teus1 M 16ae) M 12 70-0 05 24 37-0 22 34 7e* 0M 42 43* 0 00 44 Fe* Ose eF Ges Se 81* O se 13 35*' O 13 25 02* 3 57 35 42* O 17 ' 43 es* O 14 85 42* O 11 48 72* OM Se es* O 23 I' 14 00* O 10 25 67* O 21 38 07* O 13 44 13* O 11 4 07* O 90 47.37* O 87 St S3* - 0 27 14 w 0 17 N 31* 00s 3872* 0 05 44 7e* O 00 48st* eas $2.14* 0 00 l .5 2.- 0 22 - mw Ca 27 3r C ie = = - 0 23 15 94* 0.50 2781* O 44 . 38 02-020 t de 31* O 47 18 Se* O 23 2s 20* O 45 38 87* O L1 i de eS* O 08 ] 1724-0 14 26 91* O 45 3e 31* O 05 50 41* Ose 17 se* ' 024 2e S6* O 23 40 61* O 00 13 53* 0 19 3020* 0.12 19te* O $1 30 es* O 17 I 19 83* O 25. 31 S3*. 0 12 20es* O Se 321s* O as r 21 13* O 44 32 83* O 26 i j-217e* O 35' 33 48* O 27 22 42' O 00 34 13* O 19 I i t ineestons8 Irukeston s 9 inecate 810 Inecadon 811 Indicaton 812 Inecaton s 13 lemme. man s 14 SS 42* 0 00 82.18-0 22 85 42* O Jo 64 02* O 00 es 31* O 90 7153* O es Fg 07* O 90 [ S407* O 13 ' S2 83* O 30 06 07* O 14 es 87* O 25 et 96* 4 16 72.1e* O 34 2e 72* O 20 Se72* - 0 24 43 es* O 00 e6 72* O 23 40 31* O 00 70 14* O 17 72 e3* O 31 77.37* O 12 [ 57.37' O 11 87 37' O 25 7024* O 23 73 48* O DE 7e 02* ' O 17 M! SS 02* 0 19 se 02* O 00 70es* 0 00 74 13* O 23 7e 87* O 23 54 67* 0 00 a 7 {' e 74.79* 020 79 31* 0 18 75.42* 0 10 79 es* 0 13 i 30 81* O 15 O %}' J m es-D es t.. W> a .< l o! a 3 t j $,. i 9i f 1 2 U!_f Page 8 of 25 [ @m_lO ich er [ 's t 3 qc cua M 1, t i - - _.. _ -. ~ _ _ -, _

) Brunswick Nuclear Power Plant - Fall 1997 Core Shroud Examination Proi+ct - 1HDET Flaw lodication Position and Thrcugh-Wall Measurwnents - Wald1968 anocadon s 15 trocaben s 16 trocanen s 17

rocaben s*1 inecedon s 19 inecaton s 20 4m Fh Dese age. gag Fw ~m 4wnwen Dese Desem Aseseue Fts= Qasm Aassuust Fis= Daget h

F4s= Desem qy got toeg i M toeg ) M seet 3 6== 4eog 1 M teeg) tog eso,1 p., g3 g. 0 00 SO 81* Q 00 101 53* O De 103 48-0 00 10478* O2 10822" 0 00 110 st* 0 00 g4 93 g og 8157 0 05 102.18' O Os 104 13" 0 12 10L' 42* O De 100 87-0 06 11t $3-c ts 34 78* 0 14 82 18* 0 05 102 83* 0 26 104 78* 0 00 108 07' 00s 108 31* 0 18 112 18' 0 18 85 42* O 18 82 83* O to 103 48* O 00 106 72* O 00 10e 98* 0 08 112 SY 0 06 as 07* O 18 83 48* O 20 11081* O OP 113 48* O C5 88 72* O 13 $413-0 24 87 37* O 20 S4 78* O 24 114 13" 0 22 88 02* 0 07 85 42* O 08 194 T8* O 25 88 67-0 18 98 OP O 25 115 42* 0 00 89 31' - 0 25 M 72* O 48 89 96* O 14 97.37* O 24 90 81* O 00 W8 02-024 98 87* O 21 99 31* O 41 99 59* OA 10024* 0 21 100 89* O 75 frocaton # 21 Inscaton s 22 Inecaton s 23 enecabon s 24 trocaton 8 25 tradon s 26 11807* l C 00 121 53* O 00 t33 43' O 28 139 96* O 00 143 44* O G2 145 42* O 00 147 37* O 00 198 72* 0 11 122 18* 0 24 134 13* 0 16 140 5t* 0 23 144 13* 0 08 148 07* 0 11 148 02* 0 22 117 37* 025 122 83* 0 17 134 78* 0 05 141 53* 0 28 144 78* 0 14 146 72* 0.13 148 87* 0 23 C/2 y 118 02-0 09 123 48* 0 21 135 12* 0 12 142 18* 0 00 145 42* 0 00 147 37* 0 00 149 3t* 0 00 N 118 67* 0 16 124 13* 0 22 136 07* 0 14 119 31* 0 09 124 78* 0 19 136 72* 0 22 149 98* 0 10 e 119 96* 0 00 125 42* 0.25 137 37' O 19 150 81* O 12 M 128 07* O 55 138 02* O 28 151 53* O 34 128 72* O 30 138 ET* O 22 152 18* O 22 127 J T* O 28 139 31* 0 00 152 83* O $5 y 128 02* O 11 153 48* O 30 128 87* O 11 154 13* 0 28 W 129 31* 0 05 154 78* 0 00 k 129 98* O 63 130 81* O 05 i 131 53* O 14 y 132 18' 0 12 132 83* 0 09 l Nw-3 E o q ca

• GE Cc-E I

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) Brunswick Nuclear Power Plant - Fall 1997 Core Shroud Examination Profect - 1 HOE 7 Finw Indsc8 tion Position and Through-Wall hiessurements - Wold H6B Indicaton 8 27 Iru$caton s 28 Wec. bons 29 trec. ton 830 rec. con 831 Indcaton 8 32 kdcanon 8 33 l a,e p

0. pan aan.ne F1 Dessi As.=%m re.Dese ase

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• J 08 329 86*

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_-.. _ ~ -.. - _ _ .~__ _ _. _.. i Ctr: lina Pow:r & Light Comprny ESR 97 00034 Rev.O Brunswick Nuclear Plant Unit 2 Attachment E \\ Engineering Evaluation Page 1 i i l v Attachment E Ph "Lculc" Spreadsheets L i mm -,..--w--wr-wa v--s

• • vv m
• e

-e-a-- 4e- -i s-1 4 ---r e

) ) @ E' D %e, Computes Minimum Required Ligament Length for a Continuous Through Wall Flaw for Weld H1 5'l$ e- $.o.= m[@% BNP Unit 2 Normat/ Upset Emergency Faulted E Theta angle (red) 2.358 2.404 2297 gQ Pi 3.14 3.14 3.14 c' @ 23 Mean Radius 94 94 94

• ' W hC Pm (psi) 250 257 818 3Sm (psi)(304ss) 50700 50700 50700 3 -+

7Q Beta angle (rad) 0.38 0.36 0.40 h.]3 Max Pb'(psi)is 1405 1085 824 z Pb (psi) 483 637 641 y *3 Safety Factor 4 "2.258 0.K. M SD1 0.K. ~ ~ h 1.125 O.K. Max Flaw t.ength (in) ~" 443.3 ' 4 22 % Ja 431.3 Max Flaw Length (deg) - 270.2 V 2FS.5 43.2 ~~ Min. Ligament, Lealc (in) t147.3 _v 1138.7 Minimum Required Ligament Length Lcalc (in) Notes: This sheet computes 'he maximum allowable Circumferential flaw length for one through-war flaw at plaste conapse stresses. Additionally, it subtracts the flaw lengt Sw the Circumference to obtain the rnensmum required uncracked ligament length "Lealc". Directions:

1. Input the current calculated values for Pm and Pb from 0821-1012 in the appropnate ce!!.

2. Guess (iterate) the theta angle such that the Max Pb'sabsfies the required safety factor.

uym This spreadsheet was developed and benchma.ted using the Structural integnty Report S:R-94-029. and $hD Ref " Evaluation of Flaws in Austenstic Steel Piping". Transactions of the ASME. Volume 108 August 1986. O o e "B" ob Safety Factor = (Pm + Pb*)/(Pm + Pb) (ref. Section XI). Use 2.25 for Normal / Upset,1.50 for Emergency, and 1.125 for Fautled. (Ref. UFSAR) a8 Sm = 16900 psi for TP 304 Stainless Steel r.d mA ~D k. O

) ) E' S' D %e, Computes Minimum Required Ligament length for a Continuous Through Walt Flaw for Weld H4 { j j-R .4 3' S-p BNP Unrt2 Normal / Upset Emergency Faulted Rq Theta angte (rad) 2.227 2.266l 2.201 <@Q " m{ g Pi 3.14 3.14 3.14 g Mean Radeus 88 88 88 ms n Pm (psi) 234 244 844 o p @d D 3Sm (csi)(304es) 50700 50700 50700 s Beta angle (rad) 0.45 0.43 0 /.4 7Oo Max Pb'(psi)is 2564 2138 1661 Pb (psi) 1006 1340 7375 {N Safety Factor ~2.257 0.K.

• 9 1 M O.K.

m & 1. 2 0.K. Max claw Length (in) 4 3 90.9 FM

• 3 381FA Max Flaw Length (deg)

~:r 254.5 ' ~' M.7 'w353.2 < 1 84,1 M Min. Ligament, Lcalc (in). ~ ~.182.0 Minimum Required Ligament length, Lcalc (in) Notes-This sheet computes the maximum allowable C.rcumferental flaw length for one through-wall f!aw at plastic collapse stresses. Addtbonally, it subtracts the flaw length from the Circumference to obtain the minanum required uncracked ligament length "Lealc". Directions:

1. Input the current ca!culated values for Pm and Pb from 0821-1012 in tM apr ursie ceit.

2. Guess (rterate) the theta angte such that the Max Pb" satisfies the requred safety factor.

$ y> $ u rn This spreadsheet was developed and bmdu..ked using the Structuralintegrity Report SIR-94-029. and Ref. " Evaluation of Flaws in Austenstic Steel Piping". Transactions of the ASME. Volume 108. August '986.

• o,o Safety Factor = (Pm + Pb*)/(Pm + Pb) (ref. Seebon XT). Use 2.25 for Normal / Upset.1.50 for Dr.erge q. and 1.125 for Fau!ted. (Ref. UFSAR) i

@B " ~O Sm = 16900 psi for TP 304 Stainless Steel y D o b o

b ) rn to o SB* Computes Minimum Required Ugament Length for a Continuous Through Wall Fla y for Wetd H5 [j=j-a. S-@ BNP Urut2 Nonnal/ Upset Emergency Faulteci gq Theta angle (rad) 2.062 2.109 2.067 ggR Pi 3.14 3 14 3 14 & g Q3 Mean Radss 88 88 88 2 w r- { a%. Pm (psi) 210 221 821 3Sm (psi)(304ss) 50700 50700 50700 Beta angte (rad) UE 0.51 0.50 7O hS Max Pb'(psi) is 4356 3769 2983 Q Pb (psi) 1814 2434 2560 9 *3 Safety Factor

• 2J88 0.K.

E'M3 0.K. ' Prx4Jth O.K. Max Flaw Length (in) y 382.9 , 371.2

%ME3 Max Flaw Length (deg) 4 E236.3 W349.7 x -emM&3 Min. Ligament, Lcate (in) M

- al 881.7 e s1E%8_ Minimum Required Ligament Length Lealc (in) Notes: This sheet computes the maximum aSowable Circumferental flaw length for one througtMara5 flaw at '%stic ccRapse stresses. Additsorwf. It subtracts the flaw length from the CircuaJw.ce.o obtain the mamum reqtared uncracked IrM' length " Lear. Directions:

1. Input the current calculated values for Pm and Pb from OB21-1012 in the amte ceQ.

r

2. Guess (iterate) the theta ang% such that the Max Pb' satisfies the required safety factor.

T>m c (n This spreadsheet was developed and benchmarked using the Structural integr ty Report SIR-94-029. and jEI Ref

• Evaluation of Flaws in Austenitic Steel Piping". Transactions of the ASME. Volume 106 August 1986.

3. (D N

a. 3 -

Safety Factor = (Pm + Pb')/(Pm + Pb) (ref. Secten XI). Use 225 for Normal / Upset,1.50 for Drs e.~y and 1.125 for Fau.*ted. (Ref. UFSAR) $O w

• • O Sm = 16900 psi for TP 304 Stainless Steel w

mA T .k O

') ) p to o =aa Computes Minimum Required Ugament Length for a Continuous Through Wall Flaw for Weld H6a f2$ -Q & g' BNP Unit 2 Normat/ Upset Or.e.w sy Faulted g {R q Theta angle (rad) 7.922 f.985 f.974 R Pi 3.14 3.14 3.14 yge Mean Radius 88 88 BS R5 r. hto Pm (psi) 677 629 7375 3Sm (psi)(304ss) 50700 50700 50700 m -- Beta ang'e (rsd) 0.59 0.56 0 54 7Og Max Pb' (psi) is 5645 4677 3670 Pb (psi) 2162 2905 3110 9 *3 Safety Factor 2.253 0.K. > 1.582 0.K. A4 1.127 O.K. Max Flaw Length (in) ~ 338.3 " 340A

• ^ ~ asTA Max Flaw Length (deg)

-- 3220,2 - : 22T5 y -_33.2 Min Ligament, Lealc (in) , '203.8 y ' 2;3.5 Minimum Required Ligament Length, Leale (in) ' Notes: This sheet computes the maximum a!!owable Circumferental flaw length for one through-wall flaw at plastx: conapse stresses. Acdetionaily, it subtracts the flaw length from the Circumference to obtain the trurumum required uncracked ligament length "Lealc" D;rections:

1. Input the current ca'culated values for Pm and Pb from 0821-1012 in the aw ie cen.

s

2. Guess (iterate) the theta angle such that the Max Pb'sabsfies the requeed safety factor.

0>m This spreadsheet was developed and benchmarked using the Structural tr'tegnty Report SIR-94-029 and h$ Ref " Evaluation of Flaws in Austenitic Steel Piping". Transactions of the ASME Votume 1C8. August 1986. Q. to w

v. 3

• Safety Factor = (Pm + Pby(Dm + Pb) (ref. Secbon XI). Use 2.25 for Normal / Upset 1.50 for Dr.erpsi, ard 1.125 for Fau!!ed. (Ref. UFSAR)

$O -* O Sm = 16900 ps; for TP 304 Stainless Steel m m k O

) ) tp to o %aR Computes Minimum Required Ligament Length Tor a Continuous Througli Wall Flaw for Weld h6b {glQs- % ~. BNP Und2 3' - g D Normal / Upset Emergency Faulted g3; Theta angle (rad) 7.920 f.983 f.972 [nj x Pi 3.14 3.14 3.14 % { r-g Mean Radius 88 88_ 88 5 Pm (psi) 594 606 1292 6' sc5' 3Sm (psi)(304ss) 50700 50700 50700 D ad Beta angle (rad) 0.59 0.56 0.54 7O O Max Ptf (psi)is 5715 4745 3739 Pb (psi} 2204 2960 3176 Safety Factor

2.255 O.K.

"1AlH OX c c~ 1.15 O.K. N Max Flaw Length (in) w337.9 ~. 30$A - m.3 67.1 Max Flaw Length (deg) - - 2.0 - ~, -W.2 im -e-Min. Ligament, Lcalc (in) M <"2035 m <20CJ Minimum Required Ligament Length, Lealc (in) Notes: This sheet computes the maximum allowable Circum %rential P.aw tength for one through-wall few at plastic conapse stresses. Additiona!!y, it subtracts the flaw length from the Circumference to obtain the rrmmum required uncracked ligament length *1.cale". Directions:

1. Input the eterront calculated values for Pm and Pb from 0B21-1012 in the appropnate cell.

2. Guess (sterate) the theta angle such that the Max Pb' satisfies the reqtared safety factor.

o>m This spreadsheet was developed and benchmarted using the S'ructural Integnty Report SIR-94-029, and $hD Ref. "Evcluation of Flaws in Austenitic Steel Piping". Transaction s of the ASME, Volume 108, August 1986.

• g. m N

en B - Safety Factor = (Pm + Pb')/(Pm + Pb) (ref. Secbon XI). Use 225 for Norma!/ Upset,1.50 far Emergency, and 1.125 for Fau!!ed. (Ref. UFSAR) @o O ~O Sm = 16900 psi for TP 304 Stainless Steel m$ 33 k O

s ) .) en en n 4254 Computes Minimum Required Ligament Length for a Continuous Through Wall Flaw for Weld H7 73$ ok g & }a

t BNP Und 2 Normal / Upset Emeriponcy Fauded ggE Theta angle (rad) 1.879 f.881 7879 gor

& k Qo Pi 3 14 3 14 3 14 Mean Radus 64.75 84.75 8475

• ' r-

{h Pm (psi) 603 677 1330 ism (psi)(304ss) 50700 50700 50700 3 ** Beta angie (rad) 0 64 0 61 0 59 Q Max Pb'(psi)is 7399 6307 5164 g] Pb (psi) 2946 3989 4432 y3 Safety Factor & d 2.255 OK - M OX W1.12T O.K. Max Flaw Length (m) w 308.3 p 3983 x 2154 Max Flaw Length (deg) + -20BA x 345 _.5 4 n 215J Min. Ligament, Lcalc (in) 4 213.7- ' *

• 214A Minimum Required Ugament Length, Lealc [c)

Notes: This sheet computes the maximum allowable Circumferenba! flaw leng*h for one through-waE flaw at plasbc conapse stresses. AddrticnaDy it subtracts the f!aw length from the Crcumference to obtain the mamum requred uncracked Egament length *Lcale. Directions:

1. Irgmt the current calculated values for Pm and Pb from 0821-1012 in the.pr vgste ces.

2. Guess (cerate) the theta angle such that the Max Ptf satis 5es the required safety factor o

.3> m t; in This spreadsheet was developed and benchmarked using the Structuralintegrey Deport SIR-94-029. and y E:33 Ref. "Evaluabon of Flaws in Austenttic Steel Pipang". Trar'sacDons of the ASME. Volume 108, August 1986. 3.m 9 %3-Safety Factor = (Pm + Pb)'(Pm + Pb) (ref. Secton XI). Use 225 for Normal 11pset.1.50 for Ore gm cy, and 1.125 for Faufted. (Ref. UFSAR) $b -O Sm = 16900 psi for TP 204 Starniess Steel m m .k O

O O O U/2 FW H2 INJECTION CUFT/ MIN HYDROGEN INJECTION 120p H2 Inj. CFS-2 100 Cycle 12 Data 03/96 to 09/97 80 Data Summary % of time in service = 92.7% I % of time 2 target injection = 78.7% 60 "'9 " * * * '

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