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| {{#Wiki_filter:De cembe r 15 , 20 06 M r. P aul A. H arde n Si te V ic e P resi den t Nu cl ear M ana gement C ompa ny , LL C Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3-95 30 S U B JE C T: | | {{#Wiki_filter:December 15, 2006 Mr. Paul A. Harden Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 |
| P A L IS A D E S P L A N T - R E QU E S T F OR A D D ITIO N A L I N F OR M A TION R E L A TE D TO TH E P R OP OS E D C* L IC E N S E A M E N D M E N T R E QU E S T F OR STEA M GEN ER ATOR TUB E RE PA IR IN THE TUBE SH EE T (TAC N O. M D2 125)De ar M r. H arde n: Yo ur l etter of M ay 30 , 20 06, sub mitted an ap pl ic ati on to c han ge the P al is ade s N ucl ear Pl ant (Palisades) tec hnical specif ications r elated t o steam gen erat or tu be repair. Th e chang es w ould re v i se t h e r e p a i r cr i te ri a for t h e p o rt i o n o f th e t u b e s w i th i n t h e h o t-l e g re gi o n o f th e t u b e sh e e t.W e a re re v ie w in g y our requests , an d fin d th at a ddi tio nal i nformatio n i s n eed ed as sho w n i n th e e n cl o se d r e que st for a d d i ti o n a l i n form a ti o n (R A I). I d i sc u ss e d t h e e n cl o se d R A I w i th M s. A my Ha z el hoff of y our organi z ati on on De cembe r 13 , 20 06, and sh e a greed to re spo nd w ith in 60 day s o f rec ei pt o f thi s R AI. P le ase co ntac t me at (3 01) 415-142 3 i f y ou hav e que sti ons.
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| Sin ce r ely,/RA/
| | ==SUBJECT:== |
| M ahe sh L. C haw la , P roject M ana ger P ro je ct D i re ct o ra te I II D i v i si o n o f Li ce n si n g P ro je ct M a n a gem e n t Of f ic e o f N ucl ear Re acto r R egul ati on Do cket No. 50-255 E n cl o su re: RAI c c w/e n c l: S e e n e x t p a ge M r. P aul A. H arde n De cembe r 15 , 20 06 Si te V ic e P resi den t Nu cl ear M ana gement C ompa ny , LL C Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3-95 30 S U B JE C T:
| | PALISADES PLANT REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED C* LICENSE AMENDMENT REQUEST FOR STEAM GENERATOR TUBE REPAIR IN THE TUBESHEET (TAC NO. MD2125) |
| P A L IS A D E S P L A N T - R E QU E S T F OR A D D ITIO N A L I N F OR M A TION R E L A TE D TO TH E P R OP OS E D C* L IC E N S E A M E N D M E N T R E QU E S T F OR STEA M GEN ER ATOR TUB E RE PA IR IN THE TUBE SH EE T (TAC N O. M D2 125)De ar M r. H arde n: Yo ur l etter of M ay 30 , 20 06, sub mitted an ap pl ic ati on to c han ge the P al is ade s N ucl ear Pl ant (Palisades) tec hnical specif ications r elated t o steam gen erat or tu be repair. Th e chang es w ould re v i se t h e r e p a i r cr i te ri a for t h e p o rt i o n o f th e t u b e s w i th i n t h e h o t-l e g re gi o n o f th e t u b e sh e e t.W e a re re v ie w in g y our requests , an d fin d th at a ddi tio nal i nformatio n i s n eed ed as sho w n i n th e e n cl o se d r e que st for a d d i ti o n a l i n form a ti o n (R A I). I d i sc u ss e d t h e e n cl o se d R A I w i th M s. A my Ha z el hoff of y our organi z ati on on De cembe r 13 , 20 06, and sh e a greed to re spo nd w ith in 60 day s o f rec ei pt o f thi s R AI. P le ase co ntac t me at (3 01) 415-142 3 i f y ou hav e que sti ons.
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| Sin ce r ely,/RA/
| | ==Dear Mr. Harden:== |
| M ahe sh L. C haw la , P roject M ana ger P ro je ct D i re ct o ra te I II D i v i si o n o f Li ce n si n g P ro je ct M a n a gem e n t Of f ic e o f N ucl ear Re acto r R egul ati on Do cket No. 50-255 E n cl o su re: RAI c c w/e n c l: S e e n e x t p a ge D IS TR IB U TION PU BL IC Ri dsOgcRp Ri dsN rrDo rlL pl 3-1 Ri dsN rrDo rlD prRidsRg n3M ailCenter LPL3-1 r/f RidsAcrs AcnwM ailCenter RidsNrr PM M Chaw la Ri dsN rrLA THarri s GM akar AD AM S Acc ess io n N umbe r: M L06 331 017 5 OF FICE LPL3-1/PM LPL3-1/LA LPL3-1/BC NA M E M Ch aw la THarri s LR aghav an DA TE 12/1 5/06 12/1 5/06 12/1 5/06OF FICI AL RECORD COPY Pa li sad es Pl ant cc: Ro bert A. Fen ech , S eni or V ic e P resi den t Nu cl ear, Fos si l, and H y dro Operati ons Co nsu mers E nergy C ompa ny 194 5 P arna ll R d.Jac kson, M I 4 920 1 A ru n a s T. U d ry s, E squ i re Co nsu mers E nergy C ompa ny 1 En er g y Plaza Jac kson, M I 4 920 1 R e gi o n a l A d mi n i st ra to r, R e gi o n I II U.S. N ucl ear Re gula tory C ommis si on Su ite 21 0 244 3 W arren v il le R oad Li sl e, IL 605 32-4 351 Su perv is or Covert T ow nship P. O. Bo x 35 Co v ert, M I 4 904 3 Of f ic e o f the Gov erno r P. O. Bo x 30 013 Lan si ng, M I 4 890 9 U.S. N ucl ear Re gula tory C ommis si on Re si den t Ins pec tor's Of f ic e Pa li sad es Pl ant 277 82 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3 M i ch i gan D e p a rt me n t o f E n v i ro n me n ta l Qu a l i ty W aste an d H az ardo us M ateri al s D iv is io n Ha z ardo us W aste an d R adi ol ogica l Pro tecti on Se cti on Nuclear Facilities Unit C o n st i tu ti o n H a l l , L o w e r-L e v e l N o rt h 525 W est Al le gan S treet P.O. B ox 30 241 Lan si ng, M I 4 890 9-77 41 M ic hi gan D epa rtment o f A ttorne y Gen eral Sp eci al Li tigati on Di v is io n 5 2 5 W e st Ot ta w a S t.Si x th F lo or, G. M enn en W il li ams B ui ld in g Lan si ng, M I 4 891 3 M ic hae l B. Se ll man Pre si den t an d C hi ef Ex ecu tiv e Off ic er Nu cl ear M ana gement C ompa ny , LL C 700 F irs t S treet Hu dso n, M I 5 401 6 Jo n a th a n R o goff, E squ i re V i ce P re si d e n t, C o u n se l & S e cr e ta ry Nu cl ear M ana gement C ompa ny , LL C 700 F irs t S treet Hu dso n, W I 5 401 6 Do ugla s E. C oop er Se ni or V ic e P resi den t an d Ch ie f N ucl ear Of f ic er Nu cl ear M ana gement C ompa ny , LL C 700 F irs t S treet Hu dso n, W I 5 401 6 Ste phe n T. W aw ro, D ire ctor o f N u cl e a r A ss e ts Co nsu mers E nergy C ompa ny Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3 Lau rie A. La hti , M ana ger R e gul a to ry A ff a i rs Nu cl ear M ana gement C ompa ny , LL C Pa li sad es Nu cl ear Pl ant 277 80 Bl ue Sta r M emori al H ighw ay Co v ert, M I 4 904 3 ENCLOSURE R E QU E S T F OR A D D ITIO N A L I N F OR M A TION (R A I)L IC E N S E A M E N D M E N T R E QU E S T F OR R E V IS E D S TE A M GE N E R A TOR REPAIR CRIT ERIA (C* CRIT ERIA) PALISADES NUCLEAR PLANT NU CL EA R M AN AGEM EN T COM PA NY , LL C DOCK ET N O. 50-2 55 1.
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| The p ropo sed ame ndme nt i s i nten ded to al lo w tub es w ith flaw s to rema in i n s erv ic e i f the f law s are locat ed below a certa in depth in the hot-leg reg ion of the tube sheet. Th is w ill requi re p ropo si ng an al terna tiv e to the 40-perc ent, throu gh-w al l dep th c rite ria i n th e P a l i sa d e s' Te ch n i ca l S p e ci fic a ti o n s (TS s). P l e a se d i sc u ss y o u r p l a n s to r e v i se TS 5.5.8.c as f ol lo w s:A.
| | Your letter of May 30, 2006, submitted an application to change the Palisades Nuclear Plant (Palisades) technical specifications related to steam generator tube repair. The changes would revise the repair criteria for the portion of the tubes within the hot-leg region of the tubesheet. |
| Ind ic ate there i s a n a lte rnati v e to the 40-perc ent repa ir cri teri a.B.
| | We are reviewing your requests, and find that additional information is needed as shown in the enclosed request for additional information (RAI). I discussed the enclosed RAI with Ms. Amy Hazelhoff of your organization on December 13, 2006, and she agreed to respond within 60 days of receipt of this RAI. Please contact me at (301) 415-1423 if you have questions. |
| D efine the rep ai r cri teri a i n th e h ot-l eg tub esh eet regio n (i.e., d epth be lo w w hi ch f la w s ma y r e ma i n i n s e rv i ce , a n d t h e s ta rt i n g p o i n t for th e d e p th me a su re me n t).C.
| | Sincerely, |
| D efine the rep ai r cri teri a for th e re gion of the ho t-le g tube she et i n w hi ch nei ther the al terna te re pai r cri teri a n or th e 4 0-pe rcen t thro ugh-w al l cri teri a a ppl y (i.e., tu bes w ith fla w s w i th i n t h e C* d i st a n ce w i l l b e p l u gged o n d e te ct i o n).D.
| | /RA/ |
| S tate that al l f la w s l oca ted bel ow thi s d epth may rema in i n s erv ic e, re gardl ess of si z e.2.
| | Mahesh L. Chawla, Project Manager Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-255 |
| Pro pos ed TS 5.5.8.d defin es the porti on of tube that must b e i nsp ecte d, "from 12
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| .5 i nch es bel ow the tub e-to-tu bes hee t ex pan si on trans iti on in le t to the tube-to-tub esh eet w el d a t the tube ou tle t . . . ." Si nce the C* cri teri a i s a n a lte rnate rep ai r cri teri a ra ther than an in s p e c t io n cr it e r ia , it do e s no t ch a n g e t h e ob j e c t iv e in t h e cu r r e n t T S 5.5.8.d t o de t e c t f la ws f rom the inlet tube-to-tube sheet w eld to the out let tube-t o-t ubeshe et wel d. If the C* crit eria is pro perl y de f in ed as an al terna te re pai r cri teri a (a s d is cus sed i n #1 a bov e), th en in spe cti on bel ow the C* d is tanc e i n th e h ot-l eg regio n w oul d n o l onger be requi red bec aus e o f th e p h ra se , ". . . a n d t h a t ma y s a ti sfy t h e a p p l i ca b l e t u b e r e p a i r cr i te ri a" i n TS 5.5.8.d. Please discuss your plans to m odif y prop osed T S 5.5.8.d t o rem ove the r ef eren ce to th e C*di stan ce and res tore the w ordi ng ap prov ed in the Tech ni cal S pec ifica tio ns Task Force 44 9 amen dmen t (i.e., ". . . from the tub e-to-tu bes hee t w el d a t the tub e i nl et to the tub e-to-tube she et w el d a t the tub e o utl et, a nd that may sa tis f y. . . ."). In ad di tio n, th e s taff no tes that the 12.5-in ch C* di stan ce is mea sure d from the top of the tub esh eee t or the botto m of th e e x p a n si o n t ra n si ti o n , w h i ch e v e r i s l o w e r.3. | | ==Enclosure:== |
| The b asi c p remi se of the C* amen dmen t i s th at th ere is a 12.5-in ch, non-f la w ed porti on of the tube full y ex pan ded i nto the tube she et. To en sure the regi on remai ns f ree of f la w s, a n inspect ion of 100 percent of the inservice tubes in the upper reg ion of the tube sheet w ill n e e d t o b e p e r fo r me d e v e r y 2 4 e ffe c t i v e fu l l-p o w e r m o n t h s , o r o n e r e fu e l i n g o u t a ge in terv al , w hi che v er i s l ess. A s a res ul t, pl eas e d is cus s y our pl ans to rev is e y our prop ose d TS 5.5.8.d to a dd thi s i nsp ecti on requi rement (e.g., by ad di ng a para graph 5.5.8.d.4). The sta f f notes t hat if an additional parag raph 5.5.8.d.4 is added, it w ill need to be ref eren ced in 5.5.8.d (i.e., "In a d d i ti o n t o me e ti n g th e r e qui re me n ts o f d.1 , d.2 , d.3 , a n d d.4 b e l o w . . . .").4.
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| Pl eas e c onfirm th at s tructu ral an d l eakage i ntegri ty w il l be ass ess ed if si gnifica nt in di cati ons are found w ith in the i nsp ecte d re gion of the tub esh eet. The staff rec ogni z es that the cur rent approac h of plugg ing f law s on detect ion w ithin the C* distan ce should p r o vi d e a h ig h le ve l o f co n f id e n c e t h a t no po t e n t ia l l e a k in g or st r u c t u r a ll y s ig n if ic a n t f la ws ar e id en t if ied in t his re g ion. Ho wever , su ch an a pp r oa ch ca n no t ens ur e it w it h c er t ain t y.5.
| | RAI cc w/encl: See next page |
| The c al cul ati on of the in spe cti on di stan ce f or th e h ot-l eg tub esh eet regio n u sed the l ow er 95-p erce nt p redi cti on bou nd f or th e me asu red and pro jected smoo th-bo re, "first-sl ip"pul lo ut v al ues pl otted i n F igure 3 of Enc lo sure 4 to y our M ay 30 , 20 06, le tter. As di scu sse d in the R AI resp ons es to p rev io us C* rev ie w s (i.e., S ecti on 2.1.4 i n E ncl osu re 6 of y our M ay 30, 200 6, l etter), use of the l oad at "f irs t sl ip" as sumes tha t the "first mo v e" re sul ts from gri p p e r sl i p p a ge o r o th e r mo v e me n t b e si d e s mo v e me n t o f th e t u b e w i th i n t h e t u b e sh e e t. Si nce thi s a ssu mpti on abo ut th e "first mov e" w as not v eri f ie d, a nd giv en that al l tube s sho ul d re si st p ul lo ut from the tub esh eet, con f irm that if the force-pe r-uni t-le ngth for the most l imi tin g spec ime n, b ase d o n l oad at "f irs t mov e," w ere use d to de termin e th e re quire d le ngth o f ex pan ded tub ed nee ded to resi st p ul lo ut, th is l ength w oul d s til l be le ss than the p ro p o se d i n sp e ct i o n d i st a n ce (1 2.5 i n ch e s). T he staf f notes t hat in Section 2.
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| 4.3 of Enclosure 6 (which addresse s the f irst-slip crit eria f or s mooth-b ore sampl es), the f in al tw o p aragraph s e x pl ai n th at e v en if the re w ere no ex pl ans io n re si dua l con tact pres sure be tw een a tube an d tu bes hee t i n th e P al is ade s s team genera tors, a l ength of 6.75 in che s i s e nou gh to resi st th e th ree-ti mes n ormal op erati ng di f f eren tia l pres sure. The di scu ssi on id enti f ie s d iff eren tia l thermal ex pan si on and e x p a n si o n fro m t h e t u b e i n te rn a l p re ss u re a s th e s o u rc e s o f th e r e si st a n ce t o t u b e p u l l o u t. Al thou gh thi s w as referred to as the "most ex treme c ase ," i t i s n ot c le ar i f the eff ect of tube she et b ow w as in cl ude d. Pl eas e d is cus s w heth er y our ev al uati on con si dere d th e e f f e c t of t u b e s h e e t bo w.6.
| | Mr. Paul A. Harden December 15, 2006 Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 |
| For the Ri nghal s te st d ata, the f irs t-sl ip pu ll out v al ues pl otted i n F igure 3 of Enc lo sure 4 w ere proje cted from the measu red, max imu m-lo ad v al ues. P le ase di scu ss the eff ect on Fi gure 3 an d y our le akage an al y ses i f a con serv ati v e b oun d (i.e., 9 5-pe rcen t pre di cti on in terv al) w ere use d to pro ject th e first-s li p l oad v al ues for the R in ghal s d ata.7.
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| The s taff no tes that the page numb ers li sted on the co v er s hee ts o f E ncl osu res 2 a nd 3 (pages 5.5.8-11 and 5.5.8-12) do no t match the pa ge nu mbers on the botto m of the e n c l o s e d T S p a ge s (p a ge s 5.0-1 1 a n d 5.0-1 2). P l e a s e c l a r i fy w h i c h a r e t h e c o r r e c t p a ge numb ers f or th ese TS p ages. In a ddi tio n, th e s taff no tes that prop ose d TS page 5.0-1 2 sho ul d i den tify the "P rov is io ns f or S G tube i nsp ecti ons. (co nti nue d)" a s i tem "d" rathe r tha n i te m "e."8.
| | ==SUBJECT:== |
| Accor ding to Section 2.
| | PALISADES PLANT REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED C* LICENSE AMENDMENT REQUEST FOR STEAM GENERATOR TUBE REPAIR IN THE TUBESHEET (TAC NO. MD2125) |
| 5 of Enclosure 4, the prop osed inspect ion distance of 12.5 inches is bas ed on add in g the 0.28-in ch non-des tructi v e e x ami nati on ax ia l-p osi tio n u nce rtai nty to the v a l u e s o f "J o i n t L e n gth t h a t M e e ts L e a kage C ri te ri a ," (1 2.2 4 a n d 1 2.2 5 i n ch e s). H o w e v e r, si nce 12.25 + 0.2 8 = 12.5 3, i t w oul d b e c ons erv ati v e to us e a v al ue of 12.6 in che s ra ther than 12.5 i nch es. P le ase di scu ss y our pl ans to modi f y y our prop osa l to u se 12.6 i nch es as the prop ose d d is tanc e for th e a lte rnate rep ai r cri teri a (a nd in spe cti on) in the ho t-le g region o f th e t u b e sh e e t.}}
| | |
| | ==Dear Mr. Harden:== |
| | |
| | Your letter of May 30, 2006, submitted an application to change the Palisades Nuclear Plant (Palisades) technical specifications related to steam generator tube repair. The changes would revise the repair criteria for the portion of the tubes within the hot-leg region of the tubesheet. |
| | We are reviewing your requests, and find that additional information is needed as shown in the enclosed request for additional information (RAI). I discussed the enclosed RAI with Ms. Amy Hazelhoff of your organization on December 13, 2006, and she agreed to respond within 60 days of receipt of this RAI. Please contact me at (301) 415-1423 if you have questions. |
| | Sincerely, |
| | /RA/ |
| | Mahesh L. Chawla, Project Manager Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-255 |
| | |
| | ==Enclosure:== |
| | |
| | RAI cc w/encl: See next page DISTRIBUTION PUBLIC RidsOgcRp RidsNrrDorlLpl3-1 RidsNrrDorlDpr RidsRgn3MailCenter LPL3-1 r/f RidsAcrsAcnwMailCenter RidsNrrPMMChawla RidsNrrLATHarris GMakar ADAMS Accession Number: ML063310175 OFFICE LPL3-1/PM LPL3-1/LA LPL3-1/BC NAME MChawla THarris LRaghavan DATE 12/15/06 12/15/06 12/15/06 OFFICIAL RECORD COPY |
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| | Palisades Plant cc: |
| | Robert A. Fenech, Senior Vice President Michael B. Sellman Nuclear, Fossil, and Hydro Operations President and Chief Executive Officer Consumers Energy Company Nuclear Management Company, LLC 1945 Parnall Rd. 700 First Street Jackson, MI 49201 Hudson, MI 54016 Arunas T. Udrys, Esquire Jonathan Rogoff, Esquire Consumers Energy Company Vice President, Counsel & Secretary 1 Energy Plaza Nuclear Management Company, LLC Jackson, MI 49201 700 First Street Hudson, WI 54016 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Douglas E. Cooper Suite 210 Senior Vice President and 2443 Warrenville Road Chief Nuclear Officer Lisle, IL 60532-4351 Nuclear Management Company, LLC 700 First Street Supervisor Hudson, WI 54016 Covert Township P. O. Box 35 Stephen T. Wawro, Director Covert, MI 49043 of Nuclear Assets Consumers Energy Company Office of the Governor Palisades Nuclear Plant P. O. Box 30013 27780 Blue Star Memorial Highway Lansing, MI 48909 Covert, MI 49043 U.S. Nuclear Regulatory Commission Laurie A. Lahti, Manager Resident Inspector's Office Regulatory Affairs Palisades Plant Nuclear Management Company, LLC 27782 Blue Star Memorial Highway Palisades Nuclear Plant Covert, MI 49043 27780 Blue Star Memorial Highway Covert, MI 49043 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Hazardous Waste and Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michigan Department of Attorney General Special Litigation Division 525 West Ottawa St. |
| | Sixth Floor, G. Mennen Williams Building Lansing, MI 48913 |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | LICENSE AMENDMENT REQUEST FOR REVISED STEAM GENERATOR REPAIR CRITERIA (C* CRITERIA) |
| | PALISADES NUCLEAR PLANT NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-255 |
| | : 1. The proposed amendment is intended to allow tubes with flaws to remain in service if the flaws are located below a certain depth in the hot-leg region of the tubesheet. This will require proposing an alternative to the 40-percent, through-wall depth criteria in the Palisades Technical Specifications (TSs). Please discuss your plans to revise TS 5.5.8.c as follows: |
| | A. Indicate there is an alternative to the 40-percent repair criteria. |
| | B. Define the repair criteria in the hot-leg tubesheet region (i.e., depth below which flaws may remain in service, and the starting point for the depth measurement). |
| | C. Define the repair criteria for the region of the hot-leg tubesheet in which neither the alternate repair criteria nor the 40-percent through-wall criteria apply (i.e., tubes with flaws within the C* distance will be plugged on detection). |
| | D. State that all flaws located below this depth may remain in service, regardless of size. |
| | : 2. Proposed TS 5.5.8.d defines the portion of tube that must be inspected, from 12.5 inches below the tube-to-tubesheet expansion transition inlet to the tube-to-tubesheet weld at the tube outlet . . . . Since the C* criteria is an alternate repair criteria rather than an inspection criteria, it does not change the objective in the current TS 5.5.8.d to detect flaws from the inlet tube-to-tubesheet weld to the outlet tube-to-tubesheet weld. If the C* criteria is properly defined as an alternate repair criteria (as discussed in #1 above), then inspection below the C* distance in the hot-leg region would no longer be required because of the phrase, . . . and that may satisfy the applicable tube repair criteria in TS 5.5.8.d. |
| | Please discuss your plans to modify proposed TS 5.5.8.d to remove the reference to the C* |
| | distance and restore the wording approved in the Technical Specifications Task Force 449 amendment (i.e., . . . from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy. . . .). In addition, the staff notes that the 12.5-inch C* distance is measured from the top of the tubesheeet or the bottom of the expansion transition, whichever is lower. |
| | : 3. The basic premise of the C* amendment is that there is a 12.5-inch, non-flawed portion of the tube fully expanded into the tubesheet. To ensure the region remains free of flaws, an ENCLOSURE |
| | |
| | inspection of 100 percent of the inservice tubes in the upper region of the tubesheet will need to be performed every 24 effective full-power months, or one refueling outage interval, whichever is less. As a result, please discuss your plans to revise your proposed TS 5.5.8.d to add this inspection requirement (e.g., by adding a paragraph 5.5.8.d.4). The staff notes that if an additional paragraph 5.5.8.d.4 is added, it will need to be referenced in 5.5.8.d (i.e., In addition to meeting the requirements of d.1, d.2, d.3, and d.4 below . . . .). |
| | : 4. Please confirm that structural and leakage integrity will be assessed if significant indications are found within the inspected region of the tubesheet. The staff recognizes that the current approach of plugging flaws on detection within the C* distance should provide a high level of confidence that no potential leaking or structurally significant flaws are identified in this region. However, such an approach can not ensure it with certainty. |
| | : 5. The calculation of the inspection distance for the hot-leg tubesheet region used the lower 95-percent prediction bound for the measured and projected smooth-bore, first-slip pullout values plotted in Figure 3 of Enclosure 4 to your May 30, 2006, letter. As discussed in the RAI responses to previous C* reviews (i.e., Section 2.1.4 in Enclosure 6 of your May 30, 2006, letter), use of the load at first slip assumes that the first move results from gripper slippage or other movement besides movement of the tube within the tubesheet. |
| | Since this assumption about the first move was not verified, and given that all tubes should resist pullout from the tubesheet, confirm that if the force-per-unit-length for the most limiting specimen, based on load at first move, were used to determine the required length of expanded tubed needed to resist pullout, this length would still be less than the proposed inspection distance (12.5 inches). |
| | The staff notes that in Section 2.4.3 of Enclosure 6 (which addresses the first-slip criteria for smooth-bore samples), the final two paragraphs explain that even if there were no explansion residual contact pressure between a tube and tubesheet in the Palisades steam generators, a length of 6.75 inches is enough to resist the three-times normal operating differential pressure. The discussion identifies differential thermal expansion and expansion from the tube internal pressure as the sources of the resistance to tube pullout. |
| | Although this was referred to as the most extreme case, it is not clear if the effect of tubesheet bow was included. Please discuss whether your evaluation considered the effect of tubesheet bow. |
| | : 6. For the Ringhals test data, the first-slip pullout values plotted in Figure 3 of Enclosure 4 were projected from the measured, maximum-load values. Please discuss the effect on Figure 3 and your leakage analyses if a conservative bound (i.e., 95-percent prediction interval) were used to project the first-slip load values for the Ringhals data. |
| | : 7. The staff notes that the page numbers listed on the cover sheets of Enclosures 2 and 3 (pages 5.5.8-11 and 5.5.8-12) do not match the page numbers on the bottom of the enclosed TS pages (pages 5.0-11 and 5.0-12). Please clarify which are the correct page numbers for these TS pages. In addition, the staff notes that proposed TS page 5.0-12 should identify the Provisions for SG tube inspections. (continued) as item d rather than item e. |
| | : 8. According to Section 2.5 of Enclosure 4, the proposed inspection distance of 12.5 inches is based on adding the 0.28-inch non-destructive examination axial-position uncertainty to the |
| | |
| | values of Joint Length that Meets Leakage Criteria, (12.24 and 12.25 inches). However, since 12.25 + 0.28 = 12.53, it would be conservative to use a value of 12.6 inches rather than 12.5 inches. Please discuss your plans to modify your proposal to use 12.6 inches as the proposed distance for the alternate repair criteria (and inspection) in the hot-leg region of the tubesheet.}} |
Letter Sequence RAI |
|---|
TAC:MD2125, Steam Generator Tube Integrity (Approved, Closed) |
|
MONTHYEARML0633101752006-12-15015 December 2006
Request for Additional Information, Related to the Proposed C* License Amendment Request for Steam Generator Tube Repair in the Tubesheet
Project stage: RAI
ML0706400582007-02-27027 February 2007
Response to Request for Additional Information Regarding Proposed C* License Amendment Request for Steam Generator Tube Repair in the Tubesheet
Project stage: Response to RAI
ML0710303302007-04-10010 April 2007
Response to Request for Additional Information Regarding Proposed C* License Amendment Request for Steam Generator Tube Repair in the Tubesheet
Project stage: Response to RAI
ML0714202162007-05-31031 May 2007
Issuance of Amendment Tubesheet Inspection Depth for Steam Generator Tube Inspections
Project stage: Approval
ML0714501052007-05-31031 May 2007
Technical Specifications Pages Re Programs and Manuals for Steam Generator
Project stage: Request
ML0713702092007-05-31031 May 2007
Request for Withholding Information from Public Disclosure from Response to Request for Addition Information for License Amend. Request Regarding Tubesheet Inspection Depth for Steam Generator Tube Inspections
Project stage: Withholding Request Acceptance
ML0713701452007-05-31031 May 2007
Request for Withholding Information from Public Disclosure from Application for License Amendment Request Regarding Tubesheet Inspection Depth for Steam Generator Tube Inspection
Project stage: Withholding Request Acceptance
2007-02-27
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024
Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations
ML24012A2422024-01-16016 January 2024
Acceptance of Requested Licensing Action License Transfer Request
ML23236A0042023-12-27027 December 2023
Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme
ML23355A1242023-12-26026 December 2023
Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements
ML23192A0772023-12-26026 December 2023
Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance
ML23191A5222023-12-22022 December 2023
Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032)
ML23263A9772023-12-22022 December 2023
Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation
ML23354A2602023-12-21021 December 2023
Reference Simulator Inspection Request for Information
L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023
Proof of Financial Protection 10 CFR 140.15
PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023
License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations
PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023
Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements
PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023
Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments
L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023
Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point
ML23291A4402023-11-0303 November 2023
Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations
IR 05000255/20230032023-10-0404 October 2023
NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant
ML23275A0012023-10-0202 October 2023
Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant
PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023
Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82
PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023
Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations
PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023
Special Report High Range Noble Gas Monitor Inoperable
ML23215A2302023-08-0303 August 2023
Notice of Organization Change - Chief Nuclear Officer
IR 05000255/20230022023-07-19019 July 2023
NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant
ML23087A0362023-05-0202 May 2023
PSDAR Review Letter
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023
2022 Annual Non-Radiological Environmental Operating Report
L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023
HDI Annual Occupational Radiation Exposure Data Reports - 2022
PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023
and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports
PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023
2022 Radiological Environmental Operating Report
L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023
6 to Updated Final Safety Analysis Report
ML23088A0382023-03-29029 March 2023
Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance
PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023
Report of Changes to Security Plan, Revision 20
PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023
Presentation on Regulatory Path to Reauthorize Power Operations
ML23038A0982023-03-15015 March 2023
Request for Withholding Information from Public Disclosure
ML23095A0642023-03-14014 March 2023
American Nuclear Insurers, Notice of Cancellation Rescinded
PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023
Regulatory Path to Reauthorize Power Operations
PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023
Report of Changes to Palisades Nuclear Plant Technical Specification Bases
PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023
Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
ML23052A1092023-02-17017 February 2023
FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request
ML23032A3992023-02-0101 February 2023
Regulatory Path to Reauthorize Power Operations
IR 05000255/20220032022-12-28028 December 2022
NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant
L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022
Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15
PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022
Report of Changes to Security Plan, Revision 19
ML22321A2852022-11-17017 November 2022
LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant
IR 05000255/20224012022-11-0909 November 2022
Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401
PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022
Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme
PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022
International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations
PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022
Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance
PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022
Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance
ML22292A2572022-10-25025 October 2022
Permanently Defueled Emergency Plan License Amendment RAI Letter
2024-01-23
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23354A2602023-12-21021 December 2023
Reference Simulator Inspection Request for Information
ML23055A1542023-02-24024 February 2023
Attachment: Request for Additional Information on the Palisades PSDAR
ML22292A2582022-10-31031 October 2022
PDEP-EAL Amendment RAI
ML22102A2482022-04-14014 April 2022
Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications
ML21274A4172021-10-0505 October 2021
Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information Inspection Report 05000255/2021004
ML21028A4092021-01-27027 January 2021
NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv)
ML21028A0552021-01-27027 January 2021
NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application
ML20272A0112020-09-26026 September 2020
Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs
ML20133K0562020-05-14014 May 2020
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML19357A2752019-12-23023 December 2019
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000255/2020011
ML19226A2932019-08-14014 August 2019
NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant
ML19226A2922019-08-0505 August 2019
NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425
ML19122A4852019-04-29029 April 2019
NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications
ML19009A5392019-01-0909 January 2019
NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a
ML19009A5382018-12-12012 December 2018
NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a
ML18337A1382018-11-30030 November 2018
NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7
ML18337A1402018-11-29029 November 2018
NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7
ML18309A1342018-11-0808 November 2018
Supplemental Information Needed for Acceptance or Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-425, Revision 3
ML18094B0922018-04-0505 April 2018
Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59)
ML18081A2962018-03-22022 March 2018
NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305)
ML18059A8202018-02-28028 February 2018
NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition
ML17335A1042017-11-30030 November 2017
NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266)
ML17118A3342017-04-18018 April 2017
E-Mailed Request for Information Dated 04/18/2017 for Palisades Nuclear Power Station, Unit 1, Inservice Inspection - Part B Items (Exf)
ML17118A3312017-04-18018 April 2017
E-Mailed Request for Information Dated 04/18/17 for Palisades Nuclear Power Station, Unit 1, Inservice Inspection - Part a Items
ML17072A2752017-03-10010 March 2017
NRR E-mail Capture - Palisades Nuclear Plant - Final Request for Additional Information Regarding Relief Request No. RR 4-25
ML16238A0302016-08-29029 August 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action Control Rod Drive Exercise Surveillance
ML16130A0762016-05-11011 May 2016
Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternative Repair Criterion on the Steam Generator Tubes
ML16013A0642016-01-13013 January 2016
NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097)
ML15341A1662015-12-0707 December 2015
NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349)
ML15258A2432015-09-0101 September 2015
NRC Supplement to NRC Letter - Notification of NRC Inspection and Request for Information Dated May 1, 2015 - Palisades Nuclear Plant
ML15149A2462015-05-28028 May 2015
Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg)
ML15072A2542015-03-19019 March 2015
Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a
CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015
Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company
ML15022A1382015-01-22022 January 2015
E-Mail - Palisades Request for Information
ML15016A1842015-01-20020 January 2015
Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a
ML15012A3052015-01-15015 January 2015
Request for Additional Information Regarding the License Amendment Request for an Equivalent Margin Analysis Completed in Accordance with 10 CFR 50, Appendix G
ML14318A4002014-12-17017 December 2014
Vermont Yankee Nuclear and Big Rock Point - Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company (Tac Nos. MF3218 - MF3221)
ML14157A3642014-06-0505 June 2014
CDBI Request for Information
ML13353A0422013-12-16016 December 2013
NRR E-mail Capture - Request for Additional Information - Palisades - Proposed Revision to Palisades Site Emergency Plan (SEP) Emergency Response Organization (ERO) MF2321
ML13312A4232013-11-26026 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
ML13179A4622013-07-0505 July 2013
Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report
ML13051A7772013-02-19019 February 2013
Request for Additional Information, 2012 SG Inspection Report
ML12314A4222012-11-0808 November 2012
ME8074 - Request for Additional Information Regarding Replacement of Spent Fuel Pool Region I Storage Racks
ML12278A3862012-10-0404 October 2012
ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford, Request for Additional Information, Round 2, Amendment Request to Revise QA Program Manual and Staff Qualification TSs
ML12206A4042012-07-24024 July 2012
Request for Additional Information (Revised) - Palisades - SFP Rerack LAR - ME8074
ML12206A3322012-07-19019 July 2012
E-mail Combined Request for Additional Information for Several Branches of NRR for the Submittal on Palisades re-sack LAR
ML12121A7032012-04-27027 April 2012
Relief Request - Proposed Alternative - Use of Alternate ASME Code Case N-770-1 Baseline Examination - ME8492
ML1209604492012-04-0505 April 2012
ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Request for Additional Information, Revise Quality Assurance Program Manual and Staff Qualification Technical Specificat
ML12068A3882012-04-0202 April 2012
Request for Additional Information Regarding License Renewal Commitment to Submit Alloy 600 Program
ML12056A0492012-03-12012 March 2012
Enclosure 3 - Recommendation 2.3: Seismic
2023-02-24
[Table view] |
Text
December 15, 2006 Mr. Paul A. Harden Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES PLANT REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED C* LICENSE AMENDMENT REQUEST FOR STEAM GENERATOR TUBE REPAIR IN THE TUBESHEET (TAC NO. MD2125)
Dear Mr. Harden:
Your letter of May 30, 2006, submitted an application to change the Palisades Nuclear Plant (Palisades) technical specifications related to steam generator tube repair. The changes would revise the repair criteria for the portion of the tubes within the hot-leg region of the tubesheet.
We are reviewing your requests, and find that additional information is needed as shown in the enclosed request for additional information (RAI). I discussed the enclosed RAI with Ms. Amy Hazelhoff of your organization on December 13, 2006, and she agreed to respond within 60 days of receipt of this RAI. Please contact me at (301) 415-1423 if you have questions.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosure:
RAI cc w/encl: See next page
Mr. Paul A. Harden December 15, 2006 Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES PLANT REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED C* LICENSE AMENDMENT REQUEST FOR STEAM GENERATOR TUBE REPAIR IN THE TUBESHEET (TAC NO. MD2125)
Dear Mr. Harden:
Your letter of May 30, 2006, submitted an application to change the Palisades Nuclear Plant (Palisades) technical specifications related to steam generator tube repair. The changes would revise the repair criteria for the portion of the tubes within the hot-leg region of the tubesheet.
We are reviewing your requests, and find that additional information is needed as shown in the enclosed request for additional information (RAI). I discussed the enclosed RAI with Ms. Amy Hazelhoff of your organization on December 13, 2006, and she agreed to respond within 60 days of receipt of this RAI. Please contact me at (301) 415-1423 if you have questions.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION PUBLIC RidsOgcRp RidsNrrDorlLpl3-1 RidsNrrDorlDpr RidsRgn3MailCenter LPL3-1 r/f RidsAcrsAcnwMailCenter RidsNrrPMMChawla RidsNrrLATHarris GMakar ADAMS Accession Number: ML063310175 OFFICE LPL3-1/PM LPL3-1/LA LPL3-1/BC NAME MChawla THarris LRaghavan DATE 12/15/06 12/15/06 12/15/06 OFFICIAL RECORD COPY
Palisades Plant cc:
Robert A. Fenech, Senior Vice President Michael B. Sellman Nuclear, Fossil, and Hydro Operations President and Chief Executive Officer Consumers Energy Company Nuclear Management Company, LLC 1945 Parnall Rd. 700 First Street Jackson, MI 49201 Hudson, MI 54016 Arunas T. Udrys, Esquire Jonathan Rogoff, Esquire Consumers Energy Company Vice President, Counsel & Secretary 1 Energy Plaza Nuclear Management Company, LLC Jackson, MI 49201 700 First Street Hudson, WI 54016 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Douglas E. Cooper Suite 210 Senior Vice President and 2443 Warrenville Road Chief Nuclear Officer Lisle, IL 60532-4351 Nuclear Management Company, LLC 700 First Street Supervisor Hudson, WI 54016 Covert Township P. O. Box 35 Stephen T. Wawro, Director Covert, MI 49043 of Nuclear Assets Consumers Energy Company Office of the Governor Palisades Nuclear Plant P. O. Box 30013 27780 Blue Star Memorial Highway Lansing, MI 48909 Covert, MI 49043 U.S. Nuclear Regulatory Commission Laurie A. Lahti, Manager Resident Inspector's Office Regulatory Affairs Palisades Plant Nuclear Management Company, LLC 27782 Blue Star Memorial Highway Palisades Nuclear Plant Covert, MI 49043 27780 Blue Star Memorial Highway Covert, MI 49043 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Hazardous Waste and Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michigan Department of Attorney General Special Litigation Division 525 West Ottawa St.
Sixth Floor, G. Mennen Williams Building Lansing, MI 48913
REQUEST FOR ADDITIONAL INFORMATION (RAI)
LICENSE AMENDMENT REQUEST FOR REVISED STEAM GENERATOR REPAIR CRITERIA (C* CRITERIA)
PALISADES NUCLEAR PLANT NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-255
- 1. The proposed amendment is intended to allow tubes with flaws to remain in service if the flaws are located below a certain depth in the hot-leg region of the tubesheet. This will require proposing an alternative to the 40-percent, through-wall depth criteria in the Palisades Technical Specifications (TSs). Please discuss your plans to revise TS 5.5.8.c as follows:
A. Indicate there is an alternative to the 40-percent repair criteria.
B. Define the repair criteria in the hot-leg tubesheet region (i.e., depth below which flaws may remain in service, and the starting point for the depth measurement).
C. Define the repair criteria for the region of the hot-leg tubesheet in which neither the alternate repair criteria nor the 40-percent through-wall criteria apply (i.e., tubes with flaws within the C* distance will be plugged on detection).
D. State that all flaws located below this depth may remain in service, regardless of size.
- 2. Proposed TS 5.5.8.d defines the portion of tube that must be inspected, from 12.5 inches below the tube-to-tubesheet expansion transition inlet to the tube-to-tubesheet weld at the tube outlet . . . . Since the C* criteria is an alternate repair criteria rather than an inspection criteria, it does not change the objective in the current TS 5.5.8.d to detect flaws from the inlet tube-to-tubesheet weld to the outlet tube-to-tubesheet weld. If the C* criteria is properly defined as an alternate repair criteria (as discussed in #1 above), then inspection below the C* distance in the hot-leg region would no longer be required because of the phrase, . . . and that may satisfy the applicable tube repair criteria in TS 5.5.8.d.
Please discuss your plans to modify proposed TS 5.5.8.d to remove the reference to the C*
distance and restore the wording approved in the Technical Specifications Task Force 449 amendment (i.e., . . . from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy. . . .). In addition, the staff notes that the 12.5-inch C* distance is measured from the top of the tubesheeet or the bottom of the expansion transition, whichever is lower.
- 3. The basic premise of the C* amendment is that there is a 12.5-inch, non-flawed portion of the tube fully expanded into the tubesheet. To ensure the region remains free of flaws, an ENCLOSURE
inspection of 100 percent of the inservice tubes in the upper region of the tubesheet will need to be performed every 24 effective full-power months, or one refueling outage interval, whichever is less. As a result, please discuss your plans to revise your proposed TS 5.5.8.d to add this inspection requirement (e.g., by adding a paragraph 5.5.8.d.4). The staff notes that if an additional paragraph 5.5.8.d.4 is added, it will need to be referenced in 5.5.8.d (i.e., In addition to meeting the requirements of d.1, d.2, d.3, and d.4 below . . . .).
- 4. Please confirm that structural and leakage integrity will be assessed if significant indications are found within the inspected region of the tubesheet. The staff recognizes that the current approach of plugging flaws on detection within the C* distance should provide a high level of confidence that no potential leaking or structurally significant flaws are identified in this region. However, such an approach can not ensure it with certainty.
- 5. The calculation of the inspection distance for the hot-leg tubesheet region used the lower 95-percent prediction bound for the measured and projected smooth-bore, first-slip pullout values plotted in Figure 3 of Enclosure 4 to your May 30, 2006, letter. As discussed in the RAI responses to previous C* reviews (i.e., Section 2.1.4 in Enclosure 6 of your May 30, 2006, letter), use of the load at first slip assumes that the first move results from gripper slippage or other movement besides movement of the tube within the tubesheet.
Since this assumption about the first move was not verified, and given that all tubes should resist pullout from the tubesheet, confirm that if the force-per-unit-length for the most limiting specimen, based on load at first move, were used to determine the required length of expanded tubed needed to resist pullout, this length would still be less than the proposed inspection distance (12.5 inches).
The staff notes that in Section 2.4.3 of Enclosure 6 (which addresses the first-slip criteria for smooth-bore samples), the final two paragraphs explain that even if there were no explansion residual contact pressure between a tube and tubesheet in the Palisades steam generators, a length of 6.75 inches is enough to resist the three-times normal operating differential pressure. The discussion identifies differential thermal expansion and expansion from the tube internal pressure as the sources of the resistance to tube pullout.
Although this was referred to as the most extreme case, it is not clear if the effect of tubesheet bow was included. Please discuss whether your evaluation considered the effect of tubesheet bow.
- 6. For the Ringhals test data, the first-slip pullout values plotted in Figure 3 of Enclosure 4 were projected from the measured, maximum-load values. Please discuss the effect on Figure 3 and your leakage analyses if a conservative bound (i.e., 95-percent prediction interval) were used to project the first-slip load values for the Ringhals data.
- 7. The staff notes that the page numbers listed on the cover sheets of Enclosures 2 and 3 (pages 5.5.8-11 and 5.5.8-12) do not match the page numbers on the bottom of the enclosed TS pages (pages 5.0-11 and 5.0-12). Please clarify which are the correct page numbers for these TS pages. In addition, the staff notes that proposed TS page 5.0-12 should identify the Provisions for SG tube inspections. (continued) as item d rather than item e.
- 8. According to Section 2.5 of Enclosure 4, the proposed inspection distance of 12.5 inches is based on adding the 0.28-inch non-destructive examination axial-position uncertainty to the
values of Joint Length that Meets Leakage Criteria, (12.24 and 12.25 inches). However, since 12.25 + 0.28 = 12.53, it would be conservative to use a value of 12.6 inches rather than 12.5 inches. Please discuss your plans to modify your proposal to use 12.6 inches as the proposed distance for the alternate repair criteria (and inspection) in the hot-leg region of the tubesheet.
