ML19341B700

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Forwards Justification & Acceptability of Proposed Exemption Re Reactor Vessel Matl Surveillance Program & Amend to Ol. Matters Covered by Exemption Will Not Bear Upon Restart Proceeding
ML19341B700
Person / Time
Site: Crane 
Issue date: 01/29/1981
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Ahearne J, Gilinsky V, Hendrie J
NRC COMMISSION (OCM)
References
NUDOCS 8102270067
Download: ML19341B700 (4)
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Text

{{#Wiki_filter:. DLETRTR!fTinN: jputoY dT (DocRet File' TNovak NRC PDR DEisenhut Docket no. 50-189 4 RPurple 09C ORB #4 Rdg PE Memo File SECY EA MEIORANDUM FOR: Chairman Ahearne WDircks Comissioner Gilinsky EDO Rdg Commissioner Hendrie HDenton Commissioner Bradford DDilanni RReid THRU: William J. Dircks, Executive Director for Operations . w... FROM: Harold R. Denton, Director, Office of Nuclear Reactor Regulation

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TMI-1) - AN EXEMPTION By letter dated July 9,1980 (TLL 301) Metropolitan Edison Company, the licensee for TMI-1, requested an exemption from the requirement of 10 CFR 50 Appendix H II, C.4 The exemption is concerned with the reactor vessel material surveillance program. Reactor vessel material samples for TitI-l were being irradiated in TMI-2. These samples are not now available and will not be available in the near future. 10 CFR EO Appendix H pemits an onsite integrated surveillance program but does not now pemit the samples to be irradiated at another site. Eecause of the expected future condition of TMI-2, the licensee requested an exemption that would permit the integrated surveillance program to be continued in the Crystal River, Unit No. 3 (CR-3) reactor. The CR-3 reactor was selected because the neutron energy spectra is similar to TMI-l and the CR-3 reactor contains revised specimen holder tubes while TMI-l does not. There are no contentions in the pending TMI-l restart proceeding which bear upon the matters c vered by this exemption. The staff will, however, consis-tant with its practice throughout the restart proceeding, provide all parties with copies of this correspondence even though it does not relate to matters in issue in the proceeding. The, justification and acceptability of the proposed exemption and the amend-ment to the operatig ' g -- has been prepared, a copy of which is enclosed. A .< :s - M3 s .( ,,,,) g.M e l Harold R. Denton, Director

9. Office of Nuclear Reactor Regulation r.?

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Enclosure:

Propcsed Amendment.4 ,1O10227 O d O o @k

Contact:

OELD EDO :, n R. Reid. NRR JRGray* HJDfrcks See previous yellcu for concurrences. 1316/80 01/ ' /Cf 49-272Cl ..&0.R ; DL,..h .b sh,', NRDe. / sua.me p>!. 0RS = 2.:.0L.... . C-0RB M : DL.. 0N omce RReid* TNovak) - DE . ti u.... EGC)O.e t n .DD.i la.nni/.c.b g m e ),..

DISTRIBUTION: See NRC Form 6 Docket No. 50-289 TiORANDG4 FOR: Chainen Aheerne. Cornissioner,Gilinsky Consnissioner Hendrie Commissioner Bradford THRU: William J. Dircks Acting Exec,utive Director for Operations FROM: Harold R. Denton, Director, Of,fice of Nuclear Reactor Regulation SLEJECT: THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 (TMI-1) - AN EXE!9 TION ~ By letter dated July 9,1980 (Tm 301) Metropolitan Edison Company, the licensee for TMI-1, mquested an exegtion from the requirement of 10 CFR 50 Appendix H II, C.4. The exegtion is concemed with the reactor vessel material surveillance program. Reactor vessel caterial samples for THI-1 were being irradiated in TMI-2. These samples are not now available and will not be available in the near future. 10 CFR 50 Appendix H permits an onsite integrated surveillance pmgram but does not now pemit the samples to be itTadiated at another site.,,,, Because of the expected future, condition of TNI-2. the licensee requested an exegtfon that would permit the integrated surveillance program.to be continued in the Crystal River, Unjt No. 3 (CR-3) reactor. The CR-3 reactor was selected because the neutron energy spectra is similar to TMI-l and the CR-3 reactor contains revised', specimen, holder _ tubes while TMI-1_ does not. The justification and acceptability of, the proposed exemption and the amend-ment to the opemting license,has been prepared..a copy of which is enclosed. Hat $1dR.Denton, Director Office of Nuclear Reactor Regulation Enclosum: N Proposed Amendnent A j _ (, f _., .gM kph Exemption i M A-EDO 4 e,NRR hV Og/6 /80 9/ /80 AM rcks 49-27381

  • See previous yellew-for concurrences.

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F. Docket No. 50-289 i' PSiORANDLti FOR: Chaiman Ahearne Corrissioner Gilinsky Comissioner Hendrie { Corviissioner Bradford i THRU: William J. Dircks Acting Executive Director for Operations i FROM: Harold R. Denton, Director Office of Nuclear Reactor Regulation

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, L? LIT NO.1 (Tl!I-1) - AN EXE!TTION By letter dated July 9,1930 (TLL 301), Petropolitan Edison Company the licensee for T!!I-l requested an exerption fron the requirement of 10 CFR 50 Appendix H II, C,4. T% exemptien is concerned with the reactor vessel r.aterial surveillance program. The reactor vessel material sanples for TMI-l were being irradiated in TMI-2. These sannles are not now available and will not be availe.ble in .o near future. 10 CFR 50 Appendix H per-mits as a site integrated surveillance but does not remit the samples to be irradiated at another site. Because of the expected future condition of TMI-2, the licensee requested an exemption that would pemit the integrated surveillance program to be continud in the Crystal River, Unit No. 3 (CR-3) reactor. The CR-3 reactor was selected because the neutron e'terc' scer';ra is sinflar to Tt:I-l and the CR-3 reactor contains revised specimen holder tubes while TMI-l doessnot. The justification and acceptability of the proposed exemption and the arend-ment to the operating license has been prepared, a copy of which is enclosed. Harold R. Dentoa, Director Office of Nucleir Reacto'- Regulation

Enclosure:

Proposed Anendment & Exemption O D[ A-EDO WDircks CDatact: R. Reid, flRR / / 8/ /80 00:NRR D:NRR DL [. i. x n..d4:DL iAD.OR0L,j.,..D:DL lCCORB ,,$'98$$r4: svana: c).DC.D,i.Iannni/,cb,,RR,eid,g.. , g,No.v,a k' jDEisenhut...... ......HDenton .r. ECase c.ut). 8/!f/80, ,, 8/ 4/80 g/j p,, l 8/ /80 8/ /80 8/ /80 .== r:n. m eo sa., :2.:. e s.s. n.c-..n.2 o m, e 2,n m m,.w.0,,

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NUCLEAR REGULATORY COMMISSION y, e, ,'\\" E W ASHING tCN, D. C. 20555 ( / January 22, 1981 Docket !,0. 50-259 t'E30RANDLM FOR: Chaiman Ahearne Comissioner Gilinsky Connissioner Hendrie Cox.issioner Bradford THRU: William J. Dircks, Executive Director for Operations FRGit: Nrold R. Denton, Director, Office of Nuclear Reactor Regulation SUSJECT: THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TMI-1) - AN EXEMPTION 4 By letter dated July 9,1930 (TLL 301) Metropolitan Edison Ccmpany, the licensee for TMI-1, requested an exemotion fece tne reouirement of 10 CFR 50 Ap;:endix H !!, C.4. The exemption is co9cerned with the reactor vessel material surveillance' program. Reactor vessel material samples for T?tI-l were being irradiated in TMI-2. These samples are not new available and will not be available in the near future. 10 CFR 50 Appendix H pemits an onsite integrated surveillance program but does not now pemit the samples to be irraciated at another site. Because of the expected future condition of TMI-2, the licensee requested an execption :nat would pemit the integrated surveillarice program to be continued in the Crystal River, Unit No. 3 (CR-3) reactor. The CR-3 reactor was selected because tne neutron energy spectra is similar to TMI-1 and tne CR-3 reactor contains revised specimen holder tubes wnile TMI-1 does not. There are no contentions in the pending TMI-l restart proceeding which bear upon the matters covered by this exemption. The staff will, however, consis-tant with its ::ractice throughout the restart proceeding, provide all parties with copies of this correspondence even thougn it does not relate to mat:ers i in issue in the proceeding. The justification and acceptability of the proposed exemption and the amend-ment to the operating license has been prepared, a opy of which is enclosed. NW w Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosure:

p!toosed Amencment 3 Exemption Centact: R. Reid, NRR . m, ; h N f $.' f -l h O l 0 h 5

[pa ucg'o UNITED STATES !", w [,j NUCLEAR REGULATORY COMMISSION V"/ E WASHINGTON,0, C. 20555 %, v /. E %.....f Janua ry 22, 1981 i Docket No. 50-289 i i Mr. Henry D. Hukill, Vice President and Director - TMI-l Metropolitan Edison Company P. O. Box 480 fliddletown, Pennsylvania 17057

Dear Mr. Hukill:

By letter dated July 9,1980 (TLL 301), you requested an exemption from the provisions of Appendix H to 10 CFR 50 which would permit future operation of the Three' Mile Island Nuclear Station, Unit No.1 (TMI-1), while irradiating a remaining reactor vessel surveillance capsule at Crystal River Unit No. 3. This exemotion was requested because TMI-2 which is the host reactor for one TMI-l capsule will be non-operational for an indefinite period. By letter dated April 11, 1980 (TLL 165) you requested approval of proposed changes to the Technical Specifications consistent with the requested exemption. Irradiating the remaining TMI-l surveillance capsule at Crystal River, j Unit No. 3, or in test reactors, will cause the THI-l program to be out of conformance with the provision of Appendix H, which requires the irra-diation program to be performed within the TMI-l vessel or at the same site for multi-reactor sites. However, as noted in the enclosed Safety Evaluation, the nominal dimensions of the TMI-1 reactor vessel and internals are similar to those at Crystal River, Unit No. 3, and the operating conditions at these two reactors are very similar, so that with the exception of actual operating history and minor differences in power distribution, for which adjustments can be provided, the technical aspects of the material surveillance program will be achieved to our satisfaction. Based on these considerations, we have concluded that an exemption for TMI-l from this requirement for a continuing in-vessel material surveillance pro-gram as set forth in Appendix H to 10 CFR Part 50 is authorized by law, will i not be detrimental to life or property or the common defense and security and is in the public interest. Therefore, the exemption requested in your letter of July 9,1980 (TLL 301), is approved. i In addition to granting this exemption, the Connission has issued the enclosed Amendment No. 60 to Facility Operating License No. OPR-50 for the TMI-1. The amendment provides for performance of the TMI reactor vessel :raterial sur-veillance program at Crystal River, Unit No. 3, and for the submission of specified reports. Certain changes were required in the proposed Technical Specifications submitted by your staff relative to this pr3 ram. These changes have been made to the Tecnnical Specifications. a i

Mr. Henry D. Hukill -2 A copy of the Notice of Issuance is also enclosed. ince rely, f 8% (2 g rrell G. fisennut, Director s Division of Licensing Office of Nuclear Reactor Regulation Enclosures : 1. Amendment No. 60 2. Safety Evaluation 3. Notice 5 cc w/ enclosures: j See next 3 pages i I. - I i i

E Metropolitan Edison Company cc w/ enclosure (s): I Mr. Marvin I. Lewis Dr. Walter H. Jordan 6504 Bradford Terrace 881 W. Outer Drive Philadelphia, Pennsylvania 19149 Oak Ridge, Tennessee 37830 Walter W. Cohen, Consumer Advocate Dr. Linda W. Little Department of Justice 5000 Hermitage Drive Strawberry Square, 14th Floor Raleigh, North Carolina 27612 Harrisburg, Pennsylvania 17127 i Holly S. Keck Robert L. Knupp, Esq. Anti-Nuclear Group Representing Assistant Solicitor York Knupp and Andrews 245 W. Philadelphia Street P. O. Box P York, Pennsylvania 17404 407 N. Front Street Harrisburg, Pennsylvania 17108 John Levin Esq. Pennsylvania Public Utilities Com. John E. Minnich, Chairman Box 3265 Dauphin Co. Board of Comissioners Harrisburg, Pennsylvania 17120 Dauphin County Courthouse Front and Market Streets Jordan D. Cunningham, Esq. { Harrisburg, Pennsylvania 17101 Fox, Farr and Cunninghan 8 2320 North 2nd Street

  • Atomic Safety and Licensing Appeal Board Harrisburg, Pennsylvania 17110 l

U.S. Nuclear Regulatory Comission i Washington, D. C. 20555 Theodore A. Adler, Esa. WID0FF REAGER SELK0WITZ & ADLER 5

  • Atomic Safety and Licensing Board Panel P. O. Box 1547 l

U.S. Nuclear Regulatory Comission Harrisburg, Pennsylvania 17105 Washington, D. C. 20555 Ms. Marjorie M. Aamodt

  • Docketing and Service Section R.D. !5 U.S. Nuclear Regulatory Comission Coatesville, Pennsylvania 19320 Washington, D. C.

20555 Ms. Karen Sheldon Robert Q. Pollard Sheldon, Harmon & Weiss 609 Mo.celier Street 1725 I Street, N.W. - Suite 506 Baltimore, Maryland 21218 Washington, D. C. 20006 Chauncey Kepford Earl B. Hoffman Judith H. Johnsrud Dauphin County Comissioner Environmental Coalition on Nuclear Power Dauphin County Courthouse 433 Orlando Avenue Front and Market Streets State College, Pennsylvania 16801 Harrisburg, Pennsylvania 17101 Ms. Frieda Berryhill, Chainnan Ms. Ellen R. Weiss, Esq. Coalition for Nuclear Power Plant Sheldon, Hannon & Weiss Postponement 1725 I Street, N.W. 2610 Grendon Drive Suite 506 Wilmington, Delaware 19808 Washington, D. C. 20006 Mrs. Rhoda D. Carr Mr. Steven C. Sholly 1402 Marene Drive 304 South Market Street Harrisburg, Pennsylvania 17109 Mechanicsburg, Pennsylva.11a 17055 i

E 1 ~ Metropolitan Edison Company Mr. Thomas Gerusky Ms. Jane Lee Bureau of Radiation Protection R.D. 3. Box 3521 Department of Environmental Resources Etters, Pennsylvania 17319 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Karin W. Carter, Esq. 505 Executive House P. O. Box 2357 Mr. G. P. Miller Harrisburg, Pennsylvania 17120 Mr. R. R. Wilson Metropolitan Edison Company Honorable Mark Cohen P. O. Box 480 512 D-3 Main Capital Building Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 G. F. Trowbridge, Esq. Dauphin County Office Emergency Shaw, Pittman, Potts & Trowbridge Preparedness 1800 M Street, N.W. Court House, Room 7 Washington, D. O. 20036 Front & Market Streets Harrisburg, Pennsylvania 17101 Mr. E. G. Wallace Licensing Manager Department of Environmental Resources GPU Service Corporation ATTN: Director, Office of Radiological 100 Interpace oarkway Health Parsippany, New Jersey 07054 P. O. Box 2063 Harrisburg, Pennsylvania 17105 Mr. R. W. Conrad Vice President, Generation Director, Criteria and Standards Pennsylvania Electric Company Division 1007 Broad Street Office of Radiation Programs (ANR-460) Johnstown, Pennsylvania 15907 U. S. E"vironmental Protection Agency Washingwon, D. C. 20460 Miss Mary V. Southard, Chairperson Citi:: ens for a Safe Environment P. O. Box 405 Harrisburg, Pennsylvania 17108 Mr. Robert B. Borsum Babcock & Wilcox Government Publications Section Nuclear Power Generation Division State Library of Pennsylvania Suite 420, 7735 Old Georgetown Road Box 1601 (Education Building) Bethesda, Maryland 20014 Harrisburg, Pennsylvania 17126

  • Ivan W. Smith, Esq.

Mr. David D. Maxwell, Chairman Atomic Safety & Licensing Board Panel Board of Supervisors U.S. Nuclear Regulatory Comission Londonderry Township Washington, D. C. 20555 RFD#1 - Geyers Church Raod Middletown, Pennsylvania 17057 Ms. Kathy McCaughin ihree Mile Island Alert, Inc. U. S. Environmental Protection Agency 23 South 21st street Region III Office Harrisburg, Pennsylvania 17104 ATTN: EIS COORDINATOR Curtis Building (Sixth Floor) Mr. L. W. Harding 6th and Walnut Streets Supervisor of Licensing Philadelphia, Pennsylvania 19106 Metropolitan Edison Company P. O. Box 480 Mr. J. G. Herbein Middletown, Pennsylvania 17057 Director, Nuclear Assurance Metropolitan Edison Company P. O. Box 480 Middletown, PA 17057

1 i Metropolitan Edison Company < Mr. R. J. Toole Allen R. Carter, Chainnan Manager, TMI-1 Joint Legislative Connittee on Energy Metropolitan Edison Company P. O. Box 142 P. O. Box 480 Suite 513 Middletown, Pennsylvania 17057 Senate Gressette Building Colurtia, South Carolina 29202 Mr. W. E. Potts Radiological Controls Manager, TMI-l Daniel M. Pell, Esq. Metropolitan Edison Company ANGRY P. O. Box 480 32 South Beaver Street Middletown, Pennsylvania 17057 York, Pennsylvania ^ 17401 Mr. I. R. Finfrock, Jr. William S. Jordan, III, Esq. Jersey Central Power & Light Comoany Hannon & Weiss Madison Avenue at Punch Bowl Raad 1725 I Street, NW, Suite 506 Morristown, New Jersey 07950 Washington, DC 20006 J. B. Lieberman, Esq. General Counsel Berlock Israel & Libennan Federal Emergency Management Agency i 26 Broadway AT*N: Docket Clerk New York, NY 10004 1725 I Street, NW Washington, DC 20472 Mr. J. J. Colitz Mr rt Plant Engineering Manager, TMI-1 ,g 3 Metropolitan Edison Company P. O. Box 480 tietropolitan Edison Compar.y i Middletown, Pennsylvania 17057 P. O. Box 480 6, Middletown, Pennsylvania 17057 York College of Pennsylvania Mr. E. D. Fuller Country Club Road York, Pennsylvania 17405 TMI-2 Licensing Supervisor Metropolitan Edison Company P. O. Box 480 Middletown, Pennsylvania 17057 e to, Metropolitan Edison Company P. O. Box 480 Middletown, Pennsylvania 17057 Mr. Donald R. Haverkamp Mr. B. Elart. Senior Resident Inspector (TMI-1) l Manager, Plant Engineering, Unit 2 U.S.N.R.C. t Metropolitan Edison Company P. O. Box 311 l

. O. Box 480 tiiddletown, Pennsylvania 17057 Middletown, Pennsylvania 17057 1

Mr. Richard Roberts The Patriot cc w/ enclosure (s) & incoming dtd.: 812 Market Street 4/1117/9/80 Harrisburg, Pennsylvania 17105 i Governor's Office of State Planning i Mr. R. W. Heward and Development Manager, Radiological Control, Unit 2 ATTN: Coordinator, Pennsylvania l Metropolitan Edison Company State Clearinghouse l P. 0. Box 480 P. O. Box 1323 j Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 l I i

l 4 UNITED STAT ES O O* NUCLEAR REGULATORY COMMISSION l I WASHINGTON, D. C. 20584

  • g

/ METROPOLITAN EDISON COMPANY .v JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 i THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 i' AMENDMENT TO FACILITY OPERATING LICENSE f Anendment No, 60 License No. DPR-50 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Metropolitan Edison Company, et al. (the licensee) dated April 11, 1980, corplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable mquirements l have been satisfied. i I l l l I 1 I b UPE: l' L # 2 L L 4 3 5 7

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION fiff -< d Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensi.ng

Attachment:

Changes to the Technical Specifications Date of Issuance: Janua ry 22, 1981 l l I l l l

ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Revise Appendix A as follows: Remove Pages Insert Pages 4-11 4-11 4-12 4-12 4-13 4-13 4-27a 4-27a l r I l l i t

4.2 REAC*CR CCCLAN* SYS*D4 INSERV'CE INSpECTI2 Atelicability This techni:a1 specifica:ica applies to the inservice inspection of the reactor coolant system pressure boundary and pcrtions cf other safety oriented syste= pressure boundaries as shevn en Figure k.2-1. Objective The objective of this inservice inspection progrs= is to provide assurance of the centinuing integrity of the reactor ecciant syste= vhile at the sa=e ti=e =ini=1:ing radiatien expcsure to persennel in the perfor=ance of inservice inspecti:ns. Sreeificatien f k.2.1 The inservice inspectica progra to be fellowed is outlined in Table k.2-1. Except as provided for in this table and as discussed herein, the inservice inspection progrs= is in ace:rdance with the AEME Code, Section XT, Rules for Inservice Inspectics of Nuclear Reacter Ccolant Syste=s, dated January 1, i 197c, as = edified by the vinter 1970 Addenda. Pri:r :: initial plant cperatica a precperational inspection of the plant will be perfer=ed of at least the areas listed in the ASMZ Cede; pr:vided accessibility and the necessary inspection techniques are available f r each of these areas. The l caly exceptien to this vill be ereas where the necescary base line data is already available and has been cbtained by the sa=e techniques as will te used during it. service inspection. h.2.2 The reacter vessel =aterial surveillance capsules re=0ved fre= TMT-1 during 1976 shall be inserted, irradiated in and withdrawan frc= Crystal River Unit No. 3 (CR-3) in accordance with the schedule shown in Table 4.2-2. (The insertion / withdrawal schedule shown in Table 4.2-2 =ny be revised at a later date pending the restart of IMI-2.) The licensee shall be rcsronsible for the examination of these specimens and for sub=1ssion of reports of test results in accordance with 10 CFR 50, Appendix H. k.2.3 The secessible pertiens of one reae cr ceclant pu=p==:cr flyvneel asse=bly 3 vill be ultrasenically inspected within 3-1/3 years, two vithin 6-2/3 years, and all fcur by the end of the 10 year inspection interval. Ecwever, the U.T. pr:cedure is develep= ental and vill be used only : the extent that it is shown :: be neaningful. The extent of ecverage vill be li=ited := these areas of the flywheel which are accessible withcut oter disasse=bly, i.e., can te reached through the access pcrts. Also, if radiation levels at the lever access ports are prehibitive, caly the upper access perts vill be used. i .2.4 The inspectica schedule =ay be : dified to coincide with th:se refueling er =aintenance cutages =os 01csely appr: aching the inspecti:n schedule. .2.5 Sufficient ree:rds of each inspecticn shall be kept to all:v =c=parisen and evaluati:n of future inspecti:ns. 2.2.5 The inservice inspection shall be reviewed at the end Of. five years te

ensider inccrporati:n Of new inspecticn techniques and equipnen vnich have been preven practical, and a pessible extension of the pr:gra: Oc additional exa=inati:n areas. The ::::12sions of this review shall be sub=itted to the ';3C fer eval e -

4-11 Amendment No. 60

n_ k.2 7 The license sha.'.' su'-.4. a repc'-*~ ar a***14 S+4

  • = or license amecd=ent

~ ,=e that Crystal River Uni to *he IRC vithin 90 days a+ e-a.hree fails to naintain a c ' a+..,ve eac*-. +-.4.' <..a.4 cn f acter of at lets: 6c%. I The repcrt shall previle dus.4..,.a. cn,'or c ~~4 nue cperation of TMI.1 a V *u the reactor vesse sury 4'i 4 UnitNo.3,ortheapp5'1eatie[~bhe ,Y'4I.cp conduc*ed a-Crystal giver 1 8 propese an 81 ternate prepa= for cc= duct o et.or vessel surveillane, i prcgrs=, Fc- -he purpose of this technical spe 4+4-the de*inition of 4 ccnne cial cpera:1cn is *ha+- s-4ve-in c.eguin* cry Gaiae + +5, gevisics 4 ~u a - e e,s.a., cn of cunulative

  • eac -*-- '-4 ' 4.a., en factor ^" s *- ' # 8~- '< Y' reac~-~-

~*-4,< a.a -..-.cn. acto-=(C"ula+4[,jegavat: hours (ther=al) since at+ain=entcfec==,7ggy}.,,a,'.^77 (licensed power (ygt) x (CL.",,a-7,n a,-. C. pcver x (i00)) divided by h te he~-s s'e c* S..*4 :8* cf cc=nercial N. . a. operation at 100% power)). [ 6 1 .3.a .a ad'4 ** c- + o +he reports - s d - d w/ e ec.4.,., cation k.2.7' a - c-- u- -r r shall be sub .4-+e4.c he TFe - 4-- .,e w WhiCh s"--a*1:es s th! firs

  • five 7 ears cf Cae*
  • ~d~~6.xpe. ence with the TMI-1 integrated l

surveillance crcEra= e E d 4 s. a hcs ea-~-~ .r.o, at the -t=e of r --. e subnission of *his==---- 4 a, ti: e the su veillance prepas a* a hest reabb[U s$'5 'x~"e~.'7.ence.n s all be justified cn ,I,.- w basis of the attained cr a e ~s ep I i i i f 1 i k t. i e l t 4-12 Amendment No. e0 1

Insetetion 3tess a. The nuclear plant was desig=ed prior to the issuance of Secticn XI of the ASME Code, Rules for Inservice Inspection of Nuclear Reactor Ccclant Syste=2 dated January 1, 1970. Ecvever, sufficient accessibility was included in the design to perfors = cst inspections discussed in the code. The proposed 1 t inspectic: progra= fc11cvs the code except that inspections are focused en areas which engineering analysis has indicated are subject to the =cre critical stress, radiatien, or transient conditicus. The areas selected fer inspection en this basis are listed in Table k.2-1. These areas are expcsed to the scre severe ec ditiens (which are still vell within code li=its) in the reacter c clant syste=. Therefore, they are expected to indicate potential proble=s bef:re significant flaws develop in the selected areas er in other areas. It is censidered that the focused apprcach specified herein vill result is a meaningful inspection program in tha* it vill provide assurance of continuing plant integrity. In those areas where inspec*ien =ethods are develeprental, such as for re: te inspectica of the reactor vessel velds, reacter vessel no::le inside radii and velds, and ultrasenic inspectics of pressuri:er support bracket velds, the inspecti:n methods vill be develcped and tested to the extent practicable during j-preeperational inspecticus. (Oevelopment of 1:specticn techniques vill set be attempted :n radicactive equip =ent unless necessary to explcre a specified proble=.) A preoperational inspection is planned cf areas listed in the ASME C0de which are within the inservice inspection boundaries and which are accessible fer inspection. However, as discussed abcve, in areas vnere inspectie :etheds are devel=p= ental, the inspections vill only be perter =ed to the extent practicable. Cnce an inspectien methed is selected for a particular j inspection (e.g., U.T. f:r =cs; volu=etric inspecticas ), it is intended that all subsequent inservice inspecticus be perfor:ed using the identical =ethed and en the ss=e ce=penent parts wherever practicable. .-{

n additien to the above inspecticn, if any of *he ce=penents within the h

inservice inspecticn beundary are disasse= bled for :sintenance, the accessible parts vill be given a :Or=al visual exa=inati = as part of the routine plant =aintenance operaticus. [ b. Because of dn-age to the surveillance capsule helder tubes originally installed in IMI-1, irradistica of the IMI-1 capsules was to be conducted in IMI-2 i pursuant to 10 CFR 50, Appendix H, Se *ien II.C.h. One of the five re=aini=g 2C-1 capsules (Capsule I had been vithdrawn and tested earlier) was installed in a holder tube in the OC-2 react:r at the 1:1tial startup cf CC-2. "'h e Other four capsules vere scheduled for later inserti:ns. Hevever, due to the TMI-2 ::cident, Unit 2 may be cut of operatien for a considerably lenger period of ti=e than vill te OC-1. So that CC-1 vill have an engeing surveillance 'I progrs=, a CC-1 capsule vill be inserted into a holder tube in the Crystal { River Unit 3 (CR-3) reactor. Because similarities exist between l TMI-l and CR-3, appropriate adjustments and =argins can be imposed g to the surveillance capsule irradiation in CR-3 to account for such differences that =ay exist in the irradiation exposure of the TMI-l reactor vessel and the surveillance capsule. The withdrawal schedule has been fer=ulated to epti=ize the availability of irradiati:n data frc= all the capsules being irradiated in tre C3-3 rea:ter. Because the irradiatica progra: is dependent upon :ne successfu Operatien and a reas:nable utili:sti:n Of C3-3, reper-ing require =ents are included :: per=1t re-evaluati = cf the progrs= if 23-3 suffers extended cutages.

. The reae:cr : clan: pu=p =cter flywheel ultrasc=ic test precedure is being

( developed to detec* flavs of a s=all enough size to provide assurance =f

1:ued integrity based upcn a :=servative '-*~~"-* =echanie 's evaluati n.

1 4-13 Amendment No. 60 l

TA3LE h.2-2 A. 513'.'E!1*.A*TCE CAPSULE I'!SER**0N L '4"!CFEJAl SCHEUI.E AT 2C-2 (Net s : "'his schedule vill be revised at a later date pending the restart schedules of 2C-1 and 2C-2) Schedule Capsule resirnatien Insertien 'Jithdrsval CC-1A 2C-2 Start-up b d of 3rd Cycle OC-13 S d of 1st Cycle E d of 6th Cycle "".C-lO b d of 6th Cycle 2d of 15th Cycle OC-II Reu0ved end of ist Cfele of 2C-1 _v_ a. .r .a. k. u. .m.,. r _ ~.:- ...a..r.n.. u. .n. c.~ e e ...,..-e.:-.-......, _vJ&. .A.., ,,,. r. s.vue

a. vR.:

.a _. . c u... :._ m c. su a. -a Carsule Desi: nation Insertien '41thd-sval CC-lC h d of 2nd C ele h d of 5th Cycle f i l l l I l l i l r I i 4-27a Amendment No. 60 1 t I l t

,s o UNITED STATES m,'.j NUCLEAR REGULATORY COMMISSION j - '(# wAsmucTON. D. C. 20555 / i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ] SUPPORTING AMENDMENT NO. 60 TO FACILITY OPERATING LICENSE NO. DPR-50 AND EXEMPTION TO APPENDIX H OF 10 CFR PART 50 I METROPOLITAN EDISON COMPANY THREE fille ISLAND NUCLEAR STATION UNIT NO. 1 DOCXET NO. 50-289 I Introduction By letter dated July 9,1980 (TLL 301), Metropolitan Edison Coreany (Met Ed) requested that an exemption to Appendix H of 10 CFR 50 Paragraph II.C. 4 be granted allowing the indefinite operation of the Three Mile Island Nuclear Station, Unit No.1 (TMI-1) with one of the remaining reactor vessel surveillance capsules being irradiated in Crystal River. Unit No. 3 (CR-3) rather tnan in TMI-2. Met Ed, by letter dated April 11, 1980 (TLL 165), also requested approval of a procosed change to the Technical Specifications (TSs) consistent with the requested exemption. The basis _ for this request is to provide an alternative to the capsule that is in TMI-2 reactor, which is inoperable and is not expected to restart in time to conduct an adequately integrated surveillance program. In lieu of putting a backup surveillance capsule currently in storage in the TMI-l pressure vessel,- it will be placed in a host reactor, CR-3, for irradiation. In addition, data from capsules from other irradiation programs will provide input to the TMI irradiation program. This overall program is an integrated surveillance program, in which all presently operating facilities with B&W 177 fuel reactor asserblic: are participating. TMI-l contains the B&O 177 fuel reactor assemblies and is considered a particioating memoer.

Background

Neutron irradiation causes the vessel material reference nil ductility temperature, RT to increase with time and the material fracture toughness properties to deMa,sewithtime. These irradiated properties are used to establish pressure-temperature operating limits in accordance with Appendix G 10 CFR Part 50. 10 CFR Part 50, Appendix H, " Reactor Vessel Material Surveillance Program Requirements", requires a material surveillance program for reactor vessels to monitor changes in the fracture toughness properties of ferritic materials in the vessel beltline region resulting from their exposure to neutron irradiation and themal environment. Under this program, fracture toughness test data are obtained from material scecirens periodically withdrawn from the reactor vessel. Paragraph II.C.4 of Appendix H provides guidance for integrated surveillance programs for multiple reactors Iccated at a single site. However, Paragraph II.C.4 of Appendix H does not permit [' [ /. Mdk

TMI-l ' the sample of one reactor vessel material to be irradiated at another site. The intent of this provision is to assure that reactor vessel sample material will be exposed to neutron energy spectra and the environmental conditions similar to that to which the reactor vessel is exposed during its service life. Discussion & Evaluation The original TMI-1 design included three reactor vessel surveillance specimen holder tubes (SSHTS) located near the reactor inside vessel wall. The inte-grated program for TMI-l was approved as part of Amendment 29 issued April 22, 1977. Furthermore, similar integrated programs for other facilities with B&W 177 fuel assemblies were approved by the Consnission, and exemptions were granted for those facilities with the host reactors at other sites. To date, the status of the TMI-l surveillance program is that one surveillance capsule has been removed from the TMI-1 reactor vessel and tested (removed prior to the iqtiatign of the integrated program). This capsule received a fluence of 1.1 x 10' n/cm. Test results showed that weld metal (designated WF-25) is the limiting vessel material. One TMI-1 capsule was installed and still exists in the TMI-2 reactor vessel. The remaining four TMI-l capsules are in storage. Due to the'THI-2 incident,it is anticipated that TMI-2 will not be operational for at least several years. Therefore, the licensee, by letter dated April 11, 1980, requested an amendment to the TSs of TMI-1 that would pennit one of the TMI-l capsules currently in storage to be irradiated in the CR-3 reactor vessel. Because this request resulted in having the host reactor offsite for the TMI-l integrated surveillance program, Met Ed, by letter dated July 9,1980, requested an exemption from 10 CFR Appendix H. The licensee proposed that a capsule now in storage be placed in the CR-3 vessel at the end of the second cycle and withdrawn at the end of the fifth cyge. Dyringthis period, the capsule is expected to receive a fluence of 8.2 x 10 n/cm. This fluence is approximately equal to the fluence at the 1/4T location in the TNI-l reactor vessel wall at 22 effective full power years (EFpY). The TMI-l surveillance weld metal, UF-25, is also contained in a B&W research capsule being irradiated in CR-3. This capsule contains not only tensile and Charpy specimens but also several sizes of compact fracture toughness specimens. The test results on this capsule should be available by the end of IM. Finally, irradiated data on WF-25 will be obtained from a Naval Research Laboratory (NRL) program sponsored by NRC. This data should be available in the early 1980s. In regard to installing the capsule in TMI-1, part of Amendment 29 included studies of methods to install the redesigned SSHTS in TMI-1. These studies indicated that substantial difficulties would be experienced primarily because precision machinery alignment and inspection must be performed remotely and under water. Although such problems do not in themselves justify reTief from a requirement to reinstall the SSHTS in TMI-1, they would cause signi-ficant radiation to personnel. Based on excerience in removing the SSHTS at TMI-l and other reactors, B&W estimated that installing SSHTS in irradiated reactors would result in personnel exposure of about 100 man rem / reactor. The licensee reviewed this matter based on the existing conditions of TMI-l (i.e., shutdown for an extended period) and concluded an exposure of about 100 man rem would be applicable to the present conditions at TMI-1. This is due to the increased fluence that the reactor internals have been exposed to since the initial study has been r

b j TMI-l i made, which on the other hand would be offset by the decay of the short half life isotopes due to the long shutdown period. This matter was discussed with the licensee and the staff agrees with this assessment. The B&W integrated surveillance program was initiated in 1977. Since then one capsule originally belonging to Oconee 1, 2 and 3, Arkansas 1 and CR-3 reactor vessels has been removed from the host vessel and tested. A second capsule for Oconee 1, 2 and 3 and Arkansas 1 is currently being evaluated. Data generated from these capsules are satisfactory. The integrated surveillance program is con-sidered to be working as planned in monitoring radiation effects of the pressure vessel materials. Therefore, there is no need at this time to consider a limiting period to the exemption. From our review, we conclude that the TMI-l surveillance progran supplementea ey data from NRL and B&W research programs,will provide sufficient data to monitor ' ). radiation damage on the TMI-I reactor vessel weld metal throughout service life. Data on the TMI-l vessel base metal will be generated only from the TMI-l surveil-lance capsules. Since base metal is not the limiting material, we conclude that the data from the surveillance program will be sufficient to monitor radiation damags on base metal. Furthemore, we have determined that the dimensional design, the themal environment and the neutron flux distribution and the energy spectrum of the CR-3 and TMI-l reactor vessels are so similar that changes in mechanical properties due to irradiation effects will not be affected whether capsules are irradiated in CR-3 or in TMI-1. We find that irradiating a TMI-l surveillance capsule in CR-3 does not reduce the effectiveness of the surveillance program and the intent of the provisions of Paragraph II.C.4 of Appendix H are being met. Based on the above, we conclude that the proposed program to irradiate a TMI-1 surveillance capsule in the CR-3 reactor vessel is acceptable. We find that an exemption to the provisions of Paragraph II.C.4 of Appendix H of 10 CFR Part 50 is authorized by law and will not endanger life or property or the corcon defense and security. Moreover, since the exemption allowing irradiation of the TMI-1 surveillance capsule in CR-3 will avoid approximately 100 rc t-rems of occupational exposure that would result if the exemption were not granted and the surveillance capsule had to be inserted into the TMI-l vessel and since the exemption will allow the completion of the pressure vessel material sur-veillance program for THI-I without such an occupational dose, we find that the exemption is in the public-interest. Accordingly, we find that the exemption i should be granted. 1 The existing TSs pemit the reactor surveillance program for TMI-l to be irradiated only in TMI-2. We agree with Met Ed that the surveillance program cannot be continued in TMI-2 due to its present inoperable condition which is expected to exist for several years. The proposed TS change will pemit a backup surveillance capsule currently in storage to be irradiated in the CR-3 reactor vessel. We find this change acceptable because this capsule containing reactor vessel sample material of TMI-1, when irradiated in CR-3, will be exposed to the neutron energy spectra and environmental conditions similar to that to which the TMI-l reactor vessel is exposed during its service life. \\ i l l

h t i Environnental Consideration We have determined that these anendments do not autheri:e a chant e in effluent types or total ariounts nor an increase in power level and will not result in any significant environmental impact. Having made this deternination, we have further concluded that these amendments involve an action which is insignificant from the standocint of environmental impact and pursuant to 10 CFR 551.5(d)(4) that an environmental imcact statement, negative declaration or environmental impact appraisal need not be prepared in cornection with the issuance of these amendments. Conclusi on We have concluded, based on the considerations discussed above, that: (1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the healtn and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Comission's regulations and the issuance of tnese amendments will not be inimical to the comen defense and security or to the health and safety of the public. Moreover, based on the considerations discussed above, we conclude that an exemption from Paragraph II.C.4 of Appendix H of 10 CFR Part 50, permitting irradiation of a TMI-1 surveillance capsule in CR-3,is in accordance with law, will not endanger life or property or the corron defense and security and is otherwise in the public interest. Dated: January 22, 1981

.o 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCXET NO. 50-289 METROPOLITAN EDISON COMPANY, ET AL. NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND GRANT OF EXEMPTION The U. S. Nuclear Regulatory Comission (the Commission) has issued Amendment No. 60 to Facility Operating License No. DPR-50, issued to Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (the licensee) for operation of the Three Mile Island Nuclear Station, Unit No.1 (the facility) located in Londonderry Township, Dauphin County, Pennsylvania. The amendment is effective as of its date of issuance. The amendment revises the Technical Specifications to permit irradiation of the facility's reactor vessel surveillance specimens at Crystal River Unit No. 3. In connec-tion with this action, the Commission has granted an exerption to the provisions of Appendix H to Title 10 of the Code of Federal Regulations Part 50. Appendix H requires the irradiation program to be performed within the facility's vessel or at the same site for multi-reactor sites. The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate finoings as required by the Act I and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth l in the license amendment. Prior public notice of this amendment was not required l l since the amendment does not involve a significant hazards consideration. i As set forth in the Comission's letter to the licensee dated January 22, 1981, ( the exemption is authorized by law, will not endanger life or property or the comen defense and security and is otherwise in the public interest. l

7590-01 i

b ~ The Comission has determined that the issuance of the amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of the amendment. For further details with respect to this action, see (1) the licensee's application for amendment dated April 11, 1980 and the licensee's request for i exemption dated July 9,1980,(2) the Corrnission's letter to the licensee dated January 22, 1901, (3) Amendment No. 60 to License No. DPR-50, and (4) the Comission's related Safety Evaluation. All of these items are available for public inspection at the Comission's Public Cocurent Rec =,1717 H Street, N. W., Washington, D. C. and at the Government Publications Section, State Library of Pennsylvania, Box 1601 (Education Building), Harrisburg, Pennsylvania. A copy i: of items (2), (3) and (a) may be obtained upcn request addressed to the U. 5. Nuclear Regulatory Comission, Washington, D. C. 20555, Attention: Directer. Division of Licensing. t Dated at Sethesda, Paryland, this 22nd day of January 1981. FOR THE NUCLEAR REGULATORY COMMISSION O b Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing l l l l 1 L e}}

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