ML20031D271

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Response to Wi Environ Decade 810924 Basis for Contentions. Proposed Contention 3 Should Be Admitted as Basis Has Been Provided.Proposed Contentions 4-7 Should Not Be Admitted Since No Basis Provided.Certificate of Svc Encl
ML20031D271
Person / Time
Site: Point Beach  
Issue date: 10/07/1981
From: Barth C
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:
Atomic Safety and Licensing Board Panel
References
ISSUANCES-OLA, NUDOCS 8110130198
Download: ML20031D271 (53)
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{{#Wiki_filter:10/7/81 'dC0q}9 1 UNITED STATES OF AMERICA E-0CT S Jgg _g NUCLEAR REGULATORY COMMISSION f se nuetuIsID*,.~ BiFORE THE ATOMIC SAFETY AND LICENSING BOARD 2j Q In the Matter of ) s WISCONSIN ELECTRIC POWER COMPANY ) Docket No. 50-216-OLA 50-301-0LA (Point Beach Nuclear Plant, (Repair to Steam Generator Tubes) Units 1 & 2) NRC STAFF RESPONSE TO WISCONSIN ENVIRONMENTAL DECADE'S BASIS FOR CONTENTIONS DATED SEPTEMBER 24, 1981 1. INTRODUCTION During a telephone conference held on September 16, 1981 among the Staff, Licensee, WED and Licensing Boara, the Licensing Board requested WED to provide the hsis for proposed contentions 3 through 7 and requested the Staff and Licensee to respond thereto. WED, by letter dated September 24, 1981 purported tc provide the basis for their proposed contentions 3 through 7. II. DISCUSSION A. General Principles Applicable to Admission of Contentions As a general matter, for the contentions proposed to be admissible they must comply with the requirements of 10 C.F.R. 9 2.714(b) and l applicable Cocnission case law. See, e.g., Northern States Power Co. l (Prairie Island Nuclear Generating plant, Unit Nos. 1 and 2), ALAB-197, 6 AEC 188, 194 (1973), aff'd, BPI v. Atomic Energy Commission, 502 F.2d 424, 429 (D.C. Cir.1974); Duquesne Light Co. (Beaver Valley Power D507 Station, Unit No. 1), ALAB-1C3, 6 AEC 243, 245 (1973); 10 C.F.R. 9 2.714(h). Cex.gified o!hooh[6

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ADO ^ PDR -Ab9 10 C.F.R. 9 2.714(b) requires that contentions which intervenors seek to have litigated be filed along with the basis for those contentions set forth with reasonable specificity. A cnntention must be rejected where: (a) it constitutes an attack on applicable statutory requirements; (b) it challenges the basic structure of the Commission's regulatory process or is an attack on the regulations: (c) it is nothing more than a generalization regarding the intervenor's views of what applicable policies ought to be: (d) it seeks to raise an issue which is not proper for adjudication in the proceeding or does not apply to the facility in question; or (e) it seeks to raise an issue which is not concrete or litigable. Philadelphia Electric Co. (Peach Bottom Atomic Power Station, Units 2 and 3), ALAB-216, 8 AEC 13, 20-21 (1974). l The purpose of the bases requirement of 10 C.F.R. 9 2.714 is to assure that the contention in question does not suffer from any of the infirmities listed above, to establish sufficient foundation for the contention to warrant further inquiry of the subject matter in the { proceeding, and to put the other parties sufficie'Itly on notice "so that they will know at least generally what they will have to defend against or oppose". Peach Bottom supra at 20. From the standpoint of bases, it is unnecessary for the petition "to detail the evidence which will be offercd in support of each contention". Mississippi Power & Light Co. (Grand Gulf Nuclear Station, Units 1 and 2), ALAB-130, 6 AEC 423, 426 (1973). Furthermore, in examining the contentions and bases therefore, a licensing board is not ;) reach the merits of the contentions. ~ Duke Power Company (Amendment to Materials License SNM-01773 -

  • i Transportation of Spent Fuel from Oconee Nuclear Station for Storage at McGuire Nuclear Station), ALAB-528, 9 NRC 146, 151 (1979); Peach Bottom, supra at 20; Grand Gulf, _s_upra et 426. This principle was reaffirmed in Houston Lighting and Power Company (Allens Creek Nuclear GeneratingStation, Unit 1),ALAB-590,11NRC542,548(1980) where the Appeal Board pointed out that, with regard to basis, all that is required at the petition stage is that the petitioner state the reasons for its contention. This Licensing Board correctly paraphrased the Allens Creek requirement on transcript page 68 lines 8-12.

In sum, at the petition stage, although a petitioner need not establish the validity of its contentions and the bases therefore, it is incumbent upon the petitioner to set forth contentions and the bases (i.e., reasons) therefore which are sufficiently detailed and specific to demonstrate that the issues raised are admissible and that further inquiry is warranted, and to put the other parties on notice as to what they will have to defend against or oppose. This is rarticularly true where, as here, a hearing is not mandatory, in order t3 asf ure that an asserted contention raises an issue clearly open to adjudication. Cincinnati Gas & Electric Company, et al. (William H. Zimer Power Station), ALAB-305, 3 NRC 8, 12 (1976); Gulf States Utilities Company (River Bend Station, Units 1 and 2), ALAB-183, 7 AEC 222, 226 at n.10 (1974). Based on the supplemented information regarding basis submitted by WED, and as set forth below, the Staff believes only Petitioner's proposed contention 3 meets the requirements of 10 C.F.R. 1 2.714(b) and accordingly should be admitted as an issue in controversy in this

a, proceeding. Proposed Contentions 4-7 should not be admitted as issues in controversy in this proceeding. B. Argument as to Admissibility of Proposed Contentions 3-7 The gist of proposed Contention 3 is that the welding involved in the sleeving process will weaken the integrity of each original steam generator tube. The Staff does not dispute that the proposed contention is set forth with sufficient specificity so as to put the other parties on notice as to what they will have to defend against or oppose.

Rather, the Staff did not believe any basis had been provided for raising the contention.

In the supplemental information provided by WED, the reason (i.e., basis) asserted for this contention is the testimony of Licensee's employee, Mr. Porter, before the Public Se Nice Commission of Wisconsin. The emphasized portion of the testimor.y is the statement that there may be "about a 10% reduction in the Jittuate strength" of the tube as a result of the welding. Mr. Porter goes on to opine "that this reduction in ultimate strength is not a significant affect on the tube material." In the Staff's view, the quoted material marginally provides the basis (i.e., reasons) for WED Contention 3. Whether the reduction in ultimate strength is or is not a significant affect on the tube material is the natter Petitioner wishes to litigate. While it would have been preferable for Petitioner to cite to some authority wnj f believes the 10% reduction in ultimate strength will be significant with regard to the integrity el the tube material, petitioner has stated the reasons for raising the contention. Accordingly, the Staff believes WED's supplemental information provides the basis required by 10 C.F.R. 9 2.714

and Allens Creek, ppra, and the contention should be admitted as an issue in controversy. Proposed contentions 4 and 5 allege "an unexpectedly corrosive environment (No. 4) and that the " sleeve will make the eddy current test results extremely difficult and increase the probability that tubes with incipient failures may go undetected and rupture during a loca" (No. 5). As a basis for these ialtiple assertions, WED cites an NRC Staff memorandum dated September 22, 1980 regarding San Onofre. First, the cited memorandum relates to a different facility and there is no showing that the two facilities are identical so that concerns relating to San Onofre would be applicable to Point Beach.1! econd, without delving into S the underlying correctness of that memorandum, the language of the September 22, 1980 Staff memorandum does not appear to provide any basis or support for WED's assertion that there will be (a) an unexpected corrosive environment, (b) extreme difficulty in interpretation of eddy current tests and (c) increase in the probability of tube rupture during a loca. The petitioners, WED, have provided no basis as required by 10 C.F.R. 9 2.714(b) and interpreted by the Appeal Board in Allens Creek, supra, and therefore proposed contentions 4 and 5 should be denied. The Staff memorandum dated September 22, 1980 is attached. (Attachment 1). 1/ Comparison of the FSAR's filed for each facility, in fact, indicate that the San Onofre steam generator tubes are smaller in diameter ~ and have thicker walls than the tubes at Point Beach. Proposed contention 6 alleges that sleeving will reduce core cooling under accident scenarios "to an extent not bounded in previous safety analysis." WED's September 24, 1980 letter alleges as the basis for this contention, the application for amendment 95 dated December 10, 1980 to San Onofre's Unit 1 operating license. The cited application amendment number 95 does not support the assertion that sleeving will lead to unanalyzed accident scenarios at San Onofre. In fact, the licensee's conclusion that the amendment does not involve an unreviewed safety question as defined in 10 C.F.R. 6 50.59, nor does it present significant hazards considerations not described or implicit in the Final Safety Analysis implies the contrary. Amendment Application, p. 2. In any event, WED has made no showing that these facilities are so ;dentical that a concern about San Onofre would be relevant to Point Beach. Therefore, having failed to provide any basis, the proposed contention should be denied. The San Onofre application for amendment is attached hereto. Proposed contention 7 alleges that the licensee will use untrained workers to perfonn the sleeving and as basis, the September 24, 1981 letter of WED cites an alleged newspaper article that " shoddy repairs" were performed at an unnamed reactor. Assuming for purposes of intervention here that there were " shoddy repairs" at an unidentified reactor, this provides no basis for the assertion that Wisconsin Electric Power w;11 use untrained workers to perform the sleeving of steam generator tubes. There simply is no nexus between the alleged basis and the contention, and lacking basis the proferred contention should be denied. i

_7 III. CONCLUSION WED has provided basis for its proposed Contention 3 as required by 10 C.F.R. 9 2.714 and therefore this contention should be admitted. However, WED has failed to provide basis for its proposed Contentions 4-7 and these should not be admitted. Respectfully submitted, q Charles A. Barth Counsel for NRC Staff Dated at Bethesda, Maryland this 7th day of October, 1981. .--y----- ,_,,y- ,y- ,,,_,,..y y .m--

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ATTACHMENT 1 t

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,,. C. 20Gv t. /e September 22, 1980 3* Doeket ifo*.* 50-206 LICENSEE: Southern California Edison Company FACILITY: San Onofre Unit No. 1

SUBJECT:

SUMMARY

OF JULY 31, 1980 MEETING TO DISCUSS SLEEVING OF THE SAN ON0FRE UNIT NO.1 STEAM GENERATOR TUBES NRC and Southern California Edison (SCE) representatives met" in Bethesda, Maryland, on July 31, 1980, to discuss the sleeving design concept for steam generator tube repair and plans to decontaminate the steam generator bowl prior to sleeving. The meeting attendees are listed in Attachment 1. SCE requested the meeting to present details of the design concept of sleeving steam generator tubes 'with leak-tight sleeves as a repair mechanism for tubes that had undergone intergranular attack. In addition, SCE repre-sentatives presented data and a description of their proposed method of decontaminating the steam generator bowl with a hydro grit stream composed of water and magnitite. A copy of the material presented at the meeting (minus Westinghouse proprietary data) is enclosed in Attachment 2. The major items discussed during the meetings are suninarized below': 1. The NRC staff indicated some of their concerns related to the sleeving process that need to be addressed. These concerns included: inspectability of sleeved tubes; leak tightness of the sleeves; mechanical strenght of sleeved tubes; radiological exposure to workers during the repair program; pluggability of sleeved tubes; and effects of stagnation of secondary water between the sleeve and tube. 2. The sleeves installed at Palisades were of a different design than proposed for San Onofre Unit 1. The Palisades sleeves were not designed as leak tight. 3. Cold leg inspections had been performed and four (4) tubes had indications of Phosphate thinning. Approximately 1400 tubes were inspected previously and 107 tubes examined during this inspection. 4. Pressure testing was perfvemed on 25 tubes in the hot leg up to 3000 psig and no tubes leaked. The tubes are designed for a differential pressure of 2200 psig following an accident. DVPE CO 90 l o 2 Y Ooq 3

5. SCE preposes to sleeve approximately 2500 tubes per steam generator or approximately 7500 tubes out of the 11,382. 6. SCE has perfomed an evaluation.and has concluded that the sleeving does not constitute an unreviewed safety question. 7. SCE has estimated that worker exposures will be 250 man rem for inspection plus tube pulling and approximately 1000 man rem for steam operator repair. ALARA aspects w"1 be covered in the August 15, 1980 meeting. 8. The NRC staff wants design details on the mechanical plugs in time to include this aspect in our review. 9. SCE requested NRC approval to install sleeves and any remaining concerns by September 10, 1980. SCE plans to return San Onofre Unit 1 to power about November 1,1980. b $: " Stanley J. Nowicki, Project Manager Operating Reactors Branch #5 Division of Licensing Attachments: As stated l 1 l l l

Mr. R. Dietch September 27 1980 CC .. Director, Technical Assessment Charles R. Kocher, Assistant' General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459) Resemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Crystal Mall #2 SSamuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Pagion IX Office ATTN: EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisc0; California 94111 San Diego Gas & Electric Corpany P. O. Box 1831 San Diego, California 92112 Resident Inspector c/o U. S. NRC P. O. Box AA Oceanside, California 92054 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, Califor11a 92676 Mayor City of San Cleaenta San Clemente, California 92672 Chai rman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiclogical Health Section 714 P Street, Room 498 Sacramento, California 95814

ATTAC WENT 1 ATTENDANCE l. S. J. Nowicki NRC 2. R. W. Krieger SCE 3. E. G. Igne NRC 4. C. Y. Cheng NRC 5. B. L. Curtis SCE 6. W. J. Collins NRC l 7. F. Almeter NRC l 8. B. Turovlin NRC 9. C. Hinson NRC 10. J. Wing NBC 11. B. D. Liaw NRC 12. S. S. Pawlicki NRC 13. G. Georgiev NRC 14. R. Dermann NRC 15. D. Huang NRC 16. E. Murphy NRC 17. R. Emch NRC 18. F. Witt NRC ) 19. L. Barrett NRC 20. E. Brown NRC 21. H. Conroad NRC 4 j 22. L. Frank NRC 23. D. Meoli NSD W 24. P. Dtosa W NSD 25. T. Timmons W NTD 26. A. Klein W NTD 27. E. Murphy W BLO 28. C. Hirst W NSD 29. J. Taylor W NSD 30. P. Matthews NRC -rr w v--, - - - - - ~,, -,-r, +-,,,,w--, .,--n,-- .,e---- gm -,,._,-----.-,--,r--y., .--~.-,,e, ,,,.- - - + - --wm, y - - - - - - --,.r,-

ATTACHMENT 2 SCE MEETING WITH NRC JULY 31, 1980 AGENDA INTRODUCTION SCE PROGRAM PLAN STATUS UPDATE SCE E DECONTAMINATION PROCESS STEAM 6ENERATORIUBESLEEVINGPROCESS E LICENSINGCONSIDERATIONs SCE StwARY SCE I 1 e -.n,--, eon,.g y.---- nwg- _-p-,y,, p.- y, ,-,y ,.4e- ,rgt ey-,, --,e , - -ws . g -w,. ---w>v,-e-- ,,m m

/4TIONS CONTINUE RPC EDDY CURRENT TESTI,'NG INDIVIDUAL PRESSURE TEST 5 LEAKERS IN SG-C ~. \\ INCIVIDUALPRESSURETESTTUBES(TESTFIRSTWITHRPC) ~: u i': - ~- PULL TUBES (TEST FIRST WITH RPC)

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RCS PRESSURE TEST OF BUNDLE I. SS PRESSURE TEST OF BUNDLE PLUG TUBES CHE51STRYFLUSHING -~ INSTITUTE CHANGES IN CHEMISTRY CONTROL REDUCED,CONbiTIONS OPERATJONS - I:.. -... e REPAIR I-

OVERALL OBJECTIVE Return the unit to power at earliest date consistent with safe operation. REFERENCE APPROACH : Install leak tight sleeves in the. largest number of tubes consistent with logistics and channel head access, with the intent to return the unit to 100% power operation. ALTERNATE APPROACH : Mechanically plug the minimum numbe,r of-tubes consistent with sife operation. Unit will be returned to operation at reduced conditions to ar est corrosion in unplugged tubes. OPERATIONAL BASIS : Proceed in parallel with the following major tasks o Define zones for repair by means of eddy current testing, tube removals, Individual tube pressure tests and primary hydro of tube bundle o Develop sleeving process and installation procedure Design and qualify temporary plug to permit. recovery o of tubes removed fr.om operation Proceed with expedited production of 3/4" conventional-o plugs o Adapt abrasive DeCon System for operation in Model 27 SG's ~ e ?.

j RPC "A" g l l g Tube Pull Correlate RPC Tube Press S/G A RPC & Bobbin B&C Tes t in-Si tu 4 In SG-A Data yen _.y.. yf.. y-y ~ - - - - - ' - ~ ' - himary l Cear Pressure On-Site Define _ m es Test of RT of OK Hydro Safety ~ r' in As s es sment-Tubes in Tubes SG A, 8, C Lab Not OK _.9f._.__.. if y Vald Bare Sleeve as No Tes- - - - ~ II'*** 4 Zones Defined Holes Practical Zones 1 Y y Plug Secondary Remainder and/ Hydro or Operational h Constrai nts g Repair as Required - - = y Primary 4 Hydto h Seconda ry Hydro t I Repair as Required I ECT Sleeves + Chem Flush Return to Power

SUMMARY

OF TUBE EXAMINATION R24-C71 (DISTORTED DENT) 95% MAX. WALL PENETRATION SEM & MET. COMPLETE R31-C28 (GRAY TUBE) S70% MAX. WALL PENETRATION SEM & MET. COMPLETE R13-C67 (DISTORTED DENT) 590% MAX. WALL PENETRATION SEM & MET. COMPLETE IGA s250' Ril-C69 (NON DISTORTED DENT) s90% MAX. WALL PENETRATION SEM & MET. COMPLETE IGA s180' R32-C71 (LARGE DENT) EXAMINATION IN PROGRESS IGA >50% BY VISUAL EXAMINATION R14-C70 (NORMAL T/S SIGNAL) BURST TEST COMPLETE 15,000 PSI MAX. PRESSURE s1/8" LONGITUDINAL CRACK VISUAL EXAMINATION COMPLETE s50-60% WALL PENETRATION BY VISUAL EXAMINATION R17-C52 (CREVICE INDICATION) s80% MAX. WALL PENETRATION MET. COMPLETE 9 m +

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F TUBE REMOVAL AND EXAMINATION Reasons: 1. To verify RPC data 2. To provide sludge free sample for burst teit Tn laboratory 3 To outline boundary for sleeving Sample Removal: Samples #1 & 2: Periphery tube, Judged to have a small dent, but in good condition, i.e., <20% wall penetration. This tubTwifl bius'ed to, ~ obtain information to support items #1 and #3 above. 5 Samples #3, 4, & 5: Tubes judged to have penetration of <20%,35%, and 62% as detenmined by RPC. Examinations and laboratory burst tests of~ these tubes will be used to support items #1 and #2 above. Sample #6: Central region tube judged to be a non-dented " goo,d" (NDD) by RPC. Examination of this tube will be used to support items #1 and

  1. 3 above.

Logic: Sample #1 will be removed first and a preliminary examination undertaken on site. This examination will consist of Visual Examination, Radiography, and Eddy Current testing. The result of this examination will enable a preliminary evaluation to be made on the validity of RPC and the condition of the corrosion free periphery area. Sample #6 will be removed second to establish the condition of the central corrosion free region. If sample #1 & #6 agree with expected results. tubes #3. 4, 5 and' 2 Gill then be removed to obtain further confidence in the RPC data and to obtain repre-sentative tubes for laboratory pressure / leak rate / burst tests. if sample #1 and 16 da not agree with expected results, tubes #3, 4, 5 and 2 will not be removed since there will be uncertainty as to the actual tube condition and the RPC data is Judged to be suspect. s-,--- -.,-.n

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COLD LEG TUBE REMOVAL AND EXAMINATION Reasons: To determine the need for additional tubing and to establish the need for sleeving the cold leg side of the steam generators. Sample Removal: The sample to be removed should be one showing a large indication by bobbin and/or R.P.C. Logic: The sample will be removed in a manner that will expedite on site determination of tube conditions. This on site examination will consist of radiography, eddy current and visual examination. This examination will provide the basis for a decision regarding immediate tube procurement. The tube will then be sent to Pittsburgh for a more critical ex, amination to determine its condition. Logic Chart: See attachment. 0 O -p-s y .s -e

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INDIVIDUAL PRESSURE TESTS 1. Define good tubes / zone boundaries. Pressurize to 23000 psig if no leak, tube con withstand accident conditions If tube leaks, evaluate options a) Sleeve b) Plug c) Operate at reduced conditions d) Combinations of a) to c). 2. Establish integri ty of corroded tube a) In geod zones b) In active zones Press Test ~ ~ ~ ~ ~ 1r ____V Leak at If no leak e _... 2 3006-p s I y <2200 . Leak @ 9f 9P 2200 - 3000 psi Eval total Confirm integrity -outside-of zone y Sleeving Eval options 1. Sleeve 2. Plug .~ 3 Reduced options ~ Implement opt ons _

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/* ~ ~ ~ ' ,t, SCE #1/A TUBE PRESSURE TEST SELECTION R-C RPC CONV. TYPE Arc' ZONE 1 A-13-70 55% 2h0* NDD 1 13-71 89 240 NDD 2 11-60 97 350 NDD 4 ZONE 2 A-12-33 50% i80* NDD 1 13-42 56 240 80% 2 9-43 97 180 45% 3 12-27 <20 90 NDD 5 ZONE 3 A-24-39 69% 120' NDD 1 24-43 64 150 NDD 1 24-42 83 120 NDD 2 17-63 96 180 NDD 3 17-48 94 210 NDD 4 ZONE 4 A-35-47 55% 90' NDD 1 38-51 88 210 NDD 2 38-53 91 180 33% 3 39-58 96 150 NDD-3 29-73 96 360 NDD 4 NDD 5 ZONE 5 A-34-75 NDD 43-59 NDD NDD 5 NDD 5 40-34 NDD NDD 5 28-18 NDD NDD 5 12-13 NDD NDD 5 8-90 NDD NDD 5 ZONE 6 A-15-54 NDD 28-52 NDD NDD 5 ZONE 1 - S/L Accessible Manway TYPE 1 - <80% 2 - S/L Accessible ~ Nozzle 2 90 Large Arc Length 3 - Quiet Centre 3 100 Small Arc Length 4 - Active Zone R34-40 C40-60 4 194% Large Arc Length 5 - Outer Periphery 5 520 or NDD 6 - Central < =, - - - -, - - -,---g rw-r, ,n ..c ...n-n -, - ---e-- s

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i BASIS FOR DEFINING ACTIVE /lNACTIVE ZONES ~ 1 1) Plot p"". and bobbin EC data. Define zones encomposing all indications at top o tubesheet - SG-A. l 2) Validate zone boundaries with results of tube pressure tests and tube pull results. 3) Obtain RPC data for B and C and r7 peat step 1). 4) Establish zone boundaries with similitude arguments from SG-A tube pressure tests and tube removal results s 5) Confirm by results of primary hydro tests. 4 1 n.- ..,,_.,-.--, - - ~.,, --. - -... - - -. - -,,.... - -. - -.., -. _,. -., -

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e Conditions for Power Operation y ... T( '.001 - T 00'i;-~ -- Sleeves sleeves ] l Zones are Zones not Y Defined Deied Fu M -Cond i t i ons __ Oper4 tion _. li Plug / Plate .... p._ - ] ^ Reduced JL Maximum Plug /P1 ate Operating 0perate Conditior Condi tions ~ ~ - Establish Plug Establish Cri teri a Plug Crit. 1 ,-w-, ---,n-. ,,,,a,.

_ =. l ECDN PRXESS IBELCMBlT RR STEA9 GEERATOR OiANNEUiEAD MAINTENANE ACTIVITIES HIGi PESSLE HATER OE11 cal DR/ GRIT HYDR 0/ GRIT

HYDR 0/ GRIT GRIT OPTIGS - E0RIC ACID - PKETITE - AllNIFA EXPECTED SlFFAE DF - BORIC ACID 5 - 10 - t%GNETITE 20 - 50 - AL&11t!A 20 - 50 i 1 e. c..

MAGtETITE GRIT E&tBlIED PP0E19 HI IF - 10 OR GEATER ECYCLE - filf!!MIZE WASTE V0BIE

e >g M M. E o = RP c t UM E l i i s IG5 D 5 U y H EP s R M w P O I o g T L E E I L. a CR F R UE C ii U V S T t '? iMI Mp A F R G c L F Pl l E I ) U ~ E K G P '2 c RN C pNI UA g y ST P i h rCP N l P y xu S h X D E K D = E*L TT~DLS 'g =. E EA b I 6I HC A u-AR S V L g WG C T L .i w EO N e VR O v l ET L P P LNc C R M "N Q Y O O D ~\\ T O - C l P T A P l P k-A AD g x-R O PE L" EE F SF fl l l i! J< l N. ) R EFM 6 U H R C TI. i A "y, A RD T I RlGo P. P = M u P S M SE L Z r Z0N h [ s_ u h il ]i' ,l 1 l i

f EXPERIFflE BCRIC ACID GRIT - WE THRU SYSTEM - IEElfPIENT F10GPAM nUAUFICATI0fl C0WLETE - POINT BEAOL mE OWiEL HEAD - to SIGNIFIC#!T IF - TAK I, SIX OMEL HEAD - 2.5 DF. IWSilTATE GRIT - ECYCLE SYSTEM OllALIFIED DURING ETUBE Pl0GPAM - HOT TEST SUFFAE DF 0F GRATER iPRI 10 ACHIEWD

1 TE0f11 CAL ISSLES 1. QAD 00lTION AFTER ECON 2. ESIDUAL GRIT - DEilSTRY COPATIElf - R.C. PltP SEALS /CRU1 3. DILlRION 6' 4. PASTE FMELING

EXPECTED WASTE PER STENi GBERATOR lliEE TONS T f%GtETITE GRIT, (APPROXIf%TELY 5 MICR0 CURIES PER GP#D EIGHT TO 11ELVE, 55 GALLON DRLf1S 600 GALLON T RECYCLE WATER (0.5 MICR0 CURIES PER MILLILITED 2000 GALLONS OF RIfEE leTER -e

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= w ,r,

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PELIMINARY LIG4SIllG INFORi% Tim SCEDLIE PELIMlllARY DISWSSIWS W/NRC 6/18,7/1,7/10 PESENTATION OF PROGPM Pl#1 .7/22 NRC EETING TO DISCUSS SLEEVING 7/31 NRC EETING TO UPIRTE INRR% TION 8/15 NRC EETING & SLEEVI!!G EPORT 9/1 NRC APPROVAL TO INSTALL SLEEVES 9/10 FINAL 50.59 REPORT 10/7 NRC APPROVAL TO EStfE OPERATIm 11/1

RJRPOSE OF EETING e OPENING TEGlilCAL DIS 0JSSION OF 1}E SE SLEEyING PROGPAM e ESI&l AND PROESS DISClJSSIQ1 e ALA% QNSIERATIONS e ESTABl.ISH UN1B4TS OF 8/15 WETING S I i e l r l l f

SLEEVING PROGPA'i PURPOSE TO IDELOP A EPAIR PROEDURE FOR A IERCTIVE TllBE AS AN ALTERNATE TO PLUGGING, TRIS EXIDOING STE#i ENEPATOR LIE DOALL TEQUICAL OELECTIW. DEVELOP A LEAK TIGHT BmD BEMEN SLEEVE #0 TUBF IEVELOP A EMOTE TOOLING INSTALLATIm SYSTEM POTENTIAL SEALING ETHODS

~ _

BRAZING E0%NICAL WELDING l P0NIAL EXPANSIm ETHWS HYDRAULIC ROLL l l l

i t s SERIES 27 ,e 999195939 ErlIR e5a3 GI M1115nin Lth7L54%I aft 515553949 4145434,93sn555 3:1917 Is13 le s9114513 il 4 7 5 3 I I COLUMNS 8C04%949(10 885404828018 7674 12 10646 bis 4 62bC5e%5452504e4&44424038%3412 30282&24 O to IBibies2 10 8 L 4 2 4e e 4y 4 ") oom m-,- f_... .. Ja. - T. -ywL ya .y.-. c_.- 4y ,,g,_- . x y \\_.,. 43 g ( s% s 7 ... N.. 47, -~- 41 Z ip . n h;dq-4o /,2 r -q:- 4. n

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i

    1. A ACTIVITIES o DECW BOWL #O TUBES i

e EMOTE TOOLING e SHIBDING e MDCK-ljP TRAINING e TV SUREILL41E e AININISTRATION ONRDLS e BWIRNEITAL mRROLS = l o f0 DEL #0 f10NITOR EXPOSUES l i i t I i l 1 .. _.... _ _... _ _. _,.., _ _,... _... _. _ _... - _., -... _. _.. _ _.,. _ _ _ _. -. _,...,,. -, - _ -. _... _., _ _. _. -..., _ _ _ _ _, - - ~., _ _ _ _.... -. _. ~ - -..

Licensing Information Schedule Preliminary Discussions w/NRC 6/18, 7/1, 7/10 Presentation of Prog 2<s Plen 7/22 NRC Meeting to Discuss Sleeving 7/31 NRC Meeting to Update Info 8/15 NRC Mtg & Sleeving Report 9/1 Including Zones to be Repaired NRC Approval to Install Sleeves 9/10 Final Revised Reload Safety Evaluation Report 10/7 URC Approval to Resume Operation 'll/l

~ ~.. SLEEVING REPORT LICENSING INFORMATILN e Desic- 0 acept e Design Analysis e Prototype Testing Pressure Testing Thermal Cycling Corrosion Testing e Inspectability Installation Inservice e . Material Compatibility e Installation Concept e ALARA e Criteria for Zones Repaired a 10 CFR 50.59 Design Change Review . - ~...... - -. - -.

( a l Revised Reload Safety Evaluhtion Report Description of Repaired Steam Generators - Inspection Results - Tube Removal and Examination Results - Individual Tube Pressure Test Results - Zones Repaired (Sleeved and/or Pluaged) - Sleeving Report (Referenced) Evaluat' ion of Plant Performance - Reduced Temperature, Pressure and Power - T/H Effects of Sleeving - LOCA Analyses - Non-LOCA Analyses - Functional Set Point Changes ~ Licensing and Technical Specification Changes. ~ x operational Considerations - Chemical Flushing - Chcmical Control Improvements . _ ~. -

0 l ATTACHMENT 2

' ( ( A CE f Southem Califomia Edison Company O a o. som soo id.*j j p. aa44 walnut omove AvrNuc ~. ,_.. p d..,,% g December 10, 1980 - c: 5 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Subject:

Docket No. 50-206 Amendment No. 95 San Onofre Nuclear Generating Station Unit 1 Enclosed are three executed and thirty-seven conformed copies of Amendment No. 95 in Docket No. 50-206. Arrendment No, 95 consists of Proposed Change No.100 to the Technical Specifications incorporated into Provisional Operating License No. OPR-13 as Appendix A. Preposed Change No.100 is a request to revise Appendix A Technical Specifications 2.1, " REACTOR CORE - Limiting Cortination of Power, Pressure, and Temperature," 3.5.2, "Contrcl Group Insertion Limits," and 3.11, " Continuous Power Distribution Monitoring," to allow San Onofre Unit I to be operated as describec in the supporting report, " Reload Safety Evaluation, San Onofre Nuclear Generating Station, Unit 1, Cycle 8, Revision 1," dated October, 1980. This revision to the Reload Safety Evaluation is pr'o'vided to consioer the impact of the core flow reduction resulting from the steam generator mocifications now underway at San Onofre Unit 1. Accordingly, it is respectfully requested that the NRC promptly review anc take appropriate action on the enclosed Proposed Change No. 100 to the Technical Specifications, and the supporting report prior to resumption of power operation which is scheouled to commence in the first quarter of 1981. Also enclosed is Southern California Edison Company's Check No. TOl9756 dated December 4, 1980, in the amount of $4,000.00 as requirsd by 10 CFR 170.22. Very truly yours, Enclosures wea J '8 0 12120 3?? l

(. BEFORE THE UNI'ido S f ATES NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON ) COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY ) for a Class 104(b) License to Acquire, ) DOCKET NO. 50-206 Pcssess, and Use a Utilization Facility as ) Part of Unit No. 1 of the San Onofre Nuclear ) Amendment No. 95 Generating Station ) SOUTHERN CALIFORNIA EDISON COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY, pursuant to 10 CFR 50.90, hereby submit Amendment No. 95. This amendmen' consists of Proposed Change No. 100 to the Technical Specifications incorporated in Provisional Operating License No. DPR-13 as Appendices A and B. Proposed Change No. 100 is a request to revise Appendix A Technical Specifications 2.1, " REACTOR CORE - Limiting Combination of Power, Pressure, and Temperature," 3.5.2, " Control Group Insertion Limits," and 3.11, " Continuous Power Distribution Monitoring," to allow San Onofre Unit I to be operated as described in the supporting report, " Reload Safety Evaluation, San Onofre Nuclear Generating Station, Unit 1, Cycle 8, Revision 1," dated October, 1980. This revision to the Reload Safety Evaluation is provided to consider the impact of the core flow reduction resulting from the steam generator modifications now underway at San Onofre Unit 1. ' \\'hj t/E Ji 801212o413

t (. In the event of confl.ict, the information in this f.mendment No. 95 supersedes the information prEviously submitted. Accordingly, it is concluded that (1) the proposed changes do not involve an unreviewed safety question as def'.7ed in 10 CFR 50.59, nor do tney present significant hazards considerations not described or implicit in the Final Safety Analysis, and (2) there is a reasonable assuranc' that the health and safety of the public will not be endangered by the proposed change. Pursuant to 10 CFR 170.22, Proposed Change No. 100, submitted as Amendment No. 95, is determined to be a Class III chang. The basis for this determination is that the change involves a single safety issue. Accordingly, the fee of $4,000.00 corresponcing to this determination is remitted herewith as required by 10 CFR 170.22. l

C. ( 3. Subscribed on this 5 day of e d, 1980. Respectfully subnitted, SOUTHERN CALIFORNIA EDISON COMPANY By Robert Dietch Vice President Subscribed and sworn to before me this day of d /7/d I AGNES CRABTREE I wann wie. cue== I t$Nta cm[rv 4 i Notary / POD 1ic in ano for the County of I "' #_ E 9__l_Y l[d_E Lds A%geles, State of California Agnes Crabtree My Commission Expires: 47 /f /2. f G l 1 ~ _ _ _ _ _ - _. _ _ _ _ _ _.. _ _ _

f ( a Subscribed on this 2 5 r.5 day of //uss/ RAT, / 780 \\ Respectfully submitted, l SAN DIEGO GAS & ELECTRIC COMPANY i d'/ By

4. x.c- _ -

D. W. Gilman Vice President Subscribed and sworn to before me this A r h cay of W _ DJ jpro c W. A/- dd Notary Public in anc for the Ccunty of San Diego, State of California Anne R. Schmidt / My Commission Expires: / O/,/#.3 sw.,.w,wws3g.3::. :::- 9 ANNE R. SCHMIDT R3TARY PUBUC CAUTORN!A Principal Office ir. Sa a. Diet Cour.ty My Cem:ssic.- Exp. 0ct.11.1983 .vsw.w.srw.:::::: ~ e

( ~5-Charles R. Kocher James A. Beoletto Attorneys for Southern California Edison Company b By N ~ James A. Beolitto David Pigott \\ Samual . Casey Chickeri & Gregory Attorneys for San Diego Gas & Electric Company By ? U David R. Pigott l 4 0 9 9 e G e

^

(, ( UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of SOUTHERN ) CALIFORNIA EDISON COMPANY ) and SAN DIEGO GAS & ELECTRIC ) Docket No. 50-206 COMPANY (San Onofre Nuclear ) Generatino Station Unit No. 1) CERTIFICATE OF SERVICE I hereby certify that a copy of Amendment No. 95 was served on the following by deposit in the United States Mail, postage prepaid, on the 10th day of December , 1980. Henry J. McGurren, Esq. Staff Counsel U. S. Nuclear Regulatory Commission Washington, D.C. 20545 David R. Pigott, Esq. Samuel B. Casey, Esq. ~ Chickering & Gregory Three Embarcadero Center San Francisco, California 94111 John V. Morowski Bechtel Corporation P. O. Box 60860, Terminal Annex Los Angeles, California 90060 Michael L. Mellor, Esq. Thelen, Marrin, Johnson & Bridges Two Embarcadero Center San Francisco, California 94111 Huey Johnson Secretary for Resuurces State of California 1416 Ninth Street Sacramento, California 95814 Janice E. Kerr, General Counsel California Public Util'ities Commission 5066 State Building San Francisco, California 94102

{ -( _a_ J. Rengel Atomic Power Division westinghouse Electric Corporation Box 355 Pittsburgh, Pennsylvania 15230 A. E. Gaede P. O. Box 373 San Clemente, California 92672 Frederick E. John, Executive Director California Public Utilities Commission 5050 State Building San Francisco, California 94102 Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D.C. 20555 k t sa s James A. Beolett ssistant Counsel outhern California Edison Company h e p 9 3

( DESCRIPTION OF PROPOSED CHANGE AND SAFETY ANALYSIS PROPOSED CHANGE NO.100 TO THE TECHNICAL SPECIFICATIONS PROVISIONAL CFERATING LICENSE DPR-13 Tnis is a request to revise Appendix A Technical Specifications 2.1, " REACTOR CORE - Limiting Combination of Power, Pressure, and Temperature," 3.5.2, " Control Group Insertion Limits," and 3.11, " Continuous Power Distribution Manitoring." Reason for Proposed Chance By letter dated February 8, 1980, Proposed Change No. 88 to the Technical Specifications was submitted for NRC review and approval. Proposed Change No. 88 provided revisions to ensure that the Technical Specification objet-tives were met with the loading of the reactor core for Cycle 8 operation. The NRO issued Amendaent No. 49 to Provisional Operating License DPR-13 on May 19, 1980, thereby approving the revisions of Proposed Change No. 88. The steam generator repair program now underway at San Oncfre Unit I has made it necessary to determine the impact which these mooifications will have on the safety analysis for transients and accioents included in the Final Safety Analysis (FSA). ACCordingly, a reanalysis was performed and documented in the enclosed report entitled, "Relos: Safety Evaluation, San Onofre Nuclear Gener-ating Station Unit 1, Cycle 8, Revision 1," dated Octobe:, 1980. Proposed Chance L.o.100 provices the Technical Specification changes which ara neces-sary to assure operation within safety limits as a result of the reu sed Reload Safety Evaluation. Existino Specifications Tne existing specifications are as constituted in Sections 2.1, 3.5.2 and 3.11 of Appendix A to Provisional Operating License DPR-13. Proocsed Specifications Technical Specification 2.1, " Item (2) would be revised to read: "The combination of reactor power and coolant temperature shall not exceed the locus of points established for the RCS pressure in Figure 2.1.1. If the actu31 power and temerature is above the loc <s of points for the appropriate RCS pressure, the safety limit is exceeced." Figure 2.1.1 would be replaced with the figure of Enclosure 1. Table 2.1, Item 4 would be revised to read: "4. Variable Low Pressure .2 26.15 (0.984 AT + Tavg) - 14341"

(, 2-k tr.e.5 asis for Technical Specificat bn 3.5.2 (I2em 1, 2nd pars.) coulc be revise to reac: "A more restrictive limit on the design maximum value of specific power, N F ano F is applied to operation in accordance with the current 3g g safety analysis including fuel densification and ECCS performance. The values of the specific power, and F are 13.7 kW/ft., 1.55 ano 2.69 g respectively. The control group insertion limits in cmjunction with Specification B prevent exceeding these values es 'n assuming the most adverse Xe distribution." Technical Specification 3.11, Item A woulo be revised to reaa: "A. The incore axial offset limits shall not exceed the functional relationship defined by:

  • 0 For positive offsets:

1AO = 03 0 - 3.0 '0' For negative offsets: IAC = + 3.0 -O 03 where IA0 = incore axial offset P = fraction uf rated thermal power" Tne balance of Technical Specifications 2.1, 3.5.2 and 3.11 woulc remain as constitutec in Appendix A to Provisional Operating License No. DPR-13. Safety Analysis The Reload Safety Evaluation was reanalyzed assuming a maximum of 20% steam generator tube plugging which results in a reduction of 6.6% in Reactor Coolant System Thermal Design Flow. The results of the evaluation are documenteo in the enclosed report entitled, " Reload Safety Evaluation, San Onofre Nuclear Generating Station Unit 1, Cycle 8, Revision 1," cateo October, 19EO. Basec upon the analysis providec in the report discussed above, it is concluded that (1) the proposed change does not irtvolve an unreviewed safety question as oefined in 10 CFR 50.59, nor does it present significant hazaros considerations not described or implicit in the Final Safety Analysis, and (2) there is reasonable assurance that the health and safety of the puolic will not be endangered by the proposed change.

( s DCLOSURE 1 O 9 e

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  • F L; Safety Limits E. "

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UdDED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of WISCONSIN ELECTRIC POWER COMPANY Docket No. 50-266-OLA 50-301-OLA (Point Beach Nuclear Plant, ) (Repair to Steam Generator Tubes) Units 1 & 2) ) CERTIFICATE OF SERVICE I hereby certify that copies of NRC STAFF RESPONSE TO WISCONSIN ENVIRONMENTAL DECADE'S BASIS FOR CONTENTIONS DATED SEPTEMBER 24, 1981 in the above-captioned proceeding have been served on the following bv deposit in the United States mail, first class or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Comission's internal mail system, this 7th day of October 1981. Peter B. Bloch, Chairman Atomic Safety and Licensing Appeal Administrative Judge Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission Panel , Washington, D.C. 20555

  • U.S. Nuclear Regulatory Commission Atemic Safety and Licensing Board Wasnington, D.C.

20555

  • Panel Dr. Hugh C. Paxton U.S. Nuclear Regulatory Comission Administrative Judge Washington, D.C.

20555

  • 1229 - 41st Street Los Alamos, New Mexico 87544 Docketing and Service Section Office cf the Secretary Dr. Jerry R. Kline U.S. Nuclear Regulatory Commission Administrative Judge Washington, D.C.

20555

  • Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555

  • Kathleen M. Falk Wisconsin's Environmental Decade 302 East Washington Avenue Suite 203 Madison, Wisconsin 53703 Gerald Charnoff, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W. Washington, D.C. 20036 Charles A. Barth Counsel for NRC Staff .-.}}

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