IR 05000369/1979020
| ML20125B255 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 08/07/1979 |
| From: | Annast M, Hunt M, Thompson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20125B242 | List: |
| References | |
| 50-369-78-20, 50-370-78-15, NUDOCS 7910250544 | |
| Download: ML20125B255 (38) | |
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O g gd K8Guq jog UNITED ST ATEs NUCLEAR REGULATORY COMMISSION 1 pt o REGION ll
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IE Investigation Report Nos. 50-369/78-20 and 50-370/78-15 l Duke Power Company Subject: McGuire Nuclear Plant Units 1 and 2 Docket Nos. 50-369 and 50-370 l l Allegation that certain formal written statements made by Duke Power Company to the NRC were incorrect and materially affected the staff's review and acceptance of a revision to the McGuire Final Safety Analysis Report (FSAR).
April 11-13, May 3-5, July 6-28, Period of Investigation: September 10-11, November F and Decembe -6, 1978 l 10 j t v __ - M __ ( 1I' ate '
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Investigators: Office of the Director b1 h hi> h I)l21 l2
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H. D. Hunt,' Principal Inspector Projects Section Reactor Construction and En 'neering Support Branch
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TABLE OF CONTENTS i i 1. INTRODUCTION l J II. SCOPE OF INVESTIGATION I III. CONCLUSION IV. DETAILS OF INVESTIGATION Persons Contacted Allegation, Discussion and Finding Exhibits .
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I, Copy of Disputed Calculations Specific NRC Questions Duke Power Company Response to NRC Questions NRR Memorandum, dated September 14, 1978 i l
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I. INTRODUCTION eral telephone conversations The Nuclear Regulatory Commission in s icating that safety related and by letter received information idesign calculations incorrect or misleadin The Region 11 Office of Inspection and Enforcement conduc in IE Investi-tigation into the allegations and reported the dated August 2, 197 findings gation Report Nos, 50-369/78-10 and 50-370/78-4 This report concluded that of twelve separate allegations, lved elev not substantiated; however, one allegation resulted in an unreso item. This allegation was stated as follows: h
" Duke Power Company (DPC) has an existing accident ana indicates that a dropped fuel shipping DPC caskrepresentatives can f all into the spent fuel pool during certain condition have informed the NRC and stated in the FSAR f all into the poo Region 11 r.ontinued the investigation of 1.64, the unresolved Title 10 the cask drop accident analysis as authorized by Part Code of Federal Regulation II. _ SCOPE OF INVESTIGATION l
The scope of this investigation included the following: l Interviews with present and former Duke Power Company em An examination of documents and records related to the a An evaluation by NRR of the FSAR submittal with regard to material false statemen III. CONCLUSIONS Duke Power Company (DPC) performed One of several accide the calculations, by NRR, involving the spent fuel shipping cas DPC engineering the spent fuel pool under certain circumstance management reviewed the facts and believed that this calcu d hypothetical and unrealistic. issue and, based Regulation on his expe a(NRR).
formal FSAR revision to the Office of Nuclear Review by R tions, that the cask would not enter the spent fuel poo ding the NRR resulted in the conclusion that the DPC the FSAR review process because it omitt the need for additional NRR revie . .-
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. . . - . ?00R D M M IV. DETAILS OF INVESTIGATION Persons Contacted L. C. Dail, Vice President, Design Engineering J. R. Wells, Corporate QA ManagerL. R. Barnes, Q E. Braf ford, Design Engineering C. L. Ray, Jr. , Design Engineering R. B. Priory, Design Engineering l ees were inter-In addition to the above, three former DPC emp oy viewe Allegation, Discussion and Finding dicates DPC has an existing accident analysis which Allegation:
that a dropped fuel shipping cask canDPC representatives fall the fuel cask cannot pool under certain conditions.the NRC and stated into the poo ide the The licensee had been asked by NRR to provtha Discussion: ition wouldThe not results of an evaluation demonstrating a fuel result shipping cask in its vertical or tipped p investigators examined DPC calculations,0t cask of the maximum The accidents assuming a hypothetical 20 - onbe from used at of a height McGuir envelope dimensions dof possible casks ling at tof two speed. feet when the crane hits thepit.en t rage In -o maximum speed with the cask indicate theat caskfloorloose could not these two instances, the calculationsThe third calculation assum d from a height of 2 feet 11 ! tip over into the spent fuel poo d pivoting about the back that the stationary cask is droppeinches, with edge of the cask storage pit.the cask would fa Revision 6 to the i t two postulated The results of the study provided The stated conclusion was: " Based by accidents described above. is concluded that the cask wo fuel itpool due to maximum horizontal sw upon this evaluation enter the spent No potential limitations ximum lif ton caskorban beight tipping of the cask." The l such as special cask travel patterns, mature liminary were in that mentio it was modifications to fuel storage area struc third calculation (Exhibit-C-1) was preThe calculation check checked, but not approved.
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num[e s 7, 7a, 9 and 10 disa-notations on calculation sheetassumptions 6ade by Individual A, the calculator's greeing with the basiccalculationd The original person performing the assumptions were: [ No energy loss due to impac . Friction is not considere . Material deformation is not considere " Reinforced Cask The calculation checker, Individual B, hadThe noted that:There concrete concrete has the ability to absorb energy. Material deform lost on impac be imme-spalls off near the edge and the cask can beI to verify his note diately located, his positio appeared, however, to be adequateIndividual to support C, and the The immediate supervisor of both men, Individualtiv D,attempt No agreed with t principal engineer, d load case using the assumptions were unrealistically NRR l conserv more input realistic assumptions.for Revision 6 to the McGuire Question 020.2 and supplied itThe licensing engineer nsible confir submittal to NR dly when conservative
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Thus, the submittal to NRC was made persons i ' positions were aware of the existence of admitte the valid calculations that tended to cast some doubt on assurances included in the submitta i disputed Duke Power Company representatives were i statedbasedthat on un calculation was performed all previous calculat i onsenergy o i l energy of the the assumption that the majority fuel pool.of Load the kin cask would cause it to fall away from thelyze spent load cases, postulated by Individual B, thethechecker, cases N spent wI The fuel pool conclusion under any ofwas that theaccident the postulated cask would no i ned Individual A, the author of load casescalculations, 1 and 2 was j as the checker of the three additional loaof checking thesel June 11, In lieu Individual Individual A instead postulated a Load Case Individual No.A 3a 1975, performed an analysis for this new load case.d for used and the basic assumptions previously con
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P00R ORG.NA ,4 infi-no consideration of friction or matepial deformation into the and an
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nitely rigid cask, he concluded thg the cask would 12,fall 1975 spent fuel pool. The calculationf were checked on June
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by Individual B who apparently sfoted his objections onl calculation sheet immediate supervisor, was interviewed by the Individual C, the that he agreed with the checker and investigators and stated brought the di::puted calculation to the attention of his supe visor, Individual D, the Principal Enginee the assumptions assumptions and Individual D also agreed thatThereoach was a were unrealisti i to determine Individual A's reasons for the conserva h a in sincethe calculation there was no firm information on the cask, he thoug tI conservative approach should be use l tion k to calculation could not be reached to Individual C and indicated until all parameters h identifying that a fina t e casInd be purchased in the future, could be obtained (1) administrative falling into the pool. These included: k (2) controls on the operation of the crane transporting level the cas by ; modification of the north wall of the upper cask storage h k , sloping the wall to a degree such that level ofit w certain areas between the decontamination pit and th the cask storage are in the files with the understanding that the matter would be resolved when the actual cask was identifie Individual D, the Principal Engineer no longer employ was interviewed by the investigator d resolution defined in was the senior supervisor responsible for t l l tion Question clearly recalled 02 of theinvolved the details McGuire in theFSAR disputed (Exhibit difference ca cu a and stated that he had given serious attention to the ih in opinions and had He discussed the wholemade felt that the assumptions issue, for in Load det all parties involve Individual D believed along with Individual mptionc Case 3 were unrealisti d not enter were used, the analysis would show that actual calculations were not the spent fuel pool. However, The calculations were to remain tual performed to verify this belie h open for a final review when the physical details of cask could be had defined. received appropriate and proper attentio calculationsupervisory final conclusion was qualified personnel and the Individual D' based on proper review and good engineering judgmen t position was that, based on the foregoing actions, i.e., the t which he submitted for the FSAR revision was correct; , i cask could not enter the spent fuel pool (Exhibit C-3).
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formal briefing of events Duke Power Company arrangedFurther for ainvolving information the and cask d history of the disputed calculation. documents were pro the investigator Region 11 forwarded a memorandum, with enclosed statements and documents involving the cask drop28,issue 1978 to Headquarters, requesting rev iew Offic of Inspection and Enforcement on JulyThe facts submitted b of the cas follows: Duke Power Company had information that, using fuel conserva ; assumptions, the cask could conceivably enter the spent poo This information had not been provided to the Office of Nuclear Reactor Regulation (NRR),
No recalculation was made of Load Case 3 using more real assumption . Duke Power Company's decision not to include the dispute Load Case 3 as part of the FSAR submittal was a conscious ac No formal review procedure had been established which specifically required that later calculations, using in actu cask design parameters, would consider the load case questio The Office of Inrpection and Enforcemen NRR concluded that the (NRR) for a determination of materialit AR review omitted information would have been material h in the
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process and could have affected the staff's acceptance l FSAR revisio NRR concluded that the 4). l question was a material false statement by omission (E Region II was asked to provide additional information This an! mentation concerning the cask drop accident analysi included further interviews The with the additional following principals directly effort was inv in the cask drop analysi . requested in support of Headquarters review of the case: g Determine various individuals' background and experience, Obtain individuals opinions regarding the performance calculation !
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. t P00R ORIGINAL Obtain additional state- Reverify all facts and statement ment . Attempt to locate Individual B, the checker of the disputed calculatio Region 11 continued the investigation and reinterviewed i no longer employed by DPC, who performed the original calcula At this time Individual A was given a copy examin h of the and explained his rationale infuel reaching pool. Hethe conclusion readily admitted that t e cask would f all into the spent tive that the assumptions he had used for Load Case 3 were but pointed out that Cases 1 and 2. Individual A stated that he did not recall the notations made in theIndividual calculations B wasby Individual a young B, the checker inexperienced Individual A said that h kd engineer, recently According to Individual A, the checker onlyhe c ec graduated from college, at the time the calculatio * perfomed a mathematical verification of theIndividual calculationA not express any strong opinions about the h assumpt kr commented that which would have been added to the calculati disagreement with the assumption document revealed that calculation Further examination of thesheets (Form 184), used for the in December, version of Revision 12-74 i.e. the sheets were printed 11, 1975 and w The calculation was performed on June 12, 1975, 197 checked on June 12, 1975. Page 7.a was also dated June however this page was a version of Form to the assumptions on page 7.a. on June 12, 1975 because th particular page was not in existenc Individual B was located in Springfield, Virginia and wa viewed on October 10, 1978. Individual B admitted that he had of the questionable page, recorded his backdated comments approximately one i year la He stated that, initially, in 1975 he checked Although he did the calculation and found them to be correct. fee i and thus conservative, he made no further comments it that A'st m partially experienc because he was inexperienced Individual B stated and figures again, this time very carefull felt ii that he was not directly At the same time, the additional an ordered to add and enhance his career with DP .- .-
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MOR ORENAL ff to state that the year's experience had given him hecked his confidenceissue own figures and a too conservativ Individual B r added the coments on pages 7, He the found 7a, 9 and them10.to be correct.Page 7a was a new page which h he inserted time and dated this page to agree with the re coment . He recalls no further discussions on the matte The investigators reinterviewed Individual f the that he had asked Individual B approximately one year ahter original calculation was performed and checked, to take ano and to document any comments he might hav close look at it Individual B gave the calculation Individual C confirmed that lB main back to him with the added comments but not notice the backdated to backdate anythin He explained date that and did not the reason instruct for his been I request for the recheck was theand group factwas thatalso Individual planning to B had transf erred to another designIndividual C stated that he wantedi the attend graduate schoo checker to review the calculation again to record his before file he departed.He stated that he made Individual D's succe design group, Individual E, aware of the calculation, finsofa telling him about the preliminary status and disputed nature o the documen disclosed that, with the exception of Further investigationother DPC employee was apparently aware of 7, Individual C, no the later addition of page 7a and the other comments on pages 9, and 1 Individual D, the Principal Engineer, was reinterviewed o He still maintained that the assumptions made by Indivi 197 were unrealistically conservativ His basis for this was the fact that major energy dissipation would occu drop acciden the cask Individual would alsoDdeform on good energy absorber and that is presently , impact, resulting in energy dissipatio His background l the head of his own engineering consulting fir including direct experience with cask accident plant design Individual D stated that, in his opinion, ithere ring evaluation were adequate internal controls within the DPC design l l eng tionnee organization to assure future review of the preliminary ca c when an actual cask had been selecte l frankly that, based on his experience and engineering h FSAR ju in retrospect he would still have provided the input for t e submittal without reservation , l l --
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P00R ORGNAL
: and discussions with DPC l investigation Additional technical staff review of documentation during i
the course of the addit onafinal specifications revealed that DPC had still not decided Quality on theDuring Assurance discussi of the spent fuel cask.the investigators found that D Manual, Section PR-30), for all specifications of safety The cask specifi-of all engineering divisions related equipment which is to be purchased, i formal review h olution of any cations when finalized would, therefore, rece outstanding calculation Duke Power Findings: The allegation is substantiated as state l Regulatory Company formally submitted information Safety to theAnalysis Nuc ccidentear Commission Report in the the which omitted form ofthat fact a revision an existing to the Final prelimina analysis calculation indicated that the cas This constitutes a spent fuel pool under certain circumstances.The investigation disc material f alse statement by omissio judgement of an experi-that the omission was based on engineering i h all parties concerne d to give enced supervisor af ter appropriate review w t reasonable assurance that the cask drop lize issue There wou is no when the final cask specifications are finai l attempt by DPC evidence which indicates a willfulbor itta intent ona to deceive the NRC in the course of the FSAR i su m f the The backdating of page 7a in 1976 impacts h lculation on the integ individuals involved but does not materially affect t e caTh sult of the NRC results or the FSAR11,submittal 197 in 1975that d documents the c investigation begun on April be an isolated case since no other similar t aware of thebackd were identifie that other DPC employees and management were no backdating inciden i
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'he methods for sealing of penetra-Provide the description of d to 02 **) (2G. 3.4) tions, doorways and other* penings that could be subje floodin This should i in the Auxiliary Building wall forlevel the intake nuclear pipeservice from Lakeintake pipes from the pond and the lowAlso describe the means Norma the functional capability of such seal Response: . .
See revised Section I 02 Provide the results of an evaluation to demonstrate dropping of the spent the cask to enter the spent (9.1.2) tipped position can not permit fuel storage area or damage safety related equipmen . Response: 6' See revised Subdivision 9.1. It is our position that any connection with the Spent Fuel1 02 Pool Cleanup System should be desigr.ed to Seis-ic Category d (9 1.3) requirements, up to and including ( P,S P ) Figurethe firsti r.c'i S.I.3-1 r.orrally c a t e close s t ha t or automatically closed valve.4-inch valve (lKFB3)
.hich is r.A ceticr.ed for water storage tank is Duke Class E, i a *) This valve should be seiscic Categorf seismic loadin to co. ply with tr.is staff Qrnlity Group C. State your intent
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10 Kle nominal center-to-center distance of 15//2 inches rf < 95 even if immersed in unborated wate The racks are designed to preclude insertion of fuel assemblies in other than permitted locations,
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To further assure thereby assuring the necessary spacing between assemblie subcritical arrays in the fuel handling facilities, only one assembly can be manipulated at a tim Since each unit has its own fuel pool, there are no safety considerations related to sharing of component ' To preclude the cask entering the spent fuel pool, the cask crane stops are located in a position to prevent the cask from being moved into the fuel pool are The cask area is separated from the spent fuel pool by a three f reinforced concrete wall (Reference Figures 9 1.1-1 and -2).
An evaluation has been performed to assess the possibility of the cask To enter-Ing the spent fuel pool in the lif ted (vertical) and tipped positio evaluate the cask in the lifted posi; ion, the crane is assuned 'tofifty impactft. per against the crane stops traveling at the maximum crane speed #4 worizontal
minute displacemen with the cask in a position to give the maximem swtd drun and a rigid crane and rail stop, the cask center of gresity remains o the cask area side of the three ft. divider wall. To evaluate the cask in position, refer to Figure 9.l.2-1, Sheet 1 of 2.the tipped pos 1 wall of the cask area nd tip toward the ' spent fuel po9 d the maximum envelope (dimensions) are used for the possible casks to be us at PcGuire. As shown in Figure 91.2-1, Sheet 2 of 2,wal h divider the center Basedof gravity uoon (f the cask remains on the cask area side of t eis concluded that the ca fuct this evaluation it the cask., coci due to mcximum horizontal swing or tipping of The fuel pool is designed to withstand the following: normal dead and equipment loads plus design seismic loads, all normal dead, equipment and live loads, norn.a1 dead and equipment loads plus tornado wind load, therral stresses, and cask drop acciden c.1.3 3 presents a safety evaluation of the Spent Additionally, SubdivisionFuel Cooling System explaining in detall fuel cooling as required by Regulatory Guide 1.13 redundart active components,
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John G. Davis, Actin [ Director MEMORA'!DUM FOR: Office of Inspection and Enforcement . FROM: Harold R. Denton, Director Office of Nuclear Reactor Regulation s SUBJECT: REVIEW FOR POSSIBLE MATERIAL FALSE STATEMENT THE McGUIRE NUCLEAR PLANT FSAR 21, 1978, we have reviewed As requested by your memorandum of August the material you provided relating to a possible material false statement made by Duke Power Company in the McGuire FSAR concerning , a dropped fuel shipping cask's capability of entering the spent fuel l pool. Based on our review, we are of the opinion that the PSAR
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response to the staff question on this subject was a material false state:nent by omission, in that the answer did not include the fact that with regard case 3," which was part of the licensee's evaluation described in the FSAR, it had been concluded by responsible Duke Power Company officials that the question could not be resolved
until all parameters identifying the cask could be obtained."
(Quotations from statement by tapwipoa6 C, a similar quotes could also be extracted from statements included in the material you - provided by other involved Duke personnel.)
With regard to the conclusion reached by Duke personnel that the assumptions staff agree used by Edoiwooni. A in case 3 were conse were so unrealistically conservative that one could conclude, without doing or having previously perfonned further parametric calculations using more ' realistic assumptions, that the cask could not fall into the fuel poo l Harold R. Denton, Director
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