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) | |
Text
{{#Wiki_filter:. ' O UNITED ST ATEs gd K8Guq NUCLEAR REGULATORY COMMISSION g pt jo REGION ll g
101 M ARIETT A ST R E ET. N.W.
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-E [ k AUG 0 71979 '"** 50-369/78-20 and 50-370/78-15 IE Investigation Report Nos.
Duke Power Company Subject: McGuire Nuclear Plant Units 1 and 2 Docket Nos. 50-369 and 50-370 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 t v __ - M __ ( 1 10 j Investigators: H.
. Annast, Investigatof ' I' ate ' . . Office of the Director b1 h hi> h I)l21 l2 ~ Bate', H. D. Hunt,' Principal Inspector Projects Section Reactor Construction and En 'neering Support Branch //pdt(f ' / ~ Date Reviewed by: . Thompp n p eputy director Office di the Director f l Q.
7910250 s , i %
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. TABLE OF CONTENTS . i i 1. INTRODUCTION II. SCOPE OF INVESTIGATION J I III. CONCLUSION IV. DETAILS OF INVESTIGATION A.
Persons Contacted Allegation, Discussion and Finding B.
C.
Exhibits Copy of Disputed Calculations . ' I, Specific NRC Questions Duke Power Company Response to NRC Questions 2.
3.
NRR Memorandum, dated September 14, 1978 4.
i l . b , " ., __ - . .
- _ . PDDR ORGM ' - - rf . , I. INTRODUCTION eral telephone conversations The Nuclear Regulatory Commission in s icating that safety related and by letter received information idesign calculations incorrect or misleading.
The Region 11 Office of Inspection and Enforcement conduc in IE Investi-tigation into the allegations and reported the findings dated August 2, 1978.
50-369/78-10 and 50-370/78-4 This report concluded that of twelve separate allegations, elev gation Report Nos, lved not substantiated; however, one allegation resulted in an unreso This allegation was stated as follows: item.
h " Duke Power Company (DPC) has an existing accident an indicates that a dropped fuel shipping cask can f all into the DPC representatives fuel pool during certain conditions.
have informed the NRC and stated in the FSAR spent f all into the pool.
Region 11 r.ontinued the investigation of the unresolved 1.64, Title 10 the cask drop accident analysis as authorized by Part Code of Federal Regulations.
II. _ SCOPE OF INVESTIGATION The scope of this investigation included the following: Interviews with present and former Duke Power Company em A.
An examination of documents and records related to the a B.
An evaluation by NRR of the FSAR submittal with regard to C.
material false statement.
III. CONCLUSIONS Duke Power Company (DPC) performed several accide One of the calculations, by NRR, involving the spent fuel shipping cas DPC engineering fuel pool under certain circumstances.
reviewed the facts and believed that this calcu the spent management d hypothetical and unrealistic. issue and, based on his expe Regulation a formal FSAR revision to the Office of Nuclear R Review by tions, that the cask would not enter the spent fuel pool.
(NRR).
NRR resulted in the conclusion that the DPC ding the the FSAR review process because it omitt the need for additional NRR review.
..- - ,
. . ?00R D M M . - . IV. DETAILS OF INVESTIGATION Persons Contacted A.
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 ees were inter-l In addition to the above, three former DPC emp oy viewed.
Allegation, Discussion and Finding dicates DPC has an existing accident analysis which B.
that a dropped fuel shipping cask canDPC representatives Allegation: fall the fuel cask cannot pool under certain conditions.the NRC and stated ide the into the pool.
The licensee had been asked by NRR to provtha ition would not results of an evaluation demonstrating Discussion: fuel shipping cask in its vertical or tipped p The a cask of the maximum investigators examined DPC calculations, result The 0t accidents assuming a hypothetical 20 - onbe used at McGuir from a height of envelope dimensions of possible casks to d ling at two feet when the crane hits the en -o t rage pit. In maximum speed with the cask at floorloose speed.
indicate the cask could not The third calculation assum these two instances, the calculations d from a height of 2 feet 11 tip over into the spent fuel pool.
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 The results of the study provided by t two postulated i " Based was: The stated conclusion is concluded that the cask wo accidents described above.
fuel pool due to maximum horizontal sw upon this evaluation itNo potential limitations on cask ban spent ximum lif t beight or enter the tipping of the cask."
The such as special cask travel patterns, mature were mentio modifications to fuel storage area struc liminary in that it was l third calculation (Exhibit-C-1) was preThe calculation chec checked, but not approved.
t
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.- . - . .
' num[e s 7, 7a, 9 and 10 disa-on calculation sheetassumptions 6ade by Individual A, the . notations calculator's greeing with the basiccalculationd The original person performing the [ assumptions were: No energy loss due to impact.
Friction is not considered.
1.
Material deformation is not considered. Cask 2.
3.
" Reinforced 4.
The calculation checker, Individual B, had noted that:There concrete has the ability to absorb energy. Material deform The concrete spalls off near the edge and the cask can be lost on impact.
be imme-to verify his notes.
his position.
diately located, appeared, however, to be adequate to support Individual C, and the supervisor of both men, Individual D, agreed with The immediate tive.
No attempt principal engineer, the assumptions were unrealistically conserv d load case using l NRR more realistic assumptions.for Revision 6 to the McGuire Question 020.2 and supplied itThe licensing engineer confir input nsible Thus, the submittal to NRC was made when persons submittal to NRC.
dly conservative
positions were aware of the existence of admitte the valid ' calculations that tended to cast some doubt on assurances included in the submittal.
i disputed Duke Power Company representatives stated that un i were based on calculation was performed all previous calculat onsenergy o i the assumption that the majority of the kin i l energy of the fuel pool. Load cask would cause it to fall away from the spent lyzed.
load cases, postulated by Individual B, the checker, w cases No.
the spent The conclusion was that the cask would no fuel pool under any of the postulated accidents.
i ned Individual A, the author of load cases 1 and 2 was as the checker of the three additional loaof checking these June 11, l calculations, j Individual A instead postulated a Load Case No. 3 In lieu Individual B.
Individual A 1975, performed an analysis for this new load case.d for used the basic assumptions previously con and 2.
..y .. . . -
- - . . . ' W P00R ORG.NAl.. ,4 " infi-no consideration of friction or matepial deformation and an . into the nitely rigid cask, he concluded thg the cask would fall 12, 1975 The calculationf were checked on June by Individual B who apparently sfoted his objections on
spent fuel pool.
calculation sheets.
immediate supervisor, was interviewed by the checker and Individual C, the that he agreed with the investigators and stated brought the di::puted calculation to the attention of his supe visor, Individual D, the Principal Engineer.
the assumptions and Individual D also agreed thatThere was a assumptions i oach to determine Individual A's reasons for the conserva were unrealistic.
h a since there was no firm information on the cask, he thoug t in the calculations.
conservative approach should be used.
l tion calculation to Individual C and indicated that a fina h k to could not be reached until all parameters identifying t e casInd be purchased in the future, could be obtained falling into the pool.
These included: (1) administrative k (2) controls on the operation of the crane transporting the cas ; level by modification of the north wall of the upper cask storage h k sloping the wall to a degree such that it w level of , certain areas between the decontamination pit and th files with the understanding that the matter would be the cask storage area.
resolved when the actual cask was identified.
in the Individual D, the Principal Engineer no longer employ was interviewed by the investigators.
d resolution was the senior supervisor responsible for t defined in Question 020.2 of the McGuire FSAR (Exhibit l l tion clearly recalled the details involved in the disputed ca cu a difference and stated that he had given serious attention to the ih in opinions and had discussed the whole issue, in det He felt that the assumptions made for Load Individual D believed along with Individual all parties involved.
mptionc Case 3 were unrealistic.
were used, the analysis would show that d not enter calculations were not actual The calculations were to remain the spent fuel pool.
However, performed to verify this belief.
h tual open for a final review when the physical details of cask could be defined. received appropriate and proper attentio had final conclusion was calculationsupervisory personnel and the Individual D' based on proper review and good engineering judgment.
qualified t position was that, based on the foregoing actions, t i.e., the which he submitted for the FSAR revision was correct; cask could not enter the spent fuel pool (Exhibit C-3).
, i % ~ - .. ...
. . P00R ORIGINAL . formal briefing of events . Duke Power Company arranged for ainvolving the cask d Further information and history of the disputed calculation. documents were pro the investigators.
forwarded a memorandum, with enclosed statements and documents involving the cask drop issue to Headquarters, Offic Region 11 i 28, 1978 requesting rev ew of Inspection and Enforcement on JulyThe facts submitted b of the case.
follows: Duke Power Company had information that, using conserva fuel
assumptions, the cask could conceivably enter the spent 1.
pool.
information had not been provided to the Office of This 2.
Nuclear Reactor Regulation (NRR), No recalculation was made of Load Case 3 using more real
assumptions.
Duke Power Company's decision not to include the disput Load Case 3 as part of the FSAR submittal was a conscious 4.
act.
No formal review procedure had been established which specifically required that later calculations, using actu
in cask design parameters, would consider the load case question.
The Office of Inrpection and Enforcemen NRR concluded that the (NRR) for a determination of materiality.
AR review omitted information would have been material in the h process and could have affected the staff's acceptancel , NRR concluded that the 4).
l question was a material false statement by omission (E FSAR revision.
Region II was asked to provide additional information an mentation concerning the cask drop accident analysis.
This ! included further interviews with the principals directly inv The following additional effort was in the cask drop analysis.
requested in support of Headquarters review of the case: . Determine various individuals' background and experience, g 1.
Obtain individuals opinions regarding the performance 2.
calculations.
! > -g - . ~
-_.
._ , , . P00R ORIGINAL t Obtain additional state-Reverify all facts and statements.
3.
ments.
Attempt to locate Individual B, the checker of the disputed 4.
calculation.
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 of the h and explained his rationale in reaching the conclusion that t e examine.
fuel pool. He readily admitted cask would f all into the spent tive that the assumptions he had used for Load Case 3 were Individual A stated that he did not recall the that but pointed out notations made in the calculations by Individual B, the checker Cases 1 and 2.
Individual B was a young inexperienced h kd Individual A said that engineer, recently graduated from college, at the time he c ec According to Individual A, the checker only perfomed a mathematical verification of the calculation the calculation.
Individual A
not express any strong opinions about the assumpt commented that h kr which would have been added to the calculati disagreement with the assumptions.
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 calculation was performed on June 12, 1975, checked on June 12, 1975. Page 7.a was also dated June 1974.
The however this page was a version of Form assumptions on page 7.a. on June 12, 1975 because th to the particular page was not in existence.
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 year la i 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 t m A's partially because he was inexperienced and Individual B stated experience.
figures again, this time very carefully.
felt that he was not directly ordered to add an ii At the same time, the additional and enhance his career with DPC.
, . .- .- " .
. . . - MOR ORENAL - - ff to state that the year's experience had given him confidenceissue a hecked his own figures and too conservative.
Individual B r added the coments on pages 7, He the found them to be correct.Page 7a was a new page which he inserted h time and dated this page to agree with the re 7a, 9 and 10.
He recalls no further discussions on the matter.
coment. The investigators reinterviewed Individual f the that he had asked Individual B approximately one year a ter h original calculation was performed and checked, to take ano and to document any comments he might have.
the calculation close look at it Individual B gave Individual C confirmed that back to him with the added comments but main lB not notice the backdated date and did not instruct to backdate anything.
He explained that the reason for his been request for the recheck was the fact that Individual B had group and was also planning to transf erred to another designIndividual C stated that he wanted the attend graduate school.
i checker to review the calculation again to record his before he departed.He stated that he made Individual D's succe design group, Individual E, aware of the calculation, insofa files.
f telling him about the preliminary status and disputed nature o the document.
disclosed that, with the exception of Further investigationother DPC employee was apparently aware of Individual C, no 7, the later addition of page 7a and the other comments on pages 9, and 10.
Individual D, the Principal Engineer, was reinterviewed He still maintained that the assumptions made by Indiv His basis for this was the 1978.
were unrealistically conservative.
fact that major energy dissipation would occu drop accident.
the cask would also deform on good energy absorber and that Individual D is presently , impact, resulting in energy dissipation.
His background the head of his own engineering consulting fir including direct experience with cask accident in his opinion, there plant design Individual D stated that, i ring were adequate internal controls within the DPC design eng nee evaluations.
l l tion organization to assure future review of the preliminary ca c cask had been selected.
frankly that, based on his experience and engineering ju when an actual h FSAR in retrospect he would still have provided the input for t e submittal without reservations.
, l , J .. --
' . . . . P00R ORGNAL
and discussions with DPC Additional review of documentation i l investigation technical staff during the course of the addit onafinal specifications revealed that DPC had still not decided on theDuring discussi Quality Assurance 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 cations when finalized would, therefore, rece h olution of any outstanding calculations.
Duke Power The allegation is substantiated as stated.
l Regulatory Company formally submitted information to the Nuc ear Findings: Safety Analysis Commission in the form of a revision to the Fina ccident Report which omitted the fact that an existing prelimina analysis calculation indicated that the cas This constitutes a spent fuel pool under certain circumstances.The investigation disc judgement of an experi-material f alse statement by omission.
that the omission was based on engineering i h all parties concerned.
enced supervisor af ter appropriate review w t d to give reasonable assurance that the cask drop issue wou lized. There is no when the final cask specifications are fina l attempt by DPC i evidence which indicates a willful or intent ona b ittal.
to deceive the NRC in the course of the FSAR su m i f the The backdating of page 7a in 1976 impacts on the inte h lculation individuals involved but does not materially affect t e caTh results or the FSAR submittal in 1975that the c sult of the NRC 11, 1978.
d documents investigation begun on April be an isolated case since no other similar backd t aware of the were identified.
that other DPC employees and management were no backdating incident.
i , .. -
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. ' '" l NOR'ORGINAL . I CERTIFICATION OF DESIGN CALCh TION
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( . __ " ' -- -- , - - - ...... _.. .... .- - . i ' . rf 'he methods for sealing of penetra-Provide the description of d to tions, doorways and other* penings that could be subje 020.1
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(2G. 3.4) flooding.
This should i in the Auxiliary Building wall for the nuclear service intake level intake pipe from Lake pipes from the pond and the lowAlso describe the means Norman.
the functional capability of such seals.
Response: . See revised Section 3.4.
Provide the results of an evaluation to demonstrate . I 02C.2 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 equipment.
. Response: See revised Subdivision 9.1.2.3 6' is our position that any connection with the Spent Fuel
Pool Cleanup System should be desigr.ed to Seis-ic Category It 020.3 d requirements, up to and including the first r.orrally close (9 1.3) Figure S.I.3-1 i r.c'i c a t e s t ha t ( P,S P ) or automatically closed valve.4-inch valve (lKFB3) ceticr.ed for water storage tank is Duke Class E, .hich is r.A i ar.c This valve should be seiscic Categorf
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seismic loading.
~ to co. ply with tr.is staff Qrnlity Group C.
State your intent position.
Response: See revised Figure 9 1.3-1.
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- .- . , . t 9 1.2.3 Safety Evaluation _ , , ! i in the fuel storace racks. fuel is storef vertica11y in an array with a [ 10 l nominal center-to-center distance of 15//2 inches 6I The racks are designed to < 95 even if immersed in unborated water.
preclude insertion of fuel assemblies in other than permitted locations, K rf e . To further assure thereby assuring the necessary spacing between assemblies.
subcritical arrays in the fuel handling facilities, only one assembly can be manipulated at a time.
Since each unit has its own fuel pool, there are no safety considerations related to sharing of components.
' 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 The cask area is separated from the spent fuel pool by a three reinforced concrete wall (Reference Figures 9 1.1-1 and -2).
pool area.
ft.
An evaluation has been performed to assess the possibility of the cask enter-To Ing the spent fuel pool in the lif ted (vertical) and tipped position.
evaluate the cask in the lifted posi; ion, the crane is assuned to impact ' fifty ft. per the crane stops traveling at the maximum crane speed #4 worizontal against minute 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 displacement.
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
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, the center of gravity h divider wall. Based 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, a.
all normal dead, equipment and live loads, b.
norn.a1 dead and equipment loads plus tornado wind load, c.
d.
therral stresses, and cask drop accident.
e.
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, a.
P.evislen 10 ' 9.l-4b E y.At S tT < t n m.
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- - -- _-. _ - --- ,, . NUCLEAR REGULATORY COMV.lsslON . ' g
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. 'h,.,.jf g g,)h..;'f'**.: . , . . . t '%, [, ',, ,'Sepyber 14, 1978 . - ~ , , , ./ . John G. Davis, Actin [ Director MEMORA'!DUM FOR: Office of Inspection and Enforcement . Harold R. Denton, Director FROM: Office of Nuclear Reactor Regulation s REVIEW FOR POSSIBLE MATERIAL FALSE STATEMENT SUBJECT: 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 Based on our review, we are of the opinion that the PSAR ' pool.
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 used by Edoiwooni. A in case 3 were conse were so unrealistically conservative that one could conclude, without staff agrees.
doing or having previously perfonned further parametric calculations using more ' realistic assumptions, that the cask could not fall into the fuel pool.
l Harold R. Denton, Director Office of Nuclear Reactor - - Regulation cc: J. Murray, ELD . . . . l O
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