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=Text=
=Text=
{{#Wiki_filter:of(<<(o0 REGULATORY XNFORNATION DISTRIBUTION SY TEN<RXDS)DXSTRIBUTION FOR INCOMING NATERIAL 50-335 GRG;SCHMIDT A D DOCDATE: 08/07/78 FL PWR 8(LIGHT DATE RCVD: 08/15/78 REC: OREXLLY J P, NRC DOCTYPE: LETTER NOTARIZED:
{{#Wiki_filter:of(<< (o0 REGULATORY XNFORNATION DISTRIBUTION SY TEN <RXDS)
NO COPIES RECEIVED  
DXSTRIBUTION FOR INCOMING NATERIAL                                     50-335 REC:    OREXLLY J      P,                      GRG; SCHMIDT A D                   DOCDATE: 08/07/78 NRC                                            FL PWR 8( LIGHT                 DATE RCVD: 08/15/78 DOCTYPE: LETTER               NOTARIZED: NO                                           COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR 1 ENCL 1 LICENSEE EVENT REPT 50-335/78-25 ON 07/24/78 CONCERNING AN ERROR IN THE ANALYSIS FOR Tl-IE CASK DROP ACCIDENT WHICI.I MAKES TFIE TECH SPEC 3.9.14 NGI4-CONSERVATI VI:.PLANT MANE: ST LUCXE 4I:1+~+cs<sss+u<>'s<
LTR 1   ENCL 1 LICENSEE EVENT REPT 50-335/78-25 ON 07/24/78 CONCERNING AN ERROR IN THE ANALYSIS FOR Tl-IE CASK DROP ACCIDENT WHICI.I MAKES TFIE TECH SPEC 3. 9. 14 NGI4-CONSERVATI VI:.
><<><>+<H', DISTRIBUTION OF INC1DEI4T, REPORTS (DISTRIBUTION CODF A002)REVIEWER INITIAL: XBT DlSTRIBUTOR INITIAL:~THIS NATERXAI XS AS FOLLOWS%%%%%%%%4%%%%%%%%%
PLANT MANE: ST LUCXE                                                       REVIEWER  INITIAL: XBT
FOR ACTION: INTERNAL: EXTERNAL: B CI.IIEF GRBN4"BC~~+W/4 ENCL REG F WlENCL'44~W/2 ENCL I 5 C SYSTEMS BR~HIW/ENCL NOVAK/CFIECK+<tW/ENCL AD FOR ENG~~~~W/ENCL FIANAUER~~"W/ENCL A13 FOR SYS 8c PROJ4l+W/ENCL ENGXNEERING BR~~W/ENCL KREGER/J.COLLINS+4~W/ENCL K SEYFR1T/I E~~~~W/ENCL LPDR S'T PIERCEi FL++W/ENCL TIC, I IZ CARTER~~W/ENCL MSX C~H~W/ENCL ACRS CAT B++W/16 ENCL NRC PDR4'~W/ENCL NIPC~H~W/3 ENCL EMERGENCY PLAN BR+%W/ENCL EEB~~W/ENCL PLANT SYSTENS BR+>W/ENCL AD FGR Pl ANT SYSTENS%<W/ENCL REACTOR SAFETY BR>>W/ENCL VOLLMER/BUNCH+wW/ENCL POWER SYS BR~~W/ENCL DISTRIBUT10N:
                                                                                                  ~
LTR 45 ENCL 45 SIZE: 3P%%%%%%%%%%.2%%%%%4I%%%%%%%%%8c 0M 0F%0f%%0$TIIE END CONTROL NBR: 782230377 4 g'k a+~//FLORIDA POPOVER 5 LIGHT COMPANY Mr.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement, U.S.Nuclear Regulatory Commission
4I:1 DlSTRIBUTOR  INITIAL:
'30 Peachtree Street, N.M., Suite 1217 Atlanta, Georgia 30303
+~+cs<sss+u<>'s< > <<><>+<H', DISTRIBUTION OF THIS NATERXAI         XS AS FOLLOWS %%%%%%%%4%%%%%%%%%
INC1DEI4T, REPORTS (DISTRIBUTION CODF A002)
FOR ACTION:               B     CI.IIEF GRBN4 "BC~~+W/4 ENCL INTERNAL:                REG F             WlENCL                 NRC PDR4'~W/ENCL
                                      '44~W/2 ENCL                    NIPC~H~W/3 ENCL I 5 C SYSTEMS BR~HIW/ENCL                EMERGENCY PLAN BR+%W/ENCL NOVAK/CFIECK+<tW/ENCL                    EEB~~W/ENCL AD FOR ENG~~~~W/ENCL                    PLANT SYSTENS BR+>W/ENCL FIANAUER~~ "W/ENCL                      AD FGR Pl ANT SYSTENS%<W/ENCL A13   FOR SYS 8c PROJ4l+W/ENCL          REACTOR SAFETY BR>>W/ENCL ENGXNEERING BR~~W/ENCL                  VOLLMER/BUNCH+wW/ENCL KREGER/J. COLLINS+4~W/ENCL              POWER SYS BR~~W/ENCL K   SEYFR1T/I E~~~~W/ENCL EXTERNAL:                LPDR     S'T PIERCEi FL++W/ENCL TIC,     I   IZ CARTER~~W/ENCL MSX C~H~W/ENCL ACRS         CAT B++W/16 ENCL DISTRIBUT10N:             LTR 45             ENCL 45                       CONTROL NBR:    782230377 SIZE: 3P                                                                                       4
%%%%%%%%%%.2%%%%%4I%%%%%%%%%8c 0M 0F%0f%%0$               TIIE END


==Dear Mr.O'Reilly:==
g'k a  +~
REPORTABLE OCCURRENCE 335-78-25 ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
                                                                                        //
JULY 24 1978 August 7, 197g-P RN" L I-78-219m~
FLORIDA POPOVER 5 LIGHT COMPANY August 7, 197g-P RN" L I 219m~
I<<X)<..C/l~C/l~n CA CASK DROP ANALYSIS The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide prompt notification of the subject occurrence.
I
Very truly yours, JiP A.D.Schmidt Vice President Power Resour ces MAS/ms Attachment cc: Harold F.Reis, Esquire Director, Office of Inspection and Enforcement (40)Director, Office of Management Information and Program Control (3)782230377 PLOPLF.~.SERVING PFOPI.F 0 NAC FORM 666 P TTI LlCENSEF EVENT REPORT U<<*NUCLEAR AEGULATORY COMMISSION CONTROL BLQCICI I lQI (PLEASE PAINT OR TYPE ALI.A'EQUIREO INFORMATIONI Q.15<<6 LICSNSS TY)<<0 Sl A<<ja C.9 LICcNSK K COOK~4~5 I.ICK NSK NLMef<<4~<<<<PI LIB LIBI1 r 0 Ol-0 01010101-10 It<<4 II XIIIX Q~IQ<<CON'T~OI 1 8 0 2 souAc I X JQB 0 5 0 I 0 l 0 l 3 3 5 OT 0 I 60 61 COCK 8 T NUM 9 6 R EVENTOESCAIPTION ANO PAOBABL-COIYSECUcNCc QIO Because of an error in the anal sis for 7 2 4'7 8 6 0 8 Ol 7I 7 8 QB fy NTOAtf 15 RK)QAT QATK 40 the cask dro accident T.S.3.9.1 4 i s.non-conservati ve.It has been determined that a dro ed cask could impact a larger radius, therefore, a longer decay time is needed before a cask.can be moved into the spent fuel pool cask compartment.
                                                                  <<X) <..
There are no adverse conse uences because of the small amount of fuel in the pool and the high degree of conservatism in the analysis.~Oa 1 8 9 SYSTeu CAUSe CAUSK COMP.VALVS COOK CQOK S'U8CQOK CQMPON KNT COOK suacoof suscQQK~<<<<~PB Qrl~BQ>>~A Q<<<<X X X X I X X Q<<~ZQ<<~Z Qi-9 10 ll 12 12 IS 19~0 Scouf NTIAL OCCUAAKi4CK Rc)OAT RKVISIotl<<
C/l
Lca!AO KVKNTYKAA itf PORT HO.COOK HO.Q<<r<<ir<<<<r~7S~~02 5~<<~01~X 21 22~23 24 26 21 8 29 0 3'I 22 ACTION Fut<<JAS cFFKCT SI4UTCOWN At-.ACNMK NT Nr ROM PFAue CQMr.=COMPONK H r TAKcN*I TION Ctl PI.ANT Mf T<<IQO I<<OVAS 22 SUBMITTKO FOA!45ua.SUPPLISR u*NVFACTUAKR LBOLJS LRS>>IS~>>>>S LJS MS<<5 26 3)4l 42 43 44 41 CAUSE DSSCSIIPTION
                                                                  ~C/l~
<<I<<NO CORRECTIVE ACTIONS Q21 0 The cask dro was not anal zed in accordance with FSAR methodolo y, there by leading to a non-conservative basis for T.S.3.9.14.A boundin analy sis has been erformed and will be administrativel a lied in case use o the soent fuel cask is re uired before a ro osed Technical S ecificationl 9 amendment can be submitted.
n Mr. James P. O'Reilly, Director,  Region II                    CA Office of Inspection    and Enforcement, U. S. Nuclear  Regulatory Commission Peachtree  Street, N. M., Suite 1217
and a roved b the NRC.1 A ILITY S.A<<VS;I)OWfA OTIIKR5 ATUS DOO LOS~i'S~8 Is 18 12 44 ACTIVITY.CQNTK NT AKLKASKO OF Afl.KASK AM(IVNT~F*CTIVITY QSS~zQ>>~zQS'A 1 8 10 II 44 FKRSONNfL KX)OSUAKS~OII'0 Q<<r~ZQB<<'A 1 I I I'2 13 Pf ASCNNK L IPUL'Ates pZg~o"'8'"0 Q'"'"'".III<<~DQSI NOtif iCatiOri VrOm 7/4 45 gA LOCA'tloN OF<<IKLKASK Q 45 KO 30 30 a 2 II l2 LCSS OF CA OAMAC-0 F*CILITY Q42 TYPf.of>>AlrtloN zQ2 10 rueLICI TY ISSUKO OKSCAIPI.CN LPJ~glQ44 9 10 NAME OP PREPARER PIION6: I'<<I 80 30 NAC USE ONI.Y ee'69 W Reportable Occurrence 335-78-25 Licensee Event Report Pa e Two Additional Event Descri tion During power operation, the Architect/Engineer found an error in the accident analysis for the drop of a spent fuel cask into the spent fuel pool.As a result of the error;Specification 3.9.14 on spent fuel handling is non-conservative.
                                        '30 Atlanta, Georgia    30303
The analysis was originally performed assuming a single pendu-lum, which gave a drop radius of 133 inches.The FSAR methodology, however, specifies a double pendulum, which gives a drop radius of 248 inches.This means that a dropped cask could impact more, fuel elements, therefore,"fresh" spent fuel must be stored farther from the cask area and/or allowed to decay longer before the cask can be moved into the spent fuel pool.The probable consequences of the occurrence are not signifi cant because fuel was stored in the pool for only 2 months before the error was found, and there is considerable conservatism in the dose rate analysis for the cask drop acci-dent.This was the first occurrence involving a calculational error associated with a spent fuel system.}}
 
==Dear Mr. O'Reilly:==
 
REPORTABLE OCCURRENCE 335-78-25 ST. LUCIE UNIT 1 DATE OF OCCURRENCE:  JULY 24  1978 CASK DROP ANALYSIS The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide prompt notification of the subject occurrence.
Very truly yours, JiP A. D. Schmidt Vice President Power Resour ces MAS/ms Attachment cc:   Harold F. Reis, Esquire Director, Office of Inspection and Enforcement (40)
Director, Office of Management Information and Program Control (3) 782230377 PLOPLF     . ~ . SERVING PFOPI.F
 
0 NAC FORM 666                                                                                                                             U<<*NUCLEAR AEGULATORY COMMISSION P TTI LlCENSEF EVENT REPORT CONTROL BLQCICI                                                   lQI                 (PLEASE PAINT OR TYPE ALI. A'EQUIREO INFORMATIONI I
~<<<<PI        9 LIB          LIBI1 C.
LICcNSK K COOK               ~ 4 r
                                                            ~ 5 0    Ol  0            01010101-10 I.ICKNSK NLMef<<4 It 15 Q. <<4 II XIIIX Q~IQ<<
                                                                                                                                        <<6      LICSNSS    TY)      <<0      Sl A<<ja CON'T
~OI                 souAc       I X JQB       0       5       0 I 0 l0    l 3     3     5 OT     0 I 7    2    4      '7      8    6      0    8      Ol  7I    7    8    QB 1      8                      60             61               COCK 8 T NUM9 6 R                               fy NTOAtf                          15        RK)QAT QATK              40 EVENTOESCAIPTION ANO PAOBABL- COIYSECUcNCc                                     QIO 0 2          Because           of     an     error in the anal sis for the                                       cask dro                 accident               T.S.
3.9. 1 4 i s .non-conservati ve.                                       It has         been determined                     that       a   dro         ed cask could impact                   a   larger radius, therefore, a longer decay time is needed before a cask. can be moved into the spent fuel pool cask compartment.
There are no adverse conse uences because of the small amount of fuel in the pool and the high degree of conservatism in the analysis.
  ~Oa 1     8 9 SYSTeu               CAUSe           CAUSK                                                             COMP.           VALVS
                                                                                      ~
COOK                 CQOK         S'U8CQOK                   CQMPON KNT COOK                       suacoof           suscQQK
~<<<<                               ~PB             Qrl       ~BQ>>           ~A       Q<<<<X             X X XI X X                   Q<<       ~ZQ<<             ~Z       Qi-9           10           ll               12               12                               IS           19               ~0 Scouf NTIAL                         OCCUAAKi4CK               Rc)OAT                           RKVISIotl<<
Q<<r Lca!AO
                    <<ir<<<<r ACTION Fut<<JAS KVKNTYKAA
                                    ~7S 21        22 cFFKCT
                                                      ~
                                                            ~
23 SI4UTCOWN
                                                                              ~02 24 itfPORT HO.
5 26
                                                                                                        ~<<
21
                                                                                                                        ~01 8
At-.ACNMKNT COOK 29 Nr ROM
                                                                                                                                                ~X 0
PFAue CQMr.
3'I
                                                                                                                                                                              =
HO.
22 COMPONK H r TAKcN *I TION                 Ctl PI.ANT             MfT<<IQO                     I<<OVAS   22     SUBMITTKO           FOA!45ua.                                   u*NVFACTUAKR LBOLJS                         LRS>>IS
                                              <<5                    26              3)
                                                                                                                  >>>>S 4l LJS MS 42 SUPPLISR 43                 44                 41 CAUSE DSSCSIIPTION <<I<<NO CORRECTIVE ACTIONS Q21 0           The cask dro                     was         not anal zed in accordance with FSAR methodolo y, there by leading                 to     a   non-conservative basis for T.S. 3.9.14. A boundin analy sis     has been                 erformed and                   will       be   administrativel                       a     lied in             case use o the soent fuel cask is re uired before                                                           ro osed Technical                                 ecificationl S~
a                                                  S amendment               can be submitted. and                             a     roved       b     the     NRC.
9 1 A ILITY DOO S.A<<VS LOS            ~i' ;I )OWfA                           OTIIKR5 ATUS
                                                                                                    ~DQSI          NOtifiCatiOri VrOm 7/4
                                                        'A 8                   Is                 18       12                                 44     45                                                                                          KO ACTIVITY .CQNTK NT 1      8
            ~zQ>>          ~zQS'A AKLKASKO OF Afl.KASK 10            II AM(IVNT~F*CTIVITYQSS 44            45 gA LOCA'tloN OF <<IKLKASK          Q 30 FKRSONNfL KX)OSUAKS
            ~OII         '0 Q<<r   ~ZQB<<
1                           II        I'2         13                                                                                                                                         30 Pf ASCNNK L IPUL'Ates
            ~o"'8'"0           Q'"'"'                 "       .                 III<<
pZg    a     2               II         l2                                                                                                                                                     80 LCSS OF CA OAMAC- 0 F*CILITY TYPf.     of >>AlrtloN                     Q42 zQ2 10                                                                                                                                                                     30 rueLICITY                                                                                                                                            NAC USE ONI.Y ISSUKO     OKSCAIPI.CN LPJ
            ~glQ44 9         10                                                                                                                             ee  '69                                W NAME OP PREPARER                                                                                               PIION6:
I       '<<
I
 
Reportable Occurrence 335-78-25 Licensee Event Report Pa e Two Additional Event Descri tion During power operation, the Architect/Engineer found an error in the accident analysis for the drop of a spent fuel cask into the spent fuel pool. As a result of the error; Specification 3.9.14 on spent fuel handling is non-conservative. The analysis was originally performed assuming a single pendu-lum, which gave a drop radius of 133 inches. The FSAR methodology, however, specifies a double pendulum, which gives a drop radius of 248 inches. This means that a dropped cask could impact more, fuel elements, therefore, "fresh" spent fuel must be stored farther from the cask area and/or allowed to decay longer before the cask can be moved into the spent fuel pool. The probable consequences of the occurrence are not signifi cant because fuel was stored in the pool for only 2 months before the error was found, and there is considerable conservatism in the dose rate analysis for the cask drop acci-dent. This was the first occurrence involving a calculational error associated with a spent fuel system.}}

Latest revision as of 05:29, 21 October 2019

LER 1978-025-00 for St. Lucie Unit 1, on 07/24/78 Concerning an Error in the Analysis for the Cask Drop Accident Which Makes the Technical Specification 3.9.14 Non-Conservative
ML18127A651
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/07/1978
From: Schmidt A
Florida Power & Light Co
To: O'Reilly J
NRC/RGN-II, NRC/IE
References
PRN-LI-78-219 LER 1978-025-00
Download: ML18127A651 (5)


Text

of(<< (o0 REGULATORY XNFORNATION DISTRIBUTION SY TEN <RXDS)

DXSTRIBUTION FOR INCOMING NATERIAL 50-335 REC: OREXLLY J P, GRG; SCHMIDT A D DOCDATE: 08/07/78 NRC FL PWR 8( LIGHT DATE RCVD: 08/15/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT 50-335/78-25 ON 07/24/78 CONCERNING AN ERROR IN THE ANALYSIS FOR Tl-IE CASK DROP ACCIDENT WHICI.I MAKES TFIE TECH SPEC 3. 9. 14 NGI4-CONSERVATI VI:.

PLANT MANE: ST LUCXE REVIEWER INITIAL: XBT

~

4I:1 DlSTRIBUTOR INITIAL:

+~+cs<sss+u<>'s< > <<><>+<H', DISTRIBUTION OF THIS NATERXAI XS AS FOLLOWS %%%%%%%%4%%%%%%%%%

INC1DEI4T, REPORTS (DISTRIBUTION CODF A002)

FOR ACTION: B CI.IIEF GRBN4 "BC~~+W/4 ENCL INTERNAL: REG F WlENCL NRC PDR4'~W/ENCL

'44~W/2 ENCL NIPC~H~W/3 ENCL I 5 C SYSTEMS BR~HIW/ENCL EMERGENCY PLAN BR+%W/ENCL NOVAK/CFIECK+<tW/ENCL EEB~~W/ENCL AD FOR ENG~~~~W/ENCL PLANT SYSTENS BR+>W/ENCL FIANAUER~~ "W/ENCL AD FGR Pl ANT SYSTENS%<W/ENCL A13 FOR SYS 8c PROJ4l+W/ENCL REACTOR SAFETY BR>>W/ENCL ENGXNEERING BR~~W/ENCL VOLLMER/BUNCH+wW/ENCL KREGER/J. COLLINS+4~W/ENCL POWER SYS BR~~W/ENCL K SEYFR1T/I E~~~~W/ENCL EXTERNAL: LPDR S'T PIERCEi FL++W/ENCL TIC, I IZ CARTER~~W/ENCL MSX C~H~W/ENCL ACRS CAT B++W/16 ENCL DISTRIBUT10N: LTR 45 ENCL 45 CONTROL NBR: 782230377 SIZE: 3P 4

%%%%%%%%%%.2%%%%%4I%%%%%%%%%8c 0M 0F%0f%%0$ TIIE END

g'k a +~

//

FLORIDA POPOVER 5 LIGHT COMPANY August 7, 197g-P RN" L I 219m~

I

<<X) <..

C/l

~C/l~

n Mr. James P. O'Reilly, Director, Region II CA Office of Inspection and Enforcement, U. S. Nuclear Regulatory Commission Peachtree Street, N. M., Suite 1217

'30 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

REPORTABLE OCCURRENCE 335-78-25 ST. LUCIE UNIT 1 DATE OF OCCURRENCE: JULY 24 1978 CASK DROP ANALYSIS The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide prompt notification of the subject occurrence.

Very truly yours, JiP A. D. Schmidt Vice President Power Resour ces MAS/ms Attachment cc: Harold F. Reis, Esquire Director, Office of Inspection and Enforcement (40)

Director, Office of Management Information and Program Control (3) 782230377 PLOPLF . ~ . SERVING PFOPI.F

0 NAC FORM 666 U<<*NUCLEAR AEGULATORY COMMISSION P TTI LlCENSEF EVENT REPORT CONTROL BLQCICI lQI (PLEASE PAINT OR TYPE ALI. A'EQUIREO INFORMATIONI I

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3.9. 1 4 i s .non-conservati ve. It has been determined that a dro ed cask could impact a larger radius, therefore, a longer decay time is needed before a cask. can be moved into the spent fuel pool cask compartment.

There are no adverse conse uences because of the small amount of fuel in the pool and the high degree of conservatism in the analysis.

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>>>>S 4l LJS MS 42 SUPPLISR 43 44 41 CAUSE DSSCSIIPTION <<I<<NO CORRECTIVE ACTIONS Q21 0 The cask dro was not anal zed in accordance with FSAR methodolo y, there by leading to a non-conservative basis for T.S. 3.9.14. A boundin analy sis has been erformed and will be administrativel a lied in case use o the soent fuel cask is re uired before ro osed Technical ecificationl S~

a S amendment can be submitted. and a roved b the NRC.

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Reportable Occurrence 335-78-25 Licensee Event Report Pa e Two Additional Event Descri tion During power operation, the Architect/Engineer found an error in the accident analysis for the drop of a spent fuel cask into the spent fuel pool. As a result of the error; Specification 3.9.14 on spent fuel handling is non-conservative. The analysis was originally performed assuming a single pendu-lum, which gave a drop radius of 133 inches. The FSAR methodology, however, specifies a double pendulum, which gives a drop radius of 248 inches. This means that a dropped cask could impact more, fuel elements, therefore, "fresh" spent fuel must be stored farther from the cask area and/or allowed to decay longer before the cask can be moved into the spent fuel pool. The probable consequences of the occurrence are not signifi cant because fuel was stored in the pool for only 2 months before the error was found, and there is considerable conservatism in the dose rate analysis for the cask drop acci-dent. This was the first occurrence involving a calculational error associated with a spent fuel system.