ML18127A670: Difference between revisions
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{{#Wiki_filter:a fm/~~REGULATORY INFORMATION DISTRIBUTION SYSTEl'1 (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC'REILLY J P | {{#Wiki_filter:a fm/~~ | ||
NO COPIES RECEIVED | REGULATORY INFORMATION DISTRIBUTION SYSTEl'1 ( RIDS) | ||
DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC'REILLY J P ORG: SCHMIDT A D DOCDATE: 04/27/78 NRC FL PIJR 8( LIGHT DATE RCVD: 05/09/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED | |||
==SUBJECT:== | ==SUBJECT:== | ||
LTR i ENCL i FORWARDING LICENSEE EVENT REPT (RO 50-335/78-i3) | LTR i ENCL i FORWARDING LICENSEE EVENT REPT (RO 50-335/78-i3) ON 03/28/78 CONCERNING DURING SHUTDOWN FOR REFUELINGt DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC | ||
ON 03/28/78 CONCERNING DURING SHUTDOWN FOR REFUELINGt DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC 3.4.8...W/ATT.PLANT NAME: ST LUCIE 8i | : 3. 4. 8... W/ATT. | ||
'5 POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY | PLANT NAME: ST LUCIE 8i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: | ||
<t'II)E 10.1 ISTRIBUTION: | DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002) | ||
LTR 45 ENCL 45 S I ZF: 2P+3P K%%%4%%%%4 | FOR ACTION: BR C ~N/4 ENCL INTERNAL: R G FILE~~~W/ENCL NRC PDR+>W/ENCL I ~~W Ne MIPC++W/3 ENCL SCHROEDERf I PPOL I TO%4M/ENCL HOUSTON+>W/ENCL NOVAK/CHECK44W/ENCL EEB4+W/ENCL KNIGHT++WfENCL BUTI ER4+Wf ENCL HANAUER~~~l J/ENCL TEDESCO~~W/ENCL EI SENHUT+~N/ENCL BAER~~~N/ ENCL SHAO~~~W/ENCL VOLLMER/BUNCHwwW/ENCL KREGER/ J. COLL INS++WfENCL ROSA%+ltJ/ENCL K SEYFR IT/IE+4FW/ENCL EXTERNAL: LPDR S FT PIERCE( FL++W/ENCL TIC4s>W/ENCL NSIC++WfENCL ACRS CAT B4l ~W/16 ENCL | ||
%%%%%%%4M%%%%%%%%%%%%%%%4'HE END | '5 POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY <t'II)E 10. 1 ISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781300092 S I ZF: 2P+3P K%%%4%%%%4 %%%%%%%4M%%%%%%%%%%%%%%%4'HE END | ||
':.,<~F;j (j 9:-:-FLORIOA POWER III LIGHT COMPANY ,April 27, 1978 Mr.James P.O'Reilly, Director, Region II Office of Inspection and Enforcement U.S.Nuclear.Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, Georgia 30303 | ':., <~F;j (j 9:-:- | ||
FLORIOA POWER III LIGHT COMPANY | |||
,April 27, 1978 PRN-LI-7 8+~21 (C (A | |||
fll~ | |||
WP1 | |||
\A Rc7 | |||
~ | |||
( Pl C(7 CP~ | |||
Mr. James P. O'Reilly, Director, Region II Cl | |||
-<ChC 1 | |||
'(1 Office of Inspection and Enforcement U. S. Nuclear. Regulatory Commission C7 C7 230 Peachtree Street, N.W., Suite 1217 Cfk Atlanta, Georgia 30303 | |||
==Dear Mr.O'Reilly:== | ==Dear Mr. O'Reilly:== | ||
REPORTABLE OCCURRENCE 335-78-13 ST.LUCIE UNIT 1.DATE OF OCCURRENCE: | |||
MARCH 28, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE EQUIVALENT I-131 ,~The attached Licensee Event Report is being submitted in accordance.with Technical Specification 6.9 to provide 30-day notification of the subject'ccurrence. | REPORTABLE OCCURRENCE 335-78-13 ST. LUCIE UNIT 1 | ||
Very truly yours, A.D.Schmidt Vice President Power Resources MAS/mb Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)L | .DATE OF OCCURRENCE: MARCH 28, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE EQUIVALENT I-131 ,~ | ||
Reportable Occurrence 335-78-13.,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION | The attached Licensee Event Report is being submitted in accordance .with Technical Specification 6.9 to provide 30-day notification of the subject'ccurrence. | ||
=TECHNICAL SPECIFICATION REPORT"DOSE EQUIVALENT IODINE 1.Reactor power history starting 48 hours prior to the first sam le in which the limit was exceeded Prom 3/26/78 92200 until 3/28/78 90900, the plant was at.an average steady state power of 99.5%, at, which time preparations.for refueling shutdown were begun:.3/28/78 3/28/78 | Very truly yours, A. D. Schmidt Vice President Power Resources MAS/mb Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30) | ||
Region | Director, Office of Management Information and Program Control (3) 7813000P2 L | ||
[ASE PRINT AU.REGUIRED INFORMATION) | PEOPLE... SERVING PEOPLE | ||
P Reportable Occurrence 335-78-13 | |||
[iran]~oo o~z E//t 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER CESCAIPTIQN Irr4j~oo o N/A~7 89 11 12 | .,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION | ||
7 89 80 fr19J 7 89 60>f.A.Schoppman PHONE'057 552-3802 CI'0 dd'I 4 d dT | =TECHNICAL SPECIFICATION REPORT "DOSE EQUIVALENT IODINE | ||
: 1. Reactor power history starting 48 hours prior to the first sam le in which the limit was exceeded Prom 3/26/78 92200 until 3/28/78 90900, the plant was at. an average steady state power of 99.5%, at, which time preparations | |||
.for refueling shutdown were begun: | |||
.3/28/78 81000 Rx Power 92.4% | |||
3/28/78 81100 Rx Power 69.0% | |||
'/28/78 91200 Rx Power 30.0% | |||
3/28/78 '81300 Off-line (Hot. | |||
Standby for S/G Safety Valve Testing) 3/28/78 92245* Off-line (Hot Standby for S/G Safety Valve Testing)'First Iodine Sample > 1.0 yCi/gram DEQ | |||
: 2. Fuel burnu b core re ion Puel burnup by octants: | |||
Region 1 11291.08) | |||
Region 2 12256.19) | |||
Average Burnup in .Megawatt Days Region R 5 11521.31) 11521 31) per Metric Ton ,'Uranium'(llHD/MTU) | |||
Region 6 12117.92) | |||
Region 7 11453.26) | |||
Region 8 12212.59) | |||
Total Core Average Burnup 11822.35 MWD/MTU | |||
CONTROL BLOCK: | |||
[ ASE PRINT AU. REGUIRED INFORMATION) 1 UCENSEE LCENSE EVENT NAME LCENSE NUMEEA TYPE TYPE 01 F L S L S 1 0 0 0 0 0 0 0 0 0 d 1 1 1 1 ~03 89 | |||
~ | |||
7 14 15 =25 26 30 31 32 AEPOAT AEPOAT CATEGORY SOURCE OOCKET NUMecA EVENT OATE AEPOAT OATE TYPE'OD1]OON'T L 0 5 0 0 3 3 5 0 3 2 8 7 8 0 4 2 7 7 8 7 8 57 58 59 60 61 68 69 74 75 80 I | |||
EVENT OESCRlPTION QO 2 Durin shutdown for re'fueling, Dose Equivalent (DEQ) Iodine exceeded the Technical' 7 8 9 80 S ecification 3.4.8.a limit of 1.0 pCi/gram DOSE EQUIVALENT I-131. The DEQ Iodine was 69 tOD~] first measured above the limit at 2245 on 3/28/78 while the plant was in hot standby 7 8 9 60 g for required surveillance testing prior to continuation of the cooldown. The attached 7 8 9 | |||
[OD~} sheets contain the information required by (Continued -under ADDITIONAL FACTORS) 7 8 9 FAME 80 SYSTEM CAUSE CCMPQ RENT COMPONENT | |||
[Og7] ~@ | |||
CODE Q | |||
COQE | |||
~E 7 CorrtPONENT COOE 0 E LI I I SUPPUM N C MANUF~iFER 4 9 0 VIQLATICN N | |||
7 8 9 10 11 12 17 44 47 a8 CAUSF OESCRIPTION Qg8 After an extended eriod of ower o eration with a nominal level of fuel leaka,e, the 7 9 eo gg lant sbutdornr ttansient was sufficient to cause Iodine to build up (Iodine spiking 7 8 9 | |||
~10 7 BS ia i ca acitv for a short: eriod of time. | |||
FACIUTY McTHQO OF 80 STATUS POWE'A OTHER STATUS OISCOVERY oiscovERY oescaipnioN Qi r ~H ~0 0 0 gee Event oesc. N/A 8 S 10 12 13 45 dt6 80 FORM OF ACTMTY CO/TENT AELcckSEO OF RELEASE AMOUNT OF ACFiVITY LOCATION OF A~OSE | |||
~z ~z N/A 7 9 9 10 11 80 PERSONNEL EXPOSURES NUMia'EA TYPE OESCRIPTIQN | |||
[iran] ~oo o ~z E//t 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER CESCAIPTIQN Irr4j ~oo o N/A ~ | |||
7 89 11 12 PROpdLSLE CONSEGUENC S N/A 7 8 9 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPnQN N/A 89 10 80 PUBLICITY N/A 7 8 9 ~ 80 AOOITIONAL FACTORS CG Technical Soecification 3.4.8.a. This was the first event of this type. (335-78-13). | |||
7 89 80 fr19J 7 89 60 | |||
>f. A. Schoppman PHONE'057 552-3802 CI'0 dd'I 4 d dT | |||
page three Re: Reportable Occurrence 335-78-13 | |||
: 3. Clean-up flow history starting 48 hours prior to the first sam le in which the limit was exceeded From 3/26/78 92200 until 3/28/78 81400, purification flow rate was -88 gpm (two charging pumps). | |||
At 1400 on 3/28/78 a third charging pump was started, thereby raising purification flow rate to -132 gpm. | |||
The purification flow rate was maintained at -132 gpm until the start of Shutdown Cooling (SDC) at 0430 on 3/29/78. | |||
NOTE: Clean-up demineralization consisted of a mixed bed at a 1:1 ratio, cation to anion, in series with a straight anion bed. Bed volumes were 36 cubic feet each. | |||
: 4. History of de-gassing operation'tarting 48 hours prior to the first samole in which the limit was exceeded DATE LOCATION H2% H2 (cc/k ) | |||
3/20/78 VCT gas space ,95 3/21/78 RCS dissolved gas 12.1 3/23/78 Shifted to H2 regulator on VCT cover gas. | |||
3/24/78 RCS dissolved gas 16. 9 3/26/78 VCT purged several times with N2'. | |||
3/27/78 VCT gas space 3/28/78 RCS dissolved gas 90045 2;.6 3/28/78 RCS dissolved gas 90930 1.7 3/28/78 VCT gas space 91800 6 3/28/78 Purged VCT with N2 92000 3/29/78 VCT gas space 1.0 | |||
Page four Re: Reportable Occurrence 335-78-13 | |||
: 5. .The time duration when the specific activity of the primary coolant exceeded 1.0 pCi/qram DOSE EQUIVALENT I-131. | |||
Iodine 131 Dose Equivalent was greater then 1.0 pCi/gram from 3/28/78 92245 to 3/29/78 gll30. The total time above 1.0 pCi/gram was 12.75 hours. | |||
: 6. Results of S ecific Activit Anal sis (pCi/ ram) | |||
DATE TIME I-131 I-132 I-133 DEQ 3/28/78 1500 6.7 E-1 6.7 E-1 6.7 E-1 3.1 E-1 .89 3/28/78 2245 1. 6 E-0 ?,. 6 E-1 1.2 E-0 3.2 E-1 1.91 3/29/78 0100 1. 13 E-0 9.1 E-2 8.15 E-1 1.9 E-1 l. 37 3/29/78 0420 1.23 E-0 6.5 E-2 7.8 E-1 1.5 E-1 l. 46 3/29/78 0730 9.87 E-1 3.03 E-2 5.84 E-1 8.9 E-2 l. 15 3/29/78 1130 4.99 E-1 2. 37 E-1 .56 | |||
0}} |
Latest revision as of 06:29, 21 October 2019
ML18127A670 | |
Person / Time | |
---|---|
Site: | Saint Lucie |
Issue date: | 04/27/1978 |
From: | Schmidt A Florida Power & Light Co |
To: | O'Reilly J NRC/IE, NRC/RGN-II |
References | |
PRN-LI-78-121 LER 1978-013-00 | |
Download: ML18127A670 (9) | |
Text
a fm/~~
REGULATORY INFORMATION DISTRIBUTION SYSTEl'1 ( RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC'REILLY J P ORG: SCHMIDT A D DOCDATE: 04/27/78 NRC FL PIJR 8( LIGHT DATE RCVD: 05/09/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR i ENCL i FORWARDING LICENSEE EVENT REPT (RO 50-335/78-i3) ON 03/28/78 CONCERNING DURING SHUTDOWN FOR REFUELINGt DOSE EQUIVALENT IODINE EXCEEDED TECH SPEC
- 3. 4. 8... W/ATT.
PLANT NAME: ST LUCIE 8i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTION: BR C ~N/4 ENCL INTERNAL: R G FILE~~~W/ENCL NRC PDR+>W/ENCL I ~~W Ne MIPC++W/3 ENCL SCHROEDERf I PPOL I TO%4M/ENCL HOUSTON+>W/ENCL NOVAK/CHECK44W/ENCL EEB4+W/ENCL KNIGHT++WfENCL BUTI ER4+Wf ENCL HANAUER~~~l J/ENCL TEDESCO~~W/ENCL EI SENHUT+~N/ENCL BAER~~~N/ ENCL SHAO~~~W/ENCL VOLLMER/BUNCHwwW/ENCL KREGER/ J. COLL INS++WfENCL ROSA%+ltJ/ENCL K SEYFR IT/IE+4FW/ENCL EXTERNAL: LPDR S FT PIERCE( FL++W/ENCL TIC4s>W/ENCL NSIC++WfENCL ACRS CAT B4l ~W/16 ENCL
'5 POT Sl"P'I,'".TE'P PL'R Ill',C'111.ATORY <t'II)E 10. 1 ISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781300092 S I ZF: 2P+3P K%%%4%%%%4 %%%%%%%4M%%%%%%%%%%%%%%%4'HE END
':., <~F;j (j 9:-:-
FLORIOA POWER III LIGHT COMPANY
,April 27, 1978 PRN-LI-7 8+~21 (C (A
fll~
WP1
\A Rc7
~
( Pl C(7 CP~
Mr. James P. O'Reilly, Director, Region II Cl
-<ChC 1
'(1 Office of Inspection and Enforcement U. S. Nuclear. Regulatory Commission C7 C7 230 Peachtree Street, N.W., Suite 1217 Cfk Atlanta, Georgia 30303
Dear Mr. O'Reilly:
REPORTABLE OCCURRENCE 335-78-13 ST. LUCIE UNIT 1
.DATE OF OCCURRENCE: MARCH 28, 1978 TECHNICAL SPECIFICATION 3.4.8.a DOSE EQUIVALENT I-131 ,~
The attached Licensee Event Report is being submitted in accordance .with Technical Specification 6.9 to provide 30-day notification of the subject'ccurrence.
Very truly yours, A. D. Schmidt Vice President Power Resources MAS/mb Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)
Director, Office of Management Information and Program Control (3) 7813000P2 L
PEOPLE... SERVING PEOPLE
P Reportable Occurrence 335-78-13
.,Licensee Event Report Pa e two SUPPLEMENTARY INFORMATION
=TECHNICAL SPECIFICATION REPORT "DOSE EQUIVALENT IODINE
- 1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sam le in which the limit was exceeded Prom 3/26/78 92200 until 3/28/78 90900, the plant was at. an average steady state power of 99.5%, at, which time preparations
.for refueling shutdown were begun:
.3/28/78 81000 Rx Power 92.4%
3/28/78 81100 Rx Power 69.0%
'/28/78 91200 Rx Power 30.0%
3/28/78 '81300 Off-line (Hot.
Standby for S/G Safety Valve Testing) 3/28/78 92245* Off-line (Hot Standby for S/G Safety Valve Testing)'First Iodine Sample > 1.0 yCi/gram DEQ
- 2. Fuel burnu b core re ion Puel burnup by octants:
Region 1 11291.08)
Region 2 12256.19)
Average Burnup in .Megawatt Days Region R 5 11521.31) 11521 31) per Metric Ton ,'Uranium'(llHD/MTU)
Region 6 12117.92)
Region 7 11453.26)
Region 8 12212.59)
Total Core Average Burnup 11822.35 MWD/MTU
CONTROL BLOCK:
[ ASE PRINT AU. REGUIRED INFORMATION) 1 UCENSEE LCENSE EVENT NAME LCENSE NUMEEA TYPE TYPE 01 F L S L S 1 0 0 0 0 0 0 0 0 0 d 1 1 1 1 ~03 89
~
7 14 15 =25 26 30 31 32 AEPOAT AEPOAT CATEGORY SOURCE OOCKET NUMecA EVENT OATE AEPOAT OATE TYPE'OD1]OON'T L 0 5 0 0 3 3 5 0 3 2 8 7 8 0 4 2 7 7 8 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT OESCRlPTION QO 2 Durin shutdown for re'fueling, Dose Equivalent (DEQ) Iodine exceeded the Technical' 7 8 9 80 S ecification 3.4.8.a limit of 1.0 pCi/gram DOSE EQUIVALENT I-131. The DEQ Iodine was 69 tOD~] first measured above the limit at 2245 on 3/28/78 while the plant was in hot standby 7 8 9 60 g for required surveillance testing prior to continuation of the cooldown. The attached 7 8 9
[OD~} sheets contain the information required by (Continued -under ADDITIONAL FACTORS) 7 8 9 FAME 80 SYSTEM CAUSE CCMPQ RENT COMPONENT
[Og7] ~@
CODE Q
COQE
~E 7 CorrtPONENT COOE 0 E LI I I SUPPUM N C MANUF~iFER 4 9 0 VIQLATICN N
7 8 9 10 11 12 17 44 47 a8 CAUSF OESCRIPTION Qg8 After an extended eriod of ower o eration with a nominal level of fuel leaka,e, the 7 9 eo gg lant sbutdornr ttansient was sufficient to cause Iodine to build up (Iodine spiking 7 8 9
~10 7 BS ia i ca acitv for a short: eriod of time.
FACIUTY McTHQO OF 80 STATUS POWE'A OTHER STATUS OISCOVERY oiscovERY oescaipnioN Qi r ~H ~0 0 0 gee Event oesc. N/A 8 S 10 12 13 45 dt6 80 FORM OF ACTMTY CO/TENT AELcckSEO OF RELEASE AMOUNT OF ACFiVITY LOCATION OF A~OSE
~z ~z N/A 7 9 9 10 11 80 PERSONNEL EXPOSURES NUMia'EA TYPE OESCRIPTIQN
[iran] ~oo o ~z E//t 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER CESCAIPTIQN Irr4j ~oo o N/A ~
7 89 11 12 PROpdLSLE CONSEGUENC S N/A 7 8 9 LOSS OR OAMAGE TO FACILITY TYPE OESCAIPnQN N/A 89 10 80 PUBLICITY N/A 7 8 9 ~ 80 AOOITIONAL FACTORS CG Technical Soecification 3.4.8.a. This was the first event of this type. (335-78-13).
7 89 80 fr19J 7 89 60
>f. A. Schoppman PHONE'057 552-3802 CI'0 dd'I 4 d dT
page three Re: Reportable Occurrence 335-78-13
- 3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sam le in which the limit was exceeded From 3/26/78 92200 until 3/28/78 81400, purification flow rate was -88 gpm (two charging pumps).
At 1400 on 3/28/78 a third charging pump was started, thereby raising purification flow rate to -132 gpm.
The purification flow rate was maintained at -132 gpm until the start of Shutdown Cooling (SDC) at 0430 on 3/29/78.
NOTE: Clean-up demineralization consisted of a mixed bed at a 1:1 ratio, cation to anion, in series with a straight anion bed. Bed volumes were 36 cubic feet each.
- 4. History of de-gassing operation'tarting 48 hours prior to the first samole in which the limit was exceeded DATE LOCATION H2% H2 (cc/k )
3/20/78 VCT gas space ,95 3/21/78 RCS dissolved gas 12.1 3/23/78 Shifted to H2 regulator on VCT cover gas.
3/24/78 RCS dissolved gas 16. 9 3/26/78 VCT purged several times with N2'.
3/27/78 VCT gas space 3/28/78 RCS dissolved gas 90045 2;.6 3/28/78 RCS dissolved gas 90930 1.7 3/28/78 VCT gas space 91800 6 3/28/78 Purged VCT with N2 92000 3/29/78 VCT gas space 1.0
Page four Re: Reportable Occurrence 335-78-13
- 5. .The time duration when the specific activity of the primary coolant exceeded 1.0 pCi/qram DOSE EQUIVALENT I-131.
Iodine 131 Dose Equivalent was greater then 1.0 pCi/gram from 3/28/78 92245 to 3/29/78 gll30. The total time above 1.0 pCi/gram was 12.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
- 6. Results of S ecific Activit Anal sis (pCi/ ram)
DATE TIME I-131 I-132 I-133 DEQ 3/28/78 1500 6.7 E-1 6.7 E-1 6.7 E-1 3.1 E-1 .89 3/28/78 2245 1. 6 E-0 ?,. 6 E-1 1.2 E-0 3.2 E-1 1.91 3/29/78 0100 1. 13 E-0 9.1 E-2 8.15 E-1 1.9 E-1 l. 37 3/29/78 0420 1.23 E-0 6.5 E-2 7.8 E-1 1.5 E-1 l. 46 3/29/78 0730 9.87 E-1 3.03 E-2 5.84 E-1 8.9 E-2 l. 15 3/29/78 1130 4.99 E-1 2. 37 E-1 .56
0