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| number = ML18110A879
| number = ML18110A879
| issue date = 06/27/1977
| issue date = 06/27/1977
| title = LER 1977-335-27 for St. Lucie, Unit 1 on Dropped Control Element Assembly No. 39 Initiating a Turbine Runback
| title = On Dropped Control Element Assembly No. 39 Initiating a Turbine Runback
| author name = Schmidt A D
| author name = Schmidt A
| author affiliation = Florida Power & Light Co
| author affiliation = Florida Power & Light Co
| addressee name = Moseley N C
| addressee name = Moseley N
| addressee affiliation = NRC/IE, NRC/RGN-II
| addressee affiliation = NRC/IE, NRC/RGN-II
| docket = 05000335
| docket = 05000335
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:NRC FOQM 196 U.S.NUCLEAR REGULATORY COM,,~SION
{{#Wiki_filter:NRC FOQM 196 U.S. NUCLEAR REGULATORY COM,,~SION
<2~I NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL DOCKET NUMBER o-3 S F I LE NUM BE R TO: ETTE R RIG INAL Q COPY DESCRIPTION 0 NOTO R IZ E D CONC LASS IF I E D Mr.Norman C Moseley PROP INPUT FORM ENCLOSURE FROM: Florida Power&Light Company Miami, Florida A.D~Schmidt DATE OF DOCUMENT 6/27/77 DATE RECEIVED 7/22/77 NUMBER OF COPIES RECEIVED I>cc~~~Licensee Event Report (RO 50-335/77-27) on 5/27/77 concerning Control Element Assembly (CEA)f39 drppping PLANT VIAIIE: St.Lucie Unit No l R JL 7/22/77 (l-P))CKNOWLZDGZD (2 P)DO NOT REMOVE NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.COLLINS FOR ACTION/INFORMATION INTERNAL D IST RI BUTION EXTERNAL DISTRIBUTION CONTROL NUMBER ACRS 16 SENT AS AT I 772030Z50 NRC FORM 196 I2 76)
<2~
P.O.BOX 013100, MIAMI, FL 33101 I'ps~uA FLORIDA POWER&LIGHT COMPANY Regu)Bye~Fil C PRN-LI-7 7-2 0 8 Mr.Norman C.Moseley, Director, Region II Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission 230 Peachtree Street, N.W., Suite 1217 Atlanta, Georgia 30303
I NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL DOCKET NUMBER o-3 S FI LE NUMBE R TO:
ETTE R RIG INAL Q COPY DESCRIPTION 0 NOTO R IZE D CONC LASS IF I E D Mr. Norman C
Moseley PROP INPUT FORM ENCLOSURE FROM:
Florida Power
& Light Company Miami, Florida A.
D~ Schmidt DATE OF DOCUMENT 6/27/77 DATE RECEIVED 7/22/77 NUMBER OF COPIES RECEIVED I >cc ~~~
Licensee Event Report (RO 50-335/77-27) on 5/27/77 concerning Control Element Assembly (CEA) f39 drppping PLANT VIAIIE:
St. Lucie Unit No l RJL 7/22/77 (l-P)
) CKNOWLZDGZD (2 P)
DO NOT REMOVE NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.
COLLINS FOR ACTION/INFORMATION INTERNALDISTRI BUTION EXTERNALDISTRIBUTION CONTROL NUMBER ACRS 16 SENT AS AT I 772030Z50 NRC FORM 196 I2 76)


==Dear Mr.Moseley:==
P. O. BOX 013100, MIAMI, FL 33101 I'ps~uA FLORIDAPOWER & LIGHTCOMPANY Regu)Bye~
REPORTABLE OCCURRENCE 335-77-27 ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
Fil C
PRN-LI-77-2 0 8 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U.
S. Nuclear Regulatory Commission 230 Peachtree
: Street, N. W., Suite 1217 Atlanta, Georgia 30303
 
==Dear Mr. Moseley:==
REPORTABLE OCCURRENCE 335-77-27 ST.
LUCIE UNIT 1 DATE OF OCCURRENCE:
MAY 27, 1977 CEA 39 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
MAY 27, 1977 CEA 39 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.
Very truly yours, D.c x, t Vice President Power Resources MAS/cpc Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)772030250 PEOPLE..~SERVING PEOPLE II 4 I I'I 1 I A t (F CONTROL BLOCK: 1 LICENSEE EVENT REPORT CPLAASE PAINT ALL PEDUIAED INFDAFEATIDNI LCEAISEE NAME[OD1]F L S L S 1 14 15 7 89 LCENSE NUMBER 0 0-0 0 0 0 0-UCENSE EVENT TYPE TYPE 0 0 4 1 1 1 1~0033'25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE Ioa~]coNT~~~o 7 8 57 58 59 60 61 EVENT DESCRIPTION toad With the lant o eratin DOCKET NUMBER EVENT DATE REPORT DATE 0~0 5 2 68 69 74 75 at ower, and the Control Element Drive S stem 80 89 I CEDS in the Auto Se uential Mode 80 Control Element Assembl CEA 439 7 8 9 80 tpo~j h EA i't a urbine runback.Durin the run-7 8 9[oOsj 7 8 9~06 80 edwa re ulatin valve failed o en due 80 h reb causin th"A" main feedwater um to tri on low 89 SYSTEM CAUSE CODE CODE COMPONENT CODE IDD~]~RI B~B c 0 N 0 7 8 9 10 11 12 17 CAUSE DESCRIPTION I006 A was found to have a PRME COMPONENT N COMPONENT MANUFACTURER C 4 9 0 fault insertion timer 48 which would cause the 80 7 8 9 80l00m rod to be released u on recei t of an insertion si nal.The timer was re 7 8 9 laced and tested rior to returnin the lant to ower o eration.80 OTHER STATUS NA PROBABLE CONSEQUENCES Q~g 7 8 9 LOSS OR DAMAGE TO FACILITY TYPF DESCRIPTION z 7 89 10 P U8LICITY 8 9 ADDITIONAL FACTORS 7 89 FACIUTY STATUS POWFR B~03 7 8 9 10 12 13 FORM OF ACTIVITY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Qsj~oo o z'7 89 11 12 13 PERSONNEL IN JURIES NUMBER DESCRIPTION
Very truly yours, D.
~IA~00 O 7 89 11 12 METHOD OF DISCOVERY 44 45 46 44 45 NA NA NA NA NA DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80~80[QE 7 89 Qs]7 89 for continuation of Event Descri tion.60 80 NAM6 M.A.Scho man PHONE: (3 05)552-38 02 GFO 681~657 H  
c x, t Vice President Power Resources MAS/cpc Attachment cc:
~~fw REPORTABLE OCCURRENCE 335-77-27 LICENSEE EVENT REPORT PAGE TWO EVENT DESCRIPTION (Continued) suction pressure.This led to a reactor trip on low steam generator level approximately four minutes after the CEA dropped.This report is generated due to Technical Specification 3.1.3.le (CEA alignment requirements).
Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)
This was the fourth"dropped CEA" occurrence (LER's 335-76-37, 335-77-6, 335-77-17).
Director, Office of Management Information and Program Control (3) 772030250 PEOPLE..
Since the four occurrences are unrelated with respect to cause, they are not con-sidered to be generically related.(335-77-27)  
~ SERVING PEOPLE
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F CONTROL BLOCK:
1 LICENSEE EVENT REPORT CPLAASE PAINT ALLPEDUIAED INFDAFEATIDNI LCEAISEE NAME
[OD1]
F L
S L
S 1
14 15 7
89 LCENSE NUMBER 0
0 0 0
0 0 0 UCENSE EVENT TYPE TYPE 0
0 4
1 1
1 1
~0033
'25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE Ioa~]coNT~ ~ ~
o 7
8 57 58 59 60 61 EVENT DESCRIPTION toad With the lant o eratin DOCKET NUMBER EVENT DATE REPORT DATE 0
~
0 5
2 68 69 74 75 at
: ower, and the Control Element Drive S stem 80 89I CEDS in the Auto Se uential Mode 80 Control Element Assembl CEA 439 7
8 9 80 tpo~j h
EA i't a
urbine runback.
Durin the run-7 8 9
[oOsj 7
8 9
~06 80 edwa re ulatin valve failed o en due 80 h reb causin th "A" main feedwater um to tri on low 89 SYSTEM CAUSE CODE CODE COMPONENT CODE IDD~] ~RI B
~B c
0 N
0 7
8 9 10 11 12 17 CAUSE DESCRIPTION I006 A
was found to have a
PRME COMPONENT N
COMPONENT MANUFACTURER C
4 9
0 fault insertion timer 48 which would cause the 80 7
8 9 80 l00m rod to be released u on recei t of an insertion si nal.
The timer was re 7
8 9 laced and tested rior to returnin the lant to ower o eration.
80 OTHER STATUS NA PROBABLE CONSEQUENCES Q~g 7
8 9 LOSS OR DAMAGE TO FACILITY TYPF DESCRIPTION z
7 89 10 P U8LICITY 8 9 ADDITIONAL FACTORS 7
89 FACIUTY STATUS POWFR B
~03 7
8 9
10 12 13 FORM OF ACTIVITY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY NA 7
8 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Qsj ~oo o
z
'7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION
~IA ~00 O
7 89 11 12 METHOD OF DISCOVERY 44 45 46 44 45 NA NA NA NA NA DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80
~80
[QE 7
89 Qs]
7 89 for continuation of Event Descri tion.
60 80 NAM6 M. A. Scho man PHONE: (3 05) 552-38 02 GFO 681
~ 657
 
H
 
~
~
fw REPORTABLE OCCURRENCE 335-77-27 LICENSEE EVENT REPORT PAGE TWO EVENT DESCRIPTION (Continued) suction pressure.
This led to a reactor trip on low steam generator level approximately four minutes after the CEA dropped.
This report is generated due to Technical Specification 3.1.3.le (CEA alignment requirements).
This was the fourth "dropped CEA" occurrence (LER's 335-76-37, 335-77-6, 335-77-17).
Since the four occurrences are unrelated with respect to cause, they are not con-sidered to be generically related.
(335-77-27)
 
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Latest revision as of 23:47, 5 January 2025

On Dropped Control Element Assembly No. 39 Initiating a Turbine Runback
ML18110A879
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 06/27/1977
From: Schmidt A
Florida Power & Light Co
To: Moseley N
NRC/IE, NRC/RGN-II
References
LER 1977-335-27
Download: ML18110A879 (7)


Text

NRC FOQM 196 U.S. NUCLEAR REGULATORY COM,,~SION

<2~

I NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL DOCKET NUMBER o-3 S FI LE NUMBE R TO:

ETTE R RIG INAL Q COPY DESCRIPTION 0 NOTO R IZE D CONC LASS IF I E D Mr. Norman C

Moseley PROP INPUT FORM ENCLOSURE FROM:

Florida Power

& Light Company Miami, Florida A.

D~ Schmidt DATE OF DOCUMENT 6/27/77 DATE RECEIVED 7/22/77 NUMBER OF COPIES RECEIVED I >cc ~~~

Licensee Event Report (RO 50-335/77-27) on 5/27/77 concerning Control Element Assembly (CEA) f39 drppping PLANT VIAIIE:

St. Lucie Unit No l RJL 7/22/77 (l-P)

) CKNOWLZDGZD (2 P)

DO NOT REMOVE NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.

COLLINS FOR ACTION/INFORMATION INTERNALDISTRI BUTION EXTERNALDISTRIBUTION CONTROL NUMBER ACRS 16 SENT AS AT I 772030Z50 NRC FORM 196 I2 76)

P. O. BOX 013100, MIAMI, FL 33101 I'ps~uA FLORIDAPOWER & LIGHTCOMPANY Regu)Bye~

Fil C

PRN-LI-77-2 0 8 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U.

S. Nuclear Regulatory Commission 230 Peachtree

Street, N. W., Suite 1217 Atlanta, Georgia 30303

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 335-77-27 ST.

LUCIE UNIT 1 DATE OF OCCURRENCE:

MAY 27, 1977 CEA 39 The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.

Very truly yours, D.

c x, t Vice President Power Resources MAS/cpc Attachment cc:

Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)

Director, Office of Management Information and Program Control (3) 772030250 PEOPLE..

~ SERVING PEOPLE

II 4

I I'I 1

I

A t

(

F CONTROL BLOCK:

1 LICENSEE EVENT REPORT CPLAASE PAINT ALLPEDUIAED INFDAFEATIDNI LCEAISEE NAME

[OD1]

F L

S L

S 1

14 15 7

89 LCENSE NUMBER 0

0 0 0

0 0 0 UCENSE EVENT TYPE TYPE 0

0 4

1 1

1 1

~0033

'25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE Ioa~]coNT~ ~ ~

o 7

8 57 58 59 60 61 EVENT DESCRIPTION toad With the lant o eratin DOCKET NUMBER EVENT DATE REPORT DATE 0

~

0 5

2 68 69 74 75 at

ower, and the Control Element Drive S stem 80 89I CEDS in the Auto Se uential Mode 80 Control Element Assembl CEA 439 7

8 9 80 tpo~j h

EA i't a

urbine runback.

Durin the run-7 8 9

[oOsj 7

8 9

~06 80 edwa re ulatin valve failed o en due 80 h reb causin th "A" main feedwater um to tri on low 89 SYSTEM CAUSE CODE CODE COMPONENT CODE IDD~] ~RI B

~B c

0 N

0 7

8 9 10 11 12 17 CAUSE DESCRIPTION I006 A

was found to have a

PRME COMPONENT N

COMPONENT MANUFACTURER C

4 9

0 fault insertion timer 48 which would cause the 80 7

8 9 80 l00m rod to be released u on recei t of an insertion si nal.

The timer was re 7

8 9 laced and tested rior to returnin the lant to ower o eration.

80 OTHER STATUS NA PROBABLE CONSEQUENCES Q~g 7

8 9 LOSS OR DAMAGE TO FACILITY TYPF DESCRIPTION z

7 89 10 P U8LICITY 8 9 ADDITIONAL FACTORS 7

89 FACIUTY STATUS POWFR B

~03 7

8 9

10 12 13 FORM OF ACTIVITY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY NA 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Qsj ~oo o

z

'7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION

~IA ~00 O

7 89 11 12 METHOD OF DISCOVERY 44 45 46 44 45 NA NA NA NA NA DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80

~80

[QE 7

89 Qs]

7 89 for continuation of Event Descri tion.

60 80 NAM6 M. A. Scho man PHONE: (3 05) 552-38 02 GFO 681

~ 657

H

~

~

fw REPORTABLE OCCURRENCE 335-77-27 LICENSEE EVENT REPORT PAGE TWO EVENT DESCRIPTION (Continued) suction pressure.

This led to a reactor trip on low steam generator level approximately four minutes after the CEA dropped.

This report is generated due to Technical Specification 3.1.3.le (CEA alignment requirements).

This was the fourth "dropped CEA" occurrence (LER's 335-76-37, 335-77-6, 335-77-17).

Since the four occurrences are unrelated with respect to cause, they are not con-sidered to be generically related.

(335-77-27)

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