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=Text=
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{{#Wiki_filter:NRC FOQM 196 U.S.NUCLEAR REGULATORY COM,,~SION
{{#Wiki_filter:NRC FOQM 196
<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)
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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
U.S. NUCLEAR REGULATORY COM,,~SION I                             F o-3 S DOCKET NUMBER I LE NUMBE R NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL FROM:                                      DATE OF DOCUMENT TO:
Florida  Power &    Light  Company                6/27/77 Mr. Norman     C Moseley               Miami, Florida                             DATE RECEIVED A. D~ Schmidt                                       7/22/77 ETTE R                0 NOTO R IZE D        PROP                  INPUT FORM          NUMBER OF COPIES RECEIVED RIG INAL Q COPY CONC LASS IF I E D I   >cc   ~~~
DESCRIPTION                                                  ENCLOSURE Licensee Event Report (RO 50-335/77-27) on 5/27/77 concerning Control Element Assembly (CEA) f39 drppping PLANT VIAIIE:
                                                                            ) CKNOWLZDGZD St. Lucie Unit       No l                                                 DO NOT REMOVE R JL           7/22/77                       (l-P)               (2 P)
NOTE:   IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION/INFORMATION INTERNAL D IST RI BUTION EXTERNAL DISTRIBUTION                                       CONTROL NUMBER I 772030Z50 ACRS     16   SENT AS     AT NRC FORM 196 I2 76)


==Dear Mr.Moseley:==
P. O. BOX 013100, MIAMI, FL 33101 I'ps~uA FLORIDA POWER & LIGHT COMPANY Regu)Bye~
REPORTABLE OCCURRENCE 335-77-27 ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
Fil C PRN-LI- 7 7-2 0 8 Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement II U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 1217 Atlanta, Georgia      30303
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
==Dear Mr. Moseley:==
~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).
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.
This was the fourth"dropped CEA" occurrence (LER's 335-76-37, 335-77-6, 335-77-17).
Very   truly yours, D. c   x, Vice President t
Since the four occurrences are unrelated with respect to cause, they are not con-sidered to be generically related.(335-77-27)  
Power Resources MAS/cpc Attachment cc:   Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement           (30)
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Director, Office of Management Information and Program Control (3) 772030250 PEOPLE .. ~ SERVING PEOPLE
 
II I'I I
1 4        I
 
LICENSEE EVENT REPORT A   t
( F CONTROL BLOCK:                                                               CPLAASE PAINT ALL PEDUIAED INFDAFEATIDNI 1
LCEAISEE                                                                                 UCENSE              EVENT NAME                                     LCENSE NUMBER                                  TYPE                TYPE
[OD1]   F     L   S     L     S   1         0   0   0       0   0   0   00        0         4   1     1   1   1     ~0033
                  ~~~
7    89                              14    15                                            '25   26                   30   31     32 Ioa~]coNT 7 8 CATEGORY 57       58 REPORT TYPE 59 REPORT SOURCE 60     61 o
DOCKET NUMBER 0         ~ 68    69 0   5 EVENT DATE 2
74   75 REPORT DATE 80 I
EVENT DESCRIPTION With the              lant      o  eratin at ower, and the Control Element Drive S                                           stem
                                                                      't toad 89                                                                                                                                                80 CEDS         in the Auto Se uential Mode Control Element Assembl CEA                                                         439 7 8 9                                                                                                                                                   80 tpo~j 7 8 9 h                     EA   i                 a   urbine runback. Durin the run-80
[oOsj                                                                   edwa         re ulatin valve failed o en due 7    8 9                                                                                                                                                80
  ~06 89 h   reb     causin       th PRME "A" main feedwater                   um     to tri       on low 80 SYSTEM       CAUSE                                         COMPONENT            COMPONENT CODE       CODE               COMPONENT CODE                                 MANUFACTURER IDD~] ~RI B           ~B               c 0     N           0          N            C  4      9  0 7   8 9 10               11         12                         17                                                 48 CAUSE DESCRIPTION I006 7 8 9 A             was found           to   have a     fault insertion timer which                           would cause the 80 l00m      rod to be released u on                         recei t of an insertion si nal.                               The   timer     was   re 7 8 9                                                                                                                                                   80 laced and tested rior to returnin                                     the     lant to         ower o       eration.
7   89                                                                       METHOD OF 80 FACIUTY STATUS                 POWFR               OTHER STATUS          DISCOVERY                        DISCOVERY DESCRIPTION B             ~03                             NA                                                        NA 7   8       9               10             12 13                         44      45      46                                                          80 FORM OF ACTIVITY       CO@TENT RELEASEO       OF RELEASE             AMOUNT OF ACTIVITY                                           LOCATION OF RELEASE NA                                                        NA 7   8       9                 10     11                                   44      45                                                                80 PERSONNEL EXPOSURES NUMBER           TYPE       DESCRIPTION Qsj   ~oo           o         z                                               NA
'7   89               11     12     13                                                                                                               80 PERSONNEL INJURIES NUMBER           DESCRIPTION
~IA 7 89
        ~00           O                                                         NA 11   12                                                                                                                         80 PROBABLE CONSEQUENCES Q~g                                                                            NA 7    8 9 LOSS OR DAMAGE TO FACILITY TYPF      DESCRIPTION z                                                                      NA 7    89          10 P U8LICITY NA 8 9                                                                                                                                              ~ 80 ADDITIONAL FACTORS
[QE                                     for continuation of Event Descri tion.
7 89                                                                                                                                                    60 Qs]
7    89                                                                                                                                                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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Revision as of 07:19, 21 October 2019

LER 1977-335-27 for St. Lucie, Unit 1 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)
v • d • e


Text

NRC FOQM 196

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U.S. NUCLEAR REGULATORY COM,,~SION I F o-3 S DOCKET NUMBER I LE NUMBE R NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL FROM: DATE OF DOCUMENT TO:

Florida Power & Light Company 6/27/77 Mr. Norman C Moseley Miami, Florida DATE RECEIVED A. D~ Schmidt 7/22/77 ETTE R 0 NOTO R IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED RIG INAL Q COPY CONC LASS IF I E D I >cc ~~~

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

) CKNOWLZDGZD St. Lucie Unit No l DO NOT REMOVE R JL 7/22/77 (l-P) (2 P)

NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION/INFORMATION INTERNAL D IST RI BUTION EXTERNAL DISTRIBUTION CONTROL NUMBER I 772030Z50 ACRS 16 SENT AS AT NRC FORM 196 I2 76)

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 Office of Inspection and Enforcement II 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, Vice President t

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 I'I I

1 4 I

LICENSEE EVENT REPORT A t

( F CONTROL BLOCK: CPLAASE PAINT ALL PEDUIAED INFDAFEATIDNI 1

LCEAISEE UCENSE EVENT NAME LCENSE NUMBER TYPE TYPE

[OD1] F L S L S 1 0 0 0 0 0 0 00 0 4 1 1 1 1 ~0033

~~~

7 89 14 15 '25 26 30 31 32 Ioa~]coNT 7 8 CATEGORY 57 58 REPORT TYPE 59 REPORT SOURCE 60 61 o

DOCKET NUMBER 0 ~ 68 69 0 5 EVENT DATE 2

74 75 REPORT DATE 80 I

EVENT DESCRIPTION With the lant o eratin at ower, and the Control Element Drive S stem

't toad 89 80 CEDS in the Auto Se uential Mode Control Element Assembl CEA 439 7 8 9 80 tpo~j 7 8 9 h EA i a urbine runback. Durin the run-80

[oOsj edwa re ulatin valve failed o en due 7 8 9 80

~06 89 h reb causin th PRME "A" main feedwater um to tri on low 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE MANUFACTURER IDD~] ~RI B ~B c 0 N 0 N C 4 9 0 7 8 9 10 11 12 17 48 CAUSE DESCRIPTION I006 7 8 9 A was found to have a fault insertion timer which would cause the 80 l00m rod to be released u on recei t of an insertion si nal. The timer was re 7 8 9 80 laced and tested rior to returnin the lant to ower o eration.

7 89 METHOD OF 80 FACIUTY STATUS POWFR OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION B ~03 NA NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CO@TENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Qsj ~oo o z NA

'7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~IA 7 89

~00 O NA 11 12 80 PROBABLE CONSEQUENCES Q~g NA 7 8 9 LOSS OR DAMAGE TO FACILITY TYPF DESCRIPTION z NA 7 89 10 P U8LICITY NA 8 9 ~ 80 ADDITIONAL FACTORS

[QE for continuation of Event Descri tion.

7 89 60 Qs]

7 89 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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