ML18110A608: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 04/23/1976
| issue date = 04/23/1976
| title = LER 1976-007-00 for St. Lucie Unit 1, an Error in the RCS Loop Temperature Wiring Diagrams
| title = LER 1976-007-00 for St. Lucie Unit 1, an Error in the RCS Loop Temperature Wiring Diagrams
| 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 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:NRC FoRM 195 I2 7GI U.S.NUCLEAR REGULATORV C IISSION DOCKET NUMBER Mr MoseWey Florida Pwr;6 Light Co Miami, Fla R E Uhrig NRC DISTRIBuTION roR PART 50 DOCKET MATERIAL rILE NUMBER XNCXDENT RrPORT DATE OF DOCUMENT 4-23-76 DATE RECEIVED EILETTER QORIGINAL Qcopv.ONOTORIZED CI VNC LASSIF I ED PROP INPUT FORM NUMBER OF COPIES RECEIVED none signed DESCRIPTION Ltr trans the following license event report: ENCLOSURE RO/P 76-7 on 3-25-76 concerning erratic reactor coolant loop Th rIBmperature indication........
{{#Wiki_filter:U.S. NUCLEAR REGULATORV C   IISSION DOCKET NUMBER NRC FoRM 195 I2 7GI rILE NUMBER NRC DISTRIBuTION roR PART 50 DOCKET MATERIAL                                           XNCXDENT RrPORT DATE OF DOCUMENT Mr MoseWey                                            Florida    Pwr;6  Light  Co 4-23-76 Miami, Fla                          DATE RECEIVED R E  Uhrig EILETTER                         ONOTORIZED           PROP                 INPUT FORM           NUMBER OF COPIES RECEIVED QORIGINAL                    CI VNC LASSIF I ED                                                  none signed Qcopv  .
PLANT NAME: St Lucie 81 NOTE: IF PERSONNEL EXPOSURE IS XNVOLVED SEND DIRECTLY TO KREGER/J.COLLINS SAFETY BRANCH CHIEF'I 3 CYS FOR ACTION LIC~ASST: M/CYS FOR ACTION/INFORMATION usa nn ENVXRO 5-10" 76 ehf ACRS CYS QQKELW4/ENT TO LA EG PILE NRC PDR INTERNAL DISTRIBUTION SCHROEDER/XPPOLITO 0 NOVAK CHECK R IES S.NE TEDE g CO~CC~A i'AI'R SIIAO VOI~LYHR BUBCtl KRI:~E~~O~..
DESCRIPTION                                                           ENCLOSURE Ltr trans           the following license event report:           RO/P 76-7 on 3-25-76 concerning erratic reactor coolant loop Th rIBmperature indication........
NS LPDR: I=i I c.v~TIC NSXC EXTERNAL DISTRIBUTION CONTROL NUMBER qg 4R  
PLANT NAME:
~~~~~~~
St Lucie 81                               NOTE:   IF PERSONNEL EXPOSURE IS XNVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY                                       FOR ACTION/INFORMATION                  ENVXRO  5-10" 76      ehf BRANCH     CHIEF'I usa  nn 3 CYS FOR ACTION LIC ~ ASST:
CO.'B 9 joe P.O.BOX 3100 MIAMI, FLORIDA 33101 I.U I~l'~~~+Sp~;.;~~~:.~rigjij Li FLORIDA POWER&LIGHT COhIPAi'IY April 23, 1976 PRN-LI-76-97 Mr.Norman C.Moseley, Director, Region Office of Inspection and Enforcement U.S.Nucle'ar Regulatory Commission 230 Peachtree Street, N.W., Suite 818 Atlanta, Georgia 30303  
M/     CYS ACRS               CYS     QQKELW4/ ENT TO LA INTERNAL DISTRIBUTION EG PILE NRC PDR SCHROEDER/XPPOLITO 0
NOVAK CHECK R IES S               .NE TEDE g CO~CC~A i'AI'R SIIAO VOI~LYHR BUBCtl KRI:~E~~O~..                 NS EXTERNAL DISTRIBUTION                                      CONTROL NUMBER LPDR: I=i           I c.v ~
TIC NSXC qg 4R
 
~ ~ ~ ~ ~ ~ ~
P.O. BOX 3100 MIAMI, FLORIDA 33101 I       ~l'~ ~~+     I.U Sp~
CO
                                                                              ;.;~~~: .~rigjij Li FLORIDA POWER & LIGHT COhIPAi'IY
                                      .'B April 23,             1976 9
PRN-LI-76-97 joe CU Mr. Norman C. Moseley,     Director, Region   II      c Office of Inspection and Enforcement               I      00CNGIl3 U. S. Nucle'ar Regulatory Commission                       uSI4RC 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303                               M~~5 )076' RE~
                                                                            ~IDR<
CL~R


==Dear Mr..Moseley:==
==Dear Mr..Moseley:==
CgagkAB IAou >
                                                    'v OCCURRENCE  335-76    7          'EPORTABLE ST. LUCIE UNIT 1 DATE OF OCCURRENCE:    MARCH  25, 1976 WIRING DIAGRAM ERROR (Th INSTRUMENT)
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, RE8ULAT",.Y '."""'T I-II E CO Vice President Power Resources MAS/cpc Attachment cc:    Jack R. Newman, Esquire Director, Office of Inspection and Enforcement                      (30)
Director, Office of Management Information and 1
Program Control (3)
HELPING BUILD FLOFIIOA
V f
LICENSEE EVENT REPORT        ~
I'>>        ~                                                                                  ~
CONTROL BLOCK:                                                                              SE PRINT ALL REOUIRED INFORMATION) 6 UCENSEE                                                                                      LICENSE              EVENT NAME                                      LICENSE NUMBER                                      TYPE                TYPE
    ~01        F  L      4 L s            1        0  0      0    0    0    0 0            0 0          4    I. I. a  I.    ~OS
                    ~
7 89                                    14    15                                                        26                    30    31    32 REPORT    REPORT CATEGORY          TYPE    SOURCE            'OCKET NUMBER                            ~ EVENT OATS                      REPORT DATE
[OD~ICoN'7                        L        ~L        0    5 0          0 3      3 5            0    3 2 5          7 6        0    4  2  3    7 6 7    8          57      58        59      60      61                                  68      69                        74    75                        80 EVENT OESCRIPTION
  @~2        While erformin                          reo erational              testin of the Reactor Protection                                    S  stem 7    8 9                                                                                                                                                      Bo 7
[oO~]
89 p                      i                                                        em    rature indication                  was 80
  +04        observed.                Subseauent          review of Reactor Coolant S stem RCS loo N'0 7 8 9                                                                                                                                                          80 IOOI        tern    erature wirin                    dia rams revealed an error. The olarit of th'
  '7  89                                                                                                                                                        80 Jog "7 89                                                                        PRME SYSTEM        CAUSE                                          CCMPONENT                COMPONENT CODE        CODE                COMPONENT CODE        .      SUPPUER              MANUFACTURER 7
[oO~]  [iiaJ 8 9 10
                          ~o 11        12 z    N S          R U 17
                                                                        .      N 43            44 G      0 8      0 47 CAUSE OESCRIPTION
  ~os                                  e  c    was ca s d                  an e        or in the          RCS      loo      tern  erature 7 8 9                                                                                                                                                        80 Iossj 7 8 9                                                                                                                                                        Bo
  ~10 7    89      FACILITY                                                            METHOD OF 80 STATUS        "    %  POWER                OTHER STATUS            DISCOVERY                          DISCOVERY DESCRIPTION jg~          ~s              LJoaoo J                      NA                                        Preo      erational Test 7    8        9              10            12 13                            44      45        46                                                          80 FORM OF ACTIVITY        COATENT KQs 7 8 LJs'~l RELEASEO 9
OF RELEASE 10      11 AMOUNT OF ACTIVITY NA 4s LOCATION OF RELEASE NA 80 PERSONNEL, EXPOSURES 7
Q~g 89
[gJ    i~
NUMBER 11 TYPE
                                  'z 12      13 OESCRdoTION NA 80 PERSONNEL INJURIES NUMBER            DESCRIPTION
  ~i4 89
[0000 J                                                                  NA 7                        11    12                                                                                                                            80 PROBABLE          CON SEQUEN'CES Qs]                                                                              NA 7    8 9                                                                                                                                                      80 LOSS OR OAMAGE TO FACILITY TYPE        DESCRIPTION z                                                                      NA 7    89            10                                                                                                                                        80 PUBLICITY 7
7 89 89 AOOITIONAL        FACTORS'ti                                          NA n
eo 7    89                                                                                                                                                      eo M. A. Schoppman Cl'0 44t ~ 447


CU c II I 00CNGIl3 uSI4RC M~~5)076&#x17d;~IDR<CL~R RE~CgagkAB IAou>'EPORTABLE OCCURRENCE 335-76 7'v ST.LUCIE UNIT 1 DATE OF OCCURRENCE:
REPORTABLE OCCURRENCE 335-76-7 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued)                     I the Thermal Margin/Low Pressure reactor trip was found reversed on the diagrams. Component modifications were completed prior to continuing heatup to within the Th instrument range. The modifica-tions were made to comply with the original design intent, and no functions or equipment were added or deleted. Further preoperational testing and reviews of RPS wiring have indicated that this is not a repetitive problem. This was the first occurrence of this type.
MARCH 25, 1976 WIRING DIAGRAM ERROR (Th INSTRUMENT)
(335-76-7).}}
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, RE8ULAT",.Y
'."""'T I-II E CO Vice President Power Resources MAS/cpc Attachment cc: Jack R.Newman, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)1 HELPING BUILD FLOFIIOA V f I'>>~CONTROL BLOCK: LICENSEE EVENT REPORT~~SE PRINT ALL REOUIRED INFORMATION) 6 UCENSEE NAME~01 F L 4 L s 1 0 0 7 89 14 15 LICENSE NUMBER 0 0 0 0 0 0 0 LICENSE EVENT TYPE TYPE 4 I.I.a I.~OS 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE[OD~ICoN'7
~L~L 0 7 8 57 58 59 60 61'OCKET NUMBER~EVENT OATS 5 0-0 3 3 5 0 3 2 5 7 6 68 69 74 REPORT DATE 0 4 2 3 7 6 75 80 EVENT OESCRIPTION
@~2 While erformin reo erational testin of the Reactor Protection S stem 7 8 9 Bo[oO~]p i em rature indication was 7 89+04 observed.Subseauent review of Reactor Coolant S stem RCS loo 7 8 9 IOOI tern erature wirin dia rams revealed an error.The olarit of th''7 89 Jog 80 80 80"7 89 SYSTEM CAUSE CODE CODE[oO~][iiaJ~o z 7 8 9 10 11.12 CAUSE OESCRIPTION PRME CCMPONENT COMPONENT COMPONENT CODE.SUPPUER MANUFACTURER N S R U.N G 0 8 0 17 43 44 47 N'0~os 7 8 9 Iossj 7 8 9~10 7 89 FACILITY STATUS"%POWER jg~~s LJoaoo J 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY KQs LJs'~l NA 7 8 9" 10 11 PERSONNEL, EXPOSURES NUMBER TYPE OESCRdoTION Q~g[gJ i~'z 7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION
~i4[0000 J 7 89 11 12 PROBABLE CON SEQUEN'CES Qs]7 8 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION z 7 89 10 PUBLICITY 7 89 METHOD OF DISCOVERY OTHER STATUS NA DISCOVERY DESCRIPTION Preo erational Test 44 45 46 LOCATION OF RELEASE NA 4s NA NA NA NA NA AOOITIONAL FACTORS'ti n 7 89 e c was ca s d an e or in the RCS loo tern erature 80 Bo 80 80 80 80 80 80 80 eo 7 89 M.A.Schoppman eo Cl'0 44t~447 REPORTABLE OCCURRENCE 335-76-7 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued)
I the Thermal Margin/Low Pressure reactor trip was found reversed on the diagrams.Component modifications were completed prior to continuing heatup to within the Th instrument range.The modifica-tions were made to comply with the original design intent, and no functions or equipment were added or deleted.Further preoperational testing and reviews of RPS wiring have indicated that this is not a repetitive problem.This was the first occurrence of this type.(335-76-7).}}

Latest revision as of 04:31, 3 February 2020

LER 1976-007-00 for St. Lucie Unit 1, an Error in the RCS Loop Temperature Wiring Diagrams
ML18110A608
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/23/1976
From: Schmidt A
Florida Power & Light Co
To: Moseley N
NRC/IE, NRC/RGN-II
References
PRN-LI-76-97 LER 1976-007-00
Download: ML18110A608 (6)
v • d • e


Text

U.S. NUCLEAR REGULATORV C IISSION DOCKET NUMBER NRC FoRM 195 I2 7GI rILE NUMBER NRC DISTRIBuTION roR PART 50 DOCKET MATERIAL XNCXDENT RrPORT DATE OF DOCUMENT Mr MoseWey Florida Pwr;6 Light Co 4-23-76 Miami, Fla DATE RECEIVED R E Uhrig EILETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED QORIGINAL CI VNC LASSIF I ED none signed Qcopv .

DESCRIPTION ENCLOSURE Ltr trans the following license event report: RO/P 76-7 on 3-25-76 concerning erratic reactor coolant loop Th rIBmperature indication........

PLANT NAME:

St Lucie 81 NOTE: IF PERSONNEL EXPOSURE IS XNVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION ENVXRO 5-10" 76 ehf BRANCH CHIEF'I usa nn 3 CYS FOR ACTION LIC ~ ASST:

M/ CYS ACRS CYS QQKELW4/ ENT TO LA INTERNAL DISTRIBUTION EG PILE NRC PDR SCHROEDER/XPPOLITO 0

NOVAK CHECK R IES S .NE TEDE g CO~CC~A i'AI'R SIIAO VOI~LYHR BUBCtl KRI:~E~~O~.. NS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: I=i I c.v ~

TIC NSXC qg 4R

~ ~ ~ ~ ~ ~ ~

P.O. BOX 3100 MIAMI, FLORIDA 33101 I ~l'~ ~~+ I.U Sp~

CO

.;~~~
.~rigjij Li FLORIDA POWER & LIGHT COhIPAi'IY

.'B April 23, 1976 9

PRN-LI-76-97 joe CU Mr. Norman C. Moseley, Director, Region II c Office of Inspection and Enforcement I 00CNGIl3 U. S. Nucle'ar Regulatory Commission uSI4RC 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303 M~~5 )076' RE~

~IDR<

CL~R

Dear Mr..Moseley:

CgagkAB IAou >

'v OCCURRENCE 335-76 7 'EPORTABLE ST. LUCIE UNIT 1 DATE OF OCCURRENCE: MARCH 25, 1976 WIRING DIAGRAM ERROR (Th INSTRUMENT)

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, RE8ULAT",.Y '."""'T I-II E CO Vice President Power Resources MAS/cpc Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (30)

Director, Office of Management Information and 1

Program Control (3)

HELPING BUILD FLOFIIOA

V f

LICENSEE EVENT REPORT ~

I'>> ~ ~

CONTROL BLOCK: SE PRINT ALL REOUIRED INFORMATION) 6 UCENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

~01 F L 4 L s 1 0 0 0 0 0 0 0 0 0 4 I. I. a I. ~OS

~

7 89 14 15 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE 'OCKET NUMBER ~ EVENT OATS REPORT DATE

[OD~ICoN'7 L ~L 0 5 0 0 3 3 5 0 3 2 5 7 6 0 4 2 3 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION

@~2 While erformin reo erational testin of the Reactor Protection S stem 7 8 9 Bo 7

[oO~]

89 p i em rature indication was 80

+04 observed. Subseauent review of Reactor Coolant S stem RCS loo N'0 7 8 9 80 IOOI tern erature wirin dia rams revealed an error. The olarit of th'

'7 89 80 Jog "7 89 PRME SYSTEM CAUSE CCMPONENT COMPONENT CODE CODE COMPONENT CODE . SUPPUER MANUFACTURER 7

[oO~] [iiaJ 8 9 10

~o 11 12 z N S R U 17

. N 43 44 G 0 8 0 47 CAUSE OESCRIPTION

~os e c was ca s d an e or in the RCS loo tern erature 7 8 9 80 Iossj 7 8 9 Bo

~10 7 89 FACILITY METHOD OF 80 STATUS "  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION jg~ ~s LJoaoo J NA Preo erational Test 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT KQs 7 8 LJs'~l RELEASEO 9

OF RELEASE 10 11 AMOUNT OF ACTIVITY NA 4s LOCATION OF RELEASE NA 80 PERSONNEL, EXPOSURES 7

Q~g 89

[gJ i~

NUMBER 11 TYPE

'z 12 13 OESCRdoTION NA 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~i4 89

[0000 J NA 7 11 12 80 PROBABLE CON SEQUEN'CES Qs] NA 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION z NA 7 89 10 80 PUBLICITY 7

7 89 89 AOOITIONAL FACTORS'ti NA n

eo 7 89 eo M. A. Schoppman Cl'0 44t ~ 447

REPORTABLE OCCURRENCE 335-76-7 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued) I the Thermal Margin/Low Pressure reactor trip was found reversed on the diagrams. Component modifications were completed prior to continuing heatup to within the Th instrument range. The modifica-tions were made to comply with the original design intent, and no functions or equipment were added or deleted. Further preoperational testing and reviews of RPS wiring have indicated that this is not a repetitive problem. This was the first occurrence of this type.

(335-76-7).

Retrieved from "https://kanterella.com/w/index.php?title=ML18110A608&oldid=2406985"