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{{#Wiki_filter:NRC FORM 1/5 U.S.NUCLEAR REGUI ATORY COM (2 76 I NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL ION DOCKET NUMBER 50-296 FILE NUMBER INCIDENT REPORT':.TO: Norman C.Moseley FROM: TVA Chattanooga, Tennessee 3740 H.S.Fox DATE OF DOCUMENT 1>>10-77 DATE RECEIVED l-l-7 I.ET ER ORIGINAL OCOP Y QNOTORIZED PjfV N C L ASS I F I E D PROP INPUT FORM NUMBER OF COPIES RECEIVED 1 signed org.DESCRIPTION Ltr.Trans The Following:
{{#Wiki_filter:NRC FORM 1/5                                               U.S. NUCLEAR REGUI ATORY COM     ION DOCKET NUMBER (2 76 I                                                                                             50-296 FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL                                         INCIDENT REPORT   ':.
(1~~)ENCLOSURE Licensee Event Report (RO 50 296/7620)on 12-12-76 concerning that during startup testing drywell temperature recorder TR-6II-52 became erratic.(1 encl rec'd)(1 page.)=PLANT NAME: BROWNS FERRY UNXT P.3 ACZNOVn,EDGED.DONOT REMOVE NOTE: IP PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO'KREGER/J; COLLINS'-BRANCH CHIEF: W 3 CYS FOR ACTIN LIC, ASST': W CYS ACRS CYS%%8%H8 S LEE FOR ACTION/INFORMATION
TO:                                                 FROM:  TVA                                  DATE OF DOCUMENT Norman C. Moseley                                                                           1>>10-77 Chattanooga,     Tennessee   3740 H. S. Fox                           DATE RECEIVED l-l -7 I.ET ER               QNOTORIZED                 PROP                 INPUT FORM           NUMBER OF COPIES RECEIVED ORIGINAL        PjfVN C LASS I F I E D                                                        1 signed org.
~G~G-NRC PDR I&E 2'IPC SCHROEDER/IPPOLITO HOUSTON NOVhK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS INTERNAL DISTR I BUTION LPDR: ens~TIC: N~EXTERNAL DISTRIBUTION CONTROL NUMBER
OCOP Y DESCRIPTION                                                       ENCLOSURE Ltr. Trans The Following:                                       Licensee Event Report     (RO 50 296/
~~~a>If C l g<>IPW+g~~-u c IL KJ p 4 O Pl b.'~~a-tete January 10, 1977 TENNESSEE VALLEY AUTHORITY CHATTANOOGA.
7620) on 12-12-76 concerning       that during startup testing drywell temperature recorder
TENNESSEE 3740'I Regulatory Docket File Mr.Norman C.Moseley, Director U.S.Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., 8th Floor Atlanta, Georgia 30303
( 1  ~~  )                                          TR-6II-52 became     erratic.
( 1 encl rec'd   )
( 1 page.)
=PLANT NAME: BROWNS FERRY UNXT               P. 3 ACZNOVn,EDGED                                 NOTE:   IP PERSONNEL EXPOSURE IS INVOLVED
                    .DONOT REMOVE                                          SEND DIRECTLY TO 'KREGER/J; COLLINS FOR ACTION/INFORMATION BRANCH CHIEF:
W 3 CYS FOR ACTIN LIC, ASST':                               LEE W       CYS ACRS         CYS %%8%H8 S INTERNAL DISTR I BUTION
  ~G~G
  -NRC PDR I&E 2
  'IPC SCHROEDER/IPPOLITO HOUSTON NOVhK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION                                            CONTROL NUMBER LPDR:       ens     ~
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==Dear Mr.Moseley:==
                            ~ ~
TENNESSEE VALLEY AUTHORITY-BROWNS FERRY NUCLEAR PLANT UNIT 3-DOCKET NO.50-296-FACILITY OPERATING LICENSE DPR-68-REPORTABLE OCCURRENCE REPORT BFRO-50-296/7620 The enclosed report is to provide details concerning the drywell temperature recorder TR-64-52 that became erratic during startup testing.This report is submitted in accordance with Browns Ferry Technical Specifications Section 6.This event occurr on Browns Ferry Nuclear Plant unit 3.Very truly yours, TENNESSEE VALLEY AUTHORITY H.S.Fox Director of Power Production I OL t-/y>~".>wa>g~reut~~eo~us IQg Enclosure (3)CC (Enclosure):
                                ~a
Director (3)Office of Management Information and Program Control U.S.Nuclear Regulatory Commission Washington, D.C.20555 Director (40)Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission Washington, D.C.20555 An Equal Opportunity Employer t R t"J)~~f ffi, f tI~lf Jt, II m")a~'I ti~.~
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LICENSEE EVENT~REPORT<<CONTROL BLOCK:~e LICENSEE NAME+0'L B.R R B 0 89 14 15 LICENSE NUMBEA 0-0 0 0 0 0-0 LICENSE TYPE 0 4 1'1 1 25 26.30 EVENT TYPE 31 32 t'PLEASE, T ALQ REQUIRED INFORMATION)
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.AEPOAT AEPOAT CATEGORY TYPE SOURCE le+>come~8 57 58 59.60 EVENT OESCRIPTION During sta'rtup testing DOCKET NUMBER 0 5 0 0 2 9 6 EVENT DATE 1 2 1 2 7 6 AEPOAT DATE 68 69 74 75'drywell temperature recorder TR-64-52 became erratic..A 80 89 redundant indicator, TT.-64-52, was operable.(BFRO-50-296/7620) 8 9 i+04'9 80 80 80 7 8 9~as 8 9 SYSTENI CAUSE'ODE CODE~os~ID E 7 8 9 10 11 12 CAUSE OESCRIPTION Ioom I The checmcccup'le PAME Ql I elI e<<e SUPPUQI<<Qe epQele~g MANUF ACT UFER Z 9 9 9 COMPONENT CODE N S T R U N'7 43 a7 48 lead was found broken insid'e the junction box"and was connected.
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80 7 8 9 Q~I Climatic-0/600 F cu/con.'A loose set screw holding terminal block in place may 7 8 9 I~I", I-have allowed excessive vibration of thermocou le leads.80 OTHER STATUS-OFFSITE CONSEQUENCES Q~g 7 8 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION EG6 LJ 7 8 9'Io P.UBLICITY 7 89 AOO!TIONAL FACTORS 7 9 FACIUTY STATUS POWER Q~g,.B I~oe B 7 8 9 10 12 13 FOAVI OF I AC.IVITY CONTENT AELEAS O OF RELEASE AMOUNT'OF ACTIVITY~$2 Z Z EA 8 9 10 11, PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
 
~QO 0 Z 7 8 9 11 1P 13 PERSOI"NEL INJURIES I11I LQL~I 7 8 9'1 12 METHOD OF DISCOVERY 44 45 46 44 as NA DISCOVERY OESCR>PTION Routine inspection LOCATION OF RELEASE NA 80 80 80 80 80 80 80 r 89[ll9j 89 PHONE: 80 80.Gro$6 I~661 sf 0 I tp}}
TENNESSEE VALLEY AUTHORITY O              Pl CHATTANOOGA. TENNESSEE 3740'I b.
    '~~a-tete January 10, 1977          Regulatory Docket File Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region  II 230 Peachtree Street, NW., 8th Floor Atlanta, Georgia 30303
 
==Dear Mr. Moseley:==
 
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT             3-DOCKET NO. 50-296   - FACILITY OPERATING LICENSE DPR-68       - REPORTABLE OCCURRENCE REPORT BFRO-50-296/7620 The enclosed   report is to provide details concerning the drywell temperature recorder TR-64-52 that became erratic during startup testing. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6. This event occurr                 on Browns Ferry Nuclear Plant unit 3.
Very   truly yours, TENNESSEE VALLEY AUTHORITY OL t-/y>~
                                                                      ".> wa>g ~reut~~
eo~ us IQg H. S. Fox Director of  Power Production I
Enclosure (3)
CC (Enclosure):
Director (3)
Office of Management Information       and Program   Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)
Office of Inspection   and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer
 
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LICENSEE EVENT REPORT            ~
                            <<CONTROL BLOCK:                                                                           t'PLEASE,          T ALQ REQUIRED INFORMATION) .
                                            ~e LICENSEE                                                                                             LICENSE              EVENT NAME                                       LICENSE NUMBEA                                            TYPE                TYPE
    +0'             L     B. R   R   B           0   0       0   0   0     0   0   0         0           4     1'       1   1
                    ~
89                                14        15                                                    25       26.                   30     31     32 AEPOAT     AEPOAT CATEGORY         TYPE     SOURCE                 DOCKET NUMBER                                 EVENT DATE                      AEPOAT DATE 0   5   0       0     2   9     6         1     2     1   2   7   6 le+>come 8          57      58        59    . 60                                            68       69                           74     75                         80 EVENT OESCRIPTION During sta'rtup testing 'drywell temperature recorder TR-64-52 became                                                       erratic.     .A 89                                                                                                                                                                80 redundant         indicator,           TT.-64-52, was operable.                     (BFRO-50-296/7620) 8 9                                                                                                                                                               80 i+04 9                                                                                                                                                             80 7     8 9
  ~as 8 9                                                                                                                                                               80 SYSTENI       CAUSE                                             QlPAME I elI e<<e             <<Qe epQele~g
              'ODE          CODE                COMPONENT CODE                SUPPUQI                MANUF ACT UFER
  ~os        ~ID 8 9 10 E                  N   S   T   R
                                                                      '7 U             N 43 Z    9    9      9 a7           48 7                            11        12 CAUSE OESCRIPTION Ioom I The checmcccup'le                lead was found broken insid'e the junction box"and was connected.
7     8 9                                                                                                                                                               80 7
Q~   I 8 9 Climatic         -   0/600       F   cu/con. 'A loose set screw holding terminal block in place                                             may I~I",       I -have allowed excessive                     vibration of         thermocou           le leads.
7           9                                                                                                                                                             80 FACIUTY                                                                 METHOD OF STATUS                 POWER                   OTHER STATUS            DISCOVERY                              DISCOVERY OESCR>PTION Q~g,.             B I           ~oe           B                                                                 Routine inspection 7     8         9             10               12   13                           44      45        46                                                                80 FOAVI OF I               AC.IVITY       CONTENT AELEAS O       OF RELEASE               AMOUNT'OF ACTIVITY                                                       LOCATION OF RELEASE
~$   2             Z               Z                             EA                                                                     NA 8         9                 10     11,                                       44        as PERSONNEL EXPOSURES NUMBER           TYPE       DESCRIPTION
            ~QO           0         Z 7     8 9                 11       1P     13                                                                                                                             80 PERSOI"NEL INJURIES NA I11I LQL~I 7     8 9               '1     12                                                                                                                                       80 OFFSITE CONSEQUENCES Q~g 7    8 9                                                                                                                                                                80 LOSS OR OAMAGE TO FACILITY TYPE      DESCRIPTION EG6 7      8 9 LJ      'Io                                                                                                                                                  80 P.UBLICITY 7      89                                                                                                                                                                  80 AOO!TIONAL FACTORS r   89                                                                                                                                                                 80
[ll9j 89                                                                                                                                                                 80.
PHONE:
Gro $6 I ~ 661
 
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Latest revision as of 17:39, 2 February 2020

LER 1976-020-00 for Browns Ferry, Unit 3, Drywell Temperature Recorder TR-64-52 Became Erratic During Startup Testing
ML18283B448
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 01/10/1977
From: Fox H
Tennessee Valley Authority
To: Moseley N
NRC/RGN-II
References
LER 1976-020-00
Download: ML18283B448 (6)


Text

NRC FORM 1/5 U.S. NUCLEAR REGUI ATORY COM ION DOCKET NUMBER (2 76 I 50-296 FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL INCIDENT REPORT ':.

TO: FROM: TVA DATE OF DOCUMENT Norman C. Moseley 1>>10-77 Chattanooga, Tennessee 3740 H. S. Fox DATE RECEIVED l-l -7 I.ET ER QNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED ORIGINAL PjfVN C LASS I F I E D 1 signed org.

OCOP Y DESCRIPTION ENCLOSURE Ltr. Trans The Following: Licensee Event Report (RO 50 296/

7620) on 12-12-76 concerning that during startup testing drywell temperature recorder

( 1 ~~ ) TR-6II-52 became erratic.

( 1 encl rec'd )

( 1 page.)

=PLANT NAME: BROWNS FERRY UNXT P. 3 ACZNOVn,EDGED NOTE: IP PERSONNEL EXPOSURE IS INVOLVED

.DONOT REMOVE SEND DIRECTLY TO 'KREGER/J; COLLINS FOR ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTIN LIC, ASST': LEE W CYS ACRS CYS %%8%H8 S INTERNAL DISTR I BUTION

~G~G

-NRC PDR I&E 2

'IPC SCHROEDER/IPPOLITO HOUSTON NOVhK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: ens ~

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TENNESSEE VALLEY AUTHORITY O Pl CHATTANOOGA. TENNESSEE 3740'I b.

'~~a-tete January 10, 1977 Regulatory Docket File Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., 8th Floor Atlanta, Georgia 30303

Dear Mr. Moseley:

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 3-DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR-68 - REPORTABLE OCCURRENCE REPORT BFRO-50-296/7620 The enclosed report is to provide details concerning the drywell temperature recorder TR-64-52 that became erratic during startup testing. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6. This event occurr on Browns Ferry Nuclear Plant unit 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY OL t-/y>~

".> wa>g ~reut~~

eo~ us IQg H. S. Fox Director of Power Production I

Enclosure (3)

CC (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer

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LICENSEE EVENT REPORT ~

<<CONTROL BLOCK: t'PLEASE, T ALQ REQUIRED INFORMATION) .

~e LICENSEE LICENSE EVENT NAME LICENSE NUMBEA TYPE TYPE

+0' L B. R R B 0 0 0 0 0 0 0 0 0 4 1' 1 1

~

89 14 15 25 26. 30 31 32 AEPOAT AEPOAT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE AEPOAT DATE 0 5 0 0 2 9 6 1 2 1 2 7 6 le+>come 8 57 58 59 . 60 68 69 74 75 80 EVENT OESCRIPTION During sta'rtup testing 'drywell temperature recorder TR-64-52 became erratic. .A 89 80 redundant indicator, TT.-64-52, was operable. (BFRO-50-296/7620) 8 9 80 i+04 9 80 7 8 9

~as 8 9 80 SYSTENI CAUSE QlPAME I elI e<<e <<Qe epQele~g

'ODE CODE COMPONENT CODE SUPPUQI MANUF ACT UFER

~os ~ID 8 9 10 E N S T R

'7 U N 43 Z 9 9 9 a7 48 7 11 12 CAUSE OESCRIPTION Ioom I The checmcccup'le lead was found broken insid'e the junction box"and was connected.

7 8 9 80 7

Q~ I 8 9 Climatic - 0/600 F cu/con. 'A loose set screw holding terminal block in place may I~I", I -have allowed excessive vibration of thermocou le leads.

7 9 80 FACIUTY METHOD OF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY OESCR>PTION Q~g,. B I ~oe B Routine inspection 7 8 9 10 12 13 44 45 46 80 FOAVI OF I AC.IVITY CONTENT AELEAS O OF RELEASE AMOUNT'OF ACTIVITY LOCATION OF RELEASE

~$ 2 Z Z EA NA 8 9 10 11, 44 as PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~QO 0 Z 7 8 9 11 1P 13 80 PERSOI"NEL INJURIES NA I11I LQL~I 7 8 9 '1 12 80 OFFSITE CONSEQUENCES Q~g 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION EG6 7 8 9 LJ 'Io 80 P.UBLICITY 7 89 80 AOO!TIONAL FACTORS r 89 80

[ll9j 89 80.

PHONE:

Gro $6 I ~ 661

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