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See also: [[see also::IR 05000249/2019076]]


=Text=
=Text=
{{#Wiki_filter:* .'""''.-...
{{#Wiki_filter:~>'-"'~*.'""''.-
..
                ~--*'!-'*=~*~~*~"~*~*......-""''-¥-'-.--'---' ---* **-
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                                                    \>.
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                                                                          -*-~ ...:--. _;_;:_*.;. --:.... ..!...--- - --A---:-'--**-_ .... - *--*                                       *----4(~*
--:.... . .!...------A---:-'--**-_  
                                                                      *. Comrtto~h-h Edison
.... -*--* \>.
                                                                        . DrescP.ln Nuclear Power Station e
'. , l j. *.  
                                                                                                                                                                  '~"'ft~
Edison . DrescP.ln  
R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #76-748                                                                                       oc*tober 21, 1976 Mr. Jame1s G~ Keppler, Regional Di rec tor Di~ectorate of Regulatory Operat{ons - Region III u .. S. Nuclear* Regulatory. Commis*sion 799 Roosevelt Road
Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone  
* Glen Ellyn, Illinois 60137 Enclosed please find Reportable Occurrence report.number 50-249/1976-18 ..
815/942-2920  
This report is being submitted to your office in accordance *with the Dresd.en:
e
Nuclear Power Station Technical Specifications, Section 6.6.B.
BBS Ltr. #76-748 oc*tober 21, 1976 Mr. Jame 1 s G Keppler, Regional Di rec tor  
                                                                                                                                                  ' 'B.
of Regulatory  
                                                                                                                                                        ~~v
Operat{ons  
                                                                                                                                                    .*-~~      ..* . .~.er~*
-Region III u .. S. Nuclear* Regulatory.  
                                                                                                                                                        '-B. Stephenson Station Superintendent Dresden*Nuclear Power Statiort BBS:jo
Commis*sion  
                                            *Enclosure*
799 Roosevelt  
cc:       Director of Inspection & Enforcement Director of Man~gement Information & Program Control Fi.le/NRC Mail Seaton 0ac.k;;1 Gierk
Road * Glen Ellyn, Illinois 60137 Enclosed please find Reportable  
                                                                                                                                                                          . :10892 j.
Occurrence  
 
report.number  
                                              .               .           LICENSEE EVENT REPOA1a CONTROL BLg_i;:K:L     ii~,
50-249/1976-18  
t .
.. This report is being submitted  
                                                                    ~        I I' I. 6I                                          **
to your office in accordance  
(PLEASE PRINT ALL REQUIRED INFORMATION)
*with the Dresd.en:  
UC EN SEE                                                                                             LICENSE                    EVENT NAME                                     LICENSE NUMBER                                              TYPE                      TYPE
Nuclear Power Station Technical  
        **@E] II tLIDIRISl3 I                                 10101-10101010101-10101                                         14 I r 11 1t 1t I 10131 1      a9                                    14    15                                   '                 . 25       26                      30        31      32 REPORT     REPORT CATEGORY .        TYPE    SOURCE               OOCKET NUMBER                                     EVENT* DATE                           REPORT.DATE
Specifications, Section 6.6.B. .  
        * @rr]coNI               I I I IL I lLI                       1015IOl~IOIJl4lql                                  IO Iq I :u I ? I t, I . I I Io I:l Lo I 71 " I 1       a         . 57       58       59       60     61                                       68       69                             74       75                               80 EVENT DESCRIPTION (0'21 jJ)URl!V(;... '&deg;R.EFtf&#xa3;UNG OUTAGE UJCAL J...EAK-RA.TE. lt;:STING, F&#xa3;EpWATE.f< ..GHCK,.
' . . .* . . . 'B. '-B. Stephenson  
7       8 9                                                                                                                                               .                             80 folal I VAJ...V5 3-. l20 - 5'3 ..4 ANJ:> -0?.A &#xa3;XHL8 7< 8 9                                                                                          .
Station Superintendent  
ITED J...&#xa3;,(U< RATES bl=
Dresden*Nuclear  
                                                                                                                                                                '64.? AND.
Power Statiort BBS:jo *Enclosure*  
(,I 6'ol 80 lol41 lscFH RtSPEc.T1yELY (TECH SPt::c: L1MrT:* 2Cf.3WI Sc.EH). A FE.W                                                                               PAYS         &ATER.               I 7       8 9                                                                                                                                                                         /   80 lo15l8    ITHE5E Cl1ECK VAJ...VES                       WE'RE     PRES$VR12 ED To                           soo p~1G-            1N P.N         ATTEMPT                 TO           I
cc: Director of Inspection  
      . 7             9 .       .         I                                                               .                   .                                                                 80 fol61     l*Bt:TTER 'APPROXlt'YlATE:"                     ACC!J?C:NT CONDITIONS. SUBSl;;QUCNT 'RETE:STING- OF VAL..VESI
& Enforcement  
: 7. 8 9                   *                 **                                 PRME               .                           .         ($E ATTAOIEJ)SJ1CT)80 SYSTEM         CAUSE   .                             * '     COMPONENT                   COMPONENT                                                       *
Director of  
* CODE
Information  
* CODE               COMPONENT COOE               SU?PUEA                   MANUFACTURER               llDLATlJN
& Program Control Fi.le/NRC  
          ~          ICIHI lfil                       IVIAILIVIEIXI                     lAJ                   1Clfol~l51'                        lY.J
Mail Seaton 0ac.k;;1 Gierk , . . :10892 .,,,, .. *! 
      . 7       8 9 10                   11         12                         17       43               44                     47 .           48 .*
. . LICENSEE EVENT REPOA1a  
            .
** CONTROL BLg_i;:K:L I I' I I (PLEASE PRINT ALL REQUIRED INFORMATION) . t . . 6 . UC EN SEE NAME **@E] II tLIDIRISl3  
* CAU$E DESCRIPTION                                 *           .                                             .                 *           .                     . .
I 1 a 9 14 REPORT CATEGORY . TYPE LICENSE NUMBER 10101-10101010101-10101  
          ~ )IH&#xa3;                   JN1TiAl-           LI-RI FAILUR~ OF VALVE 3-<l10~S"g-,4 WA~ APPARENTLY CAUSE:]) BY                                                                           I 7       8 9                                                                                                       . .                                                       . '         80 lolsl lD1R-t               IN THE 5E11TttJfr f/R&#xa3;fl. ,               L.JHtC/=l RES UL TcT> IN ExCESSI'/&#xa3; Disc "'."To.; S~AT *** .*                                                     I 7       8 9                                                         '               .         .                                                                                 .     ' 80
15 ' . 25 REPORT SOURCE OOCKET NUMBER LICENSE TYPE 14 I r 11 1 t 1 t I 26 30 EVENT TYPE 10131 31 32 EVENT* DATE REPORT.DATE  
'..;~>;J11PJ IC-LEl+RANC&#xa3;S:                             PRES$URI     z ING-. THE . VAJ.;V{F;kf.NJ//:l-l'-*VJA-:r&#xa3;1?,..'-1EFF6:.CHl/EbY;. 'REJf>fJ0&#xa3;fJ):i~,'i.t&#xa2;i.. I 7 . 8. 9 . FACILITY
* @rr]coNI I I I IL I lLI  
                                                                                            .. *.
IO I q I :u I ? I t, I . I I I o I :l Lo I 71 " I 1 a . 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION  
* M*.ETHOO   OF                               ($c E> fl. TT. OC. kt;.,..:.
(0'21 jJ)URl!V(;...  
                                                                                                                                                                          ..Y "
'&deg;R.EFtf&#xa3;UNG  
q . .J&#xa3;&#xa3;_Tj'. .... _SQ
OUTAGE UJCAL J...EAK-RA.TE.  
    . .: .         . . . STATUS               "   POWER               OTHER STATUS           . DISCOVERY'                               DISCOVERY OESCRIPTiON .
lt;:STING, F&#xa3;EpWATE.f<  
      . 7
.. GH*CK,. 7 8 9 . 80 folal I VAJ...V*5
[ill]8 , *9I.HJ             .
3-l20 -5'3 ..4 ANJ:> -0?.A &#xa3;XHL8 ITED J...&#xa3;,(U<  
* 10Io I o Io12I 13I .               NA 44 I IBJ     45 AIA . .
RATES bl= '64.? AND. (,I 6'ol 7< 8 9 . . ' . 80 lol41 lscFH RtSPEc.T1yELY (TECH SPt::c: L1MrT:* 2Cf.3WI Sc.EH). A FE.W PAYS &ATER. I 7 8 9 / 80 lo15l ITHE5E Cl1ECK VAJ...VES  
4-6---------------------~80 I  -~
WE'RE PRES$VR12  
                      . FORM OF ACTIVITY         CONTENT RELEASED         OF RELEASE             AMOUNT OF ACTIVITY                                                         LOCATION OF RELEASE fiEl . l6J .                       ~I~          _______N..._.A_ _ ___.                                                   NA 7       a*       9                 10 . 11                                       44             45                                                                                   80 PERSONNEL.- EXPOSURES
ED To soo  
* NUMBER           TYPE       DESCRIPTION
1N P.N ATTEMPT TO I . 7 8 9 . . I . . 80 fol61 l*Bt:TTER  
[!lfil Io 10 Io I.                 1KJ . ~'______N__'._        A _ _ _ _ _ _ _ _ _ ___,___ _ _.,---_ __,I
'APPROXlt'YlATE:" ACC!J?C:NT  
    . 1         as          **       11     12       13                                                                                                                                       so PERS'ONNEL. INJURIES .
CONDITIONS.  
                        . NUMBER             DESCRIPTION ffEJ IOI O!OI                       ~--*V._A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..______,
SUBSl;;QUCNT  
7       8 9                   11   12                                                                                                                                                   80 OFFSITE CONSEQUENCES fill]           .         }JA 7       8 9                                                                                                                                                                             80 LOSS. OR DAMAGE TO _FACILITY TYPE
'RETE:STING-
* DESCRIPTION EID 1&#xa3;J                               NA : .
OF VAL..VESI  
7       as             10                                                                                                                                                               80
7. 8 9 * ** PRME . . ($*E ATTAOIEJ)SJ1*CT)80  
                    . PUBLICITY .
SYSTEM CAUSE . * ' COMPONENT  
[iI?J                     NA
COMPONENT  
      . 7         B *9                                                                                                                                                                           80 ADDITIONAL FACTORS
* * CODE * CODE COMPONENT  
          ~                          ;t/4:
COOE SU?PUEA MANUFACTURER  
* 8 9                                                                                                                                                                             80 PHONE:     &#xa3;';<,/.     ';),_,/,,5&deg;
llDLATlJN ICIHI lfil IVIAILIVIEIXI  
 
lAJ  
EVENT DESCRIPTION (Continued) 3-220-58A and -62A yielded leak rates of 20,0 and 5220 SCFR respectively, Since the leakage through valve .3-220-58A was reduced to a value below .Tech Spec limits, no further action was necessary. Valve -62A was disassembled and repaired, Redundant valves were available and operable during unit operation,   This is a repetitive occurrence. (50-249/1976-18)
lY.J . 7 8 9 10 11 12 17 43 44 47 . 48 .* . * CAU$E DESCRIPTION  
* CAUSE DESCRIPTION (Co?tinued) these clearances sufficiently to permit a satisfactory disc-to-seat seal, Disassembly of valve 3-220-62A revealed that, in addition to having dirt in the seating area, the valve also had worn disc assembly pins which resulted in an impre-cise disc-to-seat alignment. The valve was cleaned, and the disc assembly and seal ring were replaced. Following reassembly, valve -62A was retested, and a leak rate of 1.84 SCFH was obtained.
* . . * . . . )IH&#xa3; JN1TiAl-LI-RI  
* Because of the high incidence of initial LLRT *failures on the feedwater check valves, the station is currently reevaluating the method of testing these valves. The significant improvement in LLRT results which are obtained after the valves. have been back-seated with water indicates that the present testing method qoes,not allow an adequate determination of how these valves will perform tinder accident
OF VALVE APPARENTLY  
.. ,, G.OJl~.i. tions. Valves. 3-:220-58A and -62A are 18-inch, tilting disc check valves man-
CAUSE:]) BY I 7 8 9 . . . ' 80 lolsl lD1R-t IN THE 5E11TttJfr  
. . .,,~4'&#xa3;a;tttlfecf~by.'.Cr1rie** c~irfp~ny.}}
f/R&#xa3;fl. , L.JHtC/=l  
RES UL TcT> IN ExCESSI'/&#xa3;  
Disc "'."To.;  
*** .* I 7 8 9 ' . . . ' 80 ' ..  
I C-LEl+RANC&#xa3;S:  
PRES$URI z ING-. THE . VAJ.;V{F;kf.NJ//:l-l'-*VJA-:r&#xa3;1?,..'-1EFF6:.CHl/EbY;.  
.. I 7 . 8. 9 . . .. * .. * M*.ETHOO OF ($c E> fl. TT. OC. kt;.,..:.  
q ... J &#xa3;&#xa3;_ Tj' .... _SQ . '. . :;-.* FACILITY ..Y " . . . : . . . . STATUS " POWER OTHER STATUS . DISCOVERY'  
DISCOVERY  
OESCRIPTiON . [ill] , * I.HJ * Io I o Io I I . NA I IBJ AIA . . I . 7 8 9 . 10 12 13 44 45 . FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY fiEl . l6J . _______ N..._.A ___ __. LOCATION OF RELEASE NA 7 a * 9 10 . 11 44 45 80 PERSONNEL.-
EXPOSURES  
* NUMBER TYPE DESCRIPTION  
[!lfil Io 10 Io I. 1KJ . ______ N __ '.A ___________
__,__ ___ .,---_ __,I . 1 a s * * 11 12 13 so PERS'ONNEL.  
INJURIES . . NUMBER DESCRIPTION  
ffEJ IOI O!OI  
__________________
..______, 7 8 9 11 12 80 OFFSITE CONSEQUENCES  
fill] . }JA 7 8 9 80 LOSS. OR DAMAGE TO _FACILITY  
TYPE * DESCRIPTION  
EID 1&#xa3;J NA : . 7 as 10 80 . PUBLICITY . [iI?J NA . 7 B *9 80 ADDITIONAL  
FACTORS ;t/4: * 8 9 80 PHONE: &#xa3;';<,/. ';),_,/,,5&deg;
EVENT DESCRIPTION (Continued)  
3-220-58A  
and -62A yielded leak rates of 20,0 and 5220 SCFR respectively, Since the leakage through valve .3-220-58A  
was reduced to a value below .Tech Spec limits, no further action was necessary.  
Valve -62A was disassembled  
and repaired, Redundant  
valves were available  
and operable during unit operation, This is a repetitive  
occurrence.  
(50-249/1976-18)  
* CAUSE DESCRIPTION (Co?tinued)  
these clearances  
sufficiently  
to permit a satisfactory  
disc-to-seat  
seal, Disassembly  
of valve 3-220-62A  
revealed that, in addition to having dirt in the seating area, the valve also had worn disc assembly pins which resulted in an cise disc-to-seat  
alignment.  
The valve was cleaned, and the disc assembly and seal ring were replaced.  
Following  
reassembly, valve -62A was retested, and a leak rate of 1.84 SCFH was obtained.  
* Because of the high incidence  
of initial LLRT *failures  
on the feedwater  
check valves, the station is currently  
reevaluating  
the method of testing these valves. The significant  
improvement  
in LLRT results which are obtained after the valves. have been back-seated  
with water indicates  
that the present testing method qoes,not allow an adequate determination  
of how these valves will perform tinder accident .. ,,  
.. tions. Valves. 3-:220-58A  
and -62A are 18-inch, tilting disc check valves ...
}}

Latest revision as of 09:07, 24 February 2020

Letter Submitting Reportable Occurrence Number 050-249/1976-18 in Accordance with Technical Specifications, Section 6.6.B
ML17252A241
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 10/21/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #76-748
Download: ML17252A241 (3)
v • d • e


Text

~>'-"'~*.'"".-

~--*'!-'*=~*~~*~"~*~*......-""-¥-'-.--'---' ---* **-

\>.

-*-~ ...:--. _;_;:_*.;. --:.... ..!...--- - --A---:-'--**-_ .... - *--* *----4(~*

  • . Comrtto~h-h Edison

. DrescP.ln Nuclear Power Station e

'~"'ft~

R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #76-748 oc*tober 21, 1976 Mr. Jame1s G~ Keppler, Regional Di rec tor Di~ectorate of Regulatory Operat{ons - Region III u .. S. Nuclear* Regulatory. Commis*sion 799 Roosevelt Road

  • Glen Ellyn, Illinois 60137 Enclosed please find Reportable Occurrence report.number 50-249/1976-18 ..

This report is being submitted to your office in accordance *with the Dresd.en:

Nuclear Power Station Technical Specifications, Section 6.6.B.

' 'B.

~~v

.*-~~ ..* . .~.er~*

'-B. Stephenson Station Superintendent Dresden*Nuclear Power Statiort BBS:jo

  • Enclosure*

cc: Director of Inspection & Enforcement Director of Man~gement Information & Program Control Fi.le/NRC Mail Seaton 0ac.k;;1 Gierk

. :10892 j.

. . LICENSEE EVENT REPOA1a CONTROL BLg_i;:K:L ii~,

t .

~ I I' I. 6I **

(PLEASE PRINT ALL REQUIRED INFORMATION)

UC EN SEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

    • @E] II tLIDIRISl3 I 10101-10101010101-10101 14 I r 11 1t 1t I 10131 1 a9 14 15 ' . 25 26 30 31 32 REPORT REPORT CATEGORY . TYPE SOURCE OOCKET NUMBER EVENT* DATE REPORT.DATE
  • @rr]coNI I I I IL I lLI 1015IOl~IOIJl4lql IO Iq I :u I ? I t, I . I I Io I:l Lo I 71 " I 1 a . 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION (0'21 jJ)URl!V(;... '°R.EFtf£UNG OUTAGE UJCAL J...EAK-RA.TE. lt;:STING, F£EpWATE.f< ..GHCK,.

7 8 9 . 80 folal I VAJ...V5 3-. l20 - 5'3 ..4 ANJ:> -0?.A £XHL8 7< 8 9 .

ITED J...£,(U< RATES bl=

'64.? AND.

(,I 6'ol 80 lol41 lscFH RtSPEc.T1yELY (TECH SPt::c: L1MrT:* 2Cf.3WI Sc.EH). A FE.W PAYS &ATER. I 7 8 9 / 80 lo15l8 ITHE5E Cl1ECK VAJ...VES WE'RE PRES$VR12 ED To soo p~1G- 1N P.N ATTEMPT TO I

. 7 9 . . I . . 80 fol61 l*Bt:TTER 'APPROXlt'YlATE:" ACC!J?C:NT CONDITIONS. SUBSl;;QUCNT 'RETE:STING- OF VAL..VESI

7. 8 9 * ** PRME . . ($E ATTAOIEJ)SJ1CT)80 SYSTEM CAUSE . * ' COMPONENT COMPONENT *
  • CODE
  • CODE COMPONENT COOE SU?PUEA MANUFACTURER llDLATlJN

~ ICIHI lfil IVIAILIVIEIXI lAJ 1Clfol~l51' lY.J

. 7 8 9 10 11 12 17 43 44 47 . 48 .*

.

  • CAU$E DESCRIPTION * . . * . . .

~ )IH£ JN1TiAl- LI-RI FAILUR~ OF VALVE 3-<l10~S"g-,4 WA~ APPARENTLY CAUSE:]) BY I 7 8 9 . . . ' 80 lolsl lD1R-t IN THE 5E11TttJfr f/R£fl. , L.JHtC/=l RES UL TcT> IN ExCESSI'/£ Disc "'."To.; S~AT *** .* I 7 8 9 ' . . . ' 80

'..;~>;J11PJ IC-LEl+RANC£S: PRES$URI z ING-. THE . VAJ.;V{F;kf.NJ//:l-l'-*VJA-:r£1?,..'-1EFF6:.CHl/EbY;. 'REJf>fJ0£fJ):i~,'i.t¢i.. I 7 . 8. 9 . FACILITY

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  • M*.ETHOO OF ($c E> fl. TT. OC. kt;.,..:.

..Y "

q . .J££_Tj'. .... _SQ

. .: . . . . STATUS " POWER OTHER STATUS . DISCOVERY' DISCOVERY OESCRIPTiON .

. 7

[ill]8 , *9I.HJ .

  • 10Io I o Io12I 13I . NA 44 I IBJ 45 AIA . .

4-6---------------------~80 I -~

. FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE fiEl . l6J . ~I~ _______N..._.A_ _ ___. NA 7 a* 9 10 . 11 44 45 80 PERSONNEL.- EXPOSURES

  • NUMBER TYPE DESCRIPTION

[!lfil Io 10 Io I. 1KJ . ~'______N__'._ A _ _ _ _ _ _ _ _ _ ___,___ _ _.,---_ __,I

. 1 as ** 11 12 13 so PERS'ONNEL. INJURIES .

. NUMBER DESCRIPTION ffEJ IOI O!OI ~--*V._A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..______,

7 8 9 11 12 80 OFFSITE CONSEQUENCES fill] . }JA 7 8 9 80 LOSS. OR DAMAGE TO _FACILITY TYPE

  • DESCRIPTION EID 1£J NA : .

7 as 10 80

. PUBLICITY .

[iI?J NA

. 7 B *9 80 ADDITIONAL FACTORS

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  • 8 9 80 PHONE: £';<,/. ';),_,/,,5°

EVENT DESCRIPTION (Continued) 3-220-58A and -62A yielded leak rates of 20,0 and 5220 SCFR respectively, Since the leakage through valve .3-220-58A was reduced to a value below .Tech Spec limits, no further action was necessary. Valve -62A was disassembled and repaired, Redundant valves were available and operable during unit operation, This is a repetitive occurrence. (50-249/1976-18)

  • CAUSE DESCRIPTION (Co?tinued) these clearances sufficiently to permit a satisfactory disc-to-seat seal, Disassembly of valve 3-220-62A revealed that, in addition to having dirt in the seating area, the valve also had worn disc assembly pins which resulted in an impre-cise disc-to-seat alignment. The valve was cleaned, and the disc assembly and seal ring were replaced. Following reassembly, valve -62A was retested, and a leak rate of 1.84 SCFH was obtained.
  • Because of the high incidence of initial LLRT *failures on the feedwater check valves, the station is currently reevaluating the method of testing these valves. The significant improvement in LLRT results which are obtained after the valves. have been back-seated with water indicates that the present testing method qoes,not allow an adequate determination of how these valves will perform tinder accident

.. ,, G.OJl~.i. tions. Valves. 3-:220-58A and -62A are 18-inch, tilting disc check valves man-

. . .,,~4'£a;tttlfecf~by.'.Cr1rie** c~irfp~ny.

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