ML19305A907: Difference between revisions
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{{#Wiki_filter:NRC FC*1M 366 - U. S. NUCLE AR REGULATCHY COMMISSION unit 3 LICENSEE EVENT REPORT Report hw. 3-80-h/3L CONTRCL BLOCK: l l l l l l l (PLf!ASE PRINT OR TYPE ALL REQUIRED INFORMATION) . | {{#Wiki_filter:NRC FC*1M 366 - U. S. NUCLE AR REGULATCHY COMMISSION unit 3 LICENSEE EVENT REPORT Report hw. 3-80-h/3L CONTRCL BLOCK: l l l l l l l (PLf!ASE PRINT OR TYPE ALL REQUIRED INFORMATION) . | ||
. I 6 | . I 6 O i 8 9 le l A lP lB UCENSEE CODElS l 3 l@16 Ol Ol 14 UCENSE-l0NUMSER l Ol Ol 0l 0l -l Ol 0lh 2b 26 4 lTYPE UCENSE 1l JO1l 1l57 CAT l | ||
O i 8 9 le l A lP lB UCENSEE CODElS l 3 l@16 Ol Ol 14 UCENSE-l0NUMSER l Ol Ol 0l 0l -l Ol 0lh 2b 26 4 lTYPE UCENSE 1l JO1l 1l57 CAT l | |||
1l@l 58 | 1l@l 58 | ||
[ | [ | ||
CON'T 7 8 Eu lLI@l015lOl-l012 60 $1 17 18 @l68 0 69l 2 l EVENT DOctCET NUMSER 0 l 518 DATE I o l@l 760131016181 74 REPORT DATE o80l@ | CON'T 7 8 Eu lLI@l015lOl-l012 60 $1 17 18 @l68 0 69l 2 l EVENT DOctCET NUMSER 0 l 518 DATE I o l@l 760131016181 74 REPORT DATE o80l@ | ||
EVENT OESCRIPTION AND PROSA8LE CONSEQUENCES h O 2 l During the startup of Unit 3, the reactor water conductivity increased l Lo- -L31 1 and exceeded Tech. Spoc. 3.6.B.3.(a) limit of 10 umho/ca. The reactor l 0 4 I water conductivity peaked at 12.6 umho/cm and was greater than 10 for l | |||
@l approvimately h.5 hours. During the reactor startup and conductivity l 0 6 l spike, the reactor pressure rammined below $20 psig. Due to the short i f0TTl I period of tl-is occurrence and the low reactor pressure, no effects are l I 5TO I expected to the materials in the primary system boundary. I h E S 8C E COMPONENT CODE SUS ode S E FOTF1 l H l G l@ [B,j@ [ C_j @ l D l E l M l I l N l I l@ [ z_j@ [ Zj @ | @l approvimately h.5 hours. During the reactor startup and conductivity l 0 6 l spike, the reactor pressure rammined below $20 psig. Due to the short i f0TTl I period of tl-is occurrence and the low reactor pressure, no effects are l I 5TO I expected to the materials in the primary system boundary. I h E S 8C E COMPONENT CODE SUS ode S E FOTF1 l H l G l@ [B,j@ [ C_j @ l D l E l M l I l N l I l@ [ z_j@ [ Zj @ | ||
7 8 9 to 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION | 7 8 9 to 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO. | ||
@ ;LER/Ro gog 18101 L_1 loloihl l'l 10131 LL_j [-l [0_j 21 22 23 24 26 27 N M 30 38 32 AK A NT M O HO S S8 4 FOR B. L MANU A RER LxJ@L2]@ | |||
EVENT YEAR REPORT NO. CODE TYPE NO. | |||
@ ;LER/Ro gog 18101 L_1 loloihl l'l 10131 LL_j [-l [0_j 21 22 23 24 26 27 N M 30 38 32 | |||
AK A NT M O HO S S8 4 FOR B. L MANU A RER LxJ@L2]@ | |||
33 34 lol@ | 33 34 lol@ | ||
36 Lzj@ | 36 Lzj@ | ||
Line 38: | Line 31: | ||
4l l42Nl@ l43Al@ lGl2l2l0l@ | 4l l42Nl@ l43Al@ lGl2l2l0l@ | ||
44 47 l | 44 47 l | ||
CAUSE OESCRIPTION AND CORRECTIVE ACTIONS i | CAUSE OESCRIPTION AND CORRECTIVE ACTIONS i gl The reactor water conductivity increase is believed to be due to resin l i i l injection. The mechnnisa for the resin injection is unknown but is be- I | ||
gl The reactor water conductivity increase is believed to be due to resin l i i l injection. The mechnnisa for the resin injection is unknown but is be- I | |||
, 7 l lieved to be from the condensate filter /demineralizer system. Upon ex- I gl ceeding the Tech. Spec. conductivity limit the reactor was shutdown and l gl the primary coolant chemistry was brought within limits using the RWCU. l 7 0 9 80 ST $ % POWER oTHER STATUS OlSCO RY DISCCVERY DESCRIPTION | , 7 l lieved to be from the condensate filter /demineralizer system. Upon ex- I gl ceeding the Tech. Spec. conductivity limit the reactor was shutdown and l gl the primary coolant chemistry was brought within limits using the RWCU. l 7 0 9 80 ST $ % POWER oTHER STATUS OlSCO RY DISCCVERY DESCRIPTION | ||
[ijf]l0l@ l0l0l1l@l N/A l (_3_j@l Routine startup chemistry testing l A TivtTY CO TENT REi.EASto ce RELE ASE LOCATION oF RELEASE Lull l_z_1@ LzJ@l AmouNTor N/A ACTIVITY l N/A@l l | [ijf]l0l@ l0l0l1l@l N/A l (_3_j@l Routine startup chemistry testing l A TivtTY CO TENT REi.EASto ce RELE ASE LOCATION oF RELEASE Lull l_z_1@ LzJ@l AmouNTor N/A ACTIVITY l N/A@l l | ||
,ERSO~~Et Ex,OSSES NUMil( H TYPE DESCRIPTION - | |||
,ERSO~~Et Ex,OSSES | |||
LLL'_I l 0 I o I o l@LZ_J@l f/A I | LLL'_I l 0 I o I o l@LZ_J@l f/A I | ||
' " ' ,ERSON~EL'iN2u'AES '' * | ' " ' ,ERSON~EL'iN2u'AES '' * | ||
Line 57: | Line 45: | ||
121#"I9 LN_J@ l DESCRIPTIONN/A l llllIllllll1li i 10 68 69 80 o | 121#"I9 LN_J@ l DESCRIPTIONN/A l llllIllllll1li i 10 68 69 80 o | ||
NAMF O.F. PR..E.PA.RE. // p. y_.M. /__J. Cooney PHONE: | NAMF O.F. PR..E.PA.RE. // p. y_.M. /__J. Cooney PHONE: | ||
(215) 841-5020 | (215) 841-5020 o | ||
o | |||
; 8'0031 80 | ; 8'0031 80 | ||
~ %* 7}} | ~ %* 7}} |
Latest revision as of 14:00, 1 February 2020
ML19305A907 | |
Person / Time | |
---|---|
Site: | Peach Bottom |
Issue date: | 03/06/1980 |
From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
Shared Package | |
ML19305A901 | List: |
References | |
LER-80-004-03L-01, LER-80-4-3L-1, NUDOCS 8003180567 | |
Download: ML19305A907 (1) | |
Text
NRC FC*1M 366 - U. S. NUCLE AR REGULATCHY COMMISSION unit 3 LICENSEE EVENT REPORT Report hw. 3-80-h/3L CONTRCL BLOCK: l l l l l l l (PLf!ASE PRINT OR TYPE ALL REQUIRED INFORMATION) .
. I 6 O i 8 9 le l A lP lB UCENSEE CODElS l 3 l@16 Ol Ol 14 UCENSE-l0NUMSER l Ol Ol 0l 0l -l Ol 0lh 2b 26 4 lTYPE UCENSE 1l JO1l 1l57 CAT l
1l@l 58
[
CON'T 7 8 Eu lLI@l015lOl-l012 60 $1 17 18 @l68 0 69l 2 l EVENT DOctCET NUMSER 0 l 518 DATE I o l@l 760131016181 74 REPORT DATE o80l@
EVENT OESCRIPTION AND PROSA8LE CONSEQUENCES h O 2 l During the startup of Unit 3, the reactor water conductivity increased l Lo- -L31 1 and exceeded Tech. Spoc. 3.6.B.3.(a) limit of 10 umho/ca. The reactor l 0 4 I water conductivity peaked at 12.6 umho/cm and was greater than 10 for l
@l approvimately h.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. During the reactor startup and conductivity l 0 6 l spike, the reactor pressure rammined below $20 psig. Due to the short i f0TTl I period of tl-is occurrence and the low reactor pressure, no effects are l I 5TO I expected to the materials in the primary system boundary. I h E S 8C E COMPONENT CODE SUS ode S E FOTF1 l H l G l@ [B,j@ [ C_j @ l D l E l M l I l N l I l@ [ z_j@ [ Zj @
7 8 9 to 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.
@ ;LER/Ro gog 18101 L_1 loloihl l'l 10131 LL_j [-l [0_j 21 22 23 24 26 27 N M 30 38 32 AK A NT M O HO S S8 4 FOR B. L MANU A RER LxJ@L2]@
33 34 lol@
36 Lzj@
36 loIoIoIoI 37 40 LT_J@
4l l42Nl@ l43Al@ lGl2l2l0l@
44 47 l
CAUSE OESCRIPTION AND CORRECTIVE ACTIONS i gl The reactor water conductivity increase is believed to be due to resin l i i l injection. The mechnnisa for the resin injection is unknown but is be- I
, 7 l lieved to be from the condensate filter /demineralizer system. Upon ex- I gl ceeding the Tech. Spec. conductivity limit the reactor was shutdown and l gl the primary coolant chemistry was brought within limits using the RWCU. l 7 0 9 80 ST $ % POWER oTHER STATUS OlSCO RY DISCCVERY DESCRIPTION
[ijf]l0l@ l0l0l1l@l N/A l (_3_j@l Routine startup chemistry testing l A TivtTY CO TENT REi.EASto ce RELE ASE LOCATION oF RELEASE Lull l_z_1@ LzJ@l AmouNTor N/A ACTIVITY l N/A@l l
,ERSO~~Et Ex,OSSES NUMil( H TYPE DESCRIPTION -
LLL'_I l 0 I o I o l@LZ_J@l f/A I
' " ' ,ERSON~EL'iN2u'AES *
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W'A ' "M"Rf,%'N ' "" @
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PUuuuty NRC USE ONLY
- ISSUED ,
121#"I9 LN_J@ l DESCRIPTIONN/A l llllIllllll1li i 10 68 69 80 o
NAMF O.F. PR..E.PA.RE. // p. y_.M. /__J. Cooney PHONE:
(215) 841-5020 o
- 8'0031 80
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