ML19343C071: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 23: Line 23:
lo l 18 9l l O LICENSEE l11 lDCODE    lB lS l141l@l    n 0 l 0 l 0 l 0          l 0 l 0 l 0 l 0 l 0 l 0 25l 0 l@l LickNM NW.*6LH                          26    4LICENSE l 1 l TY 1 PEl 1JO l 1 51l@ll CA T $8 l@
lo l 18 9l l O LICENSEE l11 lDCODE    lB lS l141l@l    n 0 l 0 l 0 l 0          l 0 l 0 l 0 l 0 l 0 l 0 25l 0 l@l LickNM NW.*6LH                          26    4LICENSE l 1 l TY 1 PEl 1JO l 1 51l@ll CA T $8 l@
7 CON'T
7 CON'T
                    "
[ojij 7        8 3{C"'
[ojij 7        8 3{C"'
g t      lL l@l 0l 5 l OOCKET 60            61 0l -l NUYSER 0 l 3l 4 l 6M @l630 l llEVENT    ll 4D ATE l 81 11@l0 l 2REPORT 14      75      l1 l 3    l 8 l180l@
g t      lL l@l 0l 5 l OOCKET 60            61 0l -l NUYSER 0 l 3l 4 l 6M @l630 l llEVENT    ll 4D ATE l 81 11@l0 l 2REPORT 14      75      l1 l 3    l 8 l180l@
Line 43: Line 42:
       , ,      l It is in fact a chlorinated hydrocarbon which when heated decomposes to chlorides.                                                                      [
       , ,      l It is in fact a chlorinated hydrocarbon which when heated decomposes to chlorides.                                                                      [
i j,g3g] Administrative Memorandum No. 4 was issued to provide specific instructions for the                                                                            l
i j,g3g] Administrative Memorandum No. 4 was issued to provide specific instructions for the                                                                            l
,
     ,,i,y l use of any solvent that could come in contact with the reactor coolant system.                                                                            30 l
     ,,i,y l use of any solvent that could come in contact with the reactor coolant system.                                                                            30 l
7      e 9
7      e 9
                                   % POWER                      oTHER STATUS                ISCO RY                          DISCCVERY DESCRIPTION STA S i s      W@ l 0 l 0 l 0 ]@l NA                                                  l    l B l@l Routine sampling                                                  ]
                                   % POWER                      oTHER STATUS                ISCO RY                          DISCCVERY DESCRIPTION STA S i s      W@ l 0 l 0 l 0 ]@l NA                                                  l    l B l@l Routine sampling                                                  ]
ACTIVITY      CO TENT AuOuNT OF ACTIVITY                                                  LOCATION oF RELE ASE nEtt ASEo Or aELE AsE
ACTIVITY      CO TENT AuOuNT OF ACTIVITY                                                  LOCATION oF RELE ASE nEtt ASEo Or aELE AsE l        l NA                                                                      l i c 7      8  9 l Zl @ l10Z l@l NA          11                                      44        45                                                                    80 PERSONNEL EXPOSURES N UPM E R            TYPE      DESCRIPTION -
'
l i 7      1010101@l Zl@l" NA                                                                                                                                    so
l        l NA                                                                      l i c 7      8  9 l Zl @ l10Z l@l NA          11                                      44        45                                                                    80 PERSONNEL EXPOSURES N UPM E R            TYPE      DESCRIPTION -
l
.
i 7      1010101@l Zl@l" NA                                                                                                                                    so
' '        ' ' PEnSoNNabu'n',ES NumE R                oESCn,PnON@
' '        ' ' PEnSoNNabu'n',ES NumE R                oESCn,PnON@
l 11 14 110101Ol@l12 NA                                                                                                                                              80 7      8 9                11 LOSS Of OR O AVAGE TO FACILITY TvrE      L E ;c nip T I O N l
l 11 14 110101Ol@l12 NA                                                                                                                                              80 7      8 9                11 LOSS Of OR O AVAGE TO FACILITY TvrE      L E ;c nip T I O N l
1  o s e J @lm NA                                                                                                                                                ,,
1  o s e J @lm NA                                                                                                                                                ,,
NRC USE ONt v im E "5 2
NRC USE ONt v im E "5 2 cmPnOs.@                                                                                                          l1iiiiiiiiiIj?
                                                                                                                                                                              ,
cmPnOs.@                                                                                                          l1iiiiiiiiiIj?
2 o      Lxl81 x^                                                                                                                l
2 o      Lxl81 x^                                                                                                                l
                                                                                                                                       " "
                                                                                                                                       " "
* 5
* 5
            " ''
                           '8    ] O " 18 0 5 W David W. Briden DVR 81-007                naytor7HCPARER                                                                                PHONE:
                           '8    ] O " 18 0 5 W David W. Briden
7
    '
* DVR 81-007                naytor7HCPARER                                                                                PHONE:
* 7


V
V TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION U'i1T ONE SUPPLLM:'NTAL INFORMATION FOR LER NP-33-81-04 DATE OF EVENT: January 14, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System Chloride Concentration Exceeded Steady State Limit Conditions Prior to Occurrence: The unit was in Mode 5 with Power (MWT) = 0 and Load (Gross IME) = 0.
                              .
    '
  .
.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION U'i1T ONE SUPPLLM:'NTAL INFORMATION FOR LER NP-33-81-04 DATE OF EVENT: January 14, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System Chloride Concentration Exceeded Steady State Limit Conditions Prior to Occurrence: The unit was in Mode 5 with Power (MWT) = 0 and Load (Gross IME) = 0.
Description of Occurrence: During the Reactor Coolant Pump (RCP) seal repair outage, the Reactor Coolant System (RCS) chloride concentration increased in excess of the 0.15 ppm steady state limit in Technical Specification 3.4.7.      On January 14, 1981 and January 18, 1981, chlorides reached 0.64 ppm and 1.28 ppm, respectively. Both occur-rences have been attributed,to the liberal use of Spotcheck in cleaning RCP seal cavi-ties. Each time the 0.15 ppm limit was exceeded for about two days. The temperature during this entire period was about 110 F, and the system pressure was less than 500 psig with the decay heat pumps circulating only the reactor vessel.
Description of Occurrence: During the Reactor Coolant Pump (RCP) seal repair outage, the Reactor Coolant System (RCS) chloride concentration increased in excess of the 0.15 ppm steady state limit in Technical Specification 3.4.7.      On January 14, 1981 and January 18, 1981, chlorides reached 0.64 ppm and 1.28 ppm, respectively. Both occur-rences have been attributed,to the liberal use of Spotcheck in cleaning RCP seal cavi-ties. Each time the 0.15 ppm limit was exceeded for about two days. The temperature during this entire period was about 110 F, and the system pressure was less than 500 psig with the decay heat pumps circulating only the reactor vessel.
During the RCS fill following completion of the seal repair work, purification flow was stopped on January 22 and January 23, 1981. During that time, chlorides gradually increased and on January 26, 1981 at 0130 hours it reached 0.24 ppm. At that time, two RCPs were started in order to heat the system to about 180 F to attempt to break down the organic chlorides and put them into solution as ionic Cl to facilitate remo-val by demineralization. The 0530 sample showed 0.83 ppm.      This large increase from 0.24 to 0.83 ppm confirmed the heat ef fects. Purification by demineralization con-tinued and at 2130 hours on January 27, 1981, one RCP in each loop was started to circulate the entire system. As expected, the chloride concentration increased from 0.11 ppm to 0.36 ppm. The system was cleaned up to within specs by 0800 hours on January 28, 1981. This cleanup was accelerated by the fact that Purification Demin-eralizer 1-2 was recharged with new resin and purification flow was increased from 40 gpm to 140 gpm for the first time at 0300 hours on January 27, 1981.
During the RCS fill following completion of the seal repair work, purification flow was stopped on January 22 and January 23, 1981. During that time, chlorides gradually increased and on January 26, 1981 at 0130 hours it reached 0.24 ppm. At that time, two RCPs were started in order to heat the system to about 180 F to attempt to break down the organic chlorides and put them into solution as ionic Cl to facilitate remo-val by demineralization. The 0530 sample showed 0.83 ppm.      This large increase from 0.24 to 0.83 ppm confirmed the heat ef fects. Purification by demineralization con-tinued and at 2130 hours on January 27, 1981, one RCP in each loop was started to circulate the entire system. As expected, the chloride concentration increased from 0.11 ppm to 0.36 ppm. The system was cleaned up to within specs by 0800 hours on January 28, 1981. This cleanup was accelerated by the fact that Purification Demin-eralizer 1-2 was recharged with new resin and purification flow was increased from 40 gpm to 140 gpm for the first time at 0300 hours on January 27, 1981.
Line 79: Line 63:
Designation of Apparent Cause of Occurrence: During the reactor coolant pump seal outage of January 1981, Spotcheck was added to the reactor coolant system when the seal cavities were being cleaned. Spotcheck is a chlorinated hydrocarbon and heating accelerates the decomposition into chlorides. The individual who allowed the Spot-check to enter the system was not aware of the consequences of the solvent in the system since the label on the container states " certified to meet chloride purity".
Designation of Apparent Cause of Occurrence: During the reactor coolant pump seal outage of January 1981, Spotcheck was added to the reactor coolant system when the seal cavities were being cleaned. Spotcheck is a chlorinated hydrocarbon and heating accelerates the decomposition into chlorides. The individual who allowed the Spot-check to enter the system was not aware of the consequences of the solvent in the system since the label on the container states " certified to meet chloride purity".
The procedure did not have adequate warnings to indicate the solvent was detrimental to the sysven if used improperly.
The procedure did not have adequate warnings to indicate the solvent was detrimental to the sysven if used improperly.
                                                -
LER #81-003
LER #81-003
                                                    .


                              - -                                                          ..                  . - _
                                                                         .=_. ,                          -              _-- -            -              . . - -          ..
                                                                         .=_. ,                          -              _-- -            -              . . - -          ..
                                            .
            *
          .
r TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PO'JER STATION UNIT ONE SUPPLEMENTAL INFOR'!ATION FOR LER MP-33-81-04                                                                                    PAGE 2 Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The cloride concentrations for all three excursions from January 14, 1981 through January 28, 1981 were less than the transient limit of 1.50 l
r TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PO'JER STATION UNIT ONE SUPPLEMENTAL INFOR'!ATION FOR LER MP-33-81-04                                                                                    PAGE 2 Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The cloride concentrations for all three excursions from January 14, 1981 through January 28, 1981 were less than the transient limit of 1.50 l
ppm. The RCS temperature never exceeded 200 and most of the time was less than
ppm. The RCS temperature never exceeded 200 and most of the time was less than 140 F. The system pressure remained far less than 500 psig. The combination of these parameters diminishes the potential of any harm to the RCS. Material damage is definitely negligible.                In fact, very little damage could occur from any level of chlorides'less than 10 ppm if the technical specification action statement is 4            followed.
'
140 F. The system pressure remained far less than 500 psig. The combination of these parameters diminishes the potential of any harm to the RCS. Material damage is definitely negligible.                In fact, very little damage could occur from any level of chlorides'less than 10 ppm if the technical specification action statement is 4            followed.
4 Corrective Action: Administrative Memorandum No. 4 was prepared which provides speci-fic instructions regarding the use of any solvent when it is used for cleaning compon-ents which could come in contact with the reactor coolant system. This memorandum j
4 Corrective Action: Administrative Memorandum No. 4 was prepared which provides speci-fic instructions regarding the use of any solvent when it is used for cleaning compon-ents which could come in contact with the reactor coolant system. This memorandum j
has been routed to the station personnel. The Maintenance Engineer has given special                                                                          1 I          sessions to maintenance personnel to provide instructions on the controls required when reactor coolant system' components are cleaned.
has been routed to the station personnel. The Maintenance Engineer has given special                                                                          1 I          sessions to maintenance personnel to provide instructions on the controls required when reactor coolant system' components are cleaned.
Failure Data: No previous situations where the chloride concentration e::ceeded the
Failure Data: No previous situations where the chloride concentration e::ceeded the steady state' limit for water in the reactor coolant system have occurred.                                                                                    ,
,
steady state' limit for water in the reactor coolant system have occurred.                                                                                    ,
;
                                                                                                                        .
                                                                                                                                                  - .
s l.
s l.
e Y
e Y
                                                                                          .
   ., ,w-.y  ,.,,~.y-          .,,,,,%--    , , , ,    , - - - .,-,4    +,., ,  ,,m .
   ., ,w-.y  ,.,,~.y-          .,,,,,%--    , , , ,    , - - - .,-,4    +,., ,  ,,m .
3  . , , . , .g.. ,            , ,,,-,e#r  ,m    ,    ,
3  . , , . , .g.. ,            , ,,,-,e#r  ,m    ,    ,
                                                                                                                                                                    -
                                                                                                                                                               -,- , ---}}
                                                                                                                                                               -,- , ---}}

Latest revision as of 07:02, 18 February 2020

LER 81-005/03L-0:on 810114,RCS Chloride Concentration Exceeded Tech Spec Limit.Caused by Use of Spotcheck in Cleaning Reactor Coolant Pump Seal Cavities.Instructions Issued for Use of Solvents in RCS
ML19343C071
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/13/1981
From: Briden D
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19343C068 List:
References
LER-81-005-03L, LER-81-5-3L, NUDOCS 8102180544
Download: ML19343C071 (3)
v • d • e


Text

NRC FORM ;5G U b LULLLAh HLuulAlUK k Lw. .wu (7 77) .

x LICENSEE EVENT REPORT (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION)

CONTROL BLOCK: l 1

l l l l l lh 6

lo l 18 9l l O LICENSEE l11 lDCODE lB lS l141l@l n 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 l 0 25l 0 l@l LickNM NW.*6LH 26 4LICENSE l 1 l TY 1 PEl 1JO l 1 51l@ll CA T $8 l@

7 CON'T

[ojij 7 8 3{C"'

g t lL l@l 0l 5 l OOCKET 60 61 0l -l NUYSER 0 l 3l 4 l 6M @l630 l llEVENT ll 4D ATE l 81 11@l0 l 2REPORT 14 75 l1 l 3 l 8 l180l@

DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h j o l 2 l l (NP-33-81-04) On 1/14/81 Ehe Reactor Coolant System (RCS) chloride concentration was ]

f und in excess of the steady state limit of 0.15 ppm. The level was 0.64 ppm. On l

[o l3 l 1

[o141l1/18/81 the level reached 1.28 ppm. The limit was exceeded for two days each time. J Iolsl l lts cause was determined to be from the use of Spotcheck in cleaning reactor coolant [

l o is_J l pump (RCP) seal cavities. To further clean the system required some heating to decomt lo l7] l pose the solvent so that chlorides could be removed by demineralization. This l l o Ia l I caused the limits to be exceeded again on 1/26/81 and 1/27/81. ]

80 SYSTEM CAUSE cat!SE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE lolol F 8 9 l Rl Al@ W@ l Z l@ lZ lZ lZ lZ lZ lZ l@ {@ ]@

10 11 12 13 18 19 20 SEQUENTI AL oCCU R R E NCE REPORT REVISION EVENT YE AR REPORT No. CODE TYPE NO.

h ,"LE R Ro 18 l1 l g.hRT

_ 21 22

[- ,-j 2J l 0l Ol 5l 24 2b d

27 10 l3 l 28 29 W

30 l-l 31 l0 l 32 O PLA T ETH HOURS 22 S B 1T P B. SUPPLIE k MAN PACTUPER A EN AC TION l0 l0 l0 l9 40l [Y 41__ l@

lNl@ ]Z l@ lZ [9 l9 l9 l@

lJJX [gl34H lg l35C [g 'l36 Zl@ 31 42 43 44 di CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lilollThe cause was a lack of adequate warning to indicate the detrinental effects to the I

[ilil l system if used improperly. "Spotcheck" is labeled as nuclear nrade and chloride fron ]

, , l It is in fact a chlorinated hydrocarbon which when heated decomposes to chlorides. [

i j,g3g] Administrative Memorandum No. 4 was issued to provide specific instructions for the l

,,i,y l use of any solvent that could come in contact with the reactor coolant system. 30 l

7 e 9

% POWER oTHER STATUS ISCO RY DISCCVERY DESCRIPTION STA S i s W@ l 0 l 0 l 0 ]@l NA l l B l@l Routine sampling ]

ACTIVITY CO TENT AuOuNT OF ACTIVITY LOCATION oF RELE ASE nEtt ASEo Or aELE AsE l l NA l i c 7 8 9 l Zl @ l10Z l@l NA 11 44 45 80 PERSONNEL EXPOSURES N UPM E R TYPE DESCRIPTION -

l i 7 1010101@l Zl@l" NA so

' ' ' ' PEnSoNNabu'n',ES NumE R oESCn,PnON@

l 11 14 110101Ol@l12 NA 80 7 8 9 11 LOSS Of OR O AVAGE TO FACILITY TvrE L E ;c nip T I O N l

1 o s e J @lm NA ,,

NRC USE ONt v im E "5 2 cmPnOs.@ l1iiiiiiiiiIj?

2 o Lxl81 x^ l

" "

  • 5

'8 ] O " 18 0 5 W David W. Briden DVR 81-007 naytor7HCPARER PHONE:

7

V TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION U'i1T ONE SUPPLLM:'NTAL INFORMATION FOR LER NP-33-81-04 DATE OF EVENT: January 14, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System Chloride Concentration Exceeded Steady State Limit Conditions Prior to Occurrence: The unit was in Mode 5 with Power (MWT) = 0 and Load (Gross IME) = 0.

Description of Occurrence: During the Reactor Coolant Pump (RCP) seal repair outage, the Reactor Coolant System (RCS) chloride concentration increased in excess of the 0.15 ppm steady state limit in Technical Specification 3.4.7. On January 14, 1981 and January 18, 1981, chlorides reached 0.64 ppm and 1.28 ppm, respectively. Both occur-rences have been attributed,to the liberal use of Spotcheck in cleaning RCP seal cavi-ties. Each time the 0.15 ppm limit was exceeded for about two days. The temperature during this entire period was about 110 F, and the system pressure was less than 500 psig with the decay heat pumps circulating only the reactor vessel.

During the RCS fill following completion of the seal repair work, purification flow was stopped on January 22 and January 23, 1981. During that time, chlorides gradually increased and on January 26, 1981 at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> it reached 0.24 ppm. At that time, two RCPs were started in order to heat the system to about 180 F to attempt to break down the organic chlorides and put them into solution as ionic Cl to facilitate remo-val by demineralization. The 0530 sample showed 0.83 ppm. This large increase from 0.24 to 0.83 ppm confirmed the heat ef fects. Purification by demineralization con-tinued and at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on January 27, 1981, one RCP in each loop was started to circulate the entire system. As expected, the chloride concentration increased from 0.11 ppm to 0.36 ppm. The system was cleaned up to within specs by 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on January 28, 1981. This cleanup was accelerated by the fact that Purification Demin-eralizer 1-2 was recharged with new resin and purification flow was increased from 40 gpm to 140 gpm for the first time at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on January 27, 1981.

By exceeding the steady state limit, the station entered into the action statement which required that RCS pressure be limited to 500 psig. It also required an engineer-ing evaluation to determine the effects on the structural integrity of the RCS. The requirements were met.

Designation of Apparent Cause of Occurrence: During the reactor coolant pump seal outage of January 1981, Spotcheck was added to the reactor coolant system when the seal cavities were being cleaned. Spotcheck is a chlorinated hydrocarbon and heating accelerates the decomposition into chlorides. The individual who allowed the Spot-check to enter the system was not aware of the consequences of the solvent in the system since the label on the container states " certified to meet chloride purity".

The procedure did not have adequate warnings to indicate the solvent was detrimental to the sysven if used improperly.

LER #81-003

.=_. , - _-- - - . . - - ..

r TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PO'JER STATION UNIT ONE SUPPLEMENTAL INFOR'!ATION FOR LER MP-33-81-04 PAGE 2 Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The cloride concentrations for all three excursions from January 14, 1981 through January 28, 1981 were less than the transient limit of 1.50 l

ppm. The RCS temperature never exceeded 200 and most of the time was less than 140 F. The system pressure remained far less than 500 psig. The combination of these parameters diminishes the potential of any harm to the RCS. Material damage is definitely negligible. In fact, very little damage could occur from any level of chlorides'less than 10 ppm if the technical specification action statement is 4 followed.

4 Corrective Action: Administrative Memorandum No. 4 was prepared which provides speci-fic instructions regarding the use of any solvent when it is used for cleaning compon-ents which could come in contact with the reactor coolant system. This memorandum j

has been routed to the station personnel. The Maintenance Engineer has given special 1 I sessions to maintenance personnel to provide instructions on the controls required when reactor coolant system' components are cleaned.

Failure Data: No previous situations where the chloride concentration e::ceeded the steady state' limit for water in the reactor coolant system have occurred. ,

s l.

e Y

., ,w-.y ,.,,~.y- .,,,,,%-- , , , , , - - - .,-,4 +,., , ,,m .

3 . , , . , .g.. , , ,,,-,e#r ,m , ,

-,- , ---

Retrieved from "https://kanterella.com/w/index.php?title=ML19343C071&oldid=2481502"