ML19273B172: Difference between revisions

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NRO FORM 366 (7 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l                      l          l      l    l  l    l                    (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i                                          e lo ltl l0 lH lD lB S l1 l@l0 l0 l- lC l0                                                            lN  lP    lF    l-      0    l3    l 25
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                                                                                                                                                                                  @l    l bl UA T 58 l@
14          15                    LICENSE NL,,VdEH 7            8 9              LICENSEE CODE CON'T
                              '"
7            8 S iRC 60 L lhl 0 l 5 l 0 l- l 0 l 3 ! 4 [ 6Ml 0 l1 l1 l6 l7 l9 l@l 012l il 2l 7l 9 61                    DOCKET NUMB ER 6d    6')        EVENT DATE                14      15        REPORT DATE          80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h                                                                                                                      traced line 10121 l During_.the. performance of surveillance testing on 1/2/79 and 1/16/79, heat
[
o      a i temperature measurement points were below the 1050F limit as required by Technical o      4      l Specification 4.1.2.2. There was no danger to the health and safety of the public or 4 o      s          unit personnel. It                                  is a procedural practice to flush this line with water after                                                                    [
l 0      6      l boron injection is completed.                                            (NP-33-79-15) l 0      7      l
_
l O    8      l 80 7            8 9                                                                                                                                      COMP.            VALVE SYSTEM                    CAUSE        CAUSE                                                                              SUBCODE SUSCODE                CCMPONENT CODE                          SUBCODE CODE                      CODE Q                                      lP lC10l@                        B ]@ lA [@ l Z l Z l Z l Z l Z l Z l@ lZ l@                    18            13 Zl@
10 9                                11            12              fJ                                                                            REVISION 7            8                                                                                                                  OCCURRENCE              REFCRT SE QUE NTI AL                                                                                  N O.
CODE                TYPE tg g;po _ EVENT YE AR RT l7l9l                          l-l REPORT NO.
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b RE    nU                          22                23          24              26        27                28      29            30                31          J2
_ 28                                                                                                    NPRD4          PRIVE COMP.              COMPONENT SHUTOOWN                                    ATT AC HY E NT                                              M AN UF ACTUC e r<
ACTION FUTURE                    EFFECT                                                                SUBYtTTED          FORMdU8.          SUPPLIER METHOD                  uCURS W@ lZ kk k l@
TAKEN ACTION                    ON PL ANT IN l0 l0                      ! Y lh            lN      l@
b@l 33          J4
                                            @          I 35
                                                                      @        l36A '@          3/                    40 l
41                42                43              44                  47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i    o      l Both occurrences were caused by the injection of makeup (flush) water after boron in- l lTTTI I jection at a temperature lower than losoF. The tests were rerun after the heat i
In addition, a Facility Change Request was sub-                                                        l Iii>1 l tracing restored the temperature.
l i a          l mitted to either add a heat exchanger or change the Technical Specification.
l i 4          l                                                                                                                                                                                    80 7          8 9                                                                                        METHOO CF F ACILITY                                                                              DISCOV E R Y                                DISCOVERY DESCRIPTION
:. POWER                              OTHER STATUS STATUS                                                                                                                                                                                  l i    s      ] cj@ l 0l 0] 0l@l                                      NA                          l    l B l@l Surveillance Test ST 5011.0 A TIVITY        LONTENT                                                                                                            LOC ATION OF RELE ASE RELE ASED OF RELE ASE                                  AMOUNT OF ACTIVITY NA Q l 7] @ [ Zj @ l                10 NA 44 l
45 80
      '
8 9                                tt PERSONNEL f XPOSURES NOU8ER                                                                                                                                                                            l 1    7 l 0l 0l 0l@lTN                      Zl PE @lCESCRIPTION  NA                                                                                                                            C1 PERSONNE L INJURIES NUYBER              DESCRIPTION l
li IR8 I9 l d 01 d@l NA            11      12 go 7
LG33 OF CR DAY GE TO F ACillTV TYPE        DE SC4;P i TON
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Charles          ,  Alm                                          gm ,e      419 ' >'iT1                &t    bL, DVR 79-018                        , a m om om o
 
  .
.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UMIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-15 DATE OF EVENT: January 16, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:      Boron Injection Line Temperature Low Conditions Prior to Occurrence: The unit was in Mode 3, with Power (MWT) = 0, and Load (Gross MWE) = 0.
Description of Occurrence: During the performance of Section 6 of Surveillance Test ST 5011.01, " Boron Inj ection Heat Trace Test", on January 16, 1979 at 1130 hours, all line temperature measurement points were below the 1050F limit as required by Technical Specification 4.1.2.2. Also, during this investigation a similar 1979  type of at occurrence which was not reported was found to have occurred on January 2, 1030 hours. During that occurrence, only four of the eight temperature measurement points were balow the 1050F minimum required by Technical Specification 4.1.2.7 Both occurrences were caused by the Designation of Apparent Cause of Occurrence:                              The makeup injection of makeup (flush) water at a lcwer temperature than 105 .
(flush) water was at a temperature because its storage tanks are outside and main-tained only above freezing temperature.
Analysis of Occurrence:      There was no danger to the health and safety of the public or to unit personnel. The purpose of maintaining the line temperature above 105 F 1s to prevent boron crystalization which would block the boron injection flowpath.
Since it is procedural practice to flush this line with water af ter boron injection
                                .
is completed, no line blockage could occur unless the temperature of the line went below or equal to 32 F. The lowest temperature of either occurrence was 66 F.
Also, the Boric Acid Addition Tanks (the source of the concentrated boric ar.id) are normally maintained above 1200F and the line temperature returns to above 105 F when-ever the concentrated boric acid is injected.
Corrective Action: The test:5 were successfully completed af ter suf ficient tbne    was In addi-allowed for temperature recovery by the heat tracing af ter water inj ection.
tion, a Facility Change Request, FCR 78-508, was submitted to add a heat exchange r to the water injection line, add additional heat trace, or change the Technical Specification to recognize low tempercture due to water injection.
Failure Data:    There has been one previously reported borca injection line heat tracing test f ailu re on October 9,1978 (see Licensee Event Report NP-33-78-132) .
LER #79-012}}

Revision as of 17:45, 27 October 2019

LER 79-012/03L-0:on 790116,during Surveillance Testing,Heat Traced Line Temp Measurement Points Below 105 F Limit.Caused by Injection of Makeup (Flush) Water After Boron Injection at Temp Lower than 105 F.Tests Rerun Satisfactorily
ML19273B172
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/12/1979
From: Alm C
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19273B171 List:
References
LER-79-012-03L, LER-79-12-3L, NP-33-79-15, NUDOCS 7902200030
Download: ML19273B172 (2)


Text

...

..

NRO FORM 366 (7 77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i e lo ltl l0 lH lD lB S l1 l@l0 l0 l- lC l0 lN lP lF l- 0 l3 l 25

@l 26 4l 1l LICENSE ll ll TYPE 1 JO

@l l bl UA T 58 l@

14 15 LICENSE NL,,VdEH 7 8 9 LICENSEE CODE CON'T

'"

7 8 S iRC 60 L lhl 0 l 5 l 0 l- l 0 l 3 ! 4 [ 6Ml 0 l1 l1 l6 l7 l9 l@l 012l il 2l 7l 9 61 DOCKET NUMB ER 6d 6') EVENT DATE 14 15 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h traced line 10121 l During_.the. performance of surveillance testing on 1/2/79 and 1/16/79, heat

[

o a i temperature measurement points were below the 1050F limit as required by Technical o 4 l Specification 4.1.2.2. There was no danger to the health and safety of the public or 4 o s unit personnel. It is a procedural practice to flush this line with water after [

l 0 6 l boron injection is completed. (NP-33-79-15) l 0 7 l

_

l O 8 l 80 7 8 9 COMP. VALVE SYSTEM CAUSE CAUSE SUBCODE SUSCODE CCMPONENT CODE SUBCODE CODE CODE Q lP lC10l@ B ]@ lA [@ l Z l Z l Z l Z l Z l Z l@ lZ l@ 18 13 Zl@

10 9 11 12 fJ REVISION 7 8 OCCURRENCE REFCRT SE QUE NTI AL N O.

CODE TYPE tg g;po _ EVENT YE AR RT l7l9l l-l REPORT NO.

l0 1l 2l y l0 l3 l lL l l_] l0]

b RE nU 22 23 24 26 27 28 29 30 31 J2

_ 28 NPRD4 PRIVE COMP. COMPONENT SHUTOOWN ATT AC HY E NT M AN UF ACTUC e r<

ACTION FUTURE EFFECT SUBYtTTED FORMdU8. SUPPLIER METHOD uCURS W@ lZ kk k l@

TAKEN ACTION ON PL ANT IN l0 l0  ! Y lh lN l@

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@ l36A '@ 3/ 40 l

41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i o l Both occurrences were caused by the injection of makeup (flush) water after boron in- l lTTTI I jection at a temperature lower than losoF. The tests were rerun after the heat i

In addition, a Facility Change Request was sub- l Iii>1 l tracing restored the temperature.

l i a l mitted to either add a heat exchanger or change the Technical Specification.

l i 4 l 80 7 8 9 METHOO CF F ACILITY DISCOV E R Y DISCOVERY DESCRIPTION

. POWER OTHER STATUS STATUS l i s ] cj@ l 0l 0] 0l@l NA l l B l@l Surveillance Test ST 5011.0 A TIVITY LONTENT LOC ATION OF RELE ASE RELE ASED OF RELE ASE AMOUNT OF ACTIVITY NA Q l 7] @ [ Zj @ l 10 NA 44 l

45 80

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Charles , Alm gm ,e 419 ' >'iT1 &t bL, DVR 79-018 , a m om om o

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.

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UMIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-15 DATE OF EVENT: January 16, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Boron Injection Line Temperature Low Conditions Prior to Occurrence: The unit was in Mode 3, with Power (MWT) = 0, and Load (Gross MWE) = 0.

Description of Occurrence: During the performance of Section 6 of Surveillance Test ST 5011.01, " Boron Inj ection Heat Trace Test", on January 16, 1979 at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, all line temperature measurement points were below the 1050F limit as required by Technical Specification 4.1.2.2. Also, during this investigation a similar 1979 type of at occurrence which was not reported was found to have occurred on January 2, 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />. During that occurrence, only four of the eight temperature measurement points were balow the 1050F minimum required by Technical Specification 4.1.2.7 Both occurrences were caused by the Designation of Apparent Cause of Occurrence: The makeup injection of makeup (flush) water at a lcwer temperature than 105 .

(flush) water was at a temperature because its storage tanks are outside and main-tained only above freezing temperature.

Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. The purpose of maintaining the line temperature above 105 F 1s to prevent boron crystalization which would block the boron injection flowpath.

Since it is procedural practice to flush this line with water af ter boron injection

.

is completed, no line blockage could occur unless the temperature of the line went below or equal to 32 F. The lowest temperature of either occurrence was 66 F.

Also, the Boric Acid Addition Tanks (the source of the concentrated boric ar.id) are normally maintained above 1200F and the line temperature returns to above 105 F when-ever the concentrated boric acid is injected.

Corrective Action: The test:5 were successfully completed af ter suf ficient tbne was In addi-allowed for temperature recovery by the heat tracing af ter water inj ection.

tion, a Facility Change Request, FCR 78-508, was submitted to add a heat exchange r to the water injection line, add additional heat trace, or change the Technical Specification to recognize low tempercture due to water injection.

Failure Data: There has been one previously reported borca injection line heat tracing test f ailu re on October 9,1978 (see Licensee Event Report NP-33-78-132) .

LER #79-012