ML19339C867: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 20: Line 20:
=Text=
=Text=
{{#Wiki_filter:-
{{#Wiki_filter:-
                                                                                                                            - - . - - .--                        -
NRC F ORM 366                                                                                                                      U. S. NUCLEAR REGULATORY COMMISSION 87 771 LICENSEE EVENT REPORT
                                                                                  -      ..
                                -        ...          -          _
NRC F ORM 366                                                                                                                      U. S. NUCLEAR REGULATORY COMMISSION 87 771
                    -
LICENSEE EVENT REPORT
         ~
         ~
coNTRotstOcx l                    l      l      l    1  I                      (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 9 ;il I uI T I p I a I nI 1l@l 0 l 0 l- I O I O I O l 0 l 0 l- 1010                                                    25 l@l  26 4 LICENSE l11111l          1l@l5 7 G lA T 58l@
coNTRotstOcx l                    l      l      l    1  I                      (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 9 ;il I uI T I p I a I nI 1l@l 0 l 0 l- I O I O I O l 0 l 0 l- 1010                                                    25 l@l  26 4 LICENSE l11111l          1l@l5 7 G lA T 58l@
Line 45: Line 40:
t                                                                                                                                                        i l                                                                                                                                                                                80 7      8 9
t                                                                                                                                                        i l                                                                                                                                                                                80 7      8 9
                                       % POV.ER                        OTHER ST ATUS            DIS O RY                              DISCOVERY 0ESCRIPTION STA S                                                                                                                                                        '
                                       % POV.ER                        OTHER ST ATUS            DIS O RY                              DISCOVERY 0ESCRIPTION STA S                                                                                                                                                        '
f  I i i s I (1.j@ l Ol 7 l 9 l@l NA
f  I i i s I (1.j@ l Ol 7 l 9 l@l NA l    lBl@l Review of test                                                            l 4
                                                          '
l    lBl@l Review of test                                                            l 4
!              ACTIVITY        CO TENT AMOUNT OF ACTIVITY                                                      LOCATION OF RELEASE RELE ASED OF RELE ASE l NA                                                                      l WW F    a 9
!              ACTIVITY        CO TENT AMOUNT OF ACTIVITY                                                      LOCATION OF RELEASE RELE ASED OF RELE ASE l NA                                                                      l WW F    a 9
                     @ lZ l@l NA  to            11                                            44 l
                     @ lZ l@l NA  to            11                                            44 l
45                                                                      90
45                                                                      90
                       #ERSONNEL EuPOSURES NUMBER                TYPE          DESCRIPTION
                       #ERSONNEL EuPOSURES NUMBER                TYPE          DESCRIPTION
                                                                         'a                                            .                                                            l 11171 10 l 0 l 0 l@l z l@l NA
                                                                         'a                                            .                                                            l 11171 10 l 0 l 0 l@l z l@l NA l
_
l
                       'ERSONNEL INJUR ES NUveER                  OESCRiPTION l      _
                       'ERSONNEL INJUR ES NUveER                  OESCRiPTION l      _
li Is l8 l9 0 l 0 l O l@l12 NA '
li Is l8 l9 0 l 0 l O l@l12 NA '
Line 63: Line 54:
PV 8 t *CI TY                                                                                                                          NRC USE ONLY f                ISSUED        D ESCRiPTION l, l l l l l l'l l i 1 I l l:L 12 l o l l N ihl NA                                                                                                                          68 69                          80 3 7      8 9                                                                                                                                                                        o c* w* ray                                                              414/277-2811 -
PV 8 t *CI TY                                                                                                                          NRC USE ONLY f                ISSUED        D ESCRiPTION l, l l l l l l'l l i 1 I l l:L 12 l o l l N ihl NA                                                                                                                          68 69                          80 3 7      8 9                                                                                                                                                                        o c* w* ray                                                              414/277-2811 -
310e 120 lf*SoNAME OF PREPARER                                                                                                      PHONE:
310e 120 lf*SoNAME OF PREPARER                                                                                                      PHONE:
                                                                                                                                                                                        *
                                                                                                                                                                                      - , - - - -


                                                                                                                  ,              .
a o
a o
ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-002/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 On January 13, 1981, during normal operations, while reviewing the control room emergency filtration system's annual test results from April of 1980 for a control room habitability study, it was discovered that the 1980 annual test was not complete as it did not meet the testing requirements of Technical Specification 15.4.11.
ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-002/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 On January 13, 1981, during normal operations, while reviewing the control room emergency filtration system's annual test results from April of 1980 for a control room habitability study, it was discovered that the 1980 annual test was not complete as it did not meet the testing requirements of Technical Specification 15.4.11.
Line 84: Line 72:
   ---- = - -
   ---- = - -
In addition, it should be noted that the system is being evaluated'in accordance with NUREG-0737, Item III.D.3.'4..
In addition, it should be noted that the system is being evaluated'in accordance with NUREG-0737, Item III.D.3.'4..
  .
s, .m,
s, .m,
                                                                                                                                     . esp., -
                                                                                                                                     . esp., -
                                                                                           ~.e  a                    e er 4,e* e  e.sm..o s
                                                                                           ~.e  a                    e er 4,e* e  e.sm..o s d M' %GN' y
                                      '
                                          **
d M' %GN' y
                                                                       =    F                  peWse .Wes% em er Mh + "
                                                                       =    F                  peWse .Wes% em er Mh + "
n -  --n-~}}
n -  --n-~}}

Revision as of 10:57, 31 January 2020

LER 81-002/03L-0:on 810113,post Acceptance Review of Annual Test Results from 04-80,for Control Room Emergency Filtration Sys,Showed 1980 Annual Test Incomplete.Caused by Personnel Failing to Determine Sys Velocity & Flow Info
ML19339C867
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 02/04/1981
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19339C866 List:
References
LER-81-002-03L, LER-81-2-3L, NUDOCS 8102120162
Download: ML19339C867 (2)


Text

-

NRC F ORM 366 U. S. NUCLEAR REGULATORY COMMISSION 87 771 LICENSEE EVENT REPORT

~

coNTRotstOcx l l l l 1 I (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 9 ;il I uI T I p I a I nI 1l@l 0 l 0 l- I O I O I O l 0 l 0 l- 1010 25 l@l 26 4 LICENSE l11111l 1l@l5 7 G lA T 58l@

TYPE JO F 4 'l LICENSEE CODE 14 15 LICENSE NUYSER CON'T

%,"c' l L }@l 0151010 l 012 l 61668 ]@l69 0111113 EVENT DATE l 8111@i 012l 74 75 O l4 18 l 1l@

REPORT O ATE 83 F 8 60 6' OOCK ET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lol2l [On 01 81, durinc normal operation, a post acceptance review of the l 1013l ! annual test resnits from 04-80, for the control room emergency filtra- l I o 14 l Ition system, revealed that the 1980 annual test was not complete per l At this time, the control room emergency filtration system l lolsllTS 15.4.11.

l o is ] l (common to both units) was deemed inoperable by TS definition. This ledl lol7]Ito a degraded mode of operation allowed by TS's. The public health and l i o is l l safety was not affected as the system, in reality, was noerational. 80 l

$YSTEV CAUSE CAUSE COMP. VALVE CODE CODE SUSCODE COMPONENT CODE SusCODE SUSCODE 10191 I s i c l@ LAj@ l o l@ I z i z l z l z i z l z l@ 1r9 Z 1@ W @ 18 to 7 9 9 10 11 12 13 SEQUENTI AL OCCURRENCE REPORT REVISION REPORT NO. CODE TYPE NO.

LE R A0 _ EVENT YE AR O ty&a; 18111 l-l 1010121 l/l 1013_] ILI l-l 101 23 24 26 27 28 29 30 31 32

_ 29 22 ONP ANT VETH HOURS S9 6T O FOR B. 5 P'L8 E MANUFACTURER TAwfN A T ON

(_XJ@lGl@

33 J4 lzl@

JS l36Z l@ l010l0l0l 3d 40 l41 Y l@ IN 42 l@ lzl@ lzl9l9[9[@

43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l 1ilollThe event was caused by Health Physics personnel failing to determine, I 12 1 1Idurinc the acceotance review, that the test lacked system velocity and I The test was repeated and the system was found to tii21Iflow information.

[il3l l perform satisfactory on 01-15-8}. The testing procedures are being l

l

(

tii4i imodified to assure that system velocity and flow informat on is included.;

t i l 80 7 8 9

% POV.ER OTHER ST ATUS DIS O RY DISCOVERY 0ESCRIPTION STA S '

f I i i s I (1.j@ l Ol 7 l 9 l@l NA l lBl@l Review of test l 4

! ACTIVITY CO TENT AMOUNT OF ACTIVITY LOCATION OF RELEASE RELE ASED OF RELE ASE l NA l WW F a 9

@ lZ l@l NA to 11 44 l

45 90

  1. ERSONNEL EuPOSURES NUMBER TYPE DESCRIPTION

'a . l 11171 10 l 0 l 0 l@l z l@l NA l

'ERSONNEL INJUR ES NUveER OESCRiPTION l _

li Is l8 l9 0 l 0 l O l@l12 NA '

7 ti 80 LOSS OF OR DAMAGE TO F AClllTY TYPE D E SCRIPTION I

LLpj i z l@l NA 60

} 7 8 9 10

PV 8 t *CI TY NRC USE ONLY f ISSUED D ESCRiPTION l, l l l l l l'l l i 1 I l l:L 12 l o l l N ihl NA 68 69 80 3 7 8 9 o c* w* ray 414/277-2811 -

310e 120 lf*SoNAME OF PREPARER PHONE:

a o

ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-002/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 On January 13, 1981, during normal operations, while reviewing the control room emergency filtration system's annual test results from April of 1980 for a control room habitability study, it was discovered that the 1980 annual test was not complete as it did not meet the testing requirements of Technical Specification 15.4.11.

At this time, the control room emergency filtration system (common to both units) was deemed inoperable by Technical Specification definition.

This led to a degraded mode of operation allowed by the Technical Specification.

The public health and safety was not affected by this event, as the system, in reality, was operational.

The event was caused by a failure, of Health Physics personnel during the initial acceptance review, to determine that the annual test was incomplete. The 1980 annual test lacked actual system velocity and flow information. The testing procedures are being modified to assure that the tests include actual system velocity and flow information.

The subject system was retested on January 14, 1981. The resulting data was analyzed on January 15, 1981 and the system was found to function properly as no degradation of system performance was evident in comparison to previous test data.

It should be noted that there is some question in the inter-pretation of the testing requirements and acceptance criteria relating to system design conditions and In specified in Technical particular, the Specifications 15.3.12.2 and 15.4.11.4. (i.e., maximum design,

question nominal relates to what design, etc.) desien parametershould be assigned to " design velocity" and

" design flow" as specified in the above mentioned Technical Speci-fications. Investigations into this. interpretive problem are i

- underway and the resulting parameters that are to be used as testing and acceptance criterianwill.be documented in the testing procedures. . - .-. . . -

Acceptance of the retest, relating.to-velocity and flow, per-formed on January 14, 1981 was. based-cn:present system performance >

-- compared"to previous systemnperformance.:(i-e v no performance .

degradation). ,


= - -

In addition, it should be noted that the system is being evaluated'in accordance with NUREG-0737, Item III.D.3.'4..

s, .m,

. esp., -

~.e a e er 4,e* e e.sm..o s d M' %GN' y

= F peWse .Wes% em er Mh + "

n - --n-~