ML18136A465: Difference between revisions

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{{#Wiki_filter:NP._C_.fORM.36.6 (7-77) . U.S. NUCLEAR REGULATORY COMMISSION e LICENSEE EVENT REPORT -* co NTR O L BLOCK: LI --'----'--~--"'---'---'I 8 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) I VI A I s I p I s I 1 101 ° I O I -I O I O I O IO, IO I-IO IO 101 41 lj 11 11 1101 I I G) 7 S 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T ITEJ 7 8  
{{#Wiki_filter:-*
~©I O I 5 I O I O I O I 2 I 8 I O 101 11 11 11 71 11 9 J@ll 11 J 2 J 1 J 1 19 IG) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
NP._C_.fORM.36.6                                                                                                                   U.S. NUCLEAR REGULATORY COMMISSION (7-77)        .
I 1fuile reviewing Liquid Waste Release forms, it was determined that on 11/17 /79, a release was made which contained isotope activity summations greater than l.SE-03 [ilTI uCi/cc (actual summation
e           LICENSEE EVENT REPORT co NTR O L   BLOCK:         LI 1
: 1. 60E-03 uCi/cc). The Liquid Haste Radiation Monitor did _[]:II) J :ri()t __ alarm high and trip the release valve as re_qu_ired
                                                --'----'--~--"'---'---'I 6
_by Technical Specifications l 3.7.E. Since the releases did not exceed the limits allowed by Tech. Spec. 3.11.A.(2)
8                 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I and 10CFR20 App. B, the health and safety of the public were not affected.
~
This [Q]IJ event is reportable per Tech. Spec. 6.6.2.b.(4).
7        S I VI A I s I p I s I 1101 9        LICENSEE CODE              14    15
7 8 9 7 8 SYSTEM CODE [ MJ AJ@ 9 10 CAUSE CAUSE CODE SUBCODE COMPOc!ENT CODE LI@~@ I z I z I z I z I z I z 18 11 l::=J 12 13 SEQUENTIAL REPORT NO. I o I 3 J 11 18 OCCURRENCE CODE q 3j COMP. SUSCODE ~@) 19 REPORT TYPE LB VALVE SUBCODE ~@ 20 REVISION NO. L~ 80 Q LEf1/RO CVENTYEAR REPORT I 7 J 9 J NUMBER 21 22 ACTION FUTURE TAKEN ACTION EFFECT ON PLANT 23 24 26 27 28 SHUTDOWN Q ATTACHMENT METHOD HOURS \.:2. SUBMITTED 29 30 NPRD-4 FORM SUB. 31 PRIME COMP. SUPPL! ER 32 COMPONENT MANUFACTURER u@L:J@ Li@ ~ 1 °1 °1 °1 °1 u@ 33 34 35 36 3 7 40 4 1 LJ LJ@ I z 1 9 I 9 ! 91@ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 42 43 44 I The Liquid Waste Radiation Monitor, on high activity ( 1. SE-03 (uCi/cc), provides QJJJ a trip** signal to the Liquid Waste Release valve. Since the monitor can be calibrated
                                                                ° I OI - I         O I OI OIO, IO I- IO IO 101 41 LICENSE NUMBER                    25      26 lj   11 11 1101 I I G)
[III] to one isotope only, the administrative control disallows any releases with activity summations greater than l.SE-03 uCi/cc. Personnel have been instructed to use care [[ill in filling out release forms. 7 8 9 FACILITY '3Q\ STATUS % POW=R OTHER STATUS V METHOD OF 47 80 ITE] ~@ ..__l.._J
LICENSE TYPE         30   57 CAT 58 CON'T ITEJ 7         8
_O ..... !___,Oj@j Unit 2 Defueled DISCOVERY.
:~~~~~      ~©I OI 5 I OI O I OI 2 I 8 I O101 11 11 11 71 60            61            DOCKET NUMBER                  68    69        EVENT DATE 11 9   J@ll 11 74      75 J 2   J REPORT DATE 1 J 1 19 IG) 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
DISCOVERY DESCRIPTION LJ@._J _R_e_v_i_e_w_o_f_f_o_r_m_s_.
I 1fuile       reviewing Liquid Waste Release forms, it was determined that on 11/17 /79, a release was made which contained isotope activity summations greater than l.SE-03
______ --'-------'
[ilTI             uCi/cc (actual summation 1. 60E-03 uCi/cc).                                             The Liquid Haste Radiation Monitor did                                       l
8 9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY G:TIJ @) [2_j@-' __ N_A _____ ___ 7 8 9 10 11 7 45 46 80 44 NA LOCATION OF RELEASE @ 44 45 80 PERSONNEL EXPOSURES r::;;., NUMBER TYPE .DESCRIPTION~
_[]:II) J :ri()t__ alarm high and trip the release valve as re_qu_ired _by Technical Specifications 3.7.E.         Since the releases did not exceed the limits allowed by Tech. Spec. 3.11.A.(2)                                                                       I
LITI , a I o' OJu@.__ __ N_A _____________________
~                and 10CFR20 App. B, the health and safety of the public were not affected.                                                                             This
___. 8 9 11 12 13 PERSONNEL INJURIES © NUMBER DESCRIPTION 41 80 01 0 IO I~ A s 9 11 ... ,2-----------------------------------------~so LOSS OF OR DAMAGE TO FACILITY '4:i\ TYPE DESCRIPTION ~Gv~I __ N_A ____________________________
[Q]IJ             event is reportable per Tech. Spec. 6.6.2.b.(4).
____. 7 8 9 10 so ISSU:~BLl~;;CRIPTION@
7         8 9                                                                                                                                                                           80 SYSTEM               CAUSE             CAUSE                                                     COMP.          VALVE CODE                CODE           SUBCODE                 COMPOc!ENT CODE                   SUSCODE          SUBCODE
0 , NRC USE ONL y " ~I Q_ ct\A',?, 01 11 I OJ l!:Jei,___N_A
~8 7
____________
[ MJ AJ@
9_sv_:v_-___ ,--__ I I I I II I I I I I I 8 a 10 GS 69 80*;;; o*
9            10 LI@~@
e ATTACHMENT (PAGE 1 OF 1) SURRY POI.JER STATION, UNIT 1 DOCKET NO: 50-280 REPORT NO: 79-031/03X-l EVENT DATE: 11 /1 7 /79 (UPDATED REPORT) TITLE OF EVENT: Liquid Waste Release 1. DESCRIPTION OF EVENT: -* While reviewing Liquid Haste Release forms, it was determined that on 11/17/79, a release was made which contained isotope activity summations greater than 1. SE-03 uCi/cc. The Liquid Waste Radiation monitor did not alarm high and trip the release valve as required by Technical Specification
11                12 I z I z I z I z I z I z 18 ~@) ~@
: 3. 7.E. A release rate of 48 gpm was experienced over a period of 60 minutes. 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS: The Liquid Waste Radiation monitor, on high activity (1. SE-03 uCi/cc), provides a trip signal to the Liquid Waste Release valve. Since the monitor can be calibrated to one
13                            18          19              20 SEQUENTIAL                        OCCURRENCE            REPORT                        REVISION Q       LEf1/RO CVENTYEAR                                         REPORT NO.                            CODE                TYPE                          NO.
* isotope only, administrative control disallows any releases which contain activity summations greater than 1. SE-03 uCi/cc. The precalculations before release were done twice by two different individuals and both calculations were in error. Since the release did not exceed the lirni ts allowed by Technical Specification 3.11.A. 2 and 10 CFR 20, App. B, the health and safety of the public were not affected.
                ~      REPORT NUMBER I   7J 9 J           l::=J             I oI    3J  11                          q    3j          LB                            L~
: 3. CAUSE: A personnel error caused this event. 4. IMMEDIATE CORRECTIVE ACTION: A check of the waste releases was done for the month of November, to verify compliance with 10 CFR 20, App. B. 5. SUBSEQUENT CORRECTIVE ACTION: Personnel were instructed to use more care in filling out release forms. 6. ACTIONS TAKEN TO PREVENT RECURRENCE:
21           22         23               24           26       27             28       29          30              31          32 ACTION FUTURE                      EFFECT          SHUTDOWN                             Q       ATTACHMENT         NPRD-4        PRIME COMP.              COMPONENT TAKEN      ACTION              ON PLANT          METHOD                     HOURS   \.:2. SUBMITTED       FORM SUB.         SUPPL! ER             MANUFACTURER u@L:J@
33          34 Li@
35
                                                                    ~ 1 °1 °1 °1 °1 u@ LJ LJ@
36                37                    40    41 I z19I    9 ! 91@
42                43              44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                                                                                                               47 I The     Liquid Waste Radiation Monitor, on high activity ( 1. SE-03 (uCi/cc), provides QJJJ             a trip** signal to the Liquid Waste Release valve.                                                 Since the monitor can be calibrated
[III]             to one isotope only, the administrative control disallows any releases with activity summations greater than l.SE-03 uCi/cc.                                           Personnel have been instructed to use care
[[ill             in filling out release forms.
7         8   9                                                                                                                                                                       80 FACILITY                                                                 '3Q\     METHOD OF                                                            ~
STATUS               % POW=R                         OTHER STATUS       V         DISCOVERY.                            DISCOVERY DESCRIPTION ITE] ~@                       ..__l.._J_O.....!___,Oj@j Unit 2 Defueled                             LJ@._J_R_e_v_i_e_w_o_f_f_o_r_m_s_._ _ _ _ _ _--'-------'
7        8   9               10                 12     13                                 44    45          46                                                                      80 ACTIVITY       CONTENT                                                   ~
RELEASED       OF RELEASE                   AMOUNT OF ACTIVITY                                                         LOCATION OF RELEASE          @
G:TIJ         ~        @) [2_j@-'__N_A_ _ _ _ ____                                                                  NA 7       8     9             10             11                                             44           45                                                                           80 PERSONNEL EXPOSURES                               r::;;.,
NUMBER         ~ TYPE             .DESCRIPTION~
LITI , a I o' OJu@.____N_A________________________.
8   9                 11 PERSONNEL INJURIES NUMBER 12           13 DESCRIPTION 41
                                                          ©                                                                                                                           80
~
s    9 01 0IO I~ ,2-----------------------------------------~so 11      ...
A LOSS OF OR DAMAGE TO FACILITY               '4:i\
TYPE         DESCRIPTION                   ~
~            ~Gv~I__N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____.
7       89                10                                                                                                                                                         so
~
ISSU:~BLl~;;CRIPTION@
                      ~I 0 ~~            ,                         NRC USE ONL y           "
~             l!:Jei,___N_A            _ _ _ _ _ _ _ _ _ _ _ _9_sv_:v_-_                              Q_ ct\A',?, 01
_ _, - - _ _
11                    I I I I II I I I I I I I ~        OJ 8   a           10                                                                                                                     GS   69                           80*;;;
o*
 
ATTACHMENT (PAGE 1 OF 1) e SURRY POI.JER STATION, UNIT 1 (UPDATED REPORT)
                                                            -*
DOCKET NO:   50-280 REPORT NO:   79-031/03X-l EVENT DATE:   11 /1 7 /79 TITLE OF EVENT:       Liquid Waste Release
: 1. DESCRIPTION OF EVENT:
While reviewing Liquid Haste Release forms, it was determined that on 11/17/79, a release was made which contained isotope activity summations greater than
: 1. SE-03 uCi/cc.       The Liquid Waste Radiation monitor did not alarm high and trip the release valve as required by Technical Specification 3. 7.E.       A release rate of 48 gpm was experienced over a period of 60 minutes.
: 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:
The Liquid Waste Radiation monitor, on high activity (1. SE-03 uCi/cc),
provides a trip signal to the Liquid Waste Release valve.             Since the monitor can be calibrated to one
* isotope only, administrative control disallows any releases which contain activity summations greater than
: 1. SE-03 uCi/cc.       The precalculations before release were done twice by two different individuals and both calculations were in error. Since the release did not exceed the lirni ts allowed by Technical Specification 3.11.A. 2 and 10 CFR 20, App. B, the health and safety of the public were not affected.
: 3. CAUSE:
A personnel error caused this event.
: 4. IMMEDIATE CORRECTIVE ACTION:
A check of the waste releases was done for             the month of November, to verify compliance with 10 CFR 20, App.         B.
: 5. SUBSEQUENT CORRECTIVE ACTION:
Personnel   were     instructed   to use more care in filling out release forms.
: 6. ACTIONS TAKEN TO PREVENT RECURRENCE:
No further corrective action will be required.
No further corrective action will be required.
: 7. GENERIC IMPLICATIONS:
: 7. GENERIC IMPLICATIONS:
None.}}
None.}}

Revision as of 04:02, 21 October 2019

Updated LER 79-031/03X-1:on 791117,while Reviewing Liquid Waste Release Forms,Discovered That Liquid Waste Monitor Did Not Alarm High & Trip Release Valve During 791117 Isotope Activity Release.Caused by Personnel Error
ML18136A465
Person / Time
Site: Surry Dominion icon.png
Issue date: 11/21/1979
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A464 List:
References
LER-79-031-03X, LER-79-31-3X, NUDOCS 8002070291
Download: ML18136A465 (2)


Text

{{#Wiki_filter:-* NP._C_.fORM.36.6 U.S. NUCLEAR REGULATORY COMMISSION (7-77) . e LICENSEE EVENT REPORT co NTR O L BLOCK: LI 1

                                                --'----'--~--"'---'---'I 6

8 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~

7 S I VI A I s I p I s I 1101 9 LICENSEE CODE 14 15

                                                                ° I OI - I         O  I OI OIO, IO I- IO IO 101 41 LICENSE NUMBER                     25       26 lj   11 11 1101 I I G)

LICENSE TYPE 30 57 CAT 58 CON'T ITEJ 7 8

~~~~~ ~©I OI 5 I OI O I OI 2 I 8 I O101 11 11 11 71 60 61 DOCKET NUMBER 68 69 EVENT DATE 11 9 J@ll 11 74 75 J 2 J REPORT DATE 1 J 1 19 IG) 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I 1fuile reviewing Liquid Waste Release forms, it was determined that on 11/17 /79, a release was made which contained isotope activity summations greater than l.SE-03 [ilTI uCi/cc (actual summation 1. 60E-03 uCi/cc). The Liquid Haste Radiation Monitor did l _[]:II) J :ri()t__ alarm high and trip the release valve as re_qu_ired _by Technical Specifications 3.7.E. Since the releases did not exceed the limits allowed by Tech. Spec. 3.11.A.(2) I

~                 and 10CFR20 App. B, the health and safety of the public were not affected.                                                                             This

[Q]IJ event is reportable per Tech. Spec. 6.6.2.b.(4). 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPOc!ENT CODE SUSCODE SUBCODE

~8 7

[ MJ AJ@ 9 10 LI@~@ 11 12 I z I z I z I z I z I z 18 ~@) ~@ 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q LEf1/RO CVENTYEAR REPORT NO. CODE TYPE NO.

               ~      REPORT NUMBER I    7J 9 J            l::=J              I oI    3J   11                           q     3j          LB                             L~

21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN Q ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS \.:2. SUBMITTED FORM SUB. SUPPL! ER MANUFACTURER u@L:J@ 33 34 Li@ 35

                                                                   ~ 1 °1 °1 °1 °1 u@ LJ LJ@

36 37 40 41 I z19I 9 ! 91@ 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 47 I The Liquid Waste Radiation Monitor, on high activity ( 1. SE-03 (uCi/cc), provides QJJJ a trip** signal to the Liquid Waste Release valve. Since the monitor can be calibrated [III] to one isotope only, the administrative control disallows any releases with activity summations greater than l.SE-03 uCi/cc. Personnel have been instructed to use care [[ill in filling out release forms. 7 8 9 80 FACILITY '3Q\ METHOD OF ~ STATUS  % POW=R OTHER STATUS V DISCOVERY. DISCOVERY DESCRIPTION ITE] ~@ ..__l.._J_O.....!___,Oj@j Unit 2 Defueled LJ@._J_R_e_v_i_e_w_o_f_f_o_r_m_s_._ _ _ _ _ _--'-------' 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT ~ RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE @ G:TIJ ~ @) [2_j@-'__N_A_ _ _ _ ____ NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES r::;;., NUMBER ~ TYPE .DESCRIPTION~ LITI , a I o' OJu@.____N_A________________________. 8 9 11 PERSONNEL INJURIES NUMBER 12 13 DESCRIPTION 41

                                                         ©                                                                                                                            80

~ s 9 01 0IO I~ ,2-----------------------------------------~so 11 ... A LOSS OF OR DAMAGE TO FACILITY '4:i\ TYPE DESCRIPTION ~ ~ ~Gv~I__N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____. 7 89 10 so ~ ISSU:~BLl~;;CRIPTION@

                     ~I 0 ~~            ,                         NRC USE ONL y           "

~ l!:Jei,___N_A _ _ _ _ _ _ _ _ _ _ _ _9_sv_:v_-_ Q_ ct\A',?, 01 _ _, - - _ _ 11 I I I I II I I I I I I I ~ OJ 8 a 10 GS 69 80*;;; o*

ATTACHMENT (PAGE 1 OF 1) e SURRY POI.JER STATION, UNIT 1 (UPDATED REPORT)

                                                            -*

DOCKET NO: 50-280 REPORT NO: 79-031/03X-l EVENT DATE: 11 /1 7 /79 TITLE OF EVENT: Liquid Waste Release

1. DESCRIPTION OF EVENT:

While reviewing Liquid Haste Release forms, it was determined that on 11/17/79, a release was made which contained isotope activity summations greater than

1. SE-03 uCi/cc. The Liquid Waste Radiation monitor did not alarm high and trip the release valve as required by Technical Specification 3. 7.E. A release rate of 48 gpm was experienced over a period of 60 minutes.
2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:

The Liquid Waste Radiation monitor, on high activity (1. SE-03 uCi/cc), provides a trip signal to the Liquid Waste Release valve. Since the monitor can be calibrated to one

  • isotope only, administrative control disallows any releases which contain activity summations greater than
1. SE-03 uCi/cc. The precalculations before release were done twice by two different individuals and both calculations were in error. Since the release did not exceed the lirni ts allowed by Technical Specification 3.11.A. 2 and 10 CFR 20, App. B, the health and safety of the public were not affected.
3. CAUSE:

A personnel error caused this event.

4. IMMEDIATE CORRECTIVE ACTION:

A check of the waste releases was done for the month of November, to verify compliance with 10 CFR 20, App. B.

5. SUBSEQUENT CORRECTIVE ACTION:

Personnel were instructed to use more care in filling out release forms.

6. ACTIONS TAKEN TO PREVENT RECURRENCE:

No further corrective action will be required.

7. GENERIC IMPLICATIONS:

None.}}