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OYSTER CREEK                                                NUCLEAR GENERATING STATION g u gf g 5j yj                                              (609) 693-1951 P.O. BOX 388
OYSTER CREEK                                                NUCLEAR GENERATING STATION g u gf g 5j yj                                              (609) 693-1951 P.O. BOX 388
* FORKED RIVER
* FORKED RIVER
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* 08731 w.b. ua s -                                                                                                                                              .
* 08731 w.b. ua s -                                                                                                                                              .
April 27, 1981
April 27, 1981
                                                                                                                                            -
                                                                                                                                       @. ~      4 Mr. Boyce H. Grier, Director Office of Inspection and Enforcanent Region I
                                                                                                                                       @. ~      4 Mr. Boyce H. Grier, Director Office of Inspection and Enforcanent Region I
                                                                                                                                   '(\ /[' [
                                                                                                                                   '(\ /[' [
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==Dear Mr. Grier:==
==Dear Mr. Grier:==
                                                                              '<
4        sp
4        sp


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Office of Nuclear Reactor Regulations United States Nuclear Regulatory Camission Washington, D. C. 20555 Director NBC Resident Ins g-W (1)
Office of Nuclear Reactor Regulations United States Nuclear Regulatory Camission Washington, D. C. 20555 Director NBC Resident Ins g-W (1)
Oyster Creek N el a r Generating Station Forked River, N. J.
Oyster Creek N el a r Generating Station Forked River, N. J.
Ob 3 'l 8105010Y/o
Ob 3 'l 8105010Y/o S
      - . _ . _ . - - - - . - .
 
S
o      .
                                                        . - _ _ .            .
OYS'IER CREEK NUCLEAR GDERATING STATION Ebzked River, New Jersey 08731 Nontoutine Envitmo.iutal Operating Report No. 50-219/81-1 Report Date April 27, 1981 Occtu. ins Date April 15 & 16, 1981 Identification of Occtu.imm Excaading a limiting cx:niition as dafined in the Envircomental Tachnical Speci-fication, Paragraph 2.1.4.3, when within a span of two days, two indivichm1                          ~
_ _ - _ _ - _ _ _ _ . _ - - _ - .- -                        .__  - _ -
* o      .
        -
    .
OYS'IER CREEK NUCLEAR GDERATING STATION Ebzked River, New Jersey 08731 Nontoutine Envitmo.iutal Operating Report No. 50-219/81-1 Report Date
                                                                                                                      .
April 27, 1981 Occtu. ins Date April 15 & 16, 1981 Identification of Occtu.imm Excaading a limiting cx:niition as dafined in the Envircomental Tachnical Speci-fication, Paragraph 2.1.4.3, when within a span of two days, two indivichm1                          ~
dilution ptmp trips occurred in which the reserve ptmp oculd not be started within the required 15 minutes. Dur ng each occurrence, the station intake canal tm-reture was below 60.00F.
dilution ptmp trips occurred in which the reserve ptmp oculd not be started within the required 15 minutes. Dur ng each occurrence, the station intake canal tm-reture was below 60.00F.
This event is considered to be a ncteoutine envircnnental operating report as dafined in the Technical Snac4 fica *4rms, Amandix          "B",      paragraph 5.6.2.
This event is considered to be a ncteoutine envircnnental operating report as dafined in the Technical Snac4 fica *4rms, Amandix          "B",      paragraph 5.6.2.
Line 64: Line 53:
na= -intion of occuu.ma Dilution Ptmp 1-3 was manually triW at 0109 on April 15, 1981. 'Ihe ptmp i            shutdown was necessitated by low gear box oil pressure. An 4-ad< ate attspt i
na= -intion of occuu.ma Dilution Ptmp 1-3 was manually triW at 0109 on April 15, 1981. 'Ihe ptmp i            shutdown was necessitated by low gear box oil pressure. An 4-ad< ate attspt i
was made to start Dilution Ptmp 1-1, the reserve ptmp, but this failed due to a faulty seal water flow switch. Ctmpers were plaM around the flow switch and Dilution Ptmp 1-1 was started at 0545. During this occurrence, the total time of insufficient dilution ptrp operaticn was 4 hours and 36 minutes and the time of ml4ance was 4 hours and 21 minutes. The following day, April 16, 1981, the seal water suction inlet plugged with grass. Dilution Ptmps 1-1 and 1-2 tripped at 1008. Operators cleaned the inlet and started dilut' m puup 1-1 at 1020. Dilution Ptmp 1-2 was started two minutes later, but an asso-lated transient tripped ptmp 1-1. A pressure switch across the lube oil cxcler was l            reset and Dilution Ptmp 1-1 was restarted at 1042. The time of rs-dying di eharge was 5 minutes.
was made to start Dilution Ptmp 1-1, the reserve ptmp, but this failed due to a faulty seal water flow switch. Ctmpers were plaM around the flow switch and Dilution Ptmp 1-1 was started at 0545. During this occurrence, the total time of insufficient dilution ptrp operaticn was 4 hours and 36 minutes and the time of ml4ance was 4 hours and 21 minutes. The following day, April 16, 1981, the seal water suction inlet plugged with grass. Dilution Ptmps 1-1 and 1-2 tripped at 1008. Operators cleaned the inlet and started dilut' m puup 1-1 at 1020. Dilution Ptmp 1-2 was started two minutes later, but an asso-lated transient tripped ptmp 1-1. A pressure switch across the lube oil cxcler was l            reset and Dilution Ptmp 1-1 was restarted at 1042. The time of rs-dying di eharge was 5 minutes.
        .
                    -
                         .c .    , -s --
                         .c .    , -s --
: w.                  , _ . , ,      , _ , _ , , _ , - - _ . - . . . - _
: w.                  , _ . , ,      , _ , _ , , _ , - - _ . - . . . - _


                                                                                              ..
Ncmroutine Enviu-- --Fa1 Operating Report No. 50-219/81-1                          Page 2 Apparent Cause of Occe41ce Ccr.ponent Failure Analysis of Occurrence Ccx*4rmia operation of the two dilution puups when the intake water tenperature is below 60.0 F during plant operation will reduce the area of ai.Lition and thereby minimize a build-up in the fish standing stock in the discharge canal.
          '
6 At the time of the pung trips, the reactor l power level was approximately 60% of rated power. 'Ihe heat discharge to the diacharge canal was, therefore, greatly reduced. Failure to operate the dilution punps in accordux:e with Tehnical spe4 fication 2.1.4.3 had minimal, if any, adverse biological effects on aquatic organisms.
        .  .
Ncmroutine Enviu-- --Fa1 Operating Report No. 50-219/81-1                          Page 2 Apparent Cause of Occe41ce Ccr.ponent Failure
                                                                                                          .
Analysis of Occurrence Ccx*4rmia operation of the two dilution puups when the intake water tenperature is below 60.0 F during plant operation will reduce the area of ai.Lition and thereby minimize a build-up in the fish standing stock in the discharge canal.
6 At the time of the pung trips, the reactor l power level was approximately 60% of rated power. 'Ihe heat discharge to the diacharge canal was, therefore, greatly reduced. Failure to operate the dilution punps in accordux:e with Tehnical spe4 fication 2.1.4.3 had minimal, if any, adverse biological effects on aquatic
,
organisms.
I ,
I ,
Oorrective Action                                                          i i
Oorrective Action                                                          i i
r_n==44=te cxh.loct.ive actica cxmsisted of j == ring the flow switch on Dilution Pung 1-1 and restarting the pmp at 0545 on April 15, 1981. On April 16, 4wn=94 ate corrective-action consisted of resetting the lube oil cooler switch on 1-1 dilution punp and restarting the pmp at 1042.
r_n==44=te cxh.loct.ive actica cxmsisted of j == ring the flow switch on Dilution Pung 1-1 and restarting the pmp at 0545 on April 15, 1981. On April 16, 4wn=94 ate corrective-action consisted of resetting the lube oil cooler switch on 1-1 dilution punp and restarting the pmp at 1042.
:
Mxlifications to the cooling and seal water systems for the dilution pungs are presently in the design evaluation stage.
Mxlifications to the cooling and seal water systems for the dilution pungs are presently in the design evaluation stage.
l
l I
                                                                                                        .
I
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                                                                                           ?
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     ..r.        --            ._ ._  , - . . . . . . . . . _ . . - . . , - . _ _ . . . .
     ..r.        --            ._ ._  , - . . . . . . . . . _ . . - . . , - . _ _ . . . .


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                                                                                                                                                                                                 ~
7        8                                                                                                                                                                                        R EVISION SEOVENTIAL                                      OCCURRENCE                REPORT
7        8                                                                                                                                                                                        R EVISION SEOVENTIAL                                      OCCURRENCE                REPORT REPORT NO.                                          CODE                    TYPE                            N O.
                                      ,,,,
REPORT NO.                                          CODE                    TYPE                            N O.
EVENT YEAR O as=R*RO LE l#1/I                      L-J                10101/I26 24 L'J 27 l
EVENT YEAR O as=R*RO LE l#1/I                      L-J                10101/I26 24 L'J 27 l
28 I    I 29 LJ 30 L-1 31 LJ 32
28 I    I 29 LJ 30 L-1 31 LJ 32
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li i s I LJ@ l                          1        I        l@l                                            i      I        l@l                                                                                  '
li i s I LJ@ l                          1        I        l@l                                            i      I        l@l                                                                                  '
ACTIVIT y CO TENT AMOUNT OF ACTIVITY                                                                          LOCATION OF RELEASE l              RELEASED OF RELEASE I                                                                                        I i
ACTIVIT y CO TENT AMOUNT OF ACTIVITY                                                                          LOCATION OF RELEASE l              RELEASED OF RELEASE I                                                                                        I i
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l LueJ 7      8 9 LJ@ LJ@l        10                11                                                    44                45                                                                                    80 PERSONNEL EXPOSURES NUU8ER                  TYPE l
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l      1 7        l      l      l    l                  hl DESCRIPTION PERSONNE L INJU IES NUVBE R                  DESCRIPTION I
l      1 7        l      l      l    l                  hl DESCRIPTION PERSONNE L INJU IES NUVBE R                  DESCRIPTION I
ITT l l              I      l    l@l12                                                                                                                                                                        80 7      8 9                    11 LOSS OF OR DAMAGE TO FACILITY h TYPE          DESCRIPTION                          %./
ITT l l              I      l    l@l12                                                                                                                                                                        80 7      8 9                    11 LOSS OF OR DAMAGE TO FACILITY h TYPE          DESCRIPTION                          %./
I iTTU 7      8 9 LJ@l          10
I iTTU 7      8 9 LJ@l          10 i      liiiiiiiiiiil:
* i      liiiiiiiiiiil:
L2 ts.l ISSUET@OESCRIPTION l              l 10 68 69                              80 = .
L2 ts.l ISSUET@OESCRIPTION l              l 10 68 69                              80 = .
7      8 9 PHONE:
7      8 9 PHONE:
NAME OF PREPARER
NAME OF PREPARER
_        -.        _                              -
                                                                                   - - - .      . _ , _                                    -      .              , _                                                  _ _ _ .}}
                                                                                   - - - .      . _ , _                                    -      .              , _                                                  _ _ _ .}}

Latest revision as of 03:26, 31 January 2020

RO 81-001:on 810415 & 16,two Dilution Pumps Tripped & Reserve Pump Would Not Start.Caused by Component Failure. Flow Switch Jumpered After First Event,Lube Oil Cooler Switch Reset After Second
ML19345H254
Person / Time
Site: Oyster Creek
Issue date: 04/27/1981
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-50-219-81-1, NUDOCS 8105010410
Download: ML19345H254 (4)


Text

.

OYSTER CREEK NUCLEAR GENERATING STATION g u gf g 5j yj (609) 693-1951 P.O. BOX 388

  • FORKED RIVER
  • 08731 w.b. ua s - .

April 27, 1981

@. ~ 4 Mr. Boyce H. Grier, Director Office of Inspection and Enforcanent Region I

'(\ /[' [

i {- \

United States Nuclear Regulatory Ccmnissicn 631 Park Avenue p AER.?0 /gg7'2

,3'2 LA King of Prussia, Pennsylvania 19406 u.s,kl,,g g h s J

Dear Mr. Grier:

4 sp

SUBJECT:

Oyster Creek Nuclear Generating Station *

(

Docket No. 50-219 Nonroutine Envi m mr.ad.al Operating Report No. 50-219/81-1 l

'Ihis letter forwards two copies of Nonrout:l e Envimmental Operating t

Report No. 50-219/81-1 in 714ance with parag2.J 5.6.2 of Appendix B to l the Technical F4 #4 catims.

Very truly yours,

. N-van R. F Jr.

Vice Preside 1t JCP&L ,

Director - Oyster Creek IRF:dh Encla.,sures cc: Director (17 copies)

Office of Nuclear Reactor Regulations United States Nuclear Regulatory Camission Washington, D. C. 20555 Director NBC Resident Ins g-W (1)

Oyster Creek N el a r Generating Station Forked River, N. J.

Ob 3 'l 8105010Y/o S

o .

OYS'IER CREEK NUCLEAR GDERATING STATION Ebzked River, New Jersey 08731 Nontoutine Envitmo.iutal Operating Report No. 50-219/81-1 Report Date April 27, 1981 Occtu. ins Date April 15 & 16, 1981 Identification of Occtu.imm Excaading a limiting cx:niition as dafined in the Envircomental Tachnical Speci-fication, Paragraph 2.1.4.3, when within a span of two days, two indivichm1 ~

dilution ptmp trips occurred in which the reserve ptmp oculd not be started within the required 15 minutes. Dur ng each occurrence, the station intake canal tm-reture was below 60.00F.

This event is considered to be a ncteoutine envircnnental operating report as dafined in the Technical Snac4 fica *4rms, Amandix "B", paragraph 5.6.2.

Conditic 1s Pricr to Occtu.rus Steady State Power Ptmp Trip No.1 Dilution Ptmp Flow: 5.20 ES GPM Circulating Water

. Ptmp Flow 3.45 E5 GPM Ptmp Trip No. 2 Dilution Ptmp Flow: 5.20 E5 GPM Circulating Water Ptmp Flow 2.30 E5 GPM l

na= -intion of occuu.ma Dilution Ptmp 1-3 was manually triW at 0109 on April 15, 1981. 'Ihe ptmp i shutdown was necessitated by low gear box oil pressure. An 4-ad< ate attspt i

was made to start Dilution Ptmp 1-1, the reserve ptmp, but this failed due to a faulty seal water flow switch. Ctmpers were plaM around the flow switch and Dilution Ptmp 1-1 was started at 0545. During this occurrence, the total time of insufficient dilution ptrp operaticn was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 36 minutes and the time of ml4ance was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 21 minutes. The following day, April 16, 1981, the seal water suction inlet plugged with grass. Dilution Ptmps 1-1 and 1-2 tripped at 1008. Operators cleaned the inlet and started dilut' m puup 1-1 at 1020. Dilution Ptmp 1-2 was started two minutes later, but an asso-lated transient tripped ptmp 1-1. A pressure switch across the lube oil cxcler was l reset and Dilution Ptmp 1-1 was restarted at 1042. The time of rs-dying di eharge was 5 minutes.

.c . , -s --

w. , _ . , , , _ , _ , , _ , - - _ . - . . . - _

Ncmroutine Enviu-- --Fa1 Operating Report No. 50-219/81-1 Page 2 Apparent Cause of Occe41ce Ccr.ponent Failure Analysis of Occurrence Ccx*4rmia operation of the two dilution puups when the intake water tenperature is below 60.0 F during plant operation will reduce the area of ai.Lition and thereby minimize a build-up in the fish standing stock in the discharge canal.

6 At the time of the pung trips, the reactor l power level was approximately 60% of rated power. 'Ihe heat discharge to the diacharge canal was, therefore, greatly reduced. Failure to operate the dilution punps in accordux:e with Tehnical spe4 fication 2.1.4.3 had minimal, if any, adverse biological effects on aquatic organisms.

I ,

Oorrective Action i i

r_n==44=te cxh.loct.ive actica cxmsisted of j == ring the flow switch on Dilution Pung 1-1 and restarting the pmp at 0545 on April 15, 1981. On April 16, 4wn=94 ate corrective-action consisted of resetting the lube oil cooler switch on 1-1 dilution punp and restarting the pmp at 1042.

Mxlifications to the cooling and seal water systems for the dilution pungs are presently in the design evaluation stage.

l I

?

..r. -- ._ ._ , - . . . . . . . . . _ . . - . . , - . _ _ . . . .

U. S. NUCLEA3 REIULATO.;Y COMMIS$10N '

NRC FORM 366 (7 77) ' '

  • LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

IO I l l I I I I I l@l15 i I I I I LICENSE NUM8E8 I I I I I l@l26 25 l I I I LICENSE TYPE JG l@l57 CAT i 68 I@

7 8 9 LICENSEE CODE 14 CON'T 7

0 1 8

$$l l@ld l81 Pl O l Olll I lT l@l 014 I I l8lIII l@l d l 4l2l#718'l/l@

60 61 DOCKET NUM8 ER 68 69 EVENT OATE 74 75 REPOR T OATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I .

L2 LJ l l

I O I31 l l

0 4 l l

10151 I l

10161 l l

10171 l I

10181 l 80 E CODE SUSC E COMPONENT CODE SU8 CODE SU E IBB I 9

I l@ U@ LJ@ l 10 ft 12 13 I I I I I l@ U@ LJ @

18 19 20

~

7 8 R EVISION SEOVENTIAL OCCURRENCE REPORT REPORT NO. CODE TYPE N O.

EVENT YEAR O as=R*RO LE l#1/I L-J 10101/I26 24 L'J 27 l

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