ML20107H572

From kanterella
Jump to navigation Jump to search
Forwards Abnormal Occurence Report 50-219/74/31 in Compliance W/Paragraph 1.15B of TS
ML20107H572
Person / Time
Site: Oyster Creek
Issue date: 05/29/1974
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To: Anthony Giambusso
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 NUDOCS 9604240166
Download: ML20107H572 (1)
v • d • e


Text

.

. ~......, - -

_~ y g

a cf=3 ki

s m

ersey Centra Power & Lig7t Company * ~ lI

%)

MADISON AVENUE AT PUNCH BOWL ROAD

  • MORRISTOWN, N. J. 07900
  • 201-539-0111 NamenROfTNL

[yjjj,*, Public Utilities Cordoration Generat muu May 29, 1974

. p:. ~-*~ ~~

r*1 l'^'\\.,,.$

,~~t:!r m.

. y..,'

. ~t i c,

...'.'4',.

i,,

3

f.

I C "

Mr. A. Gian:busso Deputy Director for Reactor Projects f.'

id / ? ' q g

Directorate of Licensin,"

United States Atomic Energy Cor.rission Washing, ton, D. C. 20545 N ',

Dear Mz. Gia:

ibusso:

Subjed.

Gy>Lv4 Creek Suttlun Docket No. 50-219 Abnormal Occurrence Report No. 50-219/*i4/31 The purpose of this letter is to forward to ycu the attachc4 Abnormal Occurrence Report in compliance with paragraph 1.153 of the Technical Specifications.

Enclosed are forty copics of this submittal.

Very truly yours,

,)

.;c ?:.,1<a.; J ^ i3.f Cn W Donald A. Ross Manager, Nuclear Generating Stations CS Enclosures cc:

Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations, Region I l] [';.D ' )

~

a 9604240166 960213 PDR FOIA DEK0K95--258 P,DR

I i

(_)

i 1

l

~

OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/74/31 Report Date May 29, 1974 Occurrence Date May 19, 1974 Identification of Occurrence Inoperability of two Bergen-Paterson hydraulic shock and sway arrestors located on Core Spray System II and on Containment Spray System I in the reactor build-ing. This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15D.

Conditiens Priot _'to_ Occurrence 1hc plant was shat down for refueling.

1 l

Description of Occurrence During an inspection of the snubbers in the reactor building, two inoperable units and five leaking units, all Bergen-Paterson Type HSSA-10, were found.

The defective snubbers were identified as follows 4

Unit System Condition Elevation 477287 Containment Spray I Inoperable

-19' 469873 Containment Spray II Leaking 23' 469903 Shutdown Cooling Leaking 51' 469846 Core Spray II Leaking 75'

)

469855 Core Spray II Inoperable 75' 487465 B Emergency Cond.

Leaking 75' 477170 A Emergency Cond.

Leaking 75' 1

Apparent Cause of Occurrence The cause of this occurrence is attributed to seal failure.

The inoperability of the snubbers was due to a loss of the hydraulic fluid. The core spray unit had never been rebuilt with ethylene propylene (EP) seals.

The containment spray 6

() l Q) ~A ' "-u

~,

j 4

. _ =

l

{}

?. a r

i l

t i

i i

l Abnormal Occurrence No.'50-219/74/31

~ Page~2

)

unit had been partia!11y rebuilt with EP material following an inspection on

~

February 28, 1974.

The particular snubber series involved cannot be fully re-built with EP material. Several seals peculiar to the series are no longer fabricated by the snubber manufacturer.

Analysis of Occurrence, The safety significance of this occurrence was a partial loss of the seismic restraining ability for the affected 'systers.

Had the plant suffered a design basis. earthquake, the probability that these systems' would have suffered structural damage was increased.

Corrective Action The immediate corrective action was to replace the seven faulty units with-units which are equipped with EP seals and have been pressure tested to 4000 psig.

The monthly inspection of all hydraulic snubbers located outside of'the primary containment will be adhered to regardless of plant status. Those units which require maintenance and a're found to contain other than EP seals will, to the extent possible,' be replaced with units having all EP seals.

Eventually, any unit which cannot be fully equipped with EP seals will be retired.

The Generation Engineering Department is currently evaluating mechanical snubbers as possibic replacements for hydraulic snubbers.

Failure Data Manufacturer:

Bergen-Paterson T)Te:

ilSSA-10

>+=q 6

4

g b.g a'

(. j

'.. )

F

)

i.

1 r.,.

1;3;.

- i,v

,r..

4 i w

-e

. g., ;..

N s.

6 i

To:'

James:P. O'Reilly

~

Directorate,of Regulatory. Operations

- segion 4 '

~

631.ParkyAvenue

n s

4 l

King of' Prussia, Pennsylvania 194062 1

4 f

4 3

1 1

+

l b

4 i

-Free:+

Jersey.,Contral' Power 4 Light'Gespany 1

. Oyster' Crook Nuclear, Generating Station,.. Docket #506219'

~

s-P6rked'.. River, NerJersey.

08751:

w 1

N,.$..,

i l

4

.,1 i

}

Subject:

Abnormal. Occurrence Report No. 50-219/?'4/$2 i

i j

1he followingfis a preliminary report.being submitted l

J.,

J in compli'ance with the Technical Specifications 1

t j ;

paragraph 6.6.2.

i

'* Preliminary Approval:

i 4

+

F i

Add M22/74 i

r

[J. T. Cash 11,.Jr.

Date i.

l

' cos. Mr. A. Claubusso:

4 4

g e.-

3 y

f b

m m A) / n e /, 'i l hQ gv u% v 5 v s im

I a

Initi'al Telephone Date of 5

R* Port Date:

5/22/74 Occurrence:

5/21/74 4

Initial Written Time of

}

5/22/74

-Occurrence:

1100 Report Date:

OYSTE'. REEK NUCLEAR GENERATING STATION IuRKED R1VER, NEW JERSEY 08731

.AbdorsalOccurrence i

Report No. 50-219/74/1

'IDE!EIP! CATION Violation of the Technical Specifications, paragraph' _N/A _,

OF OCCURRENCE:

.It was observed.that the R90D core spray booster. pump pressure switch failed in the pomissive position. 1his created a condi-tion whereby had core spray booster pump NZ038 failed to start or failed to establish a discharge pressure of 230:psig its.

associated redundent booster pump, NZO3D, would not have started I

autosatically.

This avent is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph.

1.15D CONDITIONS PRIOR '

TO OCCURRENCE:

Steady State' Power Routine Shutdown Hot Standby operation Cold Shutdown Load Changes 'During X

Refueling Shutdown Routine Power'0peration l

Routino Startup Other (Specify)

Operation i

l

' Reactor mode switch in REFUEL with the reactor cavity flooded.

I 1

DESCRIPTION While perfoming the ennual surveillance test of the auto-0F' OCCURRENCE:

depressurisation initiation logic with the System I core spray system disabled, it was observed that :s relay, IK114D in the System II core spray booster. pump initiation logic, was in the

1. energized position... An investigation' indicated that_ the System!!!,,

, core spray booster pump discharge pressure swit&,.RV400; which actuates thin ralar was in'the closed position. The switch

g......,. n..

j J

t c

normally closes [when,the booster pump.'dischargs pressure comes

?

fi E

up to at least 230 psis, thereby energising the 1K114D relay, b!'

Normally closed contacts from the 1K114D miay act is conjimetion s

f with the IK1145 niay and RV408.passure switdi to trip the i

k N2055 booster pump and start the.redisidant NIO50 booster pump j

if the pung does'not como up to.230 psig.after five seconds.

Failure of the switch in the closed position created 'a condition f

whenby N2038 would not: have. tripped if.it failed to start or I

establibh sufficiont' discharge pressure and pump N203D would not i

h' ave started sinoshthe !!ogic was fai-led'i' the "seti'efied" n

. tr ~

t

[

positioni

' b,,

6.

o t

b It should be notodithat' this failure occurred st4 sequent to the l

x,prill 4.2 plant shutdown.since aux l ary contacts ~ from this relay A

ii I

[

,s

' actuate an alara in'the' station control room which was. rat ob.

i served during power operation. When the: plant is in theicol'd 4

i shutdown condition, this alarm is norma 11y on because"it is a I

)f houmon alarm for the 285 psig permissive switch, RN17 for. the j'

care spray parallel injection valves. Since the resocom,was l;

fully dopnssurized.this switch:was closed and the starts was on.

!I r

.i APPARENT CAUSE Design Procedure i[

OF OCCURRENGs Manufacture Unusual Service Condition il Installation /

~~ Inc.. Environmental 1

. Construction 00sponent Failum-ji Operster Other (Specify)-

I J';

lhe cause of this occurunce is presently under investigation.

'u

((

J4.'

}

. t 1) i l

t-u e

l

)

jy

. f '-), ; t

,c".-

ANALYSIS OF

<%e safety sipiificance of this event is considered to be OCCURRENG:

minimalt since the reactor was igithe shutdown condition with the-

,o cavity' flooded'. Had a IDCA'.ocoutred ih.this condition, the

(.f System.II'. com spray pumps.Which operated satisfactorily would I

.have delivered core spray flow st rated' capacity but at a lower 6

discharge pressure, assuming the booster pump failed co s' art.

t anasumannus h,*m e ntw w nwr # " *

' };

00RRBCTIVE 1he 16K114D relay was placed in the doenergized' position which

-ACTION:

- [

, is the4Eipped condition.- In this configuration, RV40B would-y

.have acted to sense improper booster pump discharge pressure and' started the redundant pump.

i-i P

p FA11MRB DATA:

WR001D Pressure Switdi Type -DAN 45-156 R21E y

=

f a

b 1

t t

i I

1

t
[
u.F.

p 5

f U

e h

7 l[

ar,',

t

+-

.r d I>

k Date:[

_5/28'/74 Propand by:

V

'~

c g:r,

,[

lc) '

di i 4

-~

  • ~-

,,

Retrieved from "https://kanterella.com/w/index.php?title=ML20107H572&oldid=4298171"