ML20010F851

From kanterella
Jump to navigation Jump to search
Forwards Summary of ECCS Outage Events in Response to TMI Item II.K.3.17.Review of LERs & ECCS Surveillance Performed to Obtain Outage Duration for 5-yr Period,Jan 1976 to Dec 1980
ML20010F851
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/04/1981
From: Hukill H
METROPOLITAN EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
References
TASK-2.K.3.17, TASK-TM L1L-243, NUDOCS 8109110456
Download: ML20010F851 (14)


Text

,

O Metropolitan Edison Company Post Office Box 480

~

g Middletown, Pennsylvania 17057 Writer's Direct Dial Nur"ber September 4, 1981 LlL-243 Office of Nuclear Reactor Regulation Attn:

John F. Stolz, Chief Operating Reactor Branch #4 U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating Licensing No. DPR-50 Docket No. 50-289 ECCS Outage Times (TI.K.3.17)

The enclosed document was prepared in response to TMI Action Plan Require-ment II.K.3.17 " Report of Outages of ECC Systems." A review of Licensee Event Reports (LER) and ECCS surveilences was performed to obtain outage durations for the 5 year period January 1976 through December 1980 for Three Mile Island Unit 1.

Cummulative outage times given are, in general, conservative since detailed records of ECCS outage times were not an in-tegral part of the Unit record.

ECCS system and general scope was ad-dressed in our submittal of April 9, 1981 (LlL-087). provides outage times for those components which directly affect system operability (which were repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). provides outage time for systems in which redundant components were available, components were l

out of service during outages when they were not required or components j

were operable but contained deficiencies requiring repair.

Further infor-mation concerning the description and the corrective action is contained in the referenced LER's.

Sincerely, l

"Y

[4rt I

H D. Hukili Director, TMI-l Enclosure cc:

B. H. Grier 09I L. Barrett 3

R. Jacobs 8109110456 810904

/

[

PDR ADOCK 05000289 P

PDR Metropolitan Edison Company is a Member of 'he General Puble Utilities System

System Operability Summary of ECCS Outage Events for TMI-1 LFR No.

1976 Outage Time LER No./Date System Dencription in Days 76-02 1/6/76 NSRW Inoperable Nuc Sue River Water Pump "A" Discharne Valve Failure O days #

to open when Pump started (NR.lA) 76-09 2/21/76 MUP Inadequate Make Up Pump A Procedural Controls (MUP1A)

.04 day +

76-10 2/21/76 D/G Diesel Generator IB Breaker failed to close due to inadequate procedure 1 day +

76-14 4/27/76 DilR The valve stem of Dil-VI was placed in operation while it was O days #

released for installation only.

76-20 5/20/76 RBI Reactor Building Isolation valve (WDC-V3) failed to close on ESAS Test Signal.

1 day +

76-21 6/21/76 MUP containment Isolation valve MU-V2B failed to close on ESAS Test Signal.

I day 76-26 6/22/76 RBP liigh Range Actuation Mode of a Reactor Building Purge Exhaust Monitor.

O days #

76-34 9/22/76 RBI Reactor Building Isolation valve CA-VI failed to fully close on remote signal 1 day 76-40 11/6/76 DIIR Abnormal degradation of the seal ring in Dlivl 2 days +

76-42 11/22/76 NSRW/DHR/EC Underground River Water Pipe cracks O days #

76-44 12/7/76' RBI Reactor Building Tsolat ion valve All-VID fniled to fully close.

.33 days Total 6.57

+*

+ Time taken is total outage durat ion since operability was not required during shutelown and repair was made during a Refueling / Scheduled Outage

  • ' Capable of performing intended function - not repaired fully until Refueling
  1. 'See Component List

' +i Long Term Shutdown via NRC Order, also, see note "+"

'^

r.

I System Operabi1ity Summary of ECCS Outage Events for TMI-I by LER No.

1977 Outage Time LER No./Date System Description in days 77-01 2/3/77 D/G Loss of Diesel Geacrator A with Diesel Generator B out of service

33. day 77-03 3/9/77 RBS Failure of Reactor Iluilding Spray Pump Suctioa Isointion Valve Motor 0 days #

l 77-11 5/19/77 ES In Motor Centrol Center failed to trip during power operations

.01 day ES 77-12 5/19/77 MUP Make Up Pump 1A was removed from service prior to checking redundant

.20 days pump 77-14 5/24/77 RBI Reactor Building Isolation Valve RB-V7 failed to close on test signal

.33 day +

77-18 6/29/77 NSRW Nuc Sue River Water Pump shaf t failed 0 days #

77-24 10/22/77 MUP Make Up Valve 14B failed to open in response to ES test signal 1 day 77-28 12/8/77 MUP Reactor Coolant Letdown Sample Isolation Valve (CAV 13) failed to

.33 day close 77-31 12/25/77 MUP Small pin hole leak at the casing drain hinge weld at MUP-IB

_ 0 days f Total 2.20 +

/

Time taken is total outage duration since operability was not required

+

during shutdown and repair was made during a Refueling / Scheduled Outage Capable of performing intended function - not repaired fully until Refueling f See Component List

++ Long Term Shutdown via NRC Order, also, see note "+"

t i

System Operability 4

Summary of ECCS Outage Event for TMI-1 by LER No.

1978 Outage Time LER No./Date System Description in days l

78-03 1/12/78 D/G Diesel Generator 1B failed start on ES test signal

.20 day t

78-04 1/17/78 MUP Packing gland leak for MUV74A

.01 day i

i 78-05 1/19/78 RBS BS-V47 A/B.were opened during the B.S. Pump operability test

.33 day 78-06 1/24/81 RBI Reactor Building Isolation valve CA-V13 failed to close when

.33 day activated by remote signal 78-10 3/18/81 MUP Make Up Pump 1A & IC time delay relay in low lube oil trip circuit 0 days #

D/G failure /10.1 pressure limit switch failure on diesel generators failure 78-19 6/5/78 RBI Reactor Building Isolation valve RB-V7 controlled fuse opened 1.0 day i

78-22 7/23/78 DG Diesel Generator A air valve tagged out without testing other diesel

.16 day i

78-25 8/19/78 NSRW Nuc River Water Pumps not selected to start on ES eignal

.37 day L

78-27 9/1/78 CF B Core Flood Tank out of spec low

.20 day

.04 day 78-28 9/8/78 RBS Leaky 0 ring in NaDii level transmitter Total 2.64 +

l

+ Time taken is total outage duration since operability was not required I

during' shutdown and repair wan made during a Refue?ing/ Scheduled Outage Capable of performing intended function - not repaired fully until Refueling See Component List 4+ Long Term Shutdown via NRC Order, also, see note "+"

l

System Operability l

Summary of ECCS Outage Events for TMI-1 by LER Wo.

1979

)

Outage Time LER No./Date System Description in days 79-01 1/7/79 DilRW Decay llent River Water Pump 1 A had a rag in pump suction 1.9 days f.

79-02 1/12/79 DIIR Dll-V5B Motor breaker tripped 1 day 79-03 2/17/79 MU MU-P-1C tripped ca overload 0 days #

79-04 2/17/79 D/G Emergency Diesel 1B tripped on overspeed

.33 days +

79-05 2/25/79 DilR/RBS Dil-V15 A/B, Dil-V6 A, DilVSA and BS-V3B packing laaks 2 days +

79-06 2/28/79 RBT.

CA-V5B failed local leak rate test 0 days #

79-07 3/23/19 DIIR/MH Dome collapse on BWST (Dil V27 vacuum breaker) 0 days #

79-06 3/10/79 RBI All-VIB failed local l eak ra t e test 2 days +

79-11 4/5/79 DilR/RBS/MU Intergranular stress corrosion cracking of 304 SS pipe O days #

79-12 6/18/79 DilR ESAS relay failed to drop o.it 0 days #

79-13 6/20/79 DilR BWST suction line crack 0 days #

Total 7.23 days +

+ Time taken is total outage duration since operability was not required during shutdown and repair was made during a Refueling / Scheduled Outage

  • Capable of performing intended function - not repaired fully until Refueling
  1. See Component List 4+ 1.ong Term Shutdown via NRC Order, also, see note "+"

System Operability Summary of ECCS Outage Events for Till-1 by LER No.

1980 Outage Time LER No./Date System

1) esc ript ion in days 80-03 2/17/79 MU P MU-V-73A/B had loose internal (tilting disc check valves)

O days #

80-06 3/25/80 RI;I RB-V7 failed local leak rate test 0 days #__

Total 0 days #

+ Time taken is total outage duration since operability was not required during shutdown and repair was made durit.g a Refueling / Scheduled Outage Capable of performing intended function - not repaired fully until Refueling

  1. See Componcat List

++ Long Term Shutdown via NRC Order, also, see note "+"

i' l

i

~

Component List Summary of ECCS Outage Events for TMT-1 LER No.

1 1976 1.

Outage Time

[

LER 130./Date System Description in Days 76-02 1/6/76 NSRW Inoperable i?uc Sue River Water Pump "A" Discharge Valve 60 days +

Failure to open when Pump started (NR-P1A).

l l

76-14 4/27/76 DilR The valve stem of Dil-V1 was placed in operation while it was 29 days +

l released for installation only.

1 76-26 6/22/76 RBP liigh Range Actuation Mode of a Reactor Building Purge Exhaust 11 days Monitor.

1 76-42 11/22/76 NSRW/DHR/EC Underground River Water Pipe cracks.

108 c'ays +

Total 208 days +

1 4

t

+ Time taken is total outage duration since operability was not required during shutdown and repair was nade during a Refueling / Scheduled Outage

  • Capable of performing intended function - not repaired fully until refueling
  1. See Component List

++ Long Term Shutdown via NRC Order, also, see note "+"

1 L

i Component List Summary of ECCS Outage Events for TM1-1 by LER No.

1977 Outage Time LER No./Date System Description in Days 77-18 6/29/77 NSRW Nuc Suc River Water Pump shaft failed.

45 days 77-31 12/25/77 MUP Small pin hole leak at the casing drain hinge weld at MUP-18 90' days Total 135 days I

I

[

l A

i

+ Time taken is total outage duration since operability was not required during shutdown and repair was made during a Refueling / Scheduled Outage Capable of5 performing intended function - not repaired fully until Refueling

  1. See Component List

++ Long Term Shutdown via NRC Order, also, see note "+"'

y Component List Summary of ECCS Outage Event for TM1-1 LER No.

1978 Outage Time LER No./Date System Inscript ion in days 78-10 3/18/81 MUP Make Up Pump 1A & IC time delay relay in low lube oil trip 60 days +

D/G circuit failure /10.1 pressure limit switch failure on diesel generators failure.

Total 60 days +

t

[

+. Time taken is total outage duration since operability was not required during shutdown and repair was made during a Refueling / Scheduled Outage Capable of performing intended function - not repaired fully until Refueling

  1. See Component List

++ Long Term Shutdown via NRC Order, also, see note "+"

Component List Summary of ECCS Outage Event s for TMI-1 by LER No.

1979 Outage Time LER No./Date System Description in Days 79-03 2/17/79 MU MU-P-1C tripped on overload.

4 days +

79-06 2/28/79 RBI CA-VSB failed local leak rate test.

30 days +

79-07 3/23/79 DilR/MU Dome Collapse on BWST (Dil V27 vacuum breaker).

360 days +

79-11 4/5/79 DilR/RBS/MU Intergranular stress corrosion cracking of 304 SS pipe.

266 days M 79-12 6/18/79 DilR ESAS relay failed to drop out.

14 days M 79-13 6/20/79 DilR BWST suction line crack.

465 days M Total 1139 days +,M

+ Time taken is total outage duration since operability was not required during shutdown and repair was vaade during a Refueling / Scheduled Outage Capable of perfor iing - intended function - not repaired fully until Refueling

  1. See Component List M Long Term Shutdown via NRC Order, niso, see note "+"

i.

A Component List Summary of ECCS Outage Events for TMI-1 by LER No.

1980 1

Outage Time LER No./Date System Description in Days 80-03 2/17/79 MU MU-P-73A/B had loose internal (tilting disc check valves).

468 days M i

l 80-06 3/25/80 RBI RB-V7 failed local leak rate test.

482 days M j

)

Total 950 days M Y

l 1

+ Time taken 13 total outage duration since operability was not required during shutdown and repair was made during a Refueling / Scheduled Outage Capable of performing intended function - not repaired fully until Refueling

  1. See Component List M Long Term Shutdown via NRC Order, also, see note "+"

i

SURVEl1.1.ANCE OF ECCS SYSTIGIS Average Outane Times Tech.

Procedure annual Time

{

- jEec.

No.._

1 tem Frequency x Avg. Time In Days

=

e l

4'.1.20 1303-4.14 Rx Bldg. Spray Fl(12) 2 hrs.

24 hrs.

1.00d i

4.6.1 1303-4.16A Diesel Gen. A Fl(12).

3 hrs.

36 hrs.

1.50d j'

4.6.1 1303-4.1611 Diesel Cen. 15 Fl(12) 3 hrs.

36 hrs.

1.50d 4.1.43 1303-4.18 4KV. ES Bus UV Relay Test Fl(12)

.5 hrs.

6 hrs.

.25d 4.1.18 1303-5.1 RB Clg & 1s01 1.ogic Cil & Comp Q(4) 50 hrs.

200 hrs.

8.33d 1

l 4.i.18, 19 1303-5.2

.l.DC Seq. & Comp Tst 111/1.o Press Inst Q(4) 4.0 16 hrs.

.67d 4.2.1 1303-11.26 Rn Isolation Valve Cycle Test A(1) 4 hrs.

4 hrs.

.16d i' -4.12.1 1303-5.7 RB Purge Air Treat op Test M(12) 1.0 hrs.

12 hrs.

.50d 4

j 4.12.1 l303-5.9 RB Air Treat Dif f Pr Test A(1) 4.0 hrs.

4 hrs.

.16d 3.8.9 1303-10.1 R15 Pury.e Sys A(1) 2 hrs.

2 hrs.

.08d 4.2.1 1303-11.16 DilR System I.eak A(1) 30 hrs.

30 hrs.

1.25d j

4.4.1 1303-11.25 Ril 1.ocal I.eak Rate W(52)

I hrs.

52 hrs.

2.16d.

l

-4.5.2 1303-12.4 Vent Dli Pumps & I.P1 1.Ines SA(2) 5 hrs.

10 hrs.

.42d i

4.2.1 1300-3C DC Pumps Function Test Fl(12) 3 hrs.

36 hrs.

1.50d 4j' 4.2.1 1300--3A A Rx Bldg. Sys Pump & Valve Test Q(4),

40 hrs.

160 hrs.

6.67d l

4.2.1 1300-3B A' DilR Sys Pump & Valve Test Q(4) 1.0 hr.

4 hrs.

.16d 4.2.1 1300-3D DR-PIA /It Pump 5. Valve' Test M(12) 4 hrs.

48 hrs.

2.0d l

4.2.1 1300-31I A MilP 1A/n/C & Valve Test Q(4) 10 hrs.

40 hrs.

1.67d 4.2.!

1300-311 B Make Up Pump Function Test M(12) 3 hrs.

36 hrs.

1.5d 4..'.1 1300-31 a NR-P 1A/ll/C Pump 6 Valve Test M(12) 5 hrs.

60 hrs.

2.5d 4.2.1 1300-3.1

-NS-PIA /B/C Valve Funct Test M(12) 3 hrs.

36 hrs.

1.5d 4.2.1 1300-3K A RR System Pump / Valve Funct Test Q(4) 6 hrs.

24 hrs.

1.00d 4

i

A "J

    • J "O

~

O "J

7 "O

O

-7 J m O N O m

'":l t "'

N M

C m n 5 &

t N.

C.

C C N m N.

C.

< C C CC 7

  • 7 C.
  • C
  • d < :C <

CC N

I

~

e l

=

.a

= u u e u

./ -

Z T

Z Z

Z

/

L b

w l

-6 L

i 4 N O - N Ps CC N D C D D C C ? C N

C C o.~

N e.e e.4 N

7

== -

4 Z

'A a

f4 O

M Z

'A L

L O

M L

f.

b Z

t,')

W th 2

2

't

.,2 Z

u y

y 6

L C

n

[

- - O C C C O-N n

w we NO O

N C C < <

N N N C M

- N N - N ll0

- *=

q

^

^

e ^

^ ^ ^ N ^ ^ N

^ ^ ^ ^ ^ ^

/=s v - - -

N.

N N

v w

v v < v v v v v

v v w

v v y.

Z O < < Z < < Z Z < < < < < < <

^

    • ~

.Z.

C.

=.

O O

t

.h.-

C L

/

E D

w C

E e

U

= ~~

~

O C

Z C

...d

~*

.e e_

n 7t w'-

C C

C w*)

0 w

w h

4.

C.

C e

.e.

a 4

k

~J s

U Z

".:. C 4

L..

.J

.e

.e

-e g

)

7 g

5 <

-. M

$ 5 b :

.5 E

O.

O.

Q

=

C U

t.

Z

- Z

  • J

==.

u Q

0 0 V Z 3

O

" v C

O E

e.;

>.= =

U C

0

= - ": < :.* Z

.A C

  • 4

.a

=

0 m

c -

b.J Z.d L

> /.

.t Z.

Q O

  • J

.O.

,G.

  • ,."" ~ ":

X 6

w w

w w

w X -

O u -

Z

C - ", =

t.-

a.

R.

0 O

O

.:d u

6 E

O Q

Ti N."

b ti,

  • i m-6 6

d 4.J

.s 0

.C.

3

'A 0

C O

t La E

~3 0

C 4

7 Z-

.t.

- /.

Z,.

m w

.. J u

X

= -

w w"

0 ::^.: N N

'.d N N f

a 2

O O i

I I

I u.

.A s.,

a w

A.

.A

~

~

e.

w

~.:. ~

.A

- - - - ~~ -

u e

. :C - M - -.--*

= -

C N.

N.

CC.

N s

4 7

~ - -== - CC C

M M Lfi e d O IA < <

4 I

I i

1 I

I i

i 1

i f

I i

1 i

e n

e

~

N N N

N.* -

f**

N

-w

. ir O O as N

at N N

.~.~

mP

~#

n m.

w w

W b

N Ll"'

f'"

N O N

==

d

.e m -

.-M N

N.

M M

    • " - $5 fl bd he he.

hk N$

< < Y

  • ?

KEY High pressure injection by the makeup and purification system.

MUP Low pressure injection by the decay heat removal system.

DHR Core flooding by the core flooding system.

CF RBC - Reactor building cooling by the reactor building emergency cooling units.

RBS - Reactor building cooling by the reactor building spray system.

The removal of fission products in the reactor building atmosphere.

RBI - Reactor building isolation.

D/G - Diesel Generator.

t DHRW - Decay Heat River Water System.

NSRW - Nuclear Services River Water System.

.j -

1

)

1 f

w