05000293/LER-1981-015-03, During Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training Revised

From kanterella
Jump to navigation Jump to search
During Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training Revised
ML20087N262
Person / Time
Site: Pilgrim
Issue date: 03/19/1984
From: Hamilton P, Harrington W
BOSTON EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BECO-#84-043, BECO-#84-43, LER-81-015-03X, LER-81-15-3X, NUDOCS 8404030276
Download: ML20087N262 (3)


LER-1981-015, During Surveillance Testing,Nozzle on 23-ft Level Cardox Sys Hose Reel Failed to Deliver Adequate Stream.Caused by Operator Error.Fire Brigade Training Revised
Event date:
Report date:
2931981015R03 - NRC Website

text

UPDATE REPORT PREVIOUS REPORT ISSUED 5/19/81 aremvn ov w e r;nM see u.c. tun.;4a r.ncutarmy camuison n siso. con y#Td se LICENSEE EVENT REPORT ke CONTROL 8 LOCK: l l

l l

l l

l@

(PLEASE PRINT OR TYPE ALL REQutRED INFORMATION) j oli l lM l A l P l P l S l llgl 0l0 l - l 0l 0l 0] 0 l 0 l -l 0l0 lgl 4 l 1 ll ll l1l@)

l lg u..........

u...........

o a u.~..,v..

n

.,c,..

CON'T Ioi5 l

g;"; y@l 0l 5l 0l-l 0 l 2l 9l3 ]@l 0 l 4l Il7 l 8 l 1 l@l0 l 3 0 l9 I 8 l 4l@

.5

..CR..NUM...

.V.N,..,.

.....,..k g

lOn4/17/81,at1130 hours, routine @surveillancetestingwasbeingconductedon EVENT OESCRIPTION ANO PROBABLE CoNSE0uENCES o2 lTl q l the Cardox System hose reels and nozzles. After successfully testing the 51 ft.l

,p ;g level hose station, a test was conducted on the 23 ft. level hose reel and noz-l lol3ll zie. The nozzle failed to deliver an adequate stream. A fire watch was im-l lo ls l l mediately established as required by Technical Specifications. Approximately l

lo l7 ll two hours later, the system was satisf actorily retested and returned to service.]

l o l 8 l l (Ref er to attachment.) This event caused no threat to the public health and saf y.

. c:e":...:'u:.

c'::

.::"n.

j ol9 l l A l B l @ @ @ [ Bj @ lP lI l P l E l X l X l @ [A_J @ l Z l @

... U. NT i. b

.CCU...NC.

.. v... N

@ !"di", IsiiI L..J l oli I s l L,o, 10131 lxl 1, 1 b_l u

n u

  • n':" ;;",":

.%"c,

'" T",. ;"

@ *:n c,",",n'.::"";.. ".'".u ;"'-

c bij@lx l@ Lz_l@

tzJO I o f of cl o I Ly_lO L2]O lA_l@

I cI 21 si si n

u o

a n

a u

u n

a u

CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS O>>

l t lo ll Cause of this event was determined to be operator error.

Engineering evaluation l l1li ll has determined that the nozzles will not permit C07 discharge unless the trigger l liTill on the hose station actuation valve is fully depressed.

Fire Brigade training l l was revised accordingly and Fire Brigade members were instructed on the correct l i 3 I

lTITl l method of activatino the Cardox System.

......... @ l:,. = =lB l@l SurveiiIance Testing l

IIIII W @ It In l n l@l NA

~

~

~

~

' !'n. :*?L',":

@l e...,,.

....u....

l NA l

l iI e I L. 2J @ l_2JSI NA g

NA

]

ITITl I 01 010 l@L..Z_J@l NUM...

.....,1.M NA l

l il s l l 0l 0l 0 l@l a

8404030276 840319 n

i.

PDR ADOCK 05000293 PDR l

n..

...c. in.

l1l9l U. @l ion NRC uSE ONLY

...u l""'n'lckni.N h NA l lljjj;llgy lg

, L, "JOI 2 o (617) 746-7900 P. J. Hamilton pgang NAME oF PREPARER

\\

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION

=

DOCKET NO. 50-293 Attachment t 31 -015-03X-1

Description

On April 17, 1981, the once a cycle surveillance (8.B.5) was being con-ducted on the Cardox Fire Protection System. This system consists of a storage ur.'t.having a. capacity of four tons which maintains liquid COThesystemks at a low temperature (-l'F) and low pressure (300 psig).

used for fire protection of the cable spreading room, as a supply source for three CO, fire hose stations (23' switchgear, 37' switchgcar and 51' generator area) and for generator purge.

When a CO h ze n zzle is removed from its brackets the mastor selector 2

/alve for the hose system opens allowing CO reach all three nozzles.

2 C0 can then be discharged by operating the squeeze trigger on the noz-zl The C0 hose reel on the 51' elevation was the first tested and was satis-7 factor?. The 23' elevation was then tested and failed. The 37' elevation was then satisf actorily tested. The testing at the 51' elevation permitted t reach all three hose reels. Heavy frost coating liquid and vaporous CO2 was observed on the pipes during this testing. The 23' elevation was re-tested within minutes and again failed. This CO station was declared in-3 Two operable, a maintenance request issued and a fire watch established.

hours later this hose station was satisf actorily tested and declared operable.

Cause and Corrective Action A review of the event by engineering revealed that the cause of the event was due to operator error and not a frozen hose station as described in the previous report. As a result of this followup investigation to the incident, it has been determined that the nozzles will not permit C0 dis-7 To elimTnate charge if the trigger or the handle is not f ully depressed.

a recurrence of this incident, the Training Department has revised the Fire Brigade training curriculum and members of the Fire Brigade have been in-structed on the correct method of activating the Cardox System.

N i

a

s WORTON EDISON COMPANY b

500 GovLaTON STRrrY l

BOSTON. MAESACHUSETTs 02199 WILLIAM O. NARRINsTON g.

March 19,1984 BEco. #84- 043 Regional Administrator, Region I U.S. Nuclear Regulatory Connission 631 Park Avenue King of Prussia, PA 19406 Docket Number 50-293 License DPR-35 Gentlemen:

l The attached. updated License Event Report 81-015/03X-1 "C02 System Hose Inoperable", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.B.2.b.

.If there are any questions on this subject, please do not hesitate to contact the. undersigned.

Very truly yours, 1))

William D. Harrington WDH/mg L

l Enclosures: LER 81-015/03X-1 cc:

Document Control Desk Office of Management Information and Program Control U.S. Nuclear Regulatory Comission Washington, D.C.

20555 Standard BECo. LER distribution Y

W 4o