05000338/LER-1979-111-01, /01T-0:on 790912,quench Spray Pumps Were Secured Prior to Pumping Required Amount of Water Into Containment as Specified in Fsar.Caused by Inaccurate Emergency Procedure for Loca.Pumps Secured

/01T-0:on 790912,quench Spray Pumps Were Secured Prior to Pumping Required Amount of Water Into Containment as Specified in Fsar.Caused by Inaccurate Emergency Procedure for Loca.Pumps Secured

ML19208C836
Person / Time
Site:	North Anna
Issue date:	09/24/1979
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19208C826	List: 05000338/LER-1979-110-01, /01T-0:on 790910,noted Ambient Temp Gauges Could Affect Capability of Diesel Generator Fan Cooling Sys So That Insufficient Cooling Would Be Provided.Caused by Improper Pitch Setting on Fan Blade 05000338/LER-1979-111-01, /01T-0:on 790912,quench Spray Pumps Were Secured Prior to Pumping Required Amount of Water Into Containment as Specified in Fsar.Caused by Inaccurate Emergency Procedure for Loca.Pumps Secured ML19208C825
References
LER-79-111-01T, LER-79-111-1T, NUDOCS 7909270555
Download: ML19208C836 (2)

LER-1979-111, /01T-0:on 790912,quench Spray Pumps Were Secured Prior to Pumping Required Amount of Water Into Containment as Specified in Fsar.Caused by Inaccurate Emergency Procedure for Loca.Pumps Secured

Event date:
Report date:
3381979111R01 - NRC Website

text

NRC F ORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-7/i LICENSEE EVENT REPORT CONTROL BLOCK: [l l

l l

l lh (PLEASE PRINT OH TYPE ALL REQUIRED INFORMATION) 1 6

1 1l1l@l l

l0 l1l l Vl Al N A l S l 1 l@l d d -l 0l d 0l 01 O! -l 0l 0l@l 4l 1l 7

8 3 LICENSEE CODE 14 15 LICENSE PJUVdhR 23 in LICENik T)Ph Ju b i L A I 5.8 CON'T 3$"c' l L l@

Q 5l Q 01 Ol 3l 3] 8l@l Oi 9l Il 2] 71 9]@l 0l 91 21 4l 7l 9l@

O 1

8 1,0 61 DOCKET NUYBER CA h3 EVENT D ATE 14 1.s REPORT D ATE N

EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o

2 l During Mode 1 operation. the station emergency orocedure for n tons of renctor 1

o a [ coolant accident was discovered to be inaccurate in that the cuench sprav numps were I

o 4

l secured prior to pumping the required amount of water into the conta W ent as o

5 l specified in the FSAR.

This event is reportable per T.S. 6.9.1.8.f. The health and

_]

o 6

l sa fe ty of the general public were not af fected by this incident.

1 o

7 l

l 0

8 80 7

8 9 SYSTEM

CAUSE

CAUSE COYP.

VALVE CODE CONE SUSCODE COYPONENT CODE SU9 CODE SUBCODE l S l B l@ l 0lh l Z l@ l A l C l C l U l M l U lh [Z_jh W h O'

7 8

9 10 11 12 13 IS 19 20 SE QUENTI AL OCCURRENCE REPORT REVISION LER RO EVENT YE AR REPORT NO.

CODF TYPE N O.

h REP l 7l 9l l-l l1l1lIl l0l1 l Tl

[--J [0_j

_ 21 22 23 24 26 21 23 23 JJ 31 32 I K A T ON O. PLANT ETH HOURS SLB IT D FOR d B.

S PPLIE MAN 'F AC URE R I H lgl4 Gl@

lZ[@

[ZJ@

}0l0l0l0]

[YJ@

W@

lAl@

l 1 4l 2l (Q 33 J

35 36 3/

40 44 42 4J 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i

O l The cause of this problem is that the procedure was written incorrect 1v in that l

li j i l [ the quench spray pumps were secured prior to the RWST beina emptied.

The procedure I

i, l 7 g l was corrected.

i a l l

11 141 l l

7 8 9 80 ST A S

% POWER OTHE R STATUS SCOV RY DISCOVERY DESCRIPTION l E l@ l0 8l2@lNA W @l Review of Emergency Procedure

_l i

5 ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l NA W @ lZ l@ l i c 7

8 9 10 11 44 45 80 PEP 50NNEL EXPOSURES NUV8 E R TYPE

DESCRIPTION

l0[0l0l@lZl@l l

1 7

i PERSONNEt INJURIES l o"l"I)**l"o lgl ""

Mhh l

in

/

9 9 11 12 J

\\ l / CJ L j l.1 80 LOSS OF OR D AVAGE TO F ACll!TV I_p['_I h tll. !

g ! /].' i,

l l

TYPE

DESCRIPTION

l W @l NA i 9 7

8 9 10 O LJ U LJ W LJ U LJ U U J 80 7 9 0 9 27 0 ST 5 CW NRC use oNov 45 ISS'K D@ DESCRIPTION 1043 (19fD i i i i i i i i i i i l!

LNj l

NA 2 o 7

8 9 10

' 68 69 80 &

O m o

<r, a

Virginia Electric and Power Company North Anna Power Station, Unit #1 Attachment: Page 1 of 1 Docket No. 50-338 Report No. LER 79-111/01T-0

Description of Event

During Mode 1 operation, the station emergency procedure for a loss of reactor coolant accident was discovered to be inaccurate in that the quench spray pumps were secured prior to pumping the required amount of water into the containment as specified in the FSAR.

This event was discovered while review-ing emergency procedures.

This event is reportable as a procedural inadequacy which could prevent the containment depressurization system f rom coping with accidents analyzed in the FSAR.

This event is reportable per T.S. 6.9.1.8.f.

No significant occurrences resulted from this ever.t.

The Unit #2 emergency procedure is also incorrect.

Probable Consequences of Occurrence The health and safety of the general public were not af fected by this incident.

The FSAR requires 455,000 gallons of water from the refueling water storage tank (RWST) to be expended into the containment at the end of quench spray pump operation.

Using the emergency procedure would have prevented this amount of water from entering the containment.

It was possible that the containment may not have been subatmospheric within one hour or may have returned to positive pressure af ter one hour with the reduced water inventory in the containment f ollowing an accident.

An increase in radioactive releases would then be expected.

Cause of Occurrence The cause of this occurrence is that the procedure was writtes ir-orrectly in that the quench spray pumps were secured prior to the RWST being

,. c ied.

Immediate Corrective Action

Standing Order #36 was written and approved by the Station Nuclear Safety and Operating Committee when the procedure error was discovered.

This standing order instructed operations personnel not to secure the quench spray pumps until the pumps were no longer pumping water into the containment.

On 09-13-79, the emergency procedure was corrected.

Scheduled Corrective Action This is considered an isolated incident, no further corrective action is required.

Action Taken to Prevent Recurrence No further action required.

10/B3 1043 051