05000321/LER-1981-111-03, /03L-0:on 811003,after Reactor Startup,Discovered Drywell to Torus Delta Pressure 1.5 Psig Not Established within 24-h After Placing Reactor Mode Switch in Run.Caused by Personnel Error & Unavailability of Boiler

/03L-0:on 811003,after Reactor Startup,Discovered Drywell to Torus Delta Pressure 1.5 Psig Not Established within 24-h After Placing Reactor Mode Switch in Run.Caused by Personnel Error & Unavailability of Boiler

ML20011A821
Person / Time
Site:	Hatch
Issue date:	10/23/1981
From:	Baxley S GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20011A816	List: 05000321/LER-1981-111, Forwards LER 81-111/03L-0 05000321/LER-1981-111-03, /03L-0:on 811003,after Reactor Startup,Discovered Drywell to Torus Delta Pressure 1.5 Psig Not Established within 24-h After Placing Reactor Mode Switch in Run.Caused by Personnel Error & Unavailability of Boiler
References
LER-81-111-03L, LER-81-111-3L, NUDOCS 8111030254
Download: ML20011A821 (2)

LER-1981-111, /03L-0:on 811003,after Reactor Startup,Discovered Drywell to Torus Delta Pressure 1.5 Psig Not Established within 24-h After Placing Reactor Mode Switch in Run.Caused by Personnel Error & Unavailability of Boiler

Event date:
Report date:
3211981111R03 - NRC Website

text

. _. _ _,

_.4 i NRC FORM 366 U. S. NUCLEAR REGUL ATORY COMMISSION (7-77)

LICENSEE EVENT REPORT t

CONTROL BLOCK:

( l l

l l

(PLEASE PRINT OR TYPE ALL RdOUIRED INFORMATION) 7 lO j i] l Gl Al El Il Hl 1l@l Ol 0l -l O l Ol'Ol O l O l -l 0 l O l@l 4 l I l I l 1l 1 l@!

l l@

7 8 9 LICENSEE CODE 14 15 UCE%E NuvaER 25 26 UCENSE TYPE JO 57 CAT 68 CON'?

10til 3M l Ll@l 0l 5l 010 l 0l 3l 2 l l l@l 11010 l 3 l 8 l 1 l@[J 10 l 2 l 3 l 8 'll l@.

8 60 61 DOCKET NUMBER 68 63 EVENT DATE 74 75 REPORT DATE 80 f

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES l O 12j [ During normal power operation fcllowing c reactor startup, it was discovered that l

o 3 l the drywell to torus delta,,ressure of 1.5 psid had not been established within 24

- l io g4i l bours afte r placing the reactor mode switch in run as required by T.S. 3.7.A.7.1.

l io is! l There were no effects upon public health and safety due to this event.

This is a p

)iO167l repetitive event.

(See LER # 50-321/1981-87).

l I O l 71 I I

i 1018i L l

l

• I[E CcYee SeCi$E

1. ^

O COMPONENT CODE' SUBC DE' SU E

i 10191 LSI Al@ [ AJ@ LA_J@ l Xl XI Xl Xl Xl Xl@ l Zl@ W @

SEQUENTIAL OCCUR REf2.E REPORT REVMION l

,. EVENT YEAR R EPORT NO.

CODE TYfE NO.

@ mgg/RO 1811l l-l I 11 11 11 M

i 01 3l

- l L l

[-j l 0l LER a

,,, 21 22 23 24 e6 27 28 29 30 31 32 T K ACT ON L NT T

HOURS 22 SB IT C FOR B.

SUPPL 1 MANUF CTURER i

LZJ@LZJ@

LZjg i Z l@

l 0 l0 l0 l l

[YJ@

[N Jg [Zj@

l Zl 9l 0l 9l g 33 34 35 36 37 40 41 42 43 44 47 J

CAUSE DE3CRIPTION AND CORRECTIVE ACTIONS h s l' Excessive time was required for drywell inerting due to the unavailability of the i

I li l 3 l l auxiliary boiler for the nitrogen vaporizer.

Since the delta pressure is established I li 121 I after drywell oxygen is reduced to less than 4% and it took the full 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to do l-i,i3i l this, the delta pressure was not established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l 11:411 I

7 8 9 80 ST S

% POWER OTHER STA TUS dis OV RY D'SCOVERY DESCRIPTION li 15 I L.cj@ l 0 l 4 l 41@l NA l

lZl@l NA l

ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT GF ACTIVITY LOCATION OF RELEASE LZJ @ LZj@j NA l

l NA l

i 6 7

8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE CESCRIPTION W l 01 0l Ol@ [_ZJ @ l NA l

'.,EnsO~~El'INJ'iES DESCRienON@

NuusER l0l0l0l@l-NA l

i a 80 7

8 9 11 12 Wu ' "fSC^"'## '"" @

[_Zj@l NA a

l i 9 y

7 a 9.

10 8111030254 811023 80 12 l a l L N]f@*"' DESCRIPTION l

lllllllll1lll; isSu l

.7 8 9 10 68 69 80 5 -

S. X. Baxley, Supt. of Operations pgoyg mN-MM

{

NAME OF PREPARER l

o a

LER #:

50-321/1981-111 Licensee: Georgia Power Company Facility Name:

Edwin I. Hatch Docket #:

50-321/1981-111

Narrative

Report for LER 50-321/1981-111 At 0530, 10-3-81, during normal reactor power operation following a reactor startup, it was discovered that the drywell to torus Delta Pressure had not been established within-24 hours of placing the mode switch to run as required by Tech. Specs. 3.7.A./.1.

The cause of the time limit being exceeded was personnel error coupled with the fact that the auxiliary boiler was unavailable for nitrogen vaporization. Since the auxiliary boiler was not available, alternative means were utilized which were far slower and resulted in excessive time being utilized on containment in-erting; in fact, the whole 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> were required.

Normal practice calls for drywell to torus Delta P to be estab-lished after'inerting is finished (because of difficulty in main-taining Delta P while inerting). After the containment had been inerted, it was realized that greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.had elapsed and drywell to torus Delta Pressure had not been established.

By 0745 CDST, a drywell to torus Delta Pressure of greater than 1.5 psid had been established.

O e

,n..

+y c

e