ML20024E156

LER 83-016/03L-0:on 830710,pressurizer Cooldown Rate Exceeded Tech Spec Limit.Caused by Personnel Error & Procedural Inadequacies.Dhr Operations Procedure Revised to Add Caution Statements Re cooldown.W/830729 Ltr

ML20024E156
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/29/1983
From:	John Marshall, Rogers P ARKANSAS POWER & LIGHT CO.
To:	Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
1CAN078315, 1CAN78315, LER-83-016-03L-01, LER-83-16-3L-1, NUDOCS 8308090315
Download: ML20024E156 (3)

Text

1

~

9 iRCFORM366-

/ (7-77) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l 1 _- l_i_l_i_l_11 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 IT~~~8 l-~f*l 9lAIRlAlNIOl74 ETCERSEE CODE II ~ 1 l2' l 0 1 ~0 l ~- 1~~0 1 0 l 0_I O I O I - l ~0 1 0 13 1 4 1 l'l 1 i 1 l 1 14 l EICERSE NUM5ER

~~

75 2I UCERSE TWE ~30 57 CAT 58-

~ l 15 l3 l~'1 1 - REPORT 1 L 16 10

-7 -8 . SOURCE 6 I 6I'~1 ~5TCkEf 1 0 1 EUR8EF 0 1 0 1 3 l ~1 78163I 17 l017l110l8 7 VlHT DXTE3~18 l~ 1 741 1-7 I 2 1 9 I 8 1 3 19

~

75 'iiEP0iiT 6KT I 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 10 sill 1l~ ion 7/10/83, while cooling down and depressurizing,'the pressurizer cooldown rate exceeded the 100* F/hr ifmit [

'l1111 lof Technical Specification (T. S. ) 3.1.2.5. The pressurizer temperature was reduced from approximately 390 8 "

1 A, ~ l111) . Ito'240' F in 77 minutes yielding a cooldown rate of 117' F/hr.

4- This event occurred when the auxiliary pressur-l.

'S y l1111 lizer spray was initiated with the valve full open for depressurization of the reactor coolant' system (RCS), I l1l1( twhic% was at'approximately 235 psio and 115' F.

After the auxiliary pressurizer spray valve w*as closed, the I h.) 11111% jexcessive'cochi5wn was terminated. Af terwards, pressurizer temperature calculations using RCS pressure

~~ ~

\ l 7,0,_111

1. 8 9Ithat the Ifmit of T.S. 3.1.2.5 had been exceeded. The T.S. 3.1.2.6 requirement to restore the temperature ]

4' SYSTEM CAUSE 80 CAUSE COMP CODE VALVE CODE .SUBCODE

? l0 9l l ~C 1 B 111 iA COMPONENT CODE SUBCODE SUBCODE 7 ~ l-~~8. 1 A 113 l 7 l ~Z l ~Z l Z l~Z l~~Z l14 lZ IZ 9 70 11 112 II 13

~ ~- I8 19 ~l15 2D~[16 SEQUENTIAL- OCCURRENCE REPORT LER/R0 l EVENT YEAR REVISION REPORT NO. CODE . TYPE NO

% 17 REPORT .l l1l_3_l .l---l l_0,1 1 1 1 1 l /,_I l _0_,,l_3_ l ' l L_,1 NUMBER ,l_21 22 23 24 26- 27 28 29 l---l l 0_I 30_ 31 32_

ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB SUPPLIER l ,Z MANUFACTURER 1 1 l18 'I_H_l19 l Z_,121 1_0_1_0_l_0_l l i22 l ,Y_,123 33 34 35 _l20 36 37 40 l N_l24 1_Z f25 i_Z_l 1 1,,9_,(9_l26-41 42_ 43 _- 44 .47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 '

11(,0_] lThe occurrence was caused by a combination of personnel error and procedural inadecuacies.

Pressurizer cool- I l_Ill ldown plots had been terminated due to the low RCS temperature. The cooldown and decay heat removal operations l djll ,lprocedures did not caution of excessive cooldown during depressurization. The decay heat removal operations l l_I,,,,,ll! lprochurewasrevisedtoaddcautionstatementsaboutexcessivecooldown.

The cooldown procedure was revised I.

l_1 7 _ (4,,_l8 9 Ito ensure pressurizer cooldown rate limits are adhered to'when using auxiliary sprey method of pressurizer e i FACILI.TY 80 METHOD OF

• g' _ , , _ , , _ _ ' STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION l~~1 l 5 l

~ I3 i NA 130 l A 131 i

%' -7

• -8 9' ~128.

, ACTIVITY CONTENT 10 ~0 ~I2 16~1 1~0 12913 44 4I 46 Operator Observation '

80 132 RFA. EASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 11111 ' (,,Z_l 33 - l_Z_l34- l NA -

135 l _ _ _ NA 7' 8 '9 10 11 136 44 .45 80 PERSONNEL EXPOSURES NUMBER' TYPE DESCRIPTION.

1.1111 l_0,_l,0,,,l ,0,_137 l_Z_l 38 i NA 7 8 9 11 '12 13 139 sPERSONNEL INJURIES .e3 NUMBER DESCRIPTION' c 11 l-0 1~~0 l 0 140 l NA 3*2 -

,V- 7~~1~~8 ~~8 l 9~ Il 12 141

• L*.3 '~ LOSS OF OR DAMAGE TO FACILITY TYPE 80

' DESCRIPTION l1111 l_Z_l42 l NA 143 PUBLICITY

1. i ISSUED DESCRIPTION i Ji7 l l l i8 .l_N_l44 l NA 145 NRC USE ONLY 9 10 68 l_l_l_l_l_!_l_l_l_l_l_i_l 69 80

.NAME OF PREPARER Patrick Rogers PHONE: (501) 964-3100

< 8309090315 830729 PDR-ADOCK 05000313

• S PDR

. . s:s .

(14RC FORM 366

./" ..(7-77)' U.S.. NUCLEAR REGULATORY COMMISSION-

--LICENSEE EVENT. REPORT

. EXHIBIT A LER'No. 50-313/83-016/03L Occurrence Date: 07/10/83' Event Description and Probable Consequences (Continued)

~

~

was <500 psia as specified in T.S.5-3.1.2.6. . This occurrence is reportable thave been reported.

per T.S. 6.1 No similar occurrences.

Cause Description and Corrective' Actions (Continued) cooling.

An analysis of the occurrence was performed by Babcock and Wilcox (B&W),

within the. bounds of previous analysis.

the NSSS The occurrence was f atigue. usage was not significantly affected (<.01 fatigue cycles).The components were not adversely affected b in the event, and the information concerning the event was provided to the other operations personnel.A discussion h

^

.-^

q i

r

~

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 July 29, 1983 1CAN078315 Mr. W. C. Seidle, Chief Reactor Project Branch #2 k

U. S. Nuclear Regulatory Commission sl Region IV g_gg 611 Ryan Plaza Drive, Suite 1000 .. _ 33 Arlington, Texas 76011

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Licensee Event Report No. 83-016/03L-0 Gentlemen:

In accordance with Arkansas Nuclear One - Unit 1 Technical Specification 6.12.3.2.b, attached is the subject report concerning an excessive pressurizer cooldown rate.

ry tru you s ohn . ars a 1 I anager, Licensing JRM:RJS:sl Attachment cc: Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Norman M. Haller, Director Office of Management & Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C. 20555 MEMBEA MOOLE SOUTH tJTILITIES SYSTEM