Text

/03X-3 on 781009:primary Coolant Oxidant Concentration Exceeded 10vpm W/Core Average Outlet Temp Greater than 1200 Degrees F.Caused by Accumulation of Water in Pcrv Insulation
	ML20064G745
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/06/1978
From:	Gahm J; PUBLIC SERVICE CO. OF COLORADO
To:	;
Shared Package
ML20064G744	List: ML20064G739; ML20064G745;
References
	LER-78-018-03X, LER-78-18-3X, NUDOCS 7812130192
	Download: ML20064G745 (8)
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_

t REPORT DATE: Daccmb r 6,1978 REPORTAELE OCCURRENCE 78-18 ISSUE 3 OCCURRENCE DATE: October 9,19 78 Page 1 of 7 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPA.'.T OF COLORADO P. O. BOX 361 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/ 78-18/03-X-3 Final Supplement IDENTIFICATION OF OCCURRENCE:

On several occasions during the period from October 9,1978, to November 14, 1978, the primary coolant oxidant concentration was in excess of 10 parts per million by

{} volume (10 vpm) with the core average outlet temperature greater than 1,200*F.

This constitutes operation in a degraded mode permitted by LC0 4.2.10, and is re-portable per Fort S t. Vrain Technical Specification AC 7.5.2(b)2.

This report is submitted as a final supplement to Reportable Occurrence Report No.

50- 26 7/ 78-18 /03-L-0.

EVENT DES CRIPTION:

From 1500 to 1508 hours0.0175 days 0.419 hours 0.00249 weeks 5.73794e-4 months on October 9,1978, the core average outlet te=perature was about 1,20l*F with a total primary coolant oxidant concentration of about 21 vp m. This event occurred during moisture removal operations with the reactor power at about 40%. Refer to Figure 1, point (1) .

From 0345 to 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months on Nove=ber 4,1978, the core average outlet temperature

(' again exceeded 1,200*F with an oxidant concentration of about 12 vpm. This event occurred during the performance of special testing which caused the core average outlet te=perature to rapidly change. Refer to Figure 2, point ([) .

On November 6,1978, a gradual increase in reactor power from about 35% to 50" was begun. The resulting increase in the core average outlet temperature re-moved moisture from the PCRV insulation and caused the fluctuating oxidant con-centrations on November 6,1978 and November 7,197S. (Figure 3, point (3) ) .

A further increase to about 60 to exceed 10.0 vpm at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on November 7,19 78 (Figure 3, pointreactor s. ). I' power caused remained above 10.0 vpm until 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on November 11,1978(Figure 3, point (j)).

CAUSE DES CRIPTION:

Recent analyses have indicated that the oxidant concentration problems experienced since :by 12, 1978, as well as those specifically addressed in this report, have been di;ectly associated with the operation of "A" circulator. It is believed that .

water had accumulated in the PCRV insulation near the inlet to "A" circulator, and was being evaporated when the circulator was run. The variations in the oxidant concentration were dependent on the evaporation rate, which in turn depended en the nu=ber of operating circulators, their speeds, and other factors affecting the primary coolant flow.

781213_0_13 L- - - - - - - -

REPORTABLE OCCURRENCE 78-18 ISSUE 3 Page 2 of 7 CAUS E DESCRIPTION (continued)

Several events which may be responsible for the accumulation of water in the PCRV insulation have been identified:

1. Reactor scram and Loop 1 shutdown on May 8,1978 - Ref:

Report No. 50-267/78-16/03-L-0.

2. Feedwater controller malfunction which caused Loop 1 shutdown on May 24,1978 - Ref: Report No. 50-267/ 78-18/03-L-0.

3. Plant shutdown on June 29, 1978, as a result of instrument bus supply problem. Ref: Report Nu=bers 50-26 7/ 78-25/01-X-1 s and 50-267/ 78-18/03-X-1.

)

4. Plant shutdown on July 31, 1978, as a result of 4160/480 volt transfor=er failure - Ref: Report Numbers 50-267/ 78-18/03-X-2 and 50-267/ 78-28/01-T-0.

CO RRECTIVE ACTION:

/

Operations in a degraded mode of LCO 4.2.10 have been a recurring problem since May 12, 19 78. .

Recent analyses have indicated that the oxidant concentration problem was directly associated with the operation of "A" circulator. This relationship suggested that water had accumulated in the PCRV insulation near the suction of the "A" circulator, and was being evaporated when "A" circulator was run. Special moisture removal operations at about 8% reactor power and 640*? core average outlet te=pera ture were begun on October 19, 1976. These operations included running "A" circulator

{") at high speed in Loop 1, and "C" and "D" circulators at normal speed in Loop 2.

"B" circulator was shutdown. It was anticipated that the oxidant concentration would equilibrate af ter an initial increase, and then subside as oxidants were re-moved by the purification sfstem. With the circulator combination described above, and with the core average outlet temperature maintained belov 1,200*F, the oxidant concentration rose to an equilibrium value of about 35 vpm by October 24, 1978.

It remained at this level until October 30, 1978, and then began a rapid decline.

Refer to Figure 2, point ([I . This rapid decline indicated that as much water as possible had been removed f rom the PCRV insulation for those plant conditions.

Removal of residual coisture from the insulation would require higher reactor power levels and temperatures. Normal 4-circulator operations resu=ed on October 31, 1978.

By November 3,1978, the oxidant concentration had declined to 5.3 vpm. At that time the reactor power was increased to about 40% to perform special testing. The resulting increase in the oxidant concentration was expected, and was due to the higher core average outlet temperature removing residual moisture from the PCRV insulation. Similarly, the gradual increase in reactor power to 600 that commenced on November 6,1978, was accompanied by an increase in the oxidant concentration which was subsequently removed by the purificatien system. The reactor has been operating at about 600 power since November 9,1978. No further problems with the oxidant concentration have been encountered. It is believed that essentially all moisture has been removed from the PCRV.

No further corrective action is anticipated or required.

, REPORTABLE OCCURRENCE 78-18 ISSUE 3

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3000 0000 0000 0000 0000 0000 0000 0000 11/3 11/6 11/7 11/8 11/9 11/10 11/11 . 11/12 DATE/ TIME

.' ..* REPORTABLE OCCURRENCE 78-18

. ISSUE 3

-__...P_e.gn _ 6 of 7 _ ,- _....-

m.40

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. . . i o 11/12 11/13 11/14 11/15 11/16 11/17 11/18 11/19 DATE/ TIME

REPORTABLE OCCURRENCE 78 ISSUE 3 Page 7 of 7

- i Prepared by: ('/ 7'I 7 f $1 Charles H. Fuller Technical Services Technician j'

Reviewed by: 1 (( . f.- / -

J/ W. Gahin yechnicalServicesSupervisor O

Reviewed by:

Frank M. Mathie Operations Manager Approved by: 4 m J7$ o ,... /,. ..-

Don'Wa rembourg [

Manager, Nuclear Production M.

O

-e ~ g*- -

.m __ _ _ . _ _

.7 771 . , * .

LICENSEE EVENT RE? ORT (PLEAsE POINT OR TYPE ALL REQUIRED INFoRMATIONI dQNTROL BLOCK: I l l l \ l lh U

f o l Ji l9l cl oLICENSEE f Fl SCCCE l Vl 1l@l 14 0

15 l 0 l -l 0 l 0LICENSE l O lNUMS01 ER0 l - l O l 0 l@l h 426 l 1 LICENSE l 1 ] 21 TYPEOJol@l 57 CAT l 58 l@ j CCWT

"' " l 10111 so(RCs l L 61@l 0] 510l 0l 0l 2l 6l 647 @l ll 01 O l 917l 872 }@l V 60 69 EVENT QATE 75 112101617181@

REPCRT CATE 30 COCK ET NUMBER EVENT DESCRIPTION AND PR09ABLE CCNSECUENCES h Io1al l On several occasions during the period from October 9,1978, to November 11, 1978, I lo eai l the pridary coolant oxidant concentration exceeded 10.0 vpm with the ccre average l 1 o i 4 I I outlet temperature greater than 1,200*F. This constitutes operation under a degraded l I o I s J l mode permitted by LCO 4.2.10, and is reportable per Fort St. Vrain Technical l lo is l l Specification AC 7.5.2(b)2. This report is submitted as a final supplement to l l Report No. 50-267/ 78-18/ 03-L-0. l t

l 0 la l l l 60 7 8 9 SYSTE M CAUSE CAUSE CCVP. VA Ly g CCOE CCCE SUSCCOE COMPONENT CCOE SUSCCCE SUSCCCE laisi 7 8 Ic la l@ l xi@ LZ_J@ I z i z i z i z i z i z i@ Iz i@ Iz i@

9 to 11 12 13 19 13 20

, SECUENTIAL CCCURAENCE REPORT REVISION lea EVENT YEAR R EPCRT No. CCOE TvPE NC.

@ sasy,40 g 17181 1--I 1011181 1/l 1013 I I x1 l-l 13I 21 22 23 24 26 27 23 29 00 33 32 K N ON ONP NT- ME WOURS 38 i PCR 1 8. 5 P Li MAN FAC ,,RER I33 x t@l34 xi@ lzi@ 11zl@

35 _ 36 l01010101 37 40 Irl@ Isl@ lzl@ lzl9l9l9l@

43 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 11 t o i l Accumulation of water in PCRV insulation is resconsibia for n-d d an t arebla-a l lilil l experienced since May.12, 1978. Moisture removed by special circulator operations. I i;; ; No further action is anticipated or required. l i t 21 i l liisi 1 1 aa E0 ST N. 480WER 3?wtR $7ATUS is C RY DISCOVERY DESCRt* TION Operator Observation I i 5 l l Zl@ l 0 l 4 l 0'2l@lo N/A a

l lAl@l 45 48 8o l

5J..v,T, asTE T

=E.E4sEs cP eELEAst tcCATicNCpREtzAsE@

h tai3 i) zl @ l z l@l 13 11 N/A AucVNT os ACTIVITY 44 lN/A 45

@l 80 I

EascyygggxpCSLRES NuveEm ~vPE C ISCR'PTY CN -

Iii2i' lcl010l@lzi@l N/A 50 I

PE=sCNstu'.Nd2,,,

s yst. CE3CA,PriaN@

'#!IclO!Ol@l J 3 12 N/A 30 i

6053 GF CM OAVAGE TO PAC.LITY

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i:::talSNIhl:o y/A i sa es l1 1I IIIfII II l!

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