05000267/LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted

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Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted
ML19351G401
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 02/13/1981
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19351G402 List:
References
P-81053, NUDOCS 8102230636
Download: ML19351G401 (9)
v • d • e


LER-1981-009, Forwards LER 81-009/03L-0.Detailed Event Analysis Submitted
Event date:
Report date:
2671981009R00 - NRC Website
v • d • e

text

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public service company ce cdendo 16805 ROAD 19%

PLATTEVILLE. COLOR ADO 80651 February 13, 1981 Fo r t S t. Vrain Unit No. 1 P-81053 r

Mr. Karl V. Seyfrit, Director Nuclear Reculatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012

Reference:

Facility Operating License No. DPR-34 4

Docket No. 50-267

Dear Mr. Seyf rit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/

81-009, Final, submitted per the requirements of Technical Specification AC 7. 5. 2 (b) 2.

l Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/81-009.

I Very truly yours,

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j k {LltL t.c,,~ 0 k W VM d

i Don Warembourg Manager, Nuclear Production DW/ cls g)

Enclosure cc: Director, MIPC

/ /

8102 280- h%

4 REPORT DATE:

Februarv 13, 1981 REPORTABLE OCCURRENCE 81-009 ISSUE 0 OCCURRENCE DATE:

Januarv 17, 1980 Page 1 of 8 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATIEVILLE, COLORADO 80651 REPORT NO. 50-267/ 81-009 /03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the period from January 16, 1981, to January 31, 1981, the plant was operated in a degraded = ode of LCO 4.2.10 on four occasions and in a degraded mode of LC0 4.2.11 on one occasion. These events are reportable per Fort S t.

Vrain Technical Specification AC 7.3.2(b)2.

EVENT

DESCRIPTION

Event 1 See Figure 1.

At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on January 17, 1981, with the average core out-let te=perature greater than 1200*F, the total primary coolant oxidants (the i

sum of carbon monoxide, carbon dioxide, and water) increased above 10 ppm.

Operation continued under these conditions until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on January 17, 1981, when the average core outlet temperature was reduced below 1200*F.

This event constitutes operation in a degraded mode of LCO 4.2.10.

Event 2 l

l See Table 1.

At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on January 17, 1931, when the average core out-let temperature was reduced as described in Event 1 above, the combination of primary coolant dewpoint and average core outlet te=perature was above the limit of LCO 4.2.11.

Operation continued in this condition until 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on January IS, 1981. This event constitutes operation in a de-graded = ode of LCO 4.2.11.

Event 3 t

See Figure 1.

At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on January 19, 1981, with average core outlet te=perature greater than 1200*F, the total primary coolant oxidants increased above 10 ppe. Operation continued under these conditions until 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on January 20, 1981. This event constitutes operation in a degraded mode of-LCO 4.2.10.

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REFORTABLE OCCURRENCE 81-009 ISSUE 0 Page 2 of 8 EVENT

DESCRIPTION

(Cont'd)

Event 4 See Figure 1.

At 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> on January 22, 1981, with average core outlet te=perature greater than 1200*F, the total pri=ary coolant oxidants increased above 10 ppa.

Operation centinued in this condition until 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on January 23, 1981. This event constitutes operation in a degraded mode of LCO 4.2.10.

Event 5 See Figure 2.

At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on January 25, 1981, with average core outlet te=perature greater than 1200*F, the total primary coolant oxidants increased above 10 ppm.

Operation continued under these conditions until 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> on January 31, 1981. This event constitutes operation in a degraded mode of LCO 4.2.10.

CAUS E DE SCRIPTION :

Event 1 At about 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on January 17, 1981, the reactor power was increased from 38% to 50% power, which increased the average core outlet te=perature from 1192*F to about 1247*F.

This was the first time core terperatures had been above 1200*F since a moisture ingress of January 3,1981, and the in-creased te=perature caused out-gassing of moisture that was absorbed in the cora graphite. The pri=ary coolant moisture increase and the resultant in-crease in graphite water reaction products, carbon =enoxide, and carbon di -

oxide caused the total primary coolant oxidant level :o exceed the 10 ppm.

level of LCO 4.2.10 at about 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on January 17, 1981. The reactor power was reduced due to the oxidant increase and. reached 1200*F at about 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on January 17, 1981. The LCO 4.2.10 is not applicable below-1200*F and operation in a degraded mode of LCO 4.2.10 ceased.

Event 2

'4 hen the average core outle te=perature was reduced below 1200*F on Janu-ary 17, 1981, as described in Event 1 above, the li=its of LCO 4.2.11 be-ca=e applicable. This LCO specifies'a maxi =um allowable primary coolant dewpoint which varies with the average core outlet t e=pe ra ture. At 1200*F, the max 1=um allowable pri=ary coolant dewpoint is -20*F.. A: 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on January 17, 1981, the pri=ary coolant dewpoint was -15*F with an average core outlet te=perature of 1200*F.

The cause of the operation in a degraded mode was the moisture out-gassed when the reac:or power was increased at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on January 17,'1981.

REPORTABLE OCCU EENCE 81-009 ISSUE O Fage 3 of 8 l

CAUS E DES CRIPT!CN: (Cont'd)

Even t 3 At about 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on January 19, 1981, reactor power level was increased, causing the average core outlet te=perature to exceed 1200*F at approximately 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />. At about 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, out-gassing =oisture caused the primary coolant total exidants to exceed 10 ppm, which placed the plant in a de-graded mode of LCO 4.2.10.

~J Event 4 At about 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> on January 22, 1981, reactor power was increased, causing the average core outlet te=perature to exceed 1200*F at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Moisture out-gassing as a result of the increased core temperature, caused pri=ary coolant total oxidants to exceed 10 pps at about 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, resulting in plant operation in a degraded mode of LCO 4.2.10.

I Event 5 At about 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on January 25, 1981, reactor power was increased, causing the average core outlet te=perature to exceed 1200*F at approximately 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />. Moisture out-gassing as a result of the increased core tempera-ture, caused total oxidants to exceel 10 ppm at about 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, resulting in plant operation in a degraded mcde of LCO 4.2.10.

During the time span of Event 5, there were four occasions - January 26, 1981, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />; i

January 29, 1981, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />; January 30, 1981, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> and again at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />; and January 31,1981, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />; when pri=ary coolant oxidant increases occurred during periods of essentially steady state power operatien. The cause of C:ese increases cannot be attributed to off-gassing j

fro = the core graphite.

Further investigation of these oxidant increases at steady state power level revealed that the increases followed =akeup to the pri:ary coolant inventory.

However, since there were cases where primary coolant inventory make-up had no effect on primary coolant oxidants, it would appear that the oxidant in-creases are not due to coisture in the =akeup helium. Checks of the make-up supply have confir:ed that there was no coisture in the make-up.

The other obvious source of oisture or oxidants in the primary coolant is the helius circulators which have water lubrication. It has not been pos-sible to identify a echanism by which the addition of primary coolant make-up would cause the hel.lus circulators to admit moisture to the primary coolant, but in an atte=pt to reduce the p abability of this source, the dif-ferential pressure between reactor pressure and buffer helium was increased and the main drain controllers on two helium circulators were recalibrated.

Since these changes were made, there have been fewer indications of coisture l

_ ingress into the pri=ary coolant.

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REPORTABLE OCCURRENCE 31-009 ISSUE O Page 4 of 8 CO RRECT!'IE ACTION:

Event 1 Average core outlet te=perature was reduced belcw 1200*F, =aking LCO 4.2.10 not applicable.

Event 2 At the reduced average core outlet te=perature achieved due to i' vent 1, the pri=aty coolant purification syste= was able to re=ove the = ore slowly out-gassing =oisture.

The pri=ary coolant dewpoint dropped below the limit of LCO 4.2.11 when suf ficient =ois ture had been re=oved.

Event 3 Average core outlet te=perature was reduced below 1200*F, =aking LCO 4.2.10 not applicable.

Event i Average core outlet te=perature was reduced below 1200* F, =aking LCO 4.2.10 not applicable.

Event 5 Average core outlet te=perature was reduced below 1200*F, =aking LCO 4.2.10 not applicable.

No further corrective acticn is anticipated or required for the five events listed in this report.

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REPORTABLE OCCL"L'tCICE S1-009 ISSUE O Page 6 of 8 4

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2 REPORTA3LE OCCURRENCE 81-009 ISSUE O Page 8 of 8 J

l Prepared By:

4-

' k., A.C 4

Richard R.

Frost Technical Services Technician Reviewed 3y-d.

M _*-,6

, j J. *d. Gahn f

TechnicaY Services Supervisor M

Reviewed 3y:

Franic M. Mathie Operations Manager Approved 3y:

b Atenc - cu.4.W Don '4arer. bourg 7'

l Manager, Nuclear Production i

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