05000267/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl

From kanterella
(Redirected from 05000267/LER-1982-017)
Jump to navigation Jump to search
Forwards LER 82-017/03L-0.Detailed Event Analysis Encl
ML20054E305
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/03/1982
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20054E306 List:
References
P-82178, NUDOCS 8206110050
Download: ML20054E305 (6)
v • d • e


LER-2082-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
2672082017R00 - NRC Website
v • d • e

text

{{#Wiki_filter:w Public service company ceechado 4 16805 Road 19 1/2, Platteville, Colorado 80651-9298 l i l June 3, 1982 Fort St. Vrain { Unit No. 1 l ([]-[]\y/_[ t q; [J 'j P-82'.78 1 f i JUN 81982 l,I f}l L L Mr. John T. Collins, Regional Administrator -- Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 . Arlington, Texas 76011

Reference:

Facility Operating License No.-DPR-34 Docket No. 50-267

Dear Mr. Collins:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-017, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2. Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/82-017.

Very truly yours, Y

Don Warembourg

Manager, Nuclear Production DW/cis Enclosure i

cc: Director, MIPC k l 8206110050 820603 h PDR ADOCK 05000267 S PDR I L 

                                                       +

REPORT DATE: June-3. 1982 REPORTABLE OCCURRENCE S2-017 ISSUE O OCCURRENCE DATE: May 12. 1982 ~Page 1 of 5 l FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLCRADO. 30651-9293 REPORT NO. 50-267/S2-017/03-L-0 Final IDENTIFICATION OF OCCURRENCE: Ouring the pericd May 12, 1982, to May 25, 1982,-with the reactor at power operation, the plant was operated in a degraded mode of LC0 ?.2.10 on two separate occasions. These events are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2. EVENT OESCRIPITCN: Event #1 At 1713 hours on May. 12, 1982, an increase.in reactor power from 40% power caused the average core outlet temperature to increase above 1200 F. Primary coolant chemistry results indicated ~ 0 ppm' CO, 18.0 ppm CO 2 , and 4.6 ppm H2 0, equaling 22.6-ppm total oxidants. This degraded made of LCO 4.2.10 continued until _1630 hours, May 13, 1982, when reactor power was reduced, and the . average core outlet temperature decreased be"ow the 1200 F limit of LCO 4.2.10. (See Table 1) Event #2 An increase in reactor power from 50% power caused the average core outlet temperature to' increase above 1200*F with total primary coolant oxidants - greater than 10 ppm. -This degraded mode of LCO 4.2.10 commenced at 0323 hours on May 19, 1982, and continued until 0820 hours on *.ay 25, 1982, when total primary coolant _ oxidants were reduced below the 10 ppm limit. During this period, the maximum level of total oxidants reached was approximately 73.3 ppm at 0400 hours on May 20, 1982. (See Table 1)-

REPORTABLE OCCURRENCE S2-017 ISSUE O page 2 of 5 CAUSE DESCRIPTION: The reactor -plant had been in a shutdown or low power operating condition over a five month period for a major system modification outage. During this period, the prestressed concrete reactor vessel had been at subatmospheric pressure several times for various activites. These conditions allowed for a gradual buildup of oxidants witnin the primary coolant and adsorption into the core graphite. Subsequent operation caused-off gassing of the moisture and other oxidants from the core graphite and insulating boundaries, which resulted in the two events. CORRECTIVE ACTION: Event #1 A reduction of reactor power and temperature made LCO 4.2.10 no longer applicable. The average core outlet temperature was decreased below 1200 F at 1630. hours on May 13, 1982. Event #2 Normal operation of the primary coolant purification system was_used to reduce total primary coolant oxidants below 10 ppm. At 0820 hours on May 25, 1992, total oxidants equalled 8.5 ppm. 

                                                                               .. b

. ' REPORTABLE OCCURRENCE S2-017 4 ISSUE O Page 3 of-5 TABLE 1 l l- l Average Corel 7otal 0xicants l 1 _ 10utlet Temp-IParts Per Million l Degraded Mode of i l l l 1 l Date ITimet erature ( F)! (com) l LCO 4.2.10 l

I I I I I I i 1----------------------------Event #1---------------------------I

! I I I I I i l5-12-8211713l >1200 l 22.6 l Yes .l~ l l l 1 I I +- 15-13-82100001 1323 1 42.8 I Yes I

l. I I I I I l 102001 1324 l 71.8 I Yes l l

I I I i l .I l 10400l 1320 I 98.7 I- Yes -l

I I I I I I

! l 106001 1310 l 102.7 [ Yes l 1 I I I I I , i 10S001 1313 1 103.2 l .Yes [

1 I I I I I l 114001 1293 l 109.5 l Yes 1.

l l 1 I I I i 116001 1214 l 95.4 I Yes [

I l 1 1 I I 4
        ,                   1         11630l                          <1200          I   LCO 4.2.10 No              I                     No           1 2

l l l l Longer Applicable l l I  ! I I .I I j________ _______________----Event #2---------------------------I I l l I l l

15-19-82l08201 >1200 1 15.0 l Yes I-i l I I I i 'l i [ 11200l 1252 1 17.5 l- Yes I i i l i I I l l

l 11600l 1240 1 -30.5 l Yes l l 1 1 I I I I [20001 1386 l 53.7 l Yes [ I I I I I I l5-20-82100001 1384 1 67.5 l Yes I l^ l I i I i I l 10400l 1384 l 73.3 I Yes l

I I I I I I l 106001 1393 I 72.5 l Yes l l 1 I I I I l l 108001 1395 l 72.5 l Yes l t I I I i i i l 11600l 1416 l 56.8 l Yes l I I I I I I i 12000! 1415 I 56.0 l Yes l i

l I

1 , 

 -{

4 f . REPORTABLE CCCURRENCE 82-017 ISSUE O , Page a of.5 TABLE 1 (Cont'd) I l l Average Corel Total 0xidants I 1 I i 10utlet Temp-IPar:s Per Million-1 Degraded Mode _of 1 i i Date ! Time!erature ( F)I (com) -l LCO 4.2.10 l

1 I l- I l l
;                         15-21-82100001_                   1409                I                    51.4             I                        Yes                  l I                  I        I                         I                                     I                                             l-i                         l                  104001         1393                1                    39.2             1.                       Yes                  I i                          l                  i        i                         l                                     I                                             l-l                          1               -108001           1394                l                    36.6             I                        Yes                  l I                  I        I                         I                                     l                          -                  I

, i 116001 1398 l _29.8 l Yes. I l i i 1 I I I i 15-22-82100001 1397 I 23.5 l Yes- l l l l 1 l 1 l l04001 1395 l 23.0 I Yes l l l l l 1 1 1 114001 1394 1 20.8. l Yes I i i i l I . -l I 

!                          l                 118001         1395-               l                    18.4             l                        Yes                  1
                                    '                                                                                                                               1.

I I I i l J 15-23-82100001 1392 -1 20.6 I Yes l 1 I I I I I 1 110001 1393 l 15.3 I Yes  ! I I I I I I l 118001 1388 l 13.0 _I Yes l l 1 l l I I I i 15-24-82100001 1382 1 14.3 I Yes 1 I I I I I I l 108001 1370 l 11.3 I Yes. l 

;                          i                 i        l                         l                                      I                                            1
.                          l                 l18001         1391                1                    11.7              l                       Yes                 -l I                 l        l                         I                                      i                                            l 3'                          l5-25-82l00001                   1391                1                    11.8              I                       Yes                  [

i i l I i 'l l l 16820f 1391 1 8.5 l No l-4 l i

t

. i 

    ,,           -     , _    . .         , . . _ , ,                - __ _ . .       . _ . - , ~         -.             - - _ _ . . , . , _ - _ _ - - _ - . _ .        -

     -.         .           _- _ = - - - -                .           -                         -      -- ..                  -_ - -- --                      -.    . _ . ._          . ..          -_ _           - -

d REPCRTABLE OCCURRENCE 81-017 ISSUE O Page 5 of 5 i t ' Prepared By: 22 % . bD .b_m Owen J. Q ton ~Q j Technical services Fechnician Reviewed By: f /1.4 Charles Fuller Technical Services Engineering Supervisor Reviewed By: _Edwi n O! Mil lo '* ~ 

                                                                                                             '/

l Station Manager i i 4 ! Approved By: _ W,a m_ M l Don Waremoourg Manager,NuclearProduct[ ion 4 l h i 4 1 r 

 - - - -     y e e - w w.      __.cy.w,-r.-.ye.     , e.,   .. ,e,,r-       , - - - - - . , - - - -           c-    ,-r    --             . - - _ . - . .- .     ,,     ,     ..---.e      -- * * ~      .-%.- r---m- 1

}}

Retrieved from "https://kanterella.com/w/index.php?title=05000267/LER-1982-017,_Forwards_LER_82-017/03L-0.Detailed_Event_Analysis_Encl&oldid=2628270"