ML20205P565

Monthly Operating Rept for Apr 1986

ML20205P565
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1986
From:	Gahm J, Novacheck F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86364, NUDOCS 8605210460
Download: ML20205P565 (9)

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PUBLIC SERVICE COMPANY OF COLORADO

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FORT ST. VRAIN NUCLEAR GENERATING STATION 1

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MONTHLY OPERATIONS REPORT I NO. 147 April, 1986

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. I O f This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34. This report is for the month of April, 1986.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY

.i RELATE 6 MAINTENANCE The month of April started with the reactor critical, in a rise to power process for primary coolant cleanup.

On April 2, 1986, the reactor and steam generators were taken through boilout. During the early morning of April 3, 1986, a major snow storm developed and the ensuing voltage upsets and system disturbances caused several problems. Several oil circuit breakers tripped open on dif ferent occasions during the morning of April 3, and at 1042 hours0.0121 days <br />0.289 hours <br />0.00172 weeks <br />3.96481e-4 months <br />, Loop 2 automatically shutdown and "B" helium purification train isolated. Management directed a manual scram of the reactor. Following the manual reactor scram, an unplanned radiological gaseous release occurred due to a suspected leak in one of the four helium circulator shutdown seals. The leak was secured, and dose calculations determined

<- that the release was approximately 3000 times less than the allcwable Permissible Concentration (MPC) at the U Maximum Exclusion Area Boundary (EAB). All significant events associated with the snow storm and manual reactor scram will be reported to the Nuclear Regulatory Commission in Licensee Event Report #86-017.

The reactor was again taken critical on April 6,1986, at 1904 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.24472e-4 months <br />. Steam generator boilout was accomplished on April 8, 1986. The main turbine / generator was rolled on April 11, 1986, at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br /> and synchronized to the grid at 1443 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.490615e-4 months <br />. The turbine tripped at 1511 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.749355e-4 months <br /> due to a faulty stop valve load control amplifier. After the amplifier was replaced, the turbine / generator was again synchronized on April 12, 1986, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, but was manually taken off at 0812 hours0.0094 days <br />0.226 hours <br />0.00134 weeks <br />3.08966e-4 months <br /> to tune the

- hot reheat intercept valves bias control. The turbine / generator was resynchronized at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />.

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On April 22, 1986, at 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br />, the turbine / generator was taken off line to repair a servo on #2 Main Steam Stop Valve and replace filters. The turbine / generator was resynchronized at 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br />.

On April 24, 1986, at 1337 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.087285e-4 months <br />, the turbine / generator tripped j on low electro-hydraulic control (EHC) pressure due to a leaking i

pressure sensing line. The sensing line was repaired and the turbine / generator was resynchronized at 1426 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.42593e-4 months <br />.

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i On April 25, 1986, at 0112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />, the turbine / generator was taken off line to investigate electro-hydraulic-control problems. The turbine / generator was resynchronized at 1641 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.244005e-4 months <br />.

On April 27, 1986, at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />, the reactor automatically scrammed due to a Reactor Pressure Low scram signal received on Plant Protective System (PPS) channel B while Results I/C personnel w5re testing High and Low Pressure trips on PPS channel "C". At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, following the shutdown of "A" and "D" helium circulators to conserve steam, an unplanned gaseous release occurred to the reactor building from the helium circulator auxiliaries. Although the maximum concentration of this release was 0.25 MPC, less than that required to be reported under 10CFR50.72, this event was reported to the Nuclear Regulatory Comi.ission as a courtesy call at 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br />. The reactor was again taken critical on April 28, 1986, at 0244 hours0.00282 days <br />0.0678 hours <br />4.034392e-4 weeks <br />9.2842e-5 months <br />. This event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report #86-018.

Steam generator boilout was accomplished on April 29, 1986, and the turbine /gererator was resynchronized at 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br />.

73 Spent fuel shipping activities were completed on April 30, 1986.

() All spent fuel has been removed from site.

2.0 SINGLE RELEAS'ES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN~ EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 _ INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MC"THLY OPERATING DATA REPORT

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, . 1. - 2 l C Top 1 or 1 i cotume to xtroc :ocrn so. 50-267

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comm my Frank J. Novachek m.traaxt (303) 785-2224, ext. 201 4

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1.  : nit ra: Fort St. Vrain, No. 1

2. reporting rertoe: 860401 through 860430

3. ucensee ser_si ruer (Wc): 842 f 4. Kareplate rating (Cress We): 342

5.  !+ sign Cectrical 7.ating (!;et We): 330

6. ari:m depeneatle Catacity (Cress We): _ 342 f

f 7. Pari:r.:= r.e;eneable capacity 0:et We): 330 i

! 8. Ir Chr.:ges 0:cc: is capacity ratings (Ite s Nu:bar 3 nrough 7) Since last Feport. Cive Reasons:

None.

1 j s. 7:..: teve: := .uch testrictee. tr x=7 c:e: We): 115.5 f :c. rusces for ras ::c:f ens. re Asy: Limited to 35% power pending completion of Environmental Qualification work.

B is N th Taar to tate Cu=uletive

n. sars to ze;cr:::s rertoe 719.0 2,879.0 59,904.0

n. ==ter or so. :s raectc r was critte.1 623.1 1,713.6 29,794.8

u. nact:r tesme rtu:ee , sours 0.0 0.0 0 '. 0

n. se es c< n e ra tc r e_-:.tn e 379.5 379.5 18,847.5

15. t=1t r e se : .e snu:or., sours 0.0 0.0 0.0

16. cress ner a: ::ern centratee ( m ) 137,250.5 182,985.1 10,078,068.3

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17. cress nec:.:cai :=e r y cener,:ee (m) 30,177.C 30,177.0 3,278,771.0

a. re: n e:trica: ::e ro cenera:ee (m) 25,762.0 15,618.0 2,911,891.0

s. ::asehecerac:or . 52.8 13.2 3bi s_

20. rai: Avat:aun ty rac tor 52.8 13.2 31.5_

n. rnit careci:7 ra::or (rst=s tcc set) 10.9_ l.6 L4,Z.

n.  :=tt caracity ract:r (trirs ett set) 10.9 1.6 1.4m7.

t i n. rate rcrcee oute rate 47_. 2.

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l :s. sh te:-:s scseeu:e4 over sex: 6 m n ti.. (rn e. care, aae nu:stion or ra:5): __ Environmental ._,

Qualification work May 31,1986, 2016 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.67088e-4 months <br />.

3. . ' r a c <., a t :- ce reper: rertoe. rsti-aree :4te or 5:ar:up: N/A

6. U 'ts In Test 5:e:2.s (T rie r to Co- e re f al Ope ra:f cn): rc:erast Achievee 1s: w1. : n u cn.1n N/A NJA rst mr. raca:cta N/A N/A .

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Issue 2 A\T. PACE DAILY UNIT POWER LEVEL Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain, No.1 Date f May 13. 1986 coepleted By Frank J. Novachek Telephone (303) 785-2224 ext. 201

>bnth April , 1986 EAY A\~.? AGE DAILY POWER LEVEL DAY AVEPAGE DAILY Poh'ER LEV 1

(!Ce-Net) (!Ge-Net) 1 0.0 17 66.0 O.0 13 69.8 2

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! 3 0,0 19 78.6 4 0.0 20 80.0 5 0.0 21 _

78.7 .

6 0J 22 62.0 7 0.0 23 84.4 8 0.0 24 80.1 9 0.0 25 17.7 10 0.0 26 81.7 11 0.0* 27 32.6 12 35.1 _ 28 0.0 13 65.0 29 21_.9

^^ 14 67,8 30 80.0 15 66.5 31 N/A 16 74.1

^Ganera tcr on line but no net generation.

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At3D l'UWER MCIU.C.'l.u, tin ~~

rar a ..r i i = >c T no. 50-267 urnT Mane. Fort St. Vrain, No. I nATE May 13. 1986 cornr. Ten av Frank J. Novachek i nr.rvar noNni April! 1986 Tei.cruoNs (303) 785-2224. ext. 201._,

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• 8%'t3 5757078 COIP'Oi3CNT l t 0, DATE TYrc DURATION . RTA50N REACTOR I.ER I CUllC CODC CAL"it AND CORRECTIVE ACTION 'IU PREVENT RECURAT.NCE l

86-01 860403 F 80.4 hrs. A 2 86-017 EC 37 Scram as a result of severe weather conditions.

l l 86-02 860427 F 13.6 hrs B 3 86-018 JC 63 Spurious scram signal during testing.

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REFUELING INFORMATION l l l l~1. Name of' Facility l Fort St. Vrain Unit No. 1 l l l 1 l 2. Scheduled date for next l l l refueling shutdown. I March 1, 1988 l 1 I I I 3. Scheduled date for restart l June 1, 1988 'l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l l operation thereafter require a l l l technical specification change l l l or other license amendment? l l l l l l If answer is yes, what, in 1 ---------------- l l general, will these be? l l l l l l If answer is no, has the reload l l l fuel design and core configura-l 1 l tion been reviewed by your l l-l Plant Safety Review Committee l No l l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reloadj l l (Reference 10 CFR Section l l l 50.59)? l l l l l l If no such review has taken l 1986 l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l ,

i l ting proposed licensing action l ---------------- l l and supporting information. l l l l l l 6. Important licensing considera -l -l l tions associated with refuel- l l l ing, e.g., new or different l l l fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant l l l changes in fuel design, new l l l operating procedures. l l l 1 l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. l b) 0 spent fuel elements l j l

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'- REFUELING _MFORPif 0N (CONTINUE 0)

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1 - . l l l 8. The present licensed spent fuell,..- -

l l pool storage capacity and the .l . l l size of any increase in ,1 Capacity is limited in size to l l licersed storage capacity that l tbout one-third of core l l has been requested or is l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. I l l l l l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l refueling that can be dis- l and DE-SC07-791001370 between l l charged to the spent fuel pool l Public Service Company of l l assuming the present licensed l Coloradu, and General Atomic l l capacity. l Company, and DOE.* l

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• lh 1992 estimated date is based on the understanding that spent fuel discharged during,the term of the Agreements will be stored by DOE at

. the Idaho Chemical, Processing Plant. The storage capacity has evidently,been sizeo to accommodate eight fuel segments. It is estinJa.ted that th& eighth fuel segment will be discharged in 1992.

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16805 WCR 19 1/2, Platteville, Colorado 80651 May 15, 1986 Fort St. Vrain Unit No. 1 P-86364 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Monthly Operations Report For April, 1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of April, 1986.

If you have any questions, please contact Mr. Mike Holmes at (303) 480-6960.

Sincerely, ll J. [h f -

Gahm Manager, Nuclear Product. ion Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. R. D. Martin, Regional Administrator, Region IV JWG:djm ff,W

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