ML19296A462
| ML19296A462 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/21/1979 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| P-79066, NUDOCS 7903270300 | |
| Download: ML19296A462 (1) | |
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public service company oe echade P. O.
Box 361, Platteville, Colorado 80651
! arch 21, 1979 Fo r t S t. Vrain Unit No. 1 P-79066 Director of Nuclear Reactor Regulation Attn:
W. P.
Gammill, Chief Operating Reactors Safeguard Branch Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.C.
20555 REF:
Facility Operating License No. DPR-34 Docket No. 50-267
Dear Sir:
Enclosed please find our Monthly Operations Report for the conth of Feb rua ry, 1979.
Very truly yours, Don Warembourg v
Manager, Nuclear Production DW/alk I
9'g i
7903'270360 k
REFUELING INFORMATION 1.
Name of Facility.
Fo rt S t.
Vrain, Uni t No. 1 l
2.
Scheduled date for next refueling February 1,19 79 shutdown.
3.
Scheduled date for restart June 1, 19 79 following refueling.
4.
Will refueling or resu=ption of operation thereafter require a technical specification change or other license amend =ent?
Yes*
If answer is yes, what, in To facilitate insertion of eight fuel test general, will these be?
elemen ts.
If answer is no, has the reload
- NOTE:
If Technical Specification change fuel design and core configura-approval is no t received from NRC in time tion been reviewed by your Plant for refueling, then the answer to #4 is Safety Review Committee to deter-NO and the reload fuel and graphite design mine whether any unreviewed have been reviewed.
safety questions are associated with the core reload (Reference i
j 10CFR Section 30.59)?
I If no such review has taken place, when is it scheduled?
3.
Scheduled date(s) for submitting proposed licensing action and succorting information.
January 9, 1978 6.
Important licensing considera-Eight test fuel elements to allow; tions associated with refueling, e.g.,
new or different fuel de-1)
Dif feren t fuel particle design.
sign or supplier, unreviewed design or perfor=ance analysis 2)
To qualify near isotropic graphite.
methods, significant changes in fuel design, new operating pro-cedures.
i i
7.
Ihe number of fuel asse=blies a) 1482 HTGR elements.
(a) in the core and (b) in j
the scent fuel storage cool.
b) 0 in fuel storage wells.
i I
I
, 3.
Ihe present licensed spent fuel capacity is limited by size only to about l pool storage capacity and the one third of core (approximately 500 HTGR size o f any increase in licensed elements).
No change is planned.
storage capacity that has been tequested or is planned, in I
number of fuel asse=blies.
}
REFUEIING ITIORMATION (CONTINUED) 9.
The projected date of the 1986 under the Three Party Agreement last refueling that can be (Contract AT f.-3)-633) between DOE, discharged to the spent fuel Public Service Company of Colorado (PS Co ),
pool assuming the present and General Atomic Company.
- licensed capaciev.
- The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP).
The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.
AVERAGE DAILY UNIT POWER LEVEL Do cke t No. 50-267 Unit Fo rt S t.
Vrain, Unit No. 1 Date 790301 Completed By J. W.
Cahm Telephone (303) 785-2253 Month Februarv, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEs' (MWe-Net)
(MWe-Net) 1 17 17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
1.'
0 23 0
13 0
29 N/A 14 0
30 N/A 15 0
31 N/A 16 0
- Generato r on line but no net generation.
UNIT smrnxMHS AND PtMER ltELAICTONS 50-267 g,,gg y.T R). _
UNIT N.ute Fo r t St. Vrain, Unit No. I uATE 790301 Curu't.ETED BY
- 3. W. Callm kl. PORT HONTil Feb rua ry i Ei., PiiON E (303) 785-2253 f tElllOD O F S!!UTTING lxMN SYSTEH Cutu'ONENT No.
IIATE TY PE DUHAflON MEASON REACTOR I.ER I CODE Q)DE CAtlSE AND CORHECTIVE ACTION 10 l'HEVL N r RECURHENCE 79-04 790201 F
665.1 A
4 79-03/03-L-0 till PUMPXX "11" boiler feed pump developed ex-cessive gland seal leakage and was declared inoperable.
"C" boi le r feed pump had been inoperable since Janua ry 5, 1978.
LCO 4.3.2 requires two boiler feed pumps to be operable during power operation.
Controlled shutdown was begun followed by a manual scram at 2% reactor power.
Repairs to the uaed pumps are in progress.
S Uttf1A RY :
Plant shutdown for refueling and turbine generator overhaul entire nonth.
.J
L OPERArniG OCA REPO F DOCKET NO.
50-267 790301 on:
CCMPLIIID 3T J. W.
Gahm
- . PsoNz (303) 785-2253 OPmTOTC STAT'.'S NOTES 1.
Unic Name:
For t S t.
Vrain, Unit No. 1 2.
Reporting Period:
790201 to 790228 3.
Licensed Thermal Power 05(c):
842 4
Nameplace Racing (, Gross }"Je):
342 5.
Design Electrical Racing Clec Mie):
330 6.
himun Oependable Capacity (Gross >*ie):
342 7.
N1 un Dependable Capacity (Nec l'Je):
330 9.
I* Changes occur in Capacity Racings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None 9.
Power Level To '4hich Rescricted, If Any (Nec 5's):
231 10.
Reasons for Restrictions, If Any: Nuclear Regulatorv Commission restriction (707.) cending resolution of certain Final Safety Analysis Report and Technical Specification bases discrepancies.
This unit is in the oower ascension phase of startuo testing program.
This Month Year to Oace Cu:::ulative 11.
Hours in Reporting Period 672 1416 12.
Number ce aours Reaccor 'aas Critical 52.0 789.4 14,263.1 13.
Reactor Reserve Shutdown Hours 0.0 0.0 0.0 it,. aours cenerator on-Line 6.9 665.3 8,507.9 13.
Cnic Reserve Shutdown Hours 0.0 0.0 0.0 16.
cross her=al Inergr enerated ( <a) 2,481 313,069 3,516,067 c
17 cross slee:rical tnergy Generaced (sa) 546 100 052 1,058,122 13.
Nec Electrical Inergy cenerated (>";a) 0 101,177 952,628 U.
Unic 3ervice Factor N/A N/A N/A 20.
Unic Availability Taccor N/A N/A N/A 21.
Unit Capacity Faccor (Using MDC Net)
N/A N/A N/A 22.
Unic Capacity Taccor (Using DER Nec)
N/A N/A N/A N/A N/A N/A 23.
Onic Forced Outage Race 2a.
Shutdowns 3cheduled Over Nex: 6 Months (? pe, Date, and Duracion of Iacn):
f Ref uelin s:, 2-1-79, 4 Months 25.
- f 3huc Oown Ac End 3f Repor: ?eriod. Iac1: aced Oate 3f 3 tar:no:
6-1-79
- 3.
Unics *n Tes: 5tatus (?-tor :o Oc==ercial :ceracian) :
Foracas;;
Acn:.eved 740201 740131 n:=u. c2n: CAL:
DU PW C;I!*.U. ILIC"*2IC:~"
7612 7A1211 I
q cio'5 iM D 00}?.E10!.U. CPEEA!!CN
. 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL V2EUE None
- 3. 0 INDICATIONS OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5
s
- This report contains the highlights of the Fort S t.
Vrain, Unit No. 1 acti-vities, operated under the provisions of the Nuclear Regulatory Commission Operating License, DPR.-34.
This report is for the month of February,1979, 1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor was shutdown for refueling on February 8,1979, af ter all required practice starts by licensed personnel and license candidates were completed. Shutdown had previously been scheduled for March 1, 1979, but due to boiler feed pump problems which could not be repaired in time to permit any significant power operation prior to March 1, 1979, the decision was made to s tart the refueling shutdown early.
Helium circulator C-2103 (C) which had been scheduled for removal for inspection, was removed on February 28, 1979.
The spare circulator is presently being prepared for installation.
The main turbine generator overhaul was started on March 5,1979, as scheduled and is to be complete by May 4,1979.
General Electric Company is the prime contractor for the job with three erectors on site at this time.
Primary coolant circulation is being maintained by one water turbine driven circulator.
Motive force is the condensate header through the condensate / firewater booster pumps. Several tests have been run to veri-fy proper core cooling under these conditions which have proven satisfac-tory cooling can be achieved with this mode of operation.
Use of the motor driven feed pump for water turbine motive force would have been necessary prior to the addition of the condensate / firewater booster pumps.
Decay heat removal is by the secondary coolant via the decay heat ex-changer. Secondary coolant flow is limited to Loop 1 at this time as Loop 2 is shutdown and isolated for maintenance.
The main condenser has been cleared out and drained in preparation for the main turbine generator overhaul. Eddy current testing and acid cleaning of the condenser tubes will be done while it is out of service.
Installation of the additional temporary auxiliary boiler is complete with testing in progress at this time that will allow placing the new boiler into service.
This should be accomplished by March 9,1979.
Fuel loading has been continually hampered by problems encountered with the fuel handling equipment, particularly the fuel handling machine it-self.
At this time, we have completed removal of the fuel and required reflectors f rom region 35.
Tests, RT-520 (Region Cons traint Devices),
RT-518 (Region 35 Inspection), and RT-518B (Region 35 Reflector Block Graphite Specimen), have also been completed in conjunction with Refueling Procedure RF-1.
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION FDNTHLY OPERATIONS REPORT NO. 62 FEBRUARY, 1979 s
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