ML19257D420

Monthly Operating Rept for Dec 1979

ML19257D420
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/03/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19257D418	List: ML19257D417 ML19257D420
References
NUDOCS 8002040351
Download: ML19257D420 (9)

Text

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l J r PfTMLY CP! RATIONS REPORT DISTRI3t' TION ud Number of Copies Depa rtmen t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

San Francisco Operations Office Attn: California Patent Group 1333 Broadway Oakland, California 94612 Dep artment o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Lattar)

Office of Nuclear Engineering Programe Washington, D.C. 20545 Dep artment o f Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Nuclear Rasetor Programs Branch Nuclear Power Development Division Mail Stop P309 Washington, D.C. 20545 Dep artmen t o f Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Attna Senior Program Coordinator P. O. Box 81325 San Diego, California 92138 Depa rtment o f Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (? Letter)

Technical Information Cantar P. O. Box 62 Oak Ridge. Tennesses 37830 Direc to r o f Nuclea r Reactor Re gula tio n - - - - - - - - - - - - - - - - - - - - - - 1 (Original P Latter)

Attus Vf 114 == P . ("===111, Chie f Operating Raaetors Safequard Branch ,

Division of Operating Raactors -

U. 5. Nuclear Regulatory Commission Washington, D.C. 20555 Philadelphia Electric Company -------------------------- 1 Attnr 1 of. Cooney .

2301 Market Street Philadelphia, Pennsylvania 18101 Prench Fmhaggy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 Attna Mrs. Duberney 1730 Rhode Island Avenue, NW Suite 1217 Washington, D.C. 20036 Colorado Department of Health -------------------------- 1 (P Latter)

Attn Al Estal 4210 East lith Avenue Denver, Colorado 80220

7. E Hawkins, Site Manager ---------------------------10 (Original of FPLG plus General Atomic Cocyany 2 copies of IPLC plus P. O. Box 426 1 copy of P Latter)

Platteville, Colorado 80651 NIC Easident Site Inspector --------------------------- 1 (P Letter) 1865 177 '

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 72 DECEIGER, 1979 i 1865 178

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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 December,1979.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The Fort St. Vrcin maintenance outage, which started on October 29, 1979, and continued through the month of November, was completed on Decemb er 17, 1979, when the main condenser was returned to service.

Normal plant valve lineups were verified and the reactor was taken critical. Clean up of the primary and secondary coolant systems had started by the end of the reporting period.

1.2 Operations Primary coolant moisture levels increased following the flooding of "C" circulator bearing cartridge. This water ingress is attributed to work being done on the low pressure separator (CN-ll58, quench line).

"B" circulator would not self-turbine following an extended shutdown period. Unsuccessful attempts were made using condensate And emergency feedwater to the pelton wheel. The circulator was finally rotated by using a combination of increased bearing water flow while applying emergency feedwater to the pelton wheel.

The reactor was taken critical on December 25, 1979, and power held at approximately 1.5% for primary and secondary coolant system clean-up. A reactor scram and Loop 2 shutdown occurred on December 30, 1979, following the operation of "C" circulator at speed. High moisture levels are attributed to the ingress which occurred on December 7, 1979. Following this shutdown, maintenance on two major Loop 2 com-ponents was started. (DN - leakage on V-2256 and oil supply flange leakage on HV-2254).

1.3 Testing Circulator speed / wobble connectors underwent environmennal testing at Wylie Labs in California.

PCRV liner corrosion Surveillance Test was completed.

PCRV rupture disc and safety valve testing was successfully completed.

"A" diesel generator semi-annual inspection was successfully cocpleted with the surge protector damage and subsequent repairs completed as noted in Section 1.4 on the following page. .

1865 179'

1. 0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR S AFETY RELATED MAINTENANCE (Cont'd)

1. 4 Major Equipment Problems "A" diesel generator was damaged during checkout of the unit following its semi-annual inspection. The generator was placed on line in the independent mode, but should have been placed on line in the parallel mode. The field winding surge protector was damaged and repaired, and the unit was returned to service.

Seat repairs were accomplished on HV-2215 and HV-2217 (L-I steam water dump valves). However, leak through of HV-2217 has been suspected following the establishment of feedwater flow through L-I. HV-2217 has been isolated while evaluating repairs.

A new guide collar was installed on HV-2302 ("B" purification train iso-lation valve) to prevent binding between operator and valve stem.

Manual operators were installed on HV-2301 and HV-2302 per GA-FCN-4251.

New bolts for "B" and "C" circulator steam inlet flanges were fabricated and installed. The previous bolts were rejected by PSC. Quality As-surance af ter reviewing manufacturers certification and perforaing

" pull" tests on bolts machined from identical material.

2.0 SINGLE RELEASES OF RADIOACTIVITY 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 MONTHLY OPERATING DATA REPORT Attached 1865'180-

CPERAM NG DATA REPo e x ytr so. 50-267 oATz 800103 Ce m.zTz: sf J. W. Gahm TzLzrsosz (303) 785-2253 OPERATING STATUS soTzs

1. Unit same: Fort S t. Vrain #1

2. aeporting Period: 791201 through 791231

3. Licensed Thermal Power CMt): 842

4. Nameplate Rating ($ roes We): 342

5. Design Electrical Rating Otet We): 330 fol/5)(

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6. wh= Dependable Capacity (Gross We): 342 (k .g J j@QAjh t

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7. ww== Dependable Capacity Cret We): 330

8. If Changes occur in capacity Xatings (Items Number 3 2 rough 7) since Last Report, Give Raasons:

Ncn e

9. Power Level To Which Rastricted, If Any (Net We): 231

10. tassons for aastrictions, If Any: Nuclear Regulatorv Cornission restriction (70%)

pending resolution of tec:oerature fluctuations.

This math Tsar to Date Cumulative

u. sours in asporting Period 744 4,417* 4,417*

1:. sumber of sours anactor was Critical 113 2,532.8 2,532.8

13. anaccer anserve shutdown sours 0.0 0.0 0.0

14. sours cenerator on-Line 0.0 982.2 982.2

15. Unit reserve shuedown sours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (153) 1,399.8 477,954.8 477,954.8

17. Cross Electrical Energy Generated OSE) 0.0 140,796 140,796 is. set tiectrical Energy ceanrated Osa) 0.0 123,584 123,584

19. Unit service ractor 0.0% 22.2% 22.2%

20. Unit Availability rector 0.0% 22.2% 22.2%

21. Unit Capacity ractor (Using ifDc set) 0.0% 8.5% 8.5%

22. cnic Capacity rsetor (using DER Net) 0.0% 8.5% 8.5%

3. cnic rareed outage zace 0.0% 65.1% 65.1%

4. shutdowns scheduled over Next 6 maths (Trpe. Data, and Duration of Each): Maintenance shutdown began October 26, 1979. It was comoleted on December 24, 1979. .

25. If Shut Down at End of Raport Period. Estimated Date of startup: 1 O [ b-ivvs Ikl

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26. Units In Test status (Prior to Comercial operation): Forecast Achieved INITIAL C1ITICALITT INITIAL ELECTRICHT COLafE1CIAL CPERATION

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort S t. Vrain Unit #1 Date 800103 Completed By J. W. Gahm Telephone (303) 785-2253 Month December, 1979 DAY AVERAGE DAILY POWER L~t.T. EL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 0 17 0 2 18 3 19 4 20 s

5 21 6 22 7 23 8 24

.9 25 10 26.

11 27 12 28-13 29 _

14 30

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15 31 sf 16 x-i865183

REFUELING INFORMATION

1. Name of Facility. Fcrt S t. Vrain, Unit No. 1

2. Scheduled date for next refueling shutdown. Septenber 1, 1980

3. Scheduled date for restart following refueling. November 1, 1980

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No If answer is yes, what, 'in general, will these be?

If answer is no, has the reload The Plant Operations Review Committee fuel design and core configura- will review any questions associated tion been reviewed by your Plant with the core reload.

Safety Review Committee to deter-mine whether any unreviewed '

safety questions are associated with the core reload (Reference . -

10CFR Section 50.59)?

If no such review has taken olace, when is it scheduled? March 1, 1980

5. Scheduled date(s) for submitting --

proposed licensing action and supporting information.

6. Important licensing considera- -

tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The nu=ber of fuel asse=blies a) 1482 HTGR fuel elements.

(a) is the core and (b) in the scent fuel storage cool. b) 244 spent HTGR fuel elements.

S. Ihe present licensed spent fuel Capacity is limited in size to about one pool storage capacity and the third of core (approximately 500 ETGR size of any increase in licensed elements) . No change is planned.

storage capacity that has been requested or is planned, in nu=ber of fuel asse=blies. 1865 184

RE7UELING INFORMATION (CONTINUED)

9. Ihe projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*

licensed cacaelty.

• 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 Agree =ent. -

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[865'185

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