ML19323A488

Monthly Operating Rept for Mar 1980

ML19323A488
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/02/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19323A487	List: ML19323A486 ML19323A488
References
NUDOCS 8004210271
Download: ML19323A488 (6)

Text

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9 M)NTHLY OPERATING INFORMATION DISTRIBt: TION Number of Cooies Di r e c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 0 (Original of P ;.,etter)

Of fice of Inspection and Enfortement U. S. Nuclear Regulatory Comission Washington, D.C. 20555 Karl V. Saffrit. Director ---------------------------- 1 (P Letter)

Region IV Office of Inspection and Enforcement Nuclear Regulatory Comission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Di r e c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2 OP Letter)

Of fice of Man .gement Information and Program Control U. S. Nucles. Regulatory Comission Washington, D.C. 20555 Ted Cintu'.a ----------------------------------- 1 (P Letter)

U. S. Nur. lear Regulatory Comission 12105 Nicional Maryland Bank Building WashinF:on, D.C. 20555 W. Bus inell, Site Manager ---------------------------- 1 (P Letter)

General Atomic Company P. O. Box 426 Platteville, Colorado 80651 NRC Resident Site Inspector --------------------------- 1 (P Letter)

Senior Vice President, Room 770 ------------------------- 1 (P Letter)

Vice President. Electrical Engineering and Planning 39th Avenue - - - - - - - - - 1 (P Letter)

" ice President, P roduction Divis ion, 3elleviev - - - - - - . - - - - - - - - - - - 1 (P Letter)

Quality Assurance Manager ---------------------------- 1 (P Letter)

S i t e En ginee ring Coo rdina to r - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Nucle ar P roj ect Manage r, 2n tballo - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Cary Reeves Public Relations, Room 950 --------------------- 1 (original of Memo)

Bill Shinkle, Property Accounting Holly Service Center ------------- 1 (Original of Memo)

Richard A. Petzke, Nuclear Project Department, Montballo - - - - - - - - - - - - - 1 (Original of Memo)

Supervisor, Licensing and Administrative Services, Nuclear Proj ect Department, &ntballo - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Supervisor, Project Engineering Nuclear Project Department, Montballo - - - - - - 1 (P Letter)

Documents Control Technician. Montballo --------------------- 2 (2 P Letters)

Correspondence Coordinator, Nuclear Project Department Montballo -------- 1 (P Letter)

N uclea r P roductio n Mana ge r - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Op e ra tions Mana ge r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Administrative Services Manager ------------------------- 1 (P Letter)

PO RC Co mmi t t e e - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

PFiles------------------------------------- 1 (P Letter)

Re c o rd S t o ra ge - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2 (P Letter)

Technical Services Review ---------------------------- 1 (P Letter)

Ta chnical Services Re fe rence No tebooka - - - - - - - - - - - - - - - - - - - - - - 1 Monthly Ope ratione Report Folder - - - - - - - - - - - - - = * - - - - - - - - - - 1 Monthly Ope rating In formation File - - - - - - - - - - - - - - - - - - - - - - - - 0 (Original of Report and 1 Copy of P Letter)

Cas Coole d Re ac to r As s ocia te s- - = = = = - - - - - - - - - - - - - - - - - - - -

• 1 (P Letter)

Attention: Mr. Dan Yueh 3344 Nortti Torrey Pines Court Suite 200 LaJolla, California 92037 Electric Powe r Research Ins titute- - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Attention: Mr. Melsin E. Lapides 3412 Hillview Avenue P. O. Box 10412 Palo Alto, California 94303 421 og y

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OPEEA M C DA n REPORT DOCKET so. 50-267 ,

DATz 800402 coMPI.rrED sr J. W. Gahm  ;

TEz.ErnonE (303) 785-2253 i OPERA M C S U TUS soTEs

1. cnic Name: Fort St. Vrain #1

2. Raporting Period: 800301 through 800331

3. t.icensed Thermal Power Oest): 842 ,

4. Nameplate Rating (Cross We): 342 I

5. Design Electrical Rating (pet We): 330

6. %d== Dependable Capecity (Grese We): 342

7. .*e== Dependable capacity Clet We): 330 '

S. If Changes occur in Capacity Ratings (Items Nder 3 Through 7) Since I.ast Report. Give Raasons:

None _

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9. Power Level To 'Jhich Restricted If Any (Net We): 231

10. Raasons for Restrictions If Any: Nuclear Regulatory Commission restriction 70% pending  :

t resolution of temperature fluctuations.

l This Month Year to Data C attative

11. sours in Reportins Period 744 2,184 ,

6,601

12. sumber of sours Raaetor was critical 676.1 363.'s 3,396.7*

13. Rasetor Reserve Shutdown Hours 0.0 0.0 0.0 t

14. sours cenarator on-t.ine 358.0 358.0 1,340.2  ;

15. enic Reserve Shutdown soure 0.0 0.0 0.0

16. Cross Thermal Energy Generated (WE) 157,856 161.149 639,104 ,

17. Gross Electrical Energy Canarated 084) 48.427 48,427 189,223

18. Net Electrical Energy censrated Osm) 43.047 43,047 166,631

19. enit Service Factor 48.1 16.4 20.3

20. unic Availability ractor 48.1 16.4 20.3

21. Unit capacity ractor (Using MDC Net) 17.5 __

6.0 7.6 _

22. cnit capacier ractor (Using DER set) 17.5 6.0 7.6 ,

23. Unit Forced Outage Rate 51.6 51.6 62.3 l

24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each): N/A

25. If Shut Down at End of Report Period. Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation): Forecas t Achieved INI H AL C1 m CAI.ITT N/A N/A INITIAI. EE. ECTR.Icr:T N/A N/A COMERCIAI. CPERATION N/A N/A

• This, number is_co_rre_CCdbe Jantm7 H ?"re 4" J.ina 12 -should h:;c cad 20.2 inncad of- 36.0.'

r i UNIT SturtIxA'NS O*4D POWER llElsUC1DNS

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tocxET No. 50-267 ,

UNIT NAME Fort St. Vrain #1 DAs 800402 COMPU.fY.D BY J. W. Gahm  ; l REPORT HONns March, 1980 TEt.EPuONE (303) 785-2253 j

i j HED10D OF ,

SuuTTING DOWN SYSTEH COW ONENT I NO. DATE TYPE IMIRATION REASON REACTOR I.ER f CODF 0)DE CAllSE AND CORRECTIVE ACTION 10 PREVENT ilECURRENCE 79-14 791026 S 98.8 B 2 N/A N/A___ N/A__ Scheduled shutdown continued for replacement of ruptured static seal.

Refer to LER 80-001/01-T-0. Generator put on line 3-5-80.

80-01 800306 S 4.15 B N/A N/A N/A N/A Turbine over-speed trip test.

80-02 800311 F 123.8 A 2 N/A N/A N/A Circulating water system 41 shut down due to tower problems.

i 80-03 800321 F 56.8 A 3 N/A N/A N/A Reactor scrammed due to instrument problems.

80-04 800324 F 49.25 A 2 N/A N/A N/A Loss of condenser vacuum.

80-05 800328 F 53.2 A N/A N/A N/A N/A 1A circulator trip and system upset. ,

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l SLRIMARY ; Plan to continue operations at 70% power. j

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AVERAGE DAILY UNIT POWER LEVEL l Docket No. 50-267 Unit Fort St. Vrain #1 i Date 800402 Completed By J. W. Gahm j i

Telephone (303) 785-2253 l Month March, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(HWe-Net) (MWe-Net)  !

I 1 0 17 124 l 2 0 18 213 f I

i 3 0 19 217 l

4 0 20 207  ;

l 5 45 21 129 i

6 66 22 0 f

7- 94 23 0 ,

i 8 87 24 0 l 9 92 25 0 j i

10 , 132 26 83 l l

l 11 16 27 151  !

12 0 28 47 ,

l 13 0 29 0 l

i 14 0 30 23 l

15 0 127 31 16 33 i

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• Generator on line but no ' net generation,  !

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REFUELING INFORMATION

l. Name of Facility. Fort St. Vrain, Unit No. 1

2. Scheduled date for next refueling i shutdown. January 1, 1981

3. Scheduled date for restart following refueling. March 1, 1981

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 will fuel design and core configura- review any questions associated with the tion been reviewed by your Plant 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 takan place, when is it scheduled? July 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 performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The number of fuel assemblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage pool. b) 244 spent HTGR fuel elements.

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

storage capacity that has been t

requested or is planned, in number of fuel assemblies.

9 REFUELING INFORMATION (CONTINUED) l t

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9. The projected date of the 1986 under the Three Party Agreement (Con- l 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 capacity.

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• 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 Cant (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.

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