ML19263C361

Monthly Operating Rept for Jan 1979

ML19263C361
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
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ML19263C354	List: ML19263C353 ML19263C361
References
NUDOCS 7902220037
Download: ML19263C361 (7)

Text

.o PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION

'ONTHLY OPERATIONS REPORT NO. 61 JANUARY , 1979 i

7902220637

e This report contains the highlights of the Fort St. 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 January,1979, 1.0 NARRATIVE SL? NARY OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The "D" helium circulator experienced another unplanned trip on Janu-ary 2, 1979. Four plant protective system logic chips were found to be failed af ter this trip. These chips had been tested to be functional the previous day. The plant was returned to 64% reactor power (200 MWe) on January 4,1979, following cleanup of the primary system helium.

Later on January 4,1979, the primary coolant moisture levels increased because of a valve failure in the circulator buf fer helium dryer system.

Due to the primary coolant oxidant impurity level exceeding 10 ppm the reactor power level was reduced to 30% of rated.

The reactor power level was increased as the helium impurity levels al-lowed and reached 60% of rated (190 MNe) on January 7,1979. On Janu-ary 5,1979, the "C" boiler feed pump was taken of f line due to high vi-b ra tion. The pump casing was found to be erroded and the plant will be limited to about 195 MNe during the eight weeks estimated to repair the pump.

The plant operated at 63% power (195 MWe) until January 19, 1979. At this time it was decided to reduce power to less than 30% and shutdown Loop 2 to repair a secondary coolant leak on steam generator trim valve T V-2228-1. The Fermanite leak repair process attempted previously in the week did not work. As the power reduction was in progress a problem developed with Loop 2 main steam bypass valve PV-2230 which resulted in loss of control of the secondary coolant flow. The main turbine gen-erator was tripped off the line at 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br />.

As a result of the turbine trip, the reactor power was reduced to 2%

awaiting the repair o f TV-2228-1 and PV-2230.

Reactor power was increased to 25% on January 22,1979, at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> and to 30% at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. Power was held at this level until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on January 24, 1979, awaiting primary coolant oxidants to reach accept-able levels to increase power. Power was increased to 63% (195 MWe) at this time.

A problem occurred with the helium dryer which necessitated bypass opera-tion during repair. Operation with the helium dryer bypassed caused primary coolant oxidants to increase beyond acceptable limits for opera-tion at 63% power and power was reduced to 42% for cleanup. Cleanup was achieved on January 30, 1979, and power was increased to 60%.

A reactor scram occurred at 1338 hours0.0155 days <br />0.372 hours <br />0.00221 weeks <br />5.09109e-4 months <br /> on January 30, 1979, due to a

dip in instrument bus two voltage caused by a short circuit during re-pair of a Gaitronics co=munications unit.

.i

. s 1.0 NARRATIVE SU3 DIARY OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE (continued)

The reactor was restarted and returned to critical on January 30, 1979, at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br />. A problem developed in "B" feed water pump which caused it to be declared inoperable, rhis problem, in conjunction with the inoperable "C" feed pump, does not permit continued operation at power. The plant will remain shutdown until the refueling, scheduled to start in mid-February, is complete.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATIONS OF FAILED-FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5

cPE?r:::C ran n?0?.T 00c IT ::o. 50-267 237 790201 CC::rt:TED 3T J. W. Gahm Trtzna::z (303) 785-2253 CPEUTI:!C STATUS

0TZS

1. Uni: ::a=e : Fo rt S t. Vrain, Unit No. 1

2. Reporting Period; 790101 to 790131

3. Licensed Ther=al Power C-!Jt): 342 4  ::a=eplace Racing (Cross >fie): 342

5. Design Electrical Rating C;et 2 7e): 330

6. Maximum Oependable Capacity (Cross :*ie): 342

7. Finximum Oependable Capaci:y (::et :*ie): 330 3.

If Changes Occur in capaci:y Ratings (Itecs :ium:er 3 Through 7) Since Last Report, Cive Reasons:

None

9. Power Level To Which Restricted, If Any (::et >5Je): 231

10. Reasons for Restrie:1cns, If Any: Nuclear Re2nlatorv Commission res triction (70*D cendine resolution of certain Final Safety Analysis Report and Technical Scecification bases dis crepancies . This unit is in the power ascension phase of startup testing program.

This Menth Year to Data C eulative

11. Hours in Repwrting Pericd 744 744 - - - - - - -

12. iutber of Hours Reactor Was Critical 737.4 737.4 14.211.1

13. Reactor Reserve Shutdemi Hours 0.0 0.0 0.0

14. Murs Generator Cn-Line 658.4 638.4 3,501.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross -'hermal Energy Generated (> sea) 310,588 310,588 3,513,386

17. Cross Electrical Energ r Generated (37.iii) 109,306 109,306 1,057,576

13.  ::e Ilectrical Energy Generated (15 a) 101,177 101,177 952,628

19. Unit Service Fac:or N/A N/A N/A

20. N/A Unic Ava11acility Fae:or N/A N/A

1. tai: Capaci:7 Factor (Using :cC ::e:) N/A N/A N/A

22. Uni: Ca:acity Fac:ce (Using ;E2 ::et) N/A N/A N/A

23. Unit Tor:ed outage nata N/A N/A N/A

24. Shutdowns Scheduled Over ::ex: 5 lbnths (Type, Date, and Duration of Zach):

Refueline; March, 1979: 2 Months

25. *f Shut Oown at End of Repor: ?eriod, Ea tinated Ca:a of 3:ar:ue: N/A

25. Units :n Test S ta tus (Prior to C a ercial Coeratiod Forecast Achieved

tT'AL c2:T: CAL: Y 740201 7 f.0131

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AVEMGE DAILY L7;IT POWER LEVEL Do ck e t ?!o . 50-267 Unit Fo rt S t. Vrain, Unit No. 1 Date 790201 Completed By J. W. Cahm Telephone (303) 785-2253 Month Januarv, 1979 DAY AVERAGE DAILY TO'.JER LE','EL DAY AVE? AGE DAILY PC'.!ER LEVEL

(:"a'e-Ne t ) ('Ee-: e t) 1 190 17 175 2 168 18 130 3 98 19 154 4 143 20 0 5 103 21 0 6 127 22 0*

7 156 '23 129 8 181 __

24 152 9 183 25 164 10 180 26 170 11 177 27 160 12 176 28 100 13- 176 29 146 14 174 30 75 15 171 31 50 16 174

• Generator on line 'aut no ne t generatica.

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1. Name of Facili:v. Fort S t. Vrain, L'ni: No. 1

2. Scheduled date for next refueling March 1, 1979 shutdewn.

3. Scheduled date for restart May 1, 1979 folleuing refuelin2.

4. '4111 refueling or resu=p; ion of operation :hereafter require a technical specifica:icn change l or other license amendment? I Yes*

If answer is yes, what, in To facilitate insertion of eight fuel tes:

general will these be? ele =ents.

If answer is no, has the reload *NOT2: If Technical Specification change fuel design and core configura- app roval is no t received frc= NRC in ti=e tion been reviewed by your Plan: i for refueling, then :he answer to 14 is Saf ety Review Co==1::ee to deter. NO and -the reload fuel and graphite design

=ine whether any unreviewed have been reviewed.

saf ety ques tions are associa:ed with the core reload (Reference 10CFR See:ica 50.39)? I If no such review has taken olace. When is it scheduled?

5. Scheduled da:e(s) for sub=1::ing proposed licensing actica and succor:ing informa:ica. January 9, 1973

6.  !=portant licensing censidera- Eight tes: fuel ele =en ts :o allev:

tions associa:ed wi:h refueling,  :

e.g., ncv or differen: fuel de-  ! 1) Differen: fuel particle design. i sign or supplier, enreviewed design or perf ormance analysis 2) To qualify near isotropic graphi:e.

, ce: hods, significant changes in 6 l fuel design, new operating pro- I cedures. {

7. The nu=ber of fuel assemblies a) 1482 E!GR ele =ents.

(a) in :he core and (b) in the scent ruel storare ocol. .)

c 0 in uel storage veris.

i

}

l l 3. The cresent licensed scen: fuel Capacity is 11=i:ed by sice :nly :c abou:

l l pcol's:Orage capaci:7 and the one :hird of core (approxi=a:ely 500 ETGR  :

sice Of any increase in licensed ile=en

s). 1o enange :s p"-a". i l storage capaci:7 : hat has been l requested or is planned, in l

! j

, number of fuel assemblies. '

e .. -

REFUELING INFO?l!ATION (CONTINUED)

/

9. The projected date of the 1986 under the Three Party Agree =ent las: refueling tha: can be (Contrac: AT (04-3)-633) between DOE, discharged :o the spent fuel Public Service Cc=pany of Colorado (? SCo) ,

pool assu=ing the presen: mad General Acc=ic Cc=pany.*

licensed cacacity. l

• The 1986 data is based on the understanding that spent fuel discharged during the ter= of the Three Par:7 Agree =ent vill be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chenical ? recessing Plan: (I C?? ) . The storage capacity has evidently been sized :o acco cdate fuel which is expected to be discharged during the eight year period covered by the Three Party Agree =ent.

e

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