ML20071Q655

Monthly Operating Rept for Nov 1982

ML20071Q655
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/07/1982
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20071Q648	List: ML20071Q645 ML20071Q655
References
NUDOCS 8212290394
Download: ML20071Q655 (8)

Text

..

l l

PUBLIC SERVICE COMPANY OF COLORADO -

FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 106 November, 1982 . ,_

l t 3

l 0 8212290394 821214 PDR ADOCK 05000267 I R PDR

_1 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 November,1982.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor power was less than 2% for much of t.he month.

Primary coolant moisture still is excessive, thus preventing reactor power from being increased.

In orcer to more rapidly reduce the moisture in the core, additional flow is being pushed through the purification train.

Although not all utilized in the purified helium header, the remainder is being directly returned back to the vessel.

Because of this increased flow rate and high primary coolant moisture, regeneration of the trains in a timely manner becomes more critical. This has been difficult to accomplish before the in-service train becomes exhausted. Presently, approximately 220 gallons of water has been taken out of the vessel via the purification trains. -li In an attempt to allow the trains to be in service longer, a change to the purification system is being implemented. This change will allow the helium purification coolers to be cooled

~to a lower temperature utilizing a chilled water system. It is believed that utilizing this system will allow more water to be removed by the cooler and thus require less frequent dryer and -

low temperature adsorber regenerations. . ,__

Presently, primary coolant moisture appears to be just starting a downward trend.

Several tests were done during the month on the System 46/ core support floor. Nitrogen gas was injected into the System 46 pumps discharge line, as it was anticipated that this gas could be detected in both the primary coolant and core support floor vent to positively determine the leak paths. However, the l nitrogen gas injection was not conclusive. Argon gas then was injected in a similar manner. This injection appears more conclusive, as argon gas was detected in the core support floor gas effluent. During either test, argon or nitrogen was not  ;

detected in the primary coolant. ,

i r Further investigations into the primary coolant moisture

? problems have included taking both steam generator economizer / evaporator superheater sections out of service, I

e. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

r sequentially taking both loops of System 46 out of service, and varying reactor power. As of the end of the month, these tests have failed to reveal that there is a source of moisture other -

than some water that may have entered the vessel during depressurization. These tests are continuing into the next month.

Recent testing has also revealed a possible leak in the front- l end cooler for 18 purification train. This situation is being further evaluated, and material availcbtlity and repair techniques are being investigated. .

A number of training starts were completed during the month for both the license candidates and the licensed personnel.

Miscellaneous drain pump, P-7508, and auxliary boiler feed pump, i

, P-8401S, were overhauled, and the motors on hydraulic pumps, P-  !

9104X and P-9105X, were removed for repairs which amounted to a motor rewind for one pump motor and replacement of the other.

The turbine water removal pump motor, P-2103, was disassembled to replace bearings and install a new coupling.

~

This pump unit awaits parts at this time.

2.0 SINGLE RELEASES 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 MONTHLY OPERATING DATA REPORT Attached 2

~

t

E T57-3 Attache.at-35

. Issue 2 Faen 1 of 1

. OrnA nsc MTA trFORT DoCzrT 30. 50-267 an December 7, 1982 Co:st,.uD st-L. hh McBride T" . treout fin 1) 7ng.999d -

1 oruArtsc Suns  !

" 30T s

1. cai: s : rnre et vrain

2. R. porting Periods R91101 thennnh 471130 ]

3. Lic.ased Thetual Power Out): Ad7 4 Nam. place Racing (cross Sle): 1d7 .

3. D. sign E1.ccrical Rating (Net !Sie): 110

6. :f=*-- Sependahl. Capacity (Grose :Sie): 119 "

7. .szimum a.,.ndahl. Capacity cret :w.): 330

3. If Change. Occur in Capacity Ratings (It.as Number 3 Through 7) Sinc. Last Report, civ. Reasons:

None

9. rw.e t vet To which autrict.d. If any (s.: :St.): 231

10. aamans for sa trictions. If any: Restriction to 70% pending resolution of contractual matters.

This Month T.ar to Data Cumulative n . sours in zaporting r.riod 720 8016 29977

u. xunber of sours auctor vu Cetescal 538.8 d745.0 19323.4 -

13. Reactor Eas.rv. Shutdown Hours 0 0 0 t:. . nours c.n.rator On-t.in. O _

3266.2 13174.5

u. enic a.s.rv. Shutdown sours 0 0 0

6. cress :s r a1 :n.ru c.nerac.d (e.s) 6541.9 1849177.5 6783122.3

17. cross n cerical ener:7 c.n rated essu) 0 635548 2326904

a. s.t n.ctrical zn.rgy c.n. cat.d (sd) 5330 573085 2127344

19. Unit S.rvic. Factor 0 40.7 43.9

20. Unit Availability Tactor O 40.7 43.9

1. enic Capacity ractor (U.ing v.':c 3.t) 0 21.7 21.5

n. Unit Capacity Tactor (Using CIR Net) 0 21.7 21.5

23. Unit Forced Outage Rat. 100_O 'U; _3 34.6 "4 Shutdowns 3ch.dul.d ov.c ': ext 6 P.anths (Type. Dat.. and Duration of Zach): Plant recoverv 821201 through 830115-1104.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Surveillance testing 830823 through 830422-744.0 hrs.. _

23. If Shut Down at Ind of R. port Period. Esti=at.d Jac. of Startup: Reactor is critical at low power.

26. Units In !.st 3catus (?tior to Co==.rcial Operation): Fo rec a s t Achieved

n nx.Cu nce.u r N/A N/A

stnA:. :.:cn:::n N/A N/A ca: tac:x. er: san:s N/A N/A

TSP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date noenmhor 7. 14A7 Completed By L. M. McBride Telephone (303) 785-2224 Month November DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL ' .

(We-Ne t) (We-Net) 1 0.0 17 0.0 2 0.0 18 0.0 3 n.n 19 0.0 4 nn 20 0.0 5 nn 21 n_n 6 nn 22 nn --

7 0.0 23 0.0 8 0.0 24 0.0 -

9 0.0 25 0.0 10 0.0 26 0.0 -

11 0.0 27 0.0 12 0.0 28 0.0 13 nn 29 0.0 is 0.0 30 0.0 15 0.0 31 N/A 13 0.0

• Cenerator on line but no net generation. ,

MwKL i, - s. .: - .. s j ; **L'<

• I .* :

" ' L ' ; ^ ' ' :- . *- ; ;. s ' .

• TSr-1 AI t as team'n t- SC .

Issue 2 Page t.d I TWIT seh TinWriS AND PtWF.R NEldK.BWN inxvEr mi. _50-267 _

,,,,,,,,,, Fort St. Vrain mTe December 7, 1982 cemr u Tni RT _L. M. McBride ,__

REr0RT eRWni November 1982 TnEne. e _(303) 785-2224

~

HE11k)t) OF SlitTTING IMWN SYSTDI C(Wr000ENT id*ATlute REASON REACTOR OHE ODIE CAtISE AN8) OnstitECTIVE ACTIDII 10 rREVENT RirtNtRFale2 tal.__ MTE _ UfE__ 51R I _

32-014821101 F 720.0 H 3 N/A IBil INSTRU Loop 1 Shutdown followed by reactor scram and turbine-generator trip on 820930. Outage continued due to primary coolant chemistry impurities.

l 1

.~

Continue to cleanup primary coolant and investigate possible steam generator tube leak.

I -

e I i u

l RE"UELING INFORMATION

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

2. Scheduled date for next refueling ~

shutdown. Sentember 1, 1983

3. Scheduled date for restart following refueling. November 1, 1983

4. Will refueling or resumptien of operation thereafter require a .

technical specifi.(tion change or other license ur.endment? Yes If answer is yes, what, in general, will these be? Use of type H-451 graphite.

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Cocuittee to deter-mine whether any unreviewed safety questions are a.ssociated with the core reload (Reference 10CFR Section 50.59)?  !

If no such review has r.aken olace, when is it schedulad? -

5. Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time; succorting information. to be determined. -

6. Important licensing considers-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 nu=ber of fuel assemblies 1482 HIGR fuel elements.

(a) in the core and (b) in the scent fuel storage pool. 11 spent HTGR fuel elements

8. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one- -

4 size of any increase in licensed  !

third of core (approxinately 500 HTGR storage capacity that has been elements). No change _is planned.

requested or is planned, in ,

nu=ber of fuel asse=olies.

__,___..._,._m. . _ . -, , _ , - _ _

REFUEI,I:C I'TFORMATION (CONTINUED) i

9. The projected date of the ,' 1992 under Agreements AT(04-3)-633 and last refueling that can be

• DE-SC07-79ID01370 between Public Service discharged to the spent fuel Company of Colorado, General Atomic pool assuming -he present Company, and DOE.*

licensed capacitv. 1

• The 1992 estimated date is based on the understanding that spent fuel discharged during the twrm of the Agreements will be store. ':y DOE. at ,

the Idaho Chemical Processing Plant. The storage capacity has evidently teen sized to accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

4 L - _ _ _ _ _ _ _ _ _ _ _ _