ML20215L392

Monthly Operating Rept for Apr 1987

ML20215L392
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/30/1987
From:	Olmstead C, Ulmer F PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CAO-161-87, NUDOCS 8705120228
Download: ML20215L392 (7)

Text

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DOCKET NO: 50-344 DATE: April 1987 COMPLETED BY: F. J. Ulmer TELEPHONE: 503/556-3713

SUMMARY

OF OPERATING EXPERIENCE OPERATION The plant entered the month of April near Mode 2, decreasing power to 1%. At 0043 the main generator breakers were opened. At 0048 the Trojan reactor entered Mode 3 and commenced cooldown in preparation for annual refueling. The plant entered Mode 6 at 1900 on April 8, 1987.

During this period major outage projects such as main condenser replacement, moisture separator reheater tube replacement, reactor coolant pump rotor inspection, and steam generator maintenance were started.

On April 9 while reactor vessel stud removal work was in progress the reactor containment building was evacuated due to higher than normal airborne and surface contamination levels. A total of 21 personnel were contaminated. On April 11 the source of the contamination was located when a fuel pellet remnant was discovered at the reactor vessel flange area. The pellet was partially pulverized and airflow dispersed fine particles to the upper levels of the containment building.

The fuel pellet was from Region F fuel that sustained major damage during Cycle 4 (1981/82). The pellet's location since 1982 is not known. An investigation is in progress to determine how the pellet may have gotten there and what corrective actions are necessary to prevent a similar incident. Extensive decontamination efforts followed to clean up all areas of containment at and above the refueling deck.

On April 17 at 1000 a Radiation Technician was performing a survey of the lower reactor cavity area in preparation for work on the fuel transfer system. The technician was in the area for about three minutes wearing double overshoes and plastic booties.

During the exit frisk from the cavity, the technician discovered an extremely radioactive particle on the heel of his right outer overshoe. He immediately removed his overshoe, placed them in a plastic bag, and exited the area. Preliminary calculation indicated a possible overexposure to his heel. More detailed and realistic calculations and measurements concluded that no federal limits were exceeded. On April 29, Portland General Electric reported to the NRC the technician's total quarterly dose as follows: whole body = 1.21 rem, extremities : 9.57 rem, and skin dose : 4.62 rem.

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Page Two Plant management immediately closed the containment building to all work and began an extensive training, survey, and cleanup program to prevent further contamination problems. On April 28, containment was reopened for refueling work.

At the end of Cycle 9 the primary-to-secondary steam generator tube leakage remained less than on gallon per day and the reactor coolant system dose equivalent iodine concentration concluded at 12% of the specification limit.

The presence of a small fuel rcd failure was confirmed by radiochemistry. The small fuel leaker is not of a magnitude to require special action and will be discharged in the normal sequences based on burnup.

MAJOR SAFETY RELATED MAINTENANCE

1. Pressurizer safety valve testing was completed. One valve failed testing criteria and will be reset and tested prior to startup.

2. All steam generator safety valves were tested satisfactorily.

3. The turbo-charger unit on the 'B' train west engine of the emergency diesel generator was replaced due to an oil leak into the air plenum.

4. 'A' train component cooling water 10-year Inservice Testing.

was completed satisfactorily.

MISCELLANEOUS MAINTENANCE 4

1. Repaired the 'C' drive of the incore flux monitoring system.

2 Install 2d and tested new electric drive system for the spent fuel transfer system.

3. Installed a modified rod control cluster assembly to satisfy NRC IE Bulletin 84-03 concerns.

4. Completed steam generator sludge lancing, yielding approximately 100 pounds per generator.

Page Thran LICENSE CHANGES Amendment No. 126 The amendment revises the Technical Specifications (TS) by providing editorial corrections to TS Sections 4.4.6.1.b and 3.4.9.3. Table 3.6-1 is revised to permit the operation of valve MD-059 to be administratively controlled in order to provide consistency between TS Sections 3.6.1.1, 3.6.3.1, and 3.7.8.3.

Amendment No. 127 This amendment is issued in accordance with Nuclear Regulatory Commission rule changes (10 CFR 50, Appendices G and H) regarding requirements for fracture toughness and for reactor vessel material surveillance programs, and as a result of a Westinghouse analysis of Surveillance Capsulo X (WCAP-10861). Trojan Technical Specification Table 4.4-5, Figures 3.4-2 and 3.4-3, the Bases for these figures, and the Bases for Technical Specification 4.4.9.1 are revised to reflect schedule changes for future specimen Capsule removal and to reflect new 10 CFR 50, Appendix G, pressure-temperature limits.

Amendment No. 128 The amendment changes the Administrative Controls section of the Technical Specifications by redefining and clarifying the review responsibilities of the Plant Review Board (PRB) and the Plant General Manager.

Amendment No. 129 This amendment changes the containment isolation valve testing requirements to allow testing in Modes other than Modes 5 and 6.

Amendment No. 130 This amendment changes the condensate storage tank operability level for Modes 1, 2, and 3 to account for unusable water volume.

MISCELLANEOQS During the month the NRC performed inspections of Trojan's Maintenance records. In pursuit of data regarding potential rod ,

control cluster cladding wear from fretting with guide tube alignment cards experienced at othor plants, Trojan's Chemistry Department sampled the reactor coolant system (RCS) for Ag 110m (silver) during plant cooldown. The sample analysis showed a level of silver in the RCS (5.5E-SuC/gm) to be 18 times lower than the minimum level of concern (IE3uC/gm established by Westinghouse.

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l OPERATING DATA REPORT I

DOCKETNO.

50-344 DATE April 1987 COMPLETED BY F. J. Ulmer TELEPHONE 503-556-3713 Ext. 495 OPERATING STATUS ,

Trojan Nuclear Plant Notes

1. Unit Name:

2. Reporting Period: Aori1 1987 3411

3. Licensed Thermal Power (MWt):

1216

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1130 1

6. Maximum Dependable Capacity (Gross MWe):

1133 l

7. Maximum Dependable Capacity (Net MWe):

1075

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons: 7 N/A t

9. Power Level To Which Restricted,if Any (Net MWe): N/A

10. Reasons For Restrictions.If Any: N/A ,

. This Month Yr to Date Cumulative 714 7 ann 934s

11. Hours In Reporting Period t 0.8 21s1 58774

12. Number Of Hours Reactor Was Cri' leal 0- 0 .i g g 7

13. Reactor Reserve Shutdown Hours 2148

- 14. Hours Generator On-Line 0.7 38188 l- 0 0 ___

3887

15. Unit Reserve Shutdown Hours

[

16. Gross Thermal Energy Generated (MWH) 0 707849s 184933817 l 16s 2360899 60645762 l 17. Gross Electrical Energy Generated (MWH) ,,,,,

-4892 22s0711 a;74t7746

18. Net Electrical Energy Generated (MWH) 0.1 74.6 62.3

19. Unit Service Factor 66.4

20. Unit Availability Facto, 0.1 74.6 j 57.7 0.6 72.7

21. Unit Capacity Factor (Using MDC Net) l .6 69.2 54.4

22. Unit Capacity Factor (Using DER Net) 0 0.6 13.8

23. Unit Forced Outage Rate

24. Shutdowns Schedu'ed Over Next 6 Months (Type. Date,and Duration of Eachl:

aiinn 6. 1QR7 25, if Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior io Commercial Operationi: Forecast Achieved NA NA INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA ,

COMMERCIAL OPER ATION  !

(0/77) f '.

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DOCKET NO. 50-344 UNIT SHUTDOWNS AND POWER REDUCTIONS UNITNAbst - Tro,an DATE 9/d/A7 NHO W " ' ""

REPORT MONTH Anril 1987 TEIAPISONE 503/;s6_ "m 7 x 495-

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Cause A Cowsective Action se W. a 1r Dne  ;- e: 3 .E g ac Evens

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• A0 " . . Prevens Recureence 6

87-02 4/1/87 S 718.3 C 1 Plant shutdown for Annual Refueling Outage.

t I .? 3 4 Method: Enidlige G.Inseriscelens F: Forced Reason:

S- Scheduled A Equipment Fathere(Explain) 140anuel for tion ed Data B-Maintenance or Test 240snesI 5 crane. Entry for IAvenee C-Refueling J Ameanistic Sc;sm. Event Report iLER) FeetNUREG.

D Regelseory Reserktion 4 Otiser tEmplain) 0161)

E-Opeseene Training & IJcense Examinsslet F-Adannistrathe $

G Operailunal Errug(Emplain) ,

Exhteet I . Seine S.orce 19177) ll-Othen iEsplaise)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-344 UNIT: Trojan l

DATE:

_ COMPLETED BY

p. 3. nimar TELEPHONE: 503/ss6-1713

l. x 495 l-I i MONTH Anril 1987 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) l l

1 -27 17 -4 l

t l 2 -26 18 -4 3 -13 19 -4 4 -12 20 '5 -11 -21 -4 6 -9 22 -4 7 -6 23 -4 l

8 -6 24 -4 9 -6 25 -4 10 -5 26 -4

-5 27 -4 l- 11

-5 28 ~4 12

-5 29

~4 13

-4

-14 30 15 -5 31 16' -4 j

l-INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

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N Portland General Electric Company Trojan Nuclear Plant ay 6, 1987 P.O. Box 439 Rainier, Oregon 97048 AO-1M-87 (503)556-3713 US' Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen Monthly Operating Data Report In accordance with the Trojan Nuclear Plant Technical Specifications. reporting requirements, the Monthly Operating Data Report is submitted for April 1987.

Sincerely,

e. s. D L a D C. A. Olmstead General Manager Attachment c: Mr. John B. Martin Regional Administrator, Region V US Nuclear Regulatory Commission Mr. David O. Kish Acting Director Department of Energy State of Oregon

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