ML20064H469

Monthly Operating Rept for Feb 1994 for TMI-1

ML20064H469
Person / Time
Site:	Crane
Issue date:	02/28/1994
From:	Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C311-94-2032, NUDOCS 9403170311
Download: ML20064H469 (7)

Text

i q

CPU Nuciaar Corporation u Nuclear an::1;r'"

Middletov n, Pennsylvania 17057-0480 (717) 944+7621 Writer's Direct Dial Number:

(717) 948-8005 March 14, 1994 C311-94-2032 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555 Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 o

Docket No. 50-289 Monthly Operating Report for February 1994 Enclosed are two copies of the February 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, Q&

W T. G. Brouc ton Vice President--and Director,_TMI WGH Attachments cc: Administrator, Region i TMl Senior Resident Inspector f

hh I

9403170311 940228 PDR ADOCK-05000289-N 3

R PDR

./

.L O U V O U GPU Nuclear Coqx> ration is a subsidiary of General Putsic Utilities Corporation V-l.

- ~. - -.

9 e'

4 OPERATIONS

SUMMARY

February 1994 g

The plant entered the month of February operating at approximately 100% power.

On February 7th, power was reduced to 80%.

The power reduction was due to a transient in the Condensate Powdex Filter System which reduced feedwater flow.

Operator action was required to reduce reactor power to 80% to reduce primary.

4 system pressure and restore proper condensate and feedwater flows. The plant remained below 100% power for approximately 5.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and after the return to 100% power, finished out the month operating at that level. The plant electrical output averaged approximately 816 MWe during the period.

MAJOR SAFETY RELATED MAINTENANCE i

During February, no major safety related maintenance was performed.

The following item is being noted since the associated transient resulted in a two hour, 20% power reduction:

Condensate Powdex Filter Bypass Valve CO-V-51 i

During the transient that occurred with Condensate Powdex Fi ier CO-T-4F, bypass valve CO-V-51 failtd to open on demand.

Plant Engint ring and Plant Maintenance are evaluating valve repair and replacement options. Mechanical binding between the valve disc and seat appears to be the roat cause_of the difficulty experienced.

It should be noted that the existing valve is i

obsolete and replacement parts are not available. As an interim step, to increase the available force to open the valve, the air pressure supplied to i

the valve operator was changed _from 60 to 85 psig.

l t

2 L

1 OPERATING DATA REPORT DOCKET NO, 50 289 DATE March 14, 1994 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 NOTES:

2. REPORTING PERIOD:

FEBRUARY 1994

3. LICEt1 SED Ti!ERMAL POWER:

2568 4.

NAMEPLATE RATING (GROSS Frde) :

871

5. DESIGN ELECTRICAL RATING (NET MWe):

819

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe) :

834

7. MAXIMUM DEPENDABLE CAPACITY (NET MWe)*

786 8.

IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-OATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD (HRS) 672.0 1416.0 170881.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL (liRS) 672.0 1416.0 94642.2

13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2283,8

-14.

HOURS GENERATOR ON-LINE (HRS) 672.0 1416.0 93520.7

15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1723847 3632590 228499242

17. GROSS ELECTRICAL ENERGY GENERATED (trdH) 580885 1223726

-76910509

18. NET ELECTRICAL ENERGY GENERATED (MWH) 548293 1155205 72219724

19. UNIT SERVICE FACTOR

(%)

100.0 100.0 54.7

20. UNIT AVAILABILITY FACTOR

(%)

100.0 100.0 54.7

21. UNIT CAPACITY FACTOR (USING MDC NET) 103.8 103.8 53,8

22. UNIT CAPACITY FACTOR (USING DER NET) 99.6 99.6 51.6

23. UNIT FORCED OUTAGE FATE

(%)

0.0 0.0 39.4 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60759.4

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

4

• Scheduled - March 17, 1994 - 4 days Repla.g_ement of leakinct pressurizer sorav valve -

25. IF SIRTT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

1.

3

k AVERAGE DAILY UNIT POWER LEVEL DOCKET No.

50-289 UNIT TMI-1 DATE flarch 14, 1994 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:

FEBRUARY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWe-NET) 1 1

821 17 818 2

819 18 816 3

817 19 815 4

819 20 813 5

820 21 813 6

819 22 815 7

802 23 016 8

820 24 816 9

818 25 818 10 814 26 818 11 808 27 817 l

12 812 28 815 l

13 816 29 NA 14 818 30 NA 15 818 31 NA 16 815 d

4

-..c. -.

2,.__..

m. - _.

i

. f W

I a

UNIT SHUTDOWNS AND PCWER REDUCTIONS DOCKET NO.

50-289 UNIT NAME TMI-1 REPORT MOrTIE February 1994 DATE N rch 14. 1994 l

COMPLETED BY W. G. Heysek j

TELEPHONE (717) 948-8191 i

t

.l t-c-a c-mg w

c _

~

T,p..

. _m m

@=ars) ha i

e_ s L

08:57 during a Pow'ex vessel overlay, the 5

94-01 02-07-94 F

0 A

4 None SD FCV At d

bypass valve around the Powdex system failed to open on high differential pressure.

Operators reduced the plant to 80% power.

The valve's operability was re-established l

by 09:20 and the plant was returned to full power operation.

i t

}

i l

1 2

3 4

F FM hhibit G-huenazasum sur

. Ranma

$Nw A'

- Failuss (F=p3e=4 3h Pzp=*tmas d Duas Emry bons E ?---

or Tm 2 hh t Less kI' bums Ropen GIRs C

• hh y a.m., w file OdURIG4!41)

Desg% Reessmues 443chs, 0,,ph, imp f

bOpesusar Taimig & 8 L -.ar F-5 nhiws s.m 3

i F'

k 6 mF a ~~ F a u wanw mss i

- 5 Y

4 REFUELING INFORMATION REQUEST

1. Name of facility:

Three Mile Island Nuclear Station, Unit 1

2. Scheduled date for next refueling shutdown:

September 8, 1995

3. Scheduled date for restart following current refueling: NA

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment 7 N0

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

NA 6.

Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

a) GPUN will continue to improve the review process by submittal of Technical Specification Change Requests (TSCR) concerning the reload-related areas of fuel assembly reconstitution and removal of cycle-dependent core limits to the Core Operating Limits Report (COLR),

1) The B&W Owners Group Topical Report BAW-2149, " Evaluation of-Replacement Rods in BWFC Fuel Assemblies", December 1991, was approved in April 1993. This report justifies the use of up to ten replacement stainless steel rods located anywhere in a single fuel assembly based on currently-approved methodology.

BAW-2149 provides the basis for reconstitution repairs of BWFC Mark B assemblies to be done under the provisions of 10 CFR 50.59 (i.e., the repair does not represent an unreviewed safety question).

TSCR 232 was submitted in August 1993 in response to Generic Letter 90-02, Supplement 1 referencing BAW-2149.

2)

TSCR 234 was submitted in November 1993 consistent with GL 88-16 and the BAW-10179P " Safety Criteria and Nothodology for Acceptable Cycle Reload Analyses" Safety Evaluation (March 16, 1993) for the removal of cycle-specific protective and maximum allowable setpoint. limits for axial power imbalance and other applicable cycle-dependent limits.

7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:

(a) 177 (b) 601

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

The present licensed capacity is 1990.

Phase 1 of the reracking project to increase spent fuel pool storage capacity permits storage of 1342 assemblies.

Upon completion of Phase II of the reracking project, the full licensed capacity will be attained.

6

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Completion of Phase I of the reracking project permits full core off-load (177 fuel assemblies) through the end of Cycle 14 and on completion of the rerack project full core off-load is assured through the end of the current operating license and beyond.

4 1

1 1

1 l -

1 7

'