ML20070S744
| ML20070S744 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/30/1994 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-94-2066, NUDOCS 9405240181 | |
| Download: ML20070S744 (7) | |
Text
.
e-0 h.r- -
GPU Nuclear Corporation Q
ggf Route 441 South P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717) 944-7621 Writer's Direct Dial PJumber:
(717) 948-8005 May 13, 1994 C311-94-2066 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 Docket No. 50-289 Monthly Operating Report for April 1994 Enclosed are two copies of the April 1994 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, T. G. Brou9hton Vice President and Director, TMI WGH Attachments cc:
Administrator, Region I TMI Senior Resident Inspector 1
q 3.*
.e t.,, 4 b
- s. 0r 9405240181 9'0430 f
PDR ADOCK 05000289 lg -
f R
PDR GPU fluclear Corporation is a subsdary of General Public Utmties Corporation A
OPERATIONS
SUMMARY
April 1994 The plant operated at approximately 100% power for the entire month of April.
- Electrical output averaged approximately 808 MWe during the period.
MAJOR SAFETY RELATED MAINTENANCE There were no major safety related maintenance items completed during the month.
.I l
l 2
$4
%'7-Y w
9 m'--
yr-y---
,,p.,
t>
. m2
OPERATING DATA REPORT DOCKET NO.
50-289 DATE May 13, 1994 COMPLETED BY W G HEYSEK OPERATING STATUS TELEPHONE (717) 948-8191
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 NOTES:
- 2. REPORTING PERIOD:
APRIL 1994
- 3. LICENSED THERMAL POWER:
2568 4.
NAMEPLATE RATING (GROSS MWe):
871
- 5. DESIGN ELECTRICAL RATING (NET MWo):
819
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
834
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWo):
786 8 IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
i 9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. IIOURS IN REPORTING PERIOD (HRS) 719.0 2879.0 172344.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 719.0 2667.2 95893.4
- 13. REACTOR RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 2283.8
- 14. HOURS GENERATOR ON-LINE (HRS) 719.0 2663.9 94768.6
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1844029 6701864 231568515
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 614931 2253103 77939886
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 581050 2116521 73181040
- 19. UNIT SERVICE FACTOR
(%)
100.0 92.5 55.0
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 92.5 55.0
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 102.8 93.5 54.0
- 22. UNIT CAPACITY FACTOR (USING DER NET) 98.7 89.8 51.8
- 23. UNIT FORCED OUTAGE RATE
(%)
0.0 0.0 39.0 UNIT FORCED OUTAGE HOURS (HRS) 0.0 0.0 60759.4
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION OF EACH):
Scheduled - June 1.
1994 15 days - QRD drop time testinq & possible maintenance
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
3
(
l-v,
{
b AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE May 13, 1994 COMPLETED BY W G HEYSEK TELEPHONE.
(717) 948-8191 MONTil:
APRIL DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-NET)
(MWo-NET) 1 814 17 810 2
812 18 810 3
810 19 802 4
815-20 808 5
812 21 811 6
809 22 815 7
811 23
.814 8
816 24 806 9
813 25 798 l
10 805 26 803 11 813 27 794 12 813 28 802 13 812 29 805 1
14 806-30 800 15 801 31 NA 16 805 j
4 4
, _ :~
, i :,, '
, e v..
1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-289 UNIT NAME 7MI-1 REPORT MONTH April 1994 DATE May 13, 1994 COMPLETED BY W-G.
Heysek-TELEPHONE (717)'948-8191 6
t N
li"*'""*
C""" A C*'"#i"'
I kWd Cwm h
Esem Code Am w Tvpe' thentim Ressed g,,g, y
Reporst Ptews Roeursue
'A' hv s
- a l
i.
None s
T
't 1
2 3
4 F Forced E=hibit G - Instructions for nessen Method preparation of Cata Entry Sheets 5 Scheduled A-Equipment failure (Eastain) 1 P*nnual for Licensee Event Report (LE R)
B-Mesntenance or Test 2-aanual Scram File (NUREG-0161)
C-Refueling 3-Automatic Scram D-Regulatory Rectriction 4-Other (Explain)
C E-Operator Training & Ltcensing Examinatic, a Ezhtbit i same source F-Administrative G-Operational Errer (Empleta) r H-Other (Euplain)
U Actually used exhibits F & II NUGEG 0161 5
6 5
L
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?
NO
- 5. Scheduled date(s) for submitting proposed licensing action and suporting 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)
TSCR 234 was suhaitted in November 1993 consistent with GL 88-16 and the BAW-10179P " Safety Criteria and Methodology 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.
b) TMI will use the new Mark B10 fuel assembly in the Cycle 11 reload batch which is an upgraded design of the Mark B9 assembly used in Cycle 10.
The Mark B9 provides a leaf-type cruciform assembly holddown spring to replace the previous coil spring designs that has experienced random failures during operation and requires visual inspection each outage.
The Mark B10 design meets all current BWFC fuel design criteria and is in use at other R&W 177 FA plants.
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.
d 7
i
>