ML20215H148
| ML20215H148 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/31/1987 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 5211-87-2080, NUDOCS 8704200173 | |
| Download: ML20215H148 (6) | |
Text
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OPERATIONS SUMARY MARCH,1987 The unit entered March in a refueling shutdown condition with fill of the Reactor Coolant System (RCS) in progress.
On March 1,1987 the RCS was filled and by March 3,1987 a 40# steam bubble was established in the pressurizer.
On March 2, during electrical preventive maintenance in the 1 "A" Auxiliary Transformer Control Cabinet, an electrician, while attempting to rectify an improperly installed relay cover, caused the 1 "A" auxiliary transformer to trip. This, in turn, caused the 1 "B" Emergency Diesel Generator to start and load. There was no major safety significance associated with the auto start of the Emergency Diesel Generator.
LER 87-002 provided details of this event.
On March 12, 1987, there was a small release of chlorine gas from the river water chlorinator system. The event occurred during a scheduled switchgear outage and restoration evolution. The root cause has been determined to be lack of procedural guidance. There was no environmental impact as a result of this relatively small gas release. This event was not reportable and no LER was processed.
The plant proceeded to heatup on March 20 reaching hot shutdown at 2140 on that date. An integrated remote shutdown system test was successfully completed on March 22, 1987. Following Heat Sink Protection System (HSPS) testing, the system was enabled (except high OTSG level isolation) to support power operation.
The reactor was taken critical and low power physics testing commenced on March 23, 1987.
Following low power physics testing and overspeed testing of the main turbine, the plant proceeded to approximately 81% reactor power whereby it is limited by indicated high OTSG levels (72%
"A"; 90% "B").
The plant remained at approximately 81% power whereby it is limited by high OTSG levels for the remainder of the month. HSPS high level isolation remains bypassed.
MAJOR SAFETY RELATED MAINTENANCE During the month of March, TMI-l was completing the scheduled 6R refueling outage and restoring plant cleanliness and returning systems to normal for l
plant startup.
The following major maintenance items were performed:
Local Leak Rate Testing - Local Leak Rate Testing (LLRT) was performed on Valves CA-V-1, 2, 3, 5, A/B,13; SA-V-2, 3: Penetrations 104, 105, 106, 210, 211; Reactor Building Fire Service Spool Pieces and AH-V-1 A/B/C/D. All testing was satisfactorily performed.
Heat Sink Protection System (HSPS) - The HSPS OTSG level instrument calibration was a significant work item in March. A vendor representative was present to aid in the calibration effort. The calibration / static alignment work was performed on the startup range transmitters first and then on the operating range transmitters. All of the calibration work was performed to support the plant startup prcgram.
Weekly checks / readings will be taken to verify instrument accuracy for the next several weeks. At that time, a determination will be made for the need to continue these checks / readings.
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OPERATING DATA REPORT l
DOCKET NO.
50-289 DATE 3-31-87 i
COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 j
OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD:
MARCH
,1987.
- 3. LICENSED THERMAL POWER (.MWT) :
2535.
- 4. NAMEPLATE RATING (GROSS MWE) :
871.
- 5. DESIGN ELECTRICAL RATING (NET MWE) :
819.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :
824.
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :
776.
- 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-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.
2160.
110257.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 198.5 198.5 40283.8
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1874.1
- 14. HOURS GENERATOR ON-LINE 133.7 133.7 39379.9
'15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 220241.
220241.
95147503.
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 75711.
75711.
31594582.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 58970.
58970.
29528945.
- 19. UNIT SERVICE FACTOR 18.0 6.2 35.7
- 20. UNIT AVAILABILITY FACTOR 18.0 6.2 35.7
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 10.2 3.5 34.3
- 22. UNIT CAPACITY FACTOR (USING DER NET) 9.7 3.3 32.7
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 60.1
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH NONE
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI-1 DATE 3-31-87 COMPLETED BY C.W. Smyth TELEPHONE (717) 948-8551 I
MONTH:
MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1
-6, 17
-9.
[
2
-6.
18
-9.
3
-7.
19
-14.
4
-7.
20
-32.
.5
-7.
21
-44.
6
-7.
22
-44.
'7
-12.
23
-44.
8
-13.
24
-45.
=
9
-11.
25
-44.
10
-11..
26 55.
11
-9.
27 286.
12
-9.
28 606.
13
-9.
29 618.
14
-9.
30 639.
15
-9.
31 677.
16
-9.
_J
50-289 DOCKET NO.
UNII SilUTDOWNS AND POWER REDUCTIONS UNIT NAME TMI-I DATE d-dl-d/
COMPl.ETED BY C.W. Smyth REPORT MON 11g MARCH 1.987 TELEPHONE f717) 948-8551 n.
f"d 3 ea c
re E4 Licensee 5%
c.
Cause & Corrective 2 _e E
E3 Action to No.
Date g,
3g g
jgE Event
- ?
$5 E
j5g Report a
$0 Prevent Recurrence b
i 37-01 10/31/86 S
610 C
N/A ft/A N/A N/A Shutdown for refueling outage.
I 2
3 4
F-l'orced Reason :
Method:
Exhibit G -Instructions S Siheduled A.I'quiprnent Failure (1.xplain) 1 -Manual for Preparation of Data H. Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee C-Refueling 4-Automatic Scram.
Event Reporn (LERI File tNllRI G-D-Regulatory Restriction 4-Ot her ( tiplaml 01611 1 -Operator Traimng & Iitenw I umination F Adnunistratsve 5
Estubit I Same S mice G Operaigonal I a ros (ITplam) 11 Othes ( L splaml 6
Actually used Exhibits F & 11 NUREC 0161
REFUELING INFORMATION REQUEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
July 1, 1988 (7R) 3.
Scheduled date for restart following refueling: September 14, 1988 (7R) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes (For 7R)
If answer is yes, in general, what will these be?
Basic Refueling Report.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
To be determined.
5.
Scheduled date(s) for submitting proposed ifcensing action and supporting information:
November 1,1987.
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:
None 7.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 284 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 752.
There are no planned increases at this time.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present ifcensed capacity:
1991 is the last refueling discharge which allows full core off-load capacity (177 fuel assemblies).
GPU Nuclear Corporation u Nuclear
- ,ome er8o s
Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
April 15, 1987 5211-87-2080 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report March, 1987 Enclosed please find two (2) copies of the liarch,1987 Monthly Operating Report for Three Mile Island Nuclear Station, Unit-1.
Sincerely,
. D. H k 11 Vice President & Director, TMI-l HDH:DVH:spb cc:
Dr. T. E. Murley R. Conte Attachments 0015C
\\
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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