ML20215E792
| ML20215E792 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/30/1986 |
| From: | Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 5211-86-2212, NUDOCS 8612230122 | |
| Download: ML20215E792 (7) | |
Text
c OPERATING DATA REPORT L
DOCKET !IO.
50-289 DATE 11-30-86 COMPLETED BY C.W. Smyth
[
TELEPHONE (717) 948-8551 l
g OPERATING STATUS I
f
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 l
- 2. REPORTING PERIOD:
NOVEMBER,1986.
E
- 3. LICENSED THERMAL POWER (MWT) :
2535.
E
- 4. NAMEPLATE RATING (GROSS MWE) :
871.
h 5s DESIGN ELECTRICAL RATING (NET MWE) :
819.
[
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) :
824.
E
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) :
776.
I
?
+
A 8.
IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
E
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE) l
- 10. REASONS FOR RESTRICTIONS, IF ANY:
I p
E E
h 5
THIS MONTH YR-TO-DATE CUMMULATIVE I
- 11. HOURS IN REPORTING PERIOD 720.
8016.
107353.
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 6268.7 40085.3
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 990.8 1874.1
- 14. HOURS GENERATOR ON-LINE 0.0 6212.3 39246.2
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
+
[
- 16. GROSS THERMAL ENERGY GENERATED (.MWH) 0.
15576865.
94927262.
l
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.
5126718.
31518871.
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.
4818263.
29469975.
- 19. UNIT SERVICE FACTOR 0.0 77.5 36.6 f
- 20. UNIT AVAILABILITY FACTOR 0.0 77.5 36.6
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 77.5 35.1 a
E
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 73.4 33.5 I
- 23. UNIT FORCED OUTAGE RATE 0.0 4.0 60.2 V
k
[
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH Currently in a Refueling Outage
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: March 20.1987 m
A
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hgIk j
B612230122 861130 PDR ADOCK 05000289 l
l R
PDR 1
' l);
. AVERAGE DAILY UNIT POWER LEVEL t-
- DOCKET NO.
50-239 UNIT
'TMI-1 DATE 11-30-86 r.
COMPLETED BY C.W. Smyth TELEPHONE (717)-948-8551 MONTH:
NOVEMBER DAY AVERAGE DAILY POWER' LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NFT)
(MWE-NET) 1-0.
17 0.
2 O.
18 0.
2 0.
19 0.
4 0.
20 0.
5 0.
21 0.
6 0.
22 0.
7 0.
23 0.
8 0..
24 0.
9 0.
25 0..
10 0.
26 0.
'11 0.
27 0.
12' 0.
28 0.
13 0.
29 0.
14 0.
30 0,
15 0.
31 N/A 16 O.
i i-4
e 50-289 DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS HI-I UNIT NAME DATE 11-30-86 COMPLETED BY C.W. Smyth REPORT MONm NOVEMBER 1ELEPHONE (7171 QaR 98i's1 E
e se
.! ?
3 j Y5 Licensee E r, g*,,
Cause & Corrective No.
Date h
5?
255 Event s2 Q
Action to
$~
jdg Report #
N0 Prevent Recurrence 6
1 1
10/31/86 S
720 C
N/A N/A N/A N/A Refueling Outage 1
1 2
3 4
F: Forted Reason:
Method:
Exhibit G - Instructions S: St heduled A Fqmpment Failure (Explam) 1-Manual for Preparation of Data l
H Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee i
C Refueling l Autunutic Scram.
Event Report (LE RI Fde (NilREG.
D Regulatory Restriction
-l Olher (INelain) 0161) 1 -Operator Training & litense liamination j
F Adnunistrative 5
Eshibit I - Same Source G Operational Ee ror (ITplam) ll Ot her (E spl.iin p 6
Actually used Exhibits F & 11 NUREC 0161
1 GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
Deceniber 15, 1986 5211-86-2212 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Dear Sir:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report November, 1986 Enclosed please find two (2) copies of the November,1986 Monthly Operating Report for Three Mile Island Nuclear Station, Unit-1.
Si ncerely, H. D. H kill Vice President & Director, TMI-l HDH:DVH:spb cc:
Dr. T. E. Murley Attachments 0015C
\\\\
I GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
\\
l
OPERATIONS
SUMMARY
k NOVEMBER,1986 The unit entered November with a scheduled plant cooldown in progress to support the Cycle 6 refueling outage.
On November 2,1986, the "A" Decay Heat Removal (DHR) System was placed into service and containment integrity was no M
longer required. The annual Emergency Plan drill was observed by the NRC on November 5,1986. The Reactor Building Integrated Leak Rate (ILRT) "As Found" test was declared a failure and reported to the NRC on November 7,1986.
On November 9,1986, the subsequent "As Lef t" ILRT was acceptable.
The remainder of the month the plant was in a partially drained, cold shutdown condition on "A" DHR with Cycle 6R outage work scope in progress.
MAJOR SAFETY RELATED MAINTENANCE During the month of November, TMI-1 performed the following major maintenance:
Reactor Building ILRT - During week one of the scheduled 6R refueling outage, Reactor Building Integrated Leak Rate Testing (ILRT) was performed.
L Preparation work included Local Leak Rate Testing (LLRT) valves BS-V-37 A/B/C/D, AH-V-1 A/B/C/D and the Reactor Building Equipment access hatch, installation of test instruments, check-out of the test panel, installation and check-out of the air compressors and valve line-ups.
After containment integrity was established, the building was pressurized to 12 psi. A 12 psi entry was made into the Reactor Building for inspection.
After the 12 psi inspection, pressure was increased to 50.6 psi. Af ter a stabilization period the pressure drop test was started. The initial test exceeded the allowable leak rate and an investigation commenced to determine the source of leakage.
A major portion of the leakage was identified, quantified and isolated.
The Reactor Building was repressurized to 50.6 psi and the pressure drop test restarted. Results of this test were satisfactory.
After the pressure drop test, a known leak was initiated in the Reactor Building on top of the previously measured leak.
Results of this instrument accuracy verification test were also satisfactory. The Reactor Building was then depressurized to 0 psi, test equipment removed and the building / components returned to normal.
OTSG Inspection and Repair Activities - OTSG work activities commenced in November with Eddy Current Test (ECT) preparations.
Preparation work included removal of the "A" and "B" OTSG upper handholes and the installation of ventilation systems with charcoal filters attached to the handholes and installation of platforms and tents at the upper manways. An OTSG bubble leak test was performed on both the "A" and "B" OTSGs with no leakage evident. The RCS was drained and the lower manways were then removed and tents installed.
ECT equipment was then set up.
1
1 OTSG Inspection and Repair Activities (Cont'd.) - Eddy Current Testing commenced on the "A" OT5G tube pull candidates followed by the remaining test program. After Plant Engineering reviewed the ECT data on the tube pull candidates, ECT was stopped and three tubes were pulled from the "A" OTSG.
Eddy Current tests were performed on the pulled tube segments and the segments were shipped off site for analysis.
ECT was then resumed on the "A" OTSG.
After review of the "A" OTSG ECT data, it was determined to test an additional 6% of the tubes.
Eddy Current Testing in the "B" OTSG started and the initial work scope completed. Af ter a review of the test data an additional 6% of the tubes were tested.
During the review of the additional 6%, it was determined to increase the work scope to an additional 12%. OTSG work will continue in December.
Reactor Vessel Head Removal Preparation - Preparations for Reactor Vessel Head Removal commenced in November with missile shield removal, uncoupling CRDM's and APSR's, disconnected cables, PI/TC cables, Inventory Tracking cables, RV head temperature RTD's, drained the Intermediate Closed Cooling System, moved new Reactor Vessel Head 0-Rings into the building, removed Reactor Vessel insulation, removal of the head fans and detensioning of the head studs.
Actual removal of the Reactor Vessel Head will occur in December.
Reactor Coolant Pump Seal Inspections - Reactor Coolant Pump Seal Inspection preparations and work commenced in November.
Reactor Coolant Pump RC-P-1 A work included scaffold installation, decon work, removal of the oil drip pan, removal of thermocouples, installation of rigging and installation of seal handli ng hardware. The spool piece on RC-P-1 A was unbolted and is ready to remove.
Reactor Coolant Pump RC-P-1C work included scaffold installation, decon work, oil drip pan removal, thermocouple removal, rigging installation and seal handling hardware installation. The spool piece was unbolted from RC-P-lC and removed. Work will continue in December.
Local Leak Rate Testing - Local Leak Rate Testing (LLRT) started in November and is continuing.
Thirty-nine valves were. completed.
Two valves will require repair work.
One of the two valves will be replaced as a modification and one will be repaired at a later date.
o l
REFUELING IWORMATION 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:
March 20,1987' (For current 6R Outage)
September'14,1988 (7R) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes (For 6R)
If answer is yes, in general, what will these be?
Conversion to 18 month fuel cycle with associated changes to Power Imbalance, Quadrant Tilt and. Rod Insertion Limits.
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)?
No If no such review has taken place, when is it scheduled?
To be determined.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
submitted November 3,1986.
(For 6R) 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 t-l 7.
' The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 208 I
The present licensed spent fuel pool storage capacity and the size of any t.
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 licensed capacity:
1991 is the last refueling discharge which allows full core off-load ca1acity (177 fuel assemblies).
,