ML20136A588
| ML20136A588 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/31/1985 |
| From: | Baran R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20136A578 | List: |
| References | |
| NUDOCS 8511190560 | |
| Download: ML20136A588 (6) | |
Text
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MONDILY OPERATING REPORT - AUGUST 1985 At the beginning of the report period, Oyster Creek was in cold shutdown.
Cleaning of Containment Spray heat exchangers, Emergency Service Water (ESW) system flushing and post-maintenance testing was completed.
Following completion of total outage work scope and surveillances, reactor startup commenced on August 3.
Reactor and generator startup was completed and power subsequently increased to 608 We by August 7.
Inad was limited by intake temperature and its effect on condenser vacuum.
On August 7, power was reduced to approximately 535 We due to excessive grass at the intake structure forcing shutdown of the dilution pumps.
In addition, steam jet air ejector (SJAE) pressure control valve V-1-38 failed in the open position.
%e valve was mechanically closed, restoring pressure control via parallel valve V-1-37.
Plant load was subsequently increased to approximately 631 We.
On August 9, reactor shutdown comenced in order to add oil to Unit Substation (USS) 1A2 and 1B2 transformers.
During the shutdown process, all IRhts were inadvertently inserted, simultaneously, into the core causing a full reactor scram. Cold shutdown was achieved on August 10.
Subsequent to adding oil to the transformers, reactor startup commenced on August 10.
Reactor. and generator startup was completed and power subsequently increased to 600 We by August 12.
On August 13, power was reduced to 570 We in response to reactor recirculation pump motor-generator (MG) set bearing temperatures exceeding the alarm setpoint of 1500F.
He alarm setpoints were determined to be too conservative and were subsequently increased to 1800F.
Power was maintained between 570 and 630 We, as limited by condenser vacuum and discharge canal temperature limits.
On August 19, power was reduced to 570 We to replace
'E' reactor recirculation pump MG Set brushes.
While at.this reduced power level, a steam leak from 1-2 drain tank water column flanges required removal of second stage steam reheaters from service.
Subsequent to returning 'E' reactor recirculation pump to service, power i
was increased to approximately 615 We.
Load was limited by second stage steam reheaters being out-of-service.
On August 25, second stage steam reheaters were returned to service following completion of repairs to No.1-2 drain tank water column valve steam leaks.
On August 26, power was increased to approximately 635 We and maintained for the balance of the report period.
Load was limited by intake temperature and its effect on condenser vacuum.
361g 8511190560 850913 ADOCK 05000219 PDR PDR R
Monthly Operating Report i
The following Licensee Event Reports were submitted during tne montn of August 1985:
Licensee Event Report 50-219/85-015 - An automatic scram occurred on low condenser vacuum from full power on July 8,1985.
The low condenser vacuum condition occurred when Operations perscnnel tripped the 1-1 Steam Jet Air Ejector (SJAE) drain pump wnen it was discovered that water was spraying from a casing crack.
This action allowed air to enter the common suction to both SJAE drain pumps whicn precluded their operation.
Control Room operators took actions to restore condenser vacuum, however, vacuum was not recovered in time to prevent a scram.
All control rods fully inserted, all plant systems responded as required, and operators took action to stabilize the reactor.
A casting Haw in tne casing combined with stress caused oy the absence of a pump support has been determined to be tne cause of the casing crack.
1-2 pump was repaired prior to plant startup, and the 1-1 pump was replaced prior to returning the plant to full power.
Supports have been placed under tne SJAE drain pumps.
Licensee Event Report 50-219/d5-017 - As a result of monitoring drywell temperatures during power operation, drywell bulk average temperatures have exceeded 1350F as calculated, whicn is one of the ini tial accident conditions as documented in Oyster Creek FDSAR Amendment 15 (Primary Containment Design Report).
This temperature is the maximum assumed at the onset of tne design basis accident.
The cause for exceeding 1350F nas been determined to be the conservatism employed in the method for calculating drywell bulk temperature, low cooling water flow to the drywel l and high intake water temperature.
However, tne sensitivity of containment response to a design basis accident using 1500F as an initial drywell temperature nas been evaluated.
The resul ts of this evaluation indicate that peak temperatures and pressures are eitner unchanged or still are well within acceptable ranges.
Corrective actions are to make use of conservatisms available in calculating drywell oulk temperature, utilize additional thermocouples at a lower elevation in the drywell, ensure sufficient cooling water flow to the drywell, and to continue temperature monitoring of the drywell to assure maintenance of bulk temperatures below 1600F.
Licensee Event Report 50-219/85-018 - Emergency Service Water (ESW) System II was declared inoperable following a high Containment Spray Heat Exchanger baffle plate differential pressure condition that developed during a system operability test.
Subsequently, System I
heat exchanger baffle plate differential pressure approacned its' allowable limit.
The decision was made to proceed to cold shutdown since continued operation of System I could not be assured and System II was inoperable.
Examination of the heat exchangers revealed that the inlet tubesheets of the heat exchangers were partially plugged with fragments of coal tar enamel which had been used to coat the inside of the ESW piping for corrosion protection.
High pressure water was used to hydrolaze each loop to remove the affected coating and prevent heat exc' anger plugging.
c
OPERATING DATA REPORT OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PERIOD:
August 1985 3.
UTILITY CONTACT:
JOSEPH R. MOLNAR 609-971-4699 4.
LICENSED THERMAL POWER (MWt):
1930 5.
NAMEPLATE RATING (GROSS MWe):
687.5 X 0.8 = 550 6.
DESIGN ELECTRICAL RATING (NET MWe):
650 7.
MAXIMUM DEPENDABLE CAPACITY (GROSS MWe):
650 8.
MAXIMUM DEPENDABLE CAPACITY (NET MWe):
620 9.
IF CHANGES OCCUR ABOVE SINCE LAST REPORT, GIVE REASONS:
NONE 10.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe): N/A 11.
REASON FOR RESTRICTION, IF ANY: NONE MONTH YEAR CUMULATIVE 12.
REPORT PERIOD HRS 744.0 5832.0 137545.0 13.
HOURS RX CRITICAL 657.3 4700.7 90328.6 14.
RX RESERVE SHTDWN HRS 0.0 0.0 469.7 15.
HRS GENERATOR ON-LINE 620.0 4478.9 88015.6 16.
UT RESERVE SHTDWN HRS 0.0 19.6 22.3 17.
GROSS THERM ENER (MWH) 1131000 7826140 145088469 18.
GROSS ELEC ENER (MWH) 369580 2644770 49027765 19.
NET ELEC ENER (MWH) 354380 2535859 47098424 20.
UT SERVICE FACTOR 83.3 76.8 64.0 21.
UT AVAIL FACTOR 83.3 77.1 64.0 22.
UT CAP FACTOR (MDC NET) 76.8 70.1 55.2 i
23.
UT CAP FACTOR (DER NET) 73.3 66.9 52.7 24.
UT FORCED OUTAGE RATE 16.7 22.9 10.5 25.
FORCED OUTAGE HRS 124.0 1333.5 10284.6 26.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, DURATION):
MAINTENANCE, OCTOBER 1, 1985 - (1 Month) 27.
IF CURRENTLY SHUTDOWN ESTIMATED STARTUP TIME:
N/A
4 AVERAGE DAILY POWER LEVEL NET MWe i
DOCKET f........
50-219 UNIT..........
0yster Creek #1 i
REPORT DATE.
.. SEPTEMBER 05, 1985 COMPILED BY.
. WILLIAM J. EMRICH, JR.
TELEPHONE #......
609-971-4637 i
MONTH AUGUST, 1985 DAY MW DAY MW l
1.
0 16.
579 2.
0 17.
596 3.
0 18.
609 4.
154 19.
611 1
5.
468 20.
571 6.
521 21.
594 7.
552 22.
595 8.
562 23.
595 1
9.
505 24.
595 10.
0 25.
596 11.
164 26.
609 12.
549 27.
609 13.
581 28.
616 14.
579 29.
615 0
15.
575 30.
609 31.
586 i
i 1
1
Oyster Creek Station il Docket No. 50-219 REFUELING INFORMATION - August, 1985 Name of Facility: Oyster Creek Station #1 Scheduled date for next refuelicg shutdown:
April 12, 1986 Scheduled date for restart following refueling: October 13, 1986
-Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Ye's
~
Scheduled date(s) for submitting proposed licensing action and supporting information:
Decembe r, 1935 Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significar.t chaages in fuel design, new operating procedures:
- 1. General Electric Fuel Assemblies - fuel design and performance analysis methods have been approved by the NRC. New operating procedures, if necessary.will be submitted at a later'date.
- 2. Exxon Fuel Assemblies - no major changes have been made nor are there any anticipated.
The number of fuel assemblies (a) in the core 560
=
(b) in the spent fuel storage pool = 1204 (c) in dry storage 4
=
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:
Present licensed capacity:
2,600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Reracking of the fuel pool is in progress. Four out of ten (10) racks have been installed to date. When reracking is completed, discharge
(
capacity to the spent fuel pool will be available until 1990 refueling outage.
DOCKET NO.
50-219 UNITSilUTDOWNS AND POWER REDilCTIONS UNIT NAME Oyster Creek DATE August 1985 COMPI.ETED FtY R. Baran REPORT MON DI August 1985 IEl.FrilONE 971-4640 jg "g
Licensee
,En,,
a, Cause A Corrective No.
Date
[
3=
3ss Event 33 g3 Action tu f$
s jiji g Repor a mo u
Preven' Recurrence t-g 39 7/22/85 P
306.3 D
1 N/A ZZ ZZZZZZ 39.
Peactor Shutdown for ESW Insnection, Cleaning and Flushing.
40 8/9/85 P
39.0 B
1&3 N/A ZZ ZZZZZZ 40.
Peactor Shutdown due to inactquate oil level in Unit Substation lA2/
1B2 transformers. Manual shutdown was in progress when all IBMs were inadvertently inserted resulting in a full reactor scram.
. 25.6% reduction in power due to tmoorary reduction in vacuum in "C" condenser. 'Ihe lCl SJAE suction valve failed coen.
1 I
(
n li 2
3 4
F: Forced Reason:
Method:
Exhibit G. Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manus!
for Preparation of Dita 34 taint: nance of Test 2-Manual Scram.
Entry Sh::ts for 1.icensee C-Refu: ling 3-Au omat Scram.
Event Report (LER) File (NilREG-D-R :ulatory Restriction 4 Other (Explain) 0161)
E-Operator Trainin & Ucense Examination F-Administrative 5
G-Operational Ermt (Explain)
Exhibit I-Same Source (9/77)
Il-Oth:r (Explaia)
.