ML20207C228
| ML20207C228 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/30/1986 |
| From: | Baran R, Fiedler P, Notigan D GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 0170A, 0839G, 0841A, 1619B, 170A, 1965B, 1968B, 839G, 841A, NUDOCS 8607210301 | |
| Download: ML20207C228 (7) | |
Text
-_ _ _ __
Monthly Operating Report The following Licensee Event Reports were submitted during the month of f
April 1986:
Licensee Event Report 50-219/86-004 - On March 6,1986, while operating at j
92% power, a surveillance was in progress on turbine stop valves 3 and 4 to t
verify anticipatory scram signals.
Coincidently, the position switch on stop valve 1 spuriously opened causing an anticipatory turbine trip reactor scram.
The reactor mode switch was inadvertantly left in the "run" Mode which caused the Main Steam Isolation valves to close when reactor pressure dropped to the low setpoint.
Due to the fact that water level increased beyond that which allowed the Isolation Condensers to be operated, pressure was controlled with the Electromatic Relief Valves until the level was lowered enough to allow Isolation Condenser operation.
Reactor pressure was lowered, the scram reset, and the Main Steam Isolation valves were opened.
The reactor was brought to a lj hot standby condition.
The cause of the scram was attributed to the failure of the position switch on turbine stop valve 1.
The switch was replaced and j
tested satisfactorily.
The remaining switches on the other 3 stop valves also tested satisfactorily.
Additionally, during this event Containment Isolation i
valve V-16-14 was declared inoperable following the scram but neither V-16-14 nor V-16-1 were deactivated closed as required by Te:hnical Specifications.
At least one valve in the penetration was closed.
This condition existed for j
approximately eight hours until V-16-14 was deactivated closed.
'j Licensee Event Report 50-219/86 On March 18, 1986, during routine surveillance testing, the Isolation Condenser automatic actuation pressure i
sensors RE15A, RE15C and RE15D tripped at values greater than those specified j
in Technical Specifications 2.3.E.
The sensors were adjusted to trip within the desired setpoint limits.
GPUN has evaluated this concern about setpoint j
drift on these pressure switches.
These sensors are scheduled to be replaced during the 11R outage with SOR pressure switches.
However, currently GPUN is
{
experiencing drift problems with other SOR sensors installed at Oyster Creek j
(reference LER 86-007, submitted on 4/26/86).
GPUN is evaluating the recent
{
events with SOR and, should we decide not to replace these switches a supplemental LER will be submitted describing our revised corrective action.
j This event had no effect upon public health or safety.
Licensee Event Report 50-219/86 On March 27, 1986, a plant shutdown was conducted due to repeatability / drift problems with Reactor Low Water Level 1
Scran switches.
The suspect Reactor Low Water Level Scram switches (SOR, l
" Static-0-Ring", model 103ASB212NXJJTTX6) were installed during the Oyster r
Creek Environmental QualiTication outage in October / November 1985.
Performance of monthly surveillances revealed setpoint dri f t problems.
Increased surveillance frequency did not resolve the setpoint drif t/
j repeatability problem.
Evaluation of the accumulated calibration data, and discussions with technical representatives of SOR, concluded that the switches c
were not meeting their design specifications, and that the magnitude and l
direction of future drifting was uncertain.
It was also determined that the i
failure mechanism was not known.
A plant shutdown was initiated and the l
Reactor Low Water Level SOR switches were replaced with a different model SOR I
switch. ~ tee replacement model (103ASBB212NXJJTTX6) is the same model number 1
as 4 switches installed in the November 1985 outage for the Reactor low Low i
Water Level switches which have performed satisfactorily.
Startup commenced i
on March 30, 1986.
l l
dam:(0841A)
]
16d 4 i
0607210301 060430 DR ADOCK 0000
//
j l
+
MON 111Y OPERATING REPORT - APRIL 1986
\\
4 At the beginning of the report period, Oyster Creek was increasing load j
following plant startup on March 30.
On April 3, plant load stabilized l
at 561 We after establishing Xenon equilibrium.
All control rods were j
fully withdrawn by April 4, in a coastdown mode due to core depletion.
On April 5, while conducting a reactor Icw water level surveillance test, a reactor low-low water level sensor activated due to inadequate sensor j
line venting.
This generated a momentary start signal for both Core l
Spray Systems, both Diesel Generators and caused a trip signal on Channel
'A' on the ATKS panel. The condition cleared after approximately one (1) i second, signals reset and all systems returned to normal.
A post-trip review conducted of the event recommended changes to the surveillance procedure to ensure adequate sensor line venting.
On April 5,
'D' reactor recirculation pump outboard seal failed.
The inboard seal previously failed during startup following the forced outage I
for replacement of the RE05 reactor water level sensors.
The pump was 1
removed from service and reactor power was maintained by the remaining four (4) recirculation pumps.
Power was reduced to approximately 520 We l
and was subsequently increased to 535 We on April 6.
1
{
On April 7, the newly installed RE05 reactor water level sensors were 1
tested and sensor RE05A1 required calibration.
RE05Al was tested daily with satisfactory results for the balance of the operating period.
The RE05 sensors will be replaced with sensors of improved design during the Cycle 11 Refueling Outage (11R).
l On April 10, in preparation for the start of the 11R outage, a secondary l
containment leak rate test was performed with satisfactory results.
)
Reactor shutdown for the 11R Refueling / Maintenance / Modifications Outage comenced on the evening of April 11.
At 2316 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.81238e-4 months <br />, Operations l
personnel commenced shutting down the plant from a load of 525 We.
The j
generator was taken off-line at 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> on April 12 and all control l
rods were fully inserted by 0653 hours0.00756 days <br />0.181 hours <br />0.00108 weeks <br />2.484665e-4 months <br />.
The reactor was less than 2120F (cold shutdown) by 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />.
On April 22, a lightning arrester in the substation failed which resulted l
in a switchyard fire. The resulting power surge caused reactor, drywell, l
Cleanup System and Reactor Building Ventilation System isolation.
l Additionally, the Standby Gas Treatment System initiated and various operating equipment was affected.
All required notifications were made.
Plant conditions were subsequently returned to normal.
1 l
l j
i 0839g
=.
l j
OPERATING DATA REPORT l'
OPERATING STATUS 1.
DOCKET:
50-219 2.
REPORTING PE.IIOD:
APRIL, 1986 3.
UTILITY CONTACT:
DONALD V. NOTIGAN 609-971-4695 4.
LICENSED 'IllEIBtAL POWER (hWt):
1930 5.
NAMEPLATE RATING (EOSS bMe):
687.5 X 0.8 = 550 i
6.
DESIGN ELECIRICAL RATING (NET hWe):
650 7.
MAXIMlM DEPENDABLE CAPACITY (20SS FMe):
650 8.
MAXIMlN DEPENDABLE CAPACITY (NET bWe):
620 9.
IF OIANGES OC0JR AB0VE SINCE LAST REPORT, GIVE REASONS:
NONE 10.
POWER LEVEL TO WHIOl RES1RICTED, IF ANY (NET FWe):
i OUTPUT DECREASES APPROXIMATELY 2 bMe PER DAY
- 11. REASON FOR RESTRICTION, IF ANY: END OF CYCLE COASTDOWN 1
l l
MONT11 YEAR O MJLATIVE 12.
REPORT PERIOD IRS 71 9. 0 2879.0 143352.0 i
- 13. IDURS RX CRITICAL 270.5 2311.5 94758.9 i
I
- 14. RX RESERVE SifrDWN IIRS 448.5 448.5 918,2 15.
IRS GENERATOR ON-LINE 266.2 2273.9 92333.0 t
- 16. UT RESERVE SifrDWN llRS 452,8 452.8 1208.6 17.
GROSS TIIERM ENER (bMt) 429438 4074338 152951807 18.
GROSS ELEC ENER (hWil) 139010 1371480 51662165
}
- 19. NET ELEC ENER (bMll) 133091 1317153 49625754 20.
UT SERVICE FACIDR 37.0 79.0 64.4 i
21.
UT AVAIL FACIDR 100.0 94.7 65.3 l
- 23. (TT CAP FACIOR (DIR NET) 28.5 70.4 53.3 24.
IJr FORCED OUTAGE RATE
- 0. 0
- 6. 3 10,3
{
\\
l 25.
FORCED OUTAGE IRS 0.0 152.3 10587.9 j
i
- 26. SilVTDOWNS SOIEDULED OVER NEXT 6 MONTIS (TYPE, DATE, DURATION):
l APRIL 12, MALYTENANCE/ REFUELING OUTAGE i
j 27.
IF CURRENTLY SilUTDOWN ESTIMATED STARTUP TIME:
10/12/86 i
1965B i -.....
l
AVERAGE DAILY POWER LEVEL NET bMe DOCKET #........
50-219 UNIT.......... 0YSTER CREEK #1 REPORT DATE.......MAY 6, 1986 C0blPILED BY....... DONALD V. NOTIGAN TELEPIONE #......
609-971-4695 bONTil APRIL,1986 DAY bM DAY FM 1.
495 16.
0 2.
445 17.
0 3.
517 18.
0 4.
514 19.
0 5.
520 20.
0 6.
506 21.
0 7.
510 22.
0 8.
507 23.
0 9.
507 24.
0 10.
506 25.
0 11.
500 26.
0 12.
18 27.
0 13.
0 28.
0 14.
0 29.
0 15.
0 30.
0 1968B
Oyster Creek Station #1 Docket No. 50-219 REFUELING INFORMATION - APRIL,1986 Name of Facility: Oyster Creek Station #1 i
Scheduled date for next refueling shutdown: April 12,1986 Scheduled date for restart following refueling: October 12, 1986 Will refueling or resumption of operation thereaf ter reqJire a Technical Specification change or other license amendment?
Yes Scheduled date(s) for submitting proposed licensing action and supporting information:
June, 1986 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:
- 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 94
=
(b) in the spent fuel storage pool = 1730 (c) in the dry storage 148
=
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:
2600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
4 Reracking of the fuel pool is in progress.
Six (6) 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.
1619B
50-219 UNIT SilDTDOWNS AF.D POWER REDUCTIONS DOCKETNO. _ Oyster Creek UNITNAME _5/1/86 DATE COMPLETED BY R.
Baran REPORTMONTil April 1986 TELErilONE 9 71-4 fi a n
'l O
c:
E E "g
.['g Licensee Eg Cause & Cortective
~
^ ' " " ' ' '
No.
Date
{
g
=
, ;a Event p
Eu Pievent Recurrence F
fE 5
j;g g Repor: #
mo g
8 46 4/12/86 S
453.8 C
1 N/A N/A N/A Plant shut down for the llR Outage.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A Equirment Failure (Explain) l Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automalle Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4 Other 8Fxplain) 0161)
E-Operator Training a Ucense Examination F-Administrative 5
Exhibit I-Same Source Gopera:lonal Error (Explain) 19/77)
Il-Other (Explain)
ENuclear
= 0 & ""
Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Numbe,:
May 15, 1986 Director Office of Management Information U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Monthly Operating Report In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1.C, enclosed are two (2) copies of the Monthly Operating Data (gray book information) for the Oyster Creek Nuclear Generating Station.
If you should have any questions, please contact the Oyster Creek Licensing Manager at (609) 971-4643.
Very truly yours, e
AA )
A
-a Wdler Vice President and Director Oyster Creek PBF:ED: dam (0170A)
Enclosures cc: Director (10)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 NRC Resident Inspector Oyster Creek Nuclear Generating Station 6
h onu noaca, ce,no, anon,s a sens,um,v onne acoe,oennc unnoes corno,anoo k
---