ML20211Q582
| ML20211Q582 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/30/1986 |
| From: | Koester G, Mike Williams KANSAS GAS & ELECTRIC CO. |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| KMLNRC-86-234, NUDOCS 8703030131 | |
| Download: ML20211Q582 (11) | |
Text
_
NOLP CREEK GENERATING STATION MONTHLY OPERATING REPORT MONTH: November YEAR: 1986 Docket No.: SIN 50-482 Facility Operating License No.: NPF-42 Report No.
21 I
Subnitted by:
Kansas Gas and Electric Canpany
'\\[ {x I
8703030131 861130
9
-%e following report highlights the operating experience of Wolf Creek Generating Station for the month of November, 1986. This report is being provided pursuant to Technical Specification 6.9.1.8.
I.
SUMMARY
OF OPERATING EXPERIENCE We plant remained in Mode 6, Refueling, throughout the month of November.
II.
MAJOR SAFETY RELATED MAINTENANCE ACTIVITIES Major safety related maintenance activities included replacement of three primary loop and one seal water return flow transmitters; replacement of three circuit boards; annual,18-month surveillance tests, and MOVATS tasts of motor operated valves; repacking manual valves; reworkire vent and drain valves and check valves; eddy current testing two and sludge lancing all stean generators; replacing ICP "C" seal cartridge; surveillance inspection of both diesel generators and replacing their keep-warm punps; replacement of both Boric Acid Storage Tank diaphragms; surveillances of the RHR; ESW arxl SI punps; replacement of the seals on both Centrifugal Chargirg Pumps; annual surveillance of switchgear; testing 17 relief valves; con 3ucting MIC inspections; refueling the reactor and settire its head.
III. CHANGES, TESTS, AND EXPERIMENTS
%e following is a brief description of safety evaluations performed pursuant to 10 CFR 50.59 on changes, tests, and experiments during the month of Novenber.
1.
Plant Modification Request KN84-044, revision 2 - Originated to correct HVAC as-built drawings and provide a3ditional docunentation to the PMR, which replaces the Fuel Building hot water heaters with electric heaters. No unreviewed safety or environmental questions are generated as a result of this plant modification.
2.
Plant Itdification Request WO84-BB089, revision 2 - Originated to correct a wiring discrepancy in the PMR, which provides annunciation if the RHR systen is not properly isolated when RCS pressure is increased. No unreviewed safety or environnental questions are generated as a result of this plant modification.
3.
Plant Modification Request WO84-BB089, revision 3 - Originated to correct a drawing discrepancy in the PMR. No unreviewed safety or environnental questions are generated as a result of this plant modification.
4.
Plant Modification Request 00354, revision 4 - Originated to correct field cable routing and Manhole 267 drainage in the PMR, which provides a service drive to the Reactor Building Equipnent Hatch. No unreviewed safety or environnental questions are generated as a result of this plant modification.
5.
Plant Pbdification Request 00441, revision 4 --Originated to allow site personnel to perform the work activities of the PMR, which adds three annunciators. No unreviewed safety or environmental questions are generated as a result of this plant modification.
6.
Plant Modification Request 00657, revision 3 - Originated to correct diaphragm attachment in the PMR, which increases the service life of the Boric Acid Storage Tank diaphragms. No unreviewed safety or environmental questions are generated as a result of this plant modification.
7.
Plant Pedification Request.00804, revision 2 - Originated to correct ductwork and provide permanent access platforms and ladders to the PMR, which provides quick disconnect of the CRDM ventilation ductwork. No unreviewed safety or environmental questions are generated as a result of this plant modification.
8.
Plant Modification Requee,c 00804, revision 3 - Originated to modify the refuelirs machine to interface with the CRDM ductwork redesign. No unreviewed safety or environmental questions are generated as a result of this plant modification.
9.
Plant Modification Request 00804, revision 4 - Originated to delete same stitch welds fran the PMR. No unreviewed safety or enviromental questions are generated as a result of this plant modification.
- 10. Plant Pbdification Request 00904 - Originated to install manual gate valves downstrean of ESW check valves EF-V046 and EF-V076 to allow testing the check valves. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 11. Plant obdification Request 01149, revision 1 - Originated to utilize an intermittent fillet weld in lieu of a continuous fillet weld in this PMR, which provides larger reservoirs for the MSIV's ard MPIV's. No Inreviewed safety or envirormental questions are generated as a result of this plant modification.
- 12. Plant Modification Request 01206, revision 2 - Originated to change the mating flange for BG-V496 for this PMR, which provides threaded cap connections to facilitate ECCS venting. No unreviewed safety or envirornnental questions are generated as a result of this plant modification.
- 13. Plant bbdification Request 01594 - Originated to modify the secondary liquid waste (HF) evaporator system to allow it to process liquid radwaste. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 14. Plant Modification Request 01722, revision 7 - Originated to prcnide additional settirgs and improve the docmentation to this PMR, which revises motor operated valve switch settings. No unreviewed safety or envirormental questions are generated as a result of this plant modification.
Page 2 of 9
- 15. Plant Modification Request 01741 - Originated to modify the Condensate Demineralizer (AK) system acid dilution water pipirg.
No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 16. Plant Modification Request 01818, revision 1 - Originated to revise the classification frm Special Scope to Safety Related for this PMR, which routes the discharge piping for the Auxiliary Feedwater Control / Main Stean Atmospheric Relief Valves Accunulator relief valves to outside. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 17. Plant Pedification Request 01820 - Originated to relocate the Condensate Pep discharge sanple tap. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 18. Plant ?bdification Request 01842, revision 1 - Originated to incorporate the Reactor Coolant System (BB) and Component Coolirg Water (EG) valves in this PMR, which separates the motor operated valve position and indication switches frm the torque bypass switches. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 19. Plant ledification Request 01864 - Originated to change the part number for replacement diaphragms for Masonellan diaphragms for casing sizes 18 and 9.
No unreviewed safety or envirorynental questions are generated as a result of this plant modification.
- 20. Plant Ibdification Request 01877 - Originated to modify the time delay circuit for starting the Diesel Fire Pump. No unreviewed safety or environnental questions are generated as a result of this plant modification.
- 21. Plant Modification Request 01879 - Originated to replace the casing drain lines of the Reactor Makeup Water Transfer Punps with pipe plugs. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 22. Plant Modification Request 01886 - Originated to replace the travel stops for 1 1/2" Yarway Hy-Drop valves. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 23. Plant Ebdification Request 01886, revision 1 - Originated to replace the stem hex nut with double jan nuts on this PMR. No unreviewed safety or environnental questions are generated as a result of this plant modification.
- 24. Plant bbdification Request 01888 - Originated to hard surface an area of Essential Service Water pipiry that is experiencirg erosion. No unreviewed safety or environmental questions are generated as a result of this plant modification.
Page 3 of 9
f.
- 25. Plant Modification Request 01903 - Originated to repair and hard surface an area of Essential Service Water piping that is experiencing erosion. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 26. Plant !Odification Request 01903, revision 1 - Originated to provide an alternate repair procedure for the PMR. No unreviewed safety or environmental questions are generated as a result of this plant modification.
- 27. Safety Evaluation 86-SE-161 - Originated to tenporarily allow lifting lead 14GKY02BB-1 at danper 6KHZ40B for troubleshooting while the danper is blocked open, the position required for a CINIS signal. No unreviewed safety or environmental questions are generated as a result of this temporary modification.
- 28. Safety Evaluation 86-SE-162 - Originated to allow tenporary lead blanketing of Stean Generator "A" primary side drain line 230-BCB-3/8" and valve BB-V265 during Modes 5 and 6.
No unreviewed safety or environnental questions are generated as a result of this tenporary nudification.
- 29. Safety Evaluation 86-SE-163 - Originated to allow tack welding the breaker rack-out assist rod to its bracket in breaker NB0ll3. No unreviewed safety or environnental questions are generated as a result of this tenporary nodification.
- 30. Safety Evaluation 86-SE-164 - Originated to temporarily allow removal of a spool piece down streau of Essential Service Water valve EF IN-47, closing EF HV-47 and blank flanging the pipe at the other end of the spool piece. Flow will be maintained through parallel valve EF IN-49. No unreviewed safety or environnental questions are generated as a result of this temporary modification.
- 31. Safety Evaluation 86-SE-165 - Originated to tenporarily allow connecting a 1 1/2" hose fran the Denineralized Water Tank valve AN-V003 to the sitr3ge lance trailer. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.
- 32. Safety Evaluation 86-SE-166 - Originated to tenporarily supply danestic water to the Canputer Roan cooling coils SGE10A and 10B during the Service Water outage. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.
- 13. Safety Evaluation 86-SE-167 - Originated to tenporarily replace five Gai-tronics handset stations with hea3 set stations during LLRT testing. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.
- 34. Safety Evaluation 86-SE-168 - Originated to allow shortening the nozzle ring set screw for Positive Displacement Charging Puup relief valve BG-8118. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.
Page 4 of 9
- 35. Sc.fety Evaluation 86-SE-170 - Originated to tenporarily use a hose to bypass a portion of the Evaporator Bottans "ank discharge piping that has been blocked with crystalized boron. No unreviewed safety or environnental questions are generated as a result of this tenporary modification.
- 36. Safety Evaluation 86-SE-171 - Originated to utilize connercial grade rivets to repair danper GK-D300. No unreviewed safety or environmental questions are generated as a result of this tenporary modification.
37 Safety Evaluation 86-SE-120, revision 1 - Originated to allow tenporary lead blanketing of the Pressurizer Spray Valves and associated piping during 1% des 5 and 6.
No unreviewed safety or environnental questions are generated as a result of this tenporary modification.
Page 5 of 9 l-
OPERATING DATA REPORP DOCKETf NO.
STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECTRIC COMPANY DATE 12-01-86 COMPLETED BY M. Williams TELEPHONE 316-364-8831 OPERATING STATUS 1.
Reporting Period:
Novenber,1986 Gross Hours in Reporting Period: 720 2.
Currently AuthoriN Power Level (MWt): 3411 Max. Depend. Capacity (MWe-Net) : 1128 Design Electrical Rating (MWe-Net): 1170 3.
Power Level to Which Restricted (If Any)(Mwe-Net):
N/A 4.
Reasons for restriction (If Any):
N/A
'Ihis mnth Yr to Date Cuuulative 5.
Number of Hours Reactor was Critical 0.0 6216.7 9007.0 6.
Reactor Reserve Shutdown Hours 0.0 92.5 171.3 7.
Hours Generator on Line 0.0 6178.4 8950.0 8.
Unit Reserve Shutdown Hours 0.0 0.0 0.0 9.
Gross Thennal Energy Gene ~:ated (M) 0.0 20,220,409 29,095,342
- 10. Gross Electrical Energy Generated (MWH) 0.0 7,069,422 10,140,512
- 11. Net Electrical Energy Generated (M)
- 0. 0_
6,766,386 9,708,486
- 12. Reactor Service Factor 0.0 77.6 82.7
- 13. Reactor Availability Factor 0.0 78.7 84.2
- 14. Unit Service Factor 0.0 77.1 82.1
- 15. Unit Availability Factor 0.0 77.1 82.1 l
- 16. Unit Capacity Factor (Using MDC) 0.0 74.8 79.0 l
l
- 17. Unit Capacity Factor (Usirg Design MWe) 0.0 72.1 76.2
- 18. Unit Forced Outage Rate
_0.0 4.5 4.3
- 19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of each): None l
20.
If Shut Ibwn at End of Report Period, Estimated Date of Startup:
12-20-86 l
l
- 21. Units in test Status (Prior to Coninercial Operation): Forecast Achieved l
l Initial Criticality 5-22-85 5-22-85 l
Initial Electricity 6-13-85 6-1_2-85 l
Coninercial Operation 9-09-85 9-03-85 l
Pqe 6 of 9 I
AVERAGE DAILY UNIT POWER LFNEL DOCKET NO.
STN 50-482 WOLF CREEK GENERATING STATION KANSAS GAS AND ELECPRIC COMPANY DATE 12-01-86 COMPLETED BY M._ Williams TELEPHONE 316-364-8831 M0t m l November, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (lWe-Net)
(lWe-Net) 1 0
17 0
2 0
18 0
3 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 0
Page 7 of 9
+
-,-----_,r-e--y.---r*-*v
- -w'-w aa-
-t'-
-w-v-4w
"e=-+*-'--------w
--*9--
+-r--s
-*'r t--
3 UNIT SHUPDOWN AND POWER REDUCTIONS DOCKET NO.
STN 50-482 WOLF CREEK GENERATING STATICM KANSAS GAS AND ELECTRIC COMPANY DATE 12-01-86 00MPLETED BY M. Williams REEORP MONTH November, 1986 TELEPHONE 316-364-8831 TYPE ME71 HODS SHUfrING F: FORCED DURATION REASON DOWN THE REACIDR CORRECTIVE ACTIONS /COPMNfS No Date S: SCHEDULED (HOURS)
(1)
OR REDUCING POWER (2) 11 861101 S
720.0 C
1 Continued refueling outage.
Simes: The first refueling outage continued throughout the month.
(1)
REASON: A: EQUIPMENT FAILURE (EXPIAIN)
E: OPERATOR TRAINING AND LICENSE EKAMINATION (2)
METHOD:
1.
MANUAL B: MAINTENANCE OR TEST F: ADMINISTRATIVE 2.
MANUAL SCRAM C: REFUELING G: OPERATIONAL ERBOR (EKPIAIN) 3.
AtTIOMATIC SCRAM D: REGUIATORY RESTRICTION H: OIEER (EXPLAIN) 4.
OIRER (EKPLAIN)
Page 8 of 9
KNISAS GAS AND ELECTRIC COMPANY WOLP CREEK GENERATING STATION UNIT NO. 1 M0tml November, 1986
SUMMARY
OF OPERATING EXPERIENCE Litted below in chronological sequence is a stmmary of operatiry experiences for this month which required load reduction or resulted in significant non-load related incidents.
DA'IE TIME EVENP Novenber 1, 1986 0000 Unit in Mode 6, Refueling Page 9 of 9 L
KANSAS GAS AND ELECTRIC COMPANY THE ELECTRC COMPANY December 15, 1986 o o,,,, e n o c. r e,,
V8CE perESeDps?. MuCLEAID Director, Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. E. H. Johnson, Director Division of Reactor Safety and Projects U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 86-234 Re:
Docket No. 50-482 Subj: November, 1986 Monthly Operating Report Gentlemen:
Enclosed is the November, 1986 Monthly Operating Report for Wolf Creek Generating Station.
This submittal is being made in accordance with the requirements of Technical Specification 6.9.1.8.
Yours very truly, 0
0 Glenn L. Koester Vice President - Nuclear GLK:see Enclosure cc: P0'Connor (2), w/a JTaylor (12), w/a JCummins, w/a
<(
201 N. Market - Wictuta, Kansas - Mail Address: PO. Box 208 I Wichita. Kansas 67201 - Telephone: Area Code (316) 2616451
_