ML20207D738
| ML20207D738 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/31/1986 |
| From: | Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8612310184 | |
| Download: ML20207D738 (58) | |
Text
,
TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUDYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION
" AUGUST 1986" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:
P. R. Wallace, Plant Manager 9
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O TABLE OF CONTENTS Page I.
Operational Summary Performance Summary 1
Significant Operational Events 1
Fuel Performance and Spent Fuel Storage Capabilities 2
PORVs and Safety Valves Summary 2
Licensee Events and Special Reports 2-4 Offsite Dose Calculation Manual Changes 4
II.
Operating Statistics A.
NRC Reports Unit one Statistics 5-7 Unit Two Statistics 8-10 B.
TVA Reports Nuclear Plant Operating Statistics 11 Unit Outage and Availability 12-13 Reactor Histograms 14 III. Maintenance Summary Electrical Maintenance 15-16 Instrument Maintenance 17-24 1
Mechanical Maintenance 25-30 Modifications 31-39 IV.
Environmental Qualification (EQ) Summary 40-46 Y
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9 OPERATIONAL SUMMApy a
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i PERFORMANCE SUNNARY August 1986 i
r The following summary describes the significant operational activities for the month of August.
In support of this summary, a chronological log of i
significant events is included in this report.
2-The units remained in an administrative shutdown the entire month due to design control review, configuration control updating and resolution of significant employee concerns. Outage.related maintenance and modifications are being performed. Unit I has been off-line 374 days. Unit 2 has been off-line 375 days.
SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 08/01/86 0001C The reactor was in mode 5.
The administrative i
shutdown due to design control review, configuration I
control updating and resolution of significant employee concerns continues, i
08/31/86 2400C The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.
Unit 2 j
Date Time Event i
I 08/01/86 0001C The reactor was in mode 5.
The administrative shutdown due to design control review, configuration
(
j control updating and resolution of significant employee concerns continues.
08/31/86 2400C The reactor was in mode 5.
The administrative i
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control updating and resolution of significant employee concerns continues.
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FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during August was 0 MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
Unit 2 The core average fuel exposure accumulated during August was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU.
SPECIAL NUCLEAR MATERIAL SAFEGUARDS & ACCOUNTABILITY SYSTEM ANNUAL REVIEW The annual review of the plant's special nuclear material (SNM) fuel inventory and records review was performed on August 5-6, 1986. A physical inventory was performed on August 5 in the new fuel storage vault on new fuel, 80 bundles, unit 2 cycle 4.
There were no discrepancies. Videotapes were also reviewed on unit I core and spent fuel pit. Again, there were no discrepancies.
SPENT FUEL PIT STORAGE CAPABILITIES The total storage capability in the spent fuel pit (SFP) is 1,386.
- However, there are five cell locations which are incapable of storing spent fuel.
Four locations (A10, All, A24, A25) are unavailable due to a suction strainer conflict, and one location (A16) is unavailable due to an instrumentation conflict.
Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1,033.
PORVs AND SAFETY VALVES
SUMMARY
No PORVs or safety valves were challenged in August 1986.
LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in August 1986.
LER Description of Event 1-86025 Two (2) inadvertent diesel generation (D/G) starts occurred on July 15 and July 24, 1986, respectively.
Item 1 At 0804 CDT, July 15, 1986, after replacing a fuse for verification on the normal feeder breaker that comes from the "2C" 6.9 kilovolt (kV) unit board, the normal feeder breaker tripped, causing the required D/G start. When attempting to transfor the 2B-B 6.9 kV board back to its normal breaker, personnel failed to verify the normal bus was energized. This caused 2B-B D/G to load due to loss of power.
Item 2 At 0904 CDT, July 24, 1986, an A-train D/G start occurred while verifying breaker data on direct current (DC) vital battery board "I."
Two (2) breakers tripped when a pcnol slipped while checking nameplate data on the breakers..
e LER Description of Event
)
1-86030 During a comparison of technical specifications (TSs),
surveillance requirements (SRs). and surveillance instructions (sis), three (3) activities had not been performed.
i
- Item 1 On July 17, 1986, at 1155 CDT, during a review of SI-3, " Daily, Weekly, and Monthly Logs," it was discovered that the utility bus tie breakers (UBTB) have not been verified open every seven (7) days as required by TS SR 2.8.1.1.1.
The instruction 4.
contains the specific SR in the procedure, however, there is no place on the data sheet to verify the UBTB. Sequoyah's held order procedure has been used to maintain all four (4) of these i
breakers open since 1974. These breakers would be used in an emergency to tie the trainized 6.9 kV shutdown boards. An SI revision will be submitted to show' verification of the UBTBs.
Item 2 During a review of Instrument Maintenance Instruction (INI) 99, 3
Response Test 11.5, " Response Time Test Of A T (Average i
Temperature) Tava Channel I Rack I," it was discovered on July 16, 1986, test the pressurizer pressure and the neutron 4
flux inputs have not been response time tested, but T.,g inputs had been tested in the past. Also, response tests 11.6 i
11.7, and 11.8 perform the same function as 11.5 Channel I, but
[
J the changes are II, III, and IV, respectively. This is required per Technical Specification Surveillance Requirement 4.3.1.1.3.
An SI revision will be submitted to perform all three (3)
}
functions.
j Item 3 On July 21, 1986, at 0600 CDT, a review of SI-205, " Channel l
Calibration For Radiation Monitoring Systems," and SI-281,
" Functional Tests of Radiation Effluent Monitors With Automatic 4'
Actuation," it was discovered that the steam generator (S/G) blowdown and condensate domineralizer effluent radiation monitors (RM) are not designed to isolate the effluent path on downscale failure as required by Technical Specification Surveillance Requirement 4.3.1.1.3.
The circuitry has never I
' existed to perform this function. A TS change will be submitted i
to remove this automatic isolation.
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s SPECIAL REPORT (S)
There were no reports submitted to the NRC in August 1986.
OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah offsite dose calculation manual during the month.
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REPORT PERIDD: AUGUST 1986 8., zc ;R M$p..
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-327 UNIT : ONE DATE : SEPTEMBER 8.1986 s
COMPLETED BY : D. C. DUPREE TELEPHONE :(B15)B70-6544 MONTH: AUGUST 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)
DAY (MWe Net) 01 0
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-327 UNIT NAME sequoyah one DATE September 2, 1986 COMPLETED BY D. C.
Dupree.
REPORT MONTH August 1986 TELEPHONE (615)870-6544 1
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SF: Forced Reason:
S: Scheduled A-Equipment Failure (Explain) 1-ilanual for Preparation of Data B-!!aintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & Li, cense Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit'I-Same Source 3
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328
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UNIT : TWO DATE : SEPTEMBER 8.1986 COMPLETED BY,: D. C. DUPREE t
TELEPHONE :C6153870-6544 MONTH: AUGUST 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CHWe Net)
DAY CHWe Net) 01 0
17 0
4 02 0
18 0
03 0
19 0
04 0
20 0
4 05 0
21 0
06 0
22 0
07 0
23 0
08 0
24 0
09 0
25 0
10 0
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-328 UNIT NAME Sequoyah Two DATE september 2, 195b COMPLETED BY D. c. Dupree REPORT !!ONTli August 1986 TELEP110NE (615)870-6544 m
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Date c
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$55 R
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4 Design Control, Configuration Upda' ting, and Employee Concerns.
2 i
3 Method:
4 Exhibit G-Instructions 2 Reason:
1F: Forced S: Scheduled A-Eijuipment Failure (Explain) 1-ifanual for Preparation of Data B-!!aintenance or Test 2-!!anual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NllREG-0161)
E-operator Training & License examiraation Outage F-Ailministrative 5-Reduction SExhibit I-Same Source' G-Operational Error (Explain) 9-Other Il-Other (Explain)
- Corrected
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TVA 73e2A (Dr@.6-eu NUCLEAR PLANT OPERATING STATISTICS 1
+l Sequoyah Nuclear Plant
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- eriod riours 744 Month August 19 86 Iten No.
Unit No.
UNIT ONE UNIT TWO PLANT I
Averace Hourly Gross Load kW 0
0 0
2 Maximum Hour Net Generation. MWh 0
0 0
3 Core Thermal Energy Gen. GWD (t)2 0
0 0
4 Steam Gen. Thermal Energy Gen., GWD (t)2 0
0 0
5 Gross Electrical Gen., MWh 0
0 0
j 6
Station Use, MWh 3,783 5,384 9,167 8
7 Net Electrical Gen., MWh
-3,783
-5,384
-9,167 5
8 Station Use, Percent N/A N/A N/A 9
Accum. Core Avg. Exposure, MWD / Ton!
0 0
0 6
10 CTEG This Month,10 BTU 0
0 0
11 SGTEG This Month,106 BTU 0
0 0
12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use Hours-Min.
0.00 0.00 0.00 15 Capacity Factor, Percent 0.0 0.0 0.0 y
16 Turbine Avail. Factor, Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 d
18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0 g
I; 19 Reactor Avail. Factor. Percent 0.0 0.0 E
20 Unit Avail. Factor. Percent
- 0. 0
- 0. 0
~
0.0
- 0. 0 21 Turbine Startuos 0
0 0
22 Reactor Cold Startuos 0
0 0
23 g
24 Gross Heat Rate, Btu /kWh N/A N/A N/A 25 Net Heat Rate,8tu/kWh N/A N/A N/A
?
26 O
27 g
28 Throttle Pressure, psig N/A N/A N/A 29 Throttle Temperature *F N/A N/A N/A j
30 Exhaust Pressure, InHg Abs.
N/A N/A N/A E
31 Intake Water Temp., 'F N/A N/A N/A H
32 33 Main Feedwater, M tb/hr N/A N/A N/A y
34 35 36 37 Full Power Capacity, EFPD 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.841' 210.8416 N
39 Oil Fired for Generation, Gallons 3,894 5
40 Oil Heatina Value. 0tu/ Gal.
138,000
~
41 Diesat! Generation. MWh 59 47 Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor, %
3 43 N/A N/A N/A N/A N/A N/A O
Remarks: IFor BFNP this value is MWD /STU and for SONP and WONP this value is MWD /MTU.
j 2(t) indicates Thermal Energy.
3 m
Date Submitted.
Date Revised
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- _a
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e
SUMMARY
OF MAINTENANCE ACTIVITIES i
6 6
e MAINTENANCE
SUMMARY
(ELECTRICAL)
P
ELECTRICAL MAINTENANCE MONTHLY
SUMMARY
09-04-06 FACE 1 COM C. COMP U FUNC SYS ADDRESS. CATE.... DESCRIPTION............................. CCRF ECTIVE ACTION.......................
B105253 1 BCTB 085 DE/4D 05/06/861-BCTB-0854E/4D sCHECK RESISTOR WIRE NO 1412fREPLACE IF NEEDEDITHIS IS A TARGET DROPPING RESISIOR,AND SINCE OUR RELAYS WOULD TRIP BUT NOT DROP TARGETS THIS INDICATED A BAD RES!STOR. IRADD H0GUE CALL B01BfE MALONE WHEN READY TO WORK-45N777-3. AUX BLD 759 B113332 2 FCV 063 0152 03/05/86 2-FCV-063-0152-AeSIS PUMP A A OUT FLOW CNTL VLV AUX 690 A11W. HANDWIEEL WILL NOT ENGAGE WHEN VLV IS CLOSE1 B115336 1 BKRB 250 DE /21 05/31/86 1-BKRB-250-DE /21-Ge120VAC U IAL INSTR POWER BOARD I IV BREAKER 21 0 NTROL BLDG EL 734. BREAKER 21 FAILED SI2:9.2 TRIP TIME REPAIR OR REPLACE BKR SPE:S 8116764 2 MIRA 068 0050 08/07/86 2-MTRA-068-0050-eINSPECT AND REPA!R RCP MTR B3 PER MI 2.7 REACT 700 B119841 2 M'10P 067 0067 05/01/86 2-MV0P-067-0067-BsVLV OPENS r/0M CONTROL RM HS BUT WON'T CLOSE FROM LOCAL OR RLMOTE HSili MUST BE HAND CRANKED CLOSED BKR IS NOT TRIPPING OR PICKING UP THERMAL 0.L'S SUSPECT CONTACT OR LIMIT PROB. DG 2BB RM B119940 0 ENG 022 000182 04/17/86 0-EdG-082-0001B2 #D/G B2 ENG IS NOT RUNNING UP TO SPEED AND D/G WOL'LD h0i LOAD TO FULL LOAD D/G 1BB B120624 1GENB092 0001A 07/09/06 1-GENB-092-0001A-AelMMERS!0N HEA1ER CONTACTOR D/G 1AA ENGINE 1A2. CONTACTS ON IMMERSION HEATER ARE PITi!NG CHANGE CONTACTS B121168 2 BKRB 050 NF/23 05/31/86 2-BKRB-050-NF/23 eHEINEMANN BREAKER TIPE CF2-Z51-1 2 POLE 15 AMP CONTROL 734.
BREAKER FAILED SI 253.2 OVER CURRENT TRIP TEST 120 VAC VITAL INSTR POWER BOARD 2-II BREAKER 23 8121314 1 GENB 082 00010 06/19/96 1-GENB-082-00018-Be8It D/G 1BB RAN FOR SI 7 MONTHLY STARTED FROM UNDERVOLTAGE CONDITION D/G STARTED AND CAME TO RATED SPEED VOLT. AND FRE0 CLOSE D/G L3ADED TO 4000KW IN APPROX 34 SEC AFTER 15-20 MIN D/G LOAD PAD DRIFTED 00VN 10 1.2 MON AFTER AFFROX 40 MIN D/G LOAD CONTROL BECAME ERRATIC AT TIMES-1 MW UP TO 4.5 MW-DG WAS THEN SHUIDOWN B121346 2 MV0P 067 0107 07/16/86 2-MV0P-067-0107-BeLOWER COMPT COOLER D EFCW SUFPLY ISOL VLV. IKR ON 2B2-B RMIV BD VLV AT EL 697 ANNULUS AZIMRTH 353 DEGREE.DURING PERF CF SI 26 TH!S VLV 4 1
/.... 6 n a.;
,,u w _ a u,4 m
9 ELECTRICAL HA!NTENANCE MONTHLY
SUMMARY
07-04-86 PACE 2 COMP C. COMP U FUNC SYS ADDFESS. DATE.... CESCRIPT!0N............................. CORRECTIVE ACTICN.......................
FAILED TO CLOSE UPON RECEIVING SIGNAL PUT INSTEAD BLEW A CONTRCL FUSE. FUSE WAS PEPLACED AND BLEW AGAIN UPON SECOND ATTEMPT. FUSE DOES NOT BLOW INSTANTLY I
BUT LAST ABOUT 30 -40 SECCNDS. NEEPED FOR COMPLETION OF SI 26 STICKER ON HS IN CONTROL TOOM B121950 1 ENG 082 0001B1 03/11/86 1-ENG-082-000181-B,1B-B 0/0 ENGINE il ACTUATOR SI 102 E/SA B126213 0 MTRB 026 0011A 08/14/86 0-MTRB-026-0011A-Be2BB FIRE PUMP INSTAKE CCW WITH HS IN CONTROL ROOM. 2BB FIRE PUMP WILL NOT START FROM EITHER AUTO OR STANDBY MAY BE A HANDSWITCH PROBLEM.
PLEASE REPAIR FPS RED DP BUT SEP BEL 2FB PUMP WCN'T B131344 2 BKRA 250 NK/25-G 05/31/86 2-BKRA-250-NK/25-0 rPEINEMANN BREAKER 125 INSTRL PO'4ER BrK IV AUX 734 KEPLACE LEFECTIVE BREAKER 13 records listed.
h..s
9 O
e MAINTENANCE
SUMMARY
(INSTRUMENTATION) l
}
9
{
i
)
7 INSTRUMENT MAINTENANCE MONTHLY REPORT FOR AUGUST 1986 COMMON PRO 1-86-215 was written because SI-244 (Periodic Functional Test of Radioactive Effluent Monitoring Instruments) was not completed within the NRC completion time. One compliance indicator. 0-FI-77-230, was found out of tolerance.
UNIT 1 PRO 1-86-211 was written because a loose pin was found in the connector cable for PS-1-72E during the performance of SI-98.2 (Channel Calibration for Engineered Safety Feature).
Submitted DCR 2276 to add capacitors to the radiation monitors to prevent EMI (electromagnetic interference) generated high radiation signals.
Preventive Maintenance 1653-063 for units 1 and 2 was written, approved, and performed to monitor containment sump level transmitters monthly. This is to obtain trending data and ensure operability is maintained.
UNIT 2 Completed refilling of RVLIS, Train A, upper pleaum sense line for LT-68-369. All fill tees were seal welded.
PR0s 2-86-71 and 2-86-72 were written because 2-LT-77-410 and 411 were found out of compliance tolerance.
Level transmitter 77-410 required refilling before calibration.
PRO 2-86-74 was written because 2-FT-63-918 was found out of tolerance during performance of SI-188 (Periodic Calibration of Chemical and Volume Control System).
Eberline postaccident radiation monitor control room terminal / printer was Installed and tested.
A special noble gas calibration was performed on 2-R-90-260 (Shield Building Vent Postaccident Radiation Monitor) in accordance with SMI-2-90-1.
A test report was prepared and submitted to DNE for evaluation of NUREG 0737 requirements.
New requirements were received for four (4) EQ binders. Three (3) of these EQ binders were baselined SQM-62 Appendix Cs were signed, and the binders were closed.
P Submitted DCR 2276 to add capacitors to the radiation monitors to prevent EMI, (electromagnetic interference) generated high radiation signals.
Preventive Maintenance 1653-063 for units 1 and 2 was written, approved, and performed to monitor containment sump level transmitters monthly. This is to obtain trending data and ensure operability is maintained. *
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MAINTENANCE
SUMMARY
(MECHANICAL)
NECHANICAL NAINTENANCE MONTHLY REPORT FOR AUGUST 1986 COMMON 1.
Bolt tightening continues as required by a special maintenance instruction.
2.
The seal on CDWE recirculation pump was rebuilt.
3.
Fire door A130 was replaced with a new one.
4.
Shaft sleeve and packing replacement on the ERCW pumps continued.
5.
Upper pump shaft replacement on "RA" ERCW pump was completed.
6.
The reinsulating of ERCW screen wash piping began after weld inspections.
7.
The rebuilding and testing of "A" York chiller package was completed.
8.
The changeout of fuel oil manifold and injector filters on 15-2 due to low fuel pressure was completed.
9.
A proventive inspection of the gas stripper feed pump was performed.
i h <
i 7
MECHANICAL MAINTENANCE MONTHLY REPORT FOR AUGUST 1986 UNIT 1 1.
The resetting of main steam safety valve rings began as a result of calculations indicating excessive blowdown at current ring settings.
2.
A modification was successfully completed to the the wafer valve (fuel transfer canal) linkage to eliminate continual failures when operating this valve.
3.
Disassembly of the main generator began for the rotor removal to allow an electrical maintenance modification to the stator, s
4.
The removal of three main steam safety valves was performed for possible testing of ring settings.
5.
The alignment check of the auziliary feedwater pump / turbine was completed.
6.
The rebuilding of "A" and "B" stator cooling water pumps was completod.
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MECHANICAL MAINTENANCE MONTHLY REPORT FOR AUGUST 1986 t
UNIT 2
~.
1.
An adequacy test was performed on unit 2 steam dump header to determine hanger loading;for sizing of an additional hanger.
- 2. ' Structural reinforcements of internal supports were performed in A, B,
. ~ and C condensers and replaced failed short-cycle line in C condenser.
g.
3.
The resetting of main steam safety valve rings began as a result of calculatTons indisating excessive blowdown at current ring settings.
4.
Damper / door repairs to reduce air leakage for SI-149 test were s
continued.
5.
Troubleshooting was completed on 2-FCV-1-29.
Determined that crossed scienoids was the problem.
6 The inspection of the RCPs 2-1, 2-2, and 2-4 was completed. The replacement of potentially defective No. 1 seal housing 0-ring static seals was completed.
7.
The steam generators were closed after eddy-current testing and tube plugging were completed.
8.
As a result of an NRC IE notice, the inspection of auxiliary feedwater check valves for loose discs was completed.
e
- MCCHMICAL MINTEMMCE M0llTHLY SUMMRY 09-11-84 PAGE 1 COMP
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,a B103447 0 EU 039 0527 07/16/84 0-ULY-039-0527,ULV LEAKING. PHYSI IS IN WORM RUBBER SEATS.' INSTALLED NEW Ruf*ER
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0.0025 SCFH 1_
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/ PRESSURE GUAGE PERFORMED FUNCTIDNAL YdMNb U M,.
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' NEW TEST CYLINDER, PERFDPJ1ED SI-7 AND RETURED TO SERVICE y
8123302 1 ENG 082 1B/2 08/11/841-ENG-082-10/2,EEPRDu], PUMP IS DIRTY FILTERS AND WCRH FUEL MANIFULD.
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AND REPAIR CAMISTER FILTER'S. REPLACED FUEL MANIFULD USING MANIFCLD FRCN STH DIESEL (REF. WR-B112635) AND ADJUSTED FUEL PRES!URE DN FUEL DIL PLTP. PERFCRMED SI-7, RETURNED TO SER') ICE.
B123303 1 ENG 082 1B/2 08/11/841-ENG-082-1B/2,EwNPRDu), REPLACE ALL DEBRIS IS FUEL. INSTALLED 16 NEW FUEL 3
FUEL INJECTORS CN D/G ENGINE 18-2 INJECTER ASSEHBLYS, PERFORMED SI-7 AND
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6 MAINTENANCE
SUMMARY
(MODIFICATIONS)
.o
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SUMMARY
OF WORK COMPLETED MODIFICATIONS AUGUST 1986 NUREG 0588 ECN 6231 - Remove Interferences The remaining work will be performed under ECN 6681.
APPENDIX R ECN 5435 - Fire Doors The installation of weatherstripping continues as resources permit.
ECW 6300 - Additional Sprin'klers and Draft Stops The draft stop workplan was approved, and the sprinkler workplan is in the approval cycle. A workplan is being prepared for the electrical portion.
ECN 6311 - Operator Extension on PORV This work has been completed except for final cycling at startup.
OTHER ITEMS ECN 2783 and 5202 - Installation of Fifth Diesel Six electrical-related workplans for the fifth diesel installation have been placed in the workplan closing cycle. Twelve other workplans are in writing.
ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of isolation valves remains in the approval cycle. Some insulation activities remain incomplete.
DNE is revising the USQD.
ECNs 5034 and 5743 - Various Platforms in Lower Containment Because of new weld inspection requirements, Modifications Group B i
is waiting on DNE to furnish inspection requirements on tack welds to hold down grating. "
e ECW 5111 - Remove Power From Old Carpenter Shop at Dry Active Waste Building Modifications Group C is holding the completion of this ECN until the completion of the Dry Active Waste Building.
Power is needed for construction power.
ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete. Caps have been installed on the valve nipples.
ECN 5703 - Reinforcement of Block Walls Unit 1 is still incomplete.
ECN 5713 - Various Platforms in Lower Containment The first trolley was modified by the vendor.
Power Stores has been unable to receive it because of paperwork problems. The remaining trollies are being prepared for shipment to the vendor for modification. Work will continue when the trollies are returned.
ECN 5724 - CVCS/RHR Supports One hanger and one notification of indication remain incomplete--waiting on DNE.
ECN 5880 - UNID Tags for Class 1E Fuses DNE furnished an approved fuse listing. Three workplans have been approved, and field verification of Class 1E fuses has begun.
ECNs 5938, 6305, and 6571 - Replace Feedwater Heater and Eroded Pipe l
Modifications Group B is supporting postmodification testing (PMT) on heaters 1 and 2 on both units as requested.
Insulation work on unit 1 continues.
Installation of the monorail on unit 2 continues l
in preparation for the changeout of feedwater heaters 3 and 4.
ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been
~
remanufactured or replaced.
e 1
ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete (prior to mode 4).. a^$
e ECN 6185 - Offsite Paging System Functional tests of the remote mobile units remain to be completed.
ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete and scheduled for startup.
ECM 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block. installation are couplete.
Modifications Group A is waiting for a technical specification change to place the circuits in operation.
ECN 6237 - Modify Snubbers The workplan was approved, and work is scheduled to start in early September.
ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement All the bundles and piping have been replaced. Work continues on instrumentation, cleanup, and insulation.
ECN 6380 - Replacement of Barton Pressure Transmitters i
4 The transmitters were returned to the vendor for retesting on August 29.
The workplan has been approved, and work will continue j
the first week of September.
ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Work is being held pending current transformer switching for the safe installation of heater strips.
i ECNs 6402 and 6439 - Pressurizer Instrumentation Relocation All work is complete.
In-service tests will be performed when the system is brought up to temperature and pressure.
ECN 6417 - Install Alternate Seal Water for Pumps, CDWE Modifications Group B is waiting for design to be completed and materials to be received.
~
ECN 6459 - Declassify Certain IE Equipment Conduit tags and nameplates are being changed out. Work should be complete by September 4.
- "'E
ECNs 6491 and 6534 - ERCW Supports All hangers for unit 2 (ECN 6534) have been completed. Six hangers remain for unit 1.
Drawings are still to be issued for drawing-change-only workplan (ECN 6534).
ECN 6543 - Install Public Safety Access Portals and Modify Entrance Road Work is being held pending the release of drawings from DNE.
ECN 6556 - Replace Solenoid Hangers Work is in progress.
ECN 6599 - Unit 2 Shield Building Anchor Problem An SM1 procedure was approved to test the holding capacity of the small anchor bolts that were added to the original scope. All initial testing was completed. The results required additional testing, which is in progress.
ECN 6601 - Removal of EGTS Backdraft Dampers PMT remains to be completed by the Engineering Test Section.
ECN 6610 - Modify Air Return Fan Supports Unit 1 work still remains.
ECNs 6631 and 6683 - Snubber Replacements / Modifications ECN 6631 for unit 2 was completed. Two unit 2 supports remain incomplete for ECN 6683.
ECN 6636 - Replace Cable in Valve Room conduit installation and variance writing are underway.
ECN 6637 - Control Air Drawing Discrepancies The workplan is in the approval cycle.
Another ECN is being released.
9 ECN 6648 - Time-Delay CCS Pump Three of five pump motors are complete.
ECN 6661 - Upgrade ERCW Piping Work was started and remains in progress. '
i ECN 6667 - Delete Torque Switch MOVs The workplan is still in the approval cycle.
It has been held since July 1 pending the resolution of PORC comments.
ECN 6672 - Modify Hangers in High-Pressure Fire Protection in Unit 2. Elevation 690 Pipe Chase Fieldwork was completed.
ECN 6681 - Supports for ERCW to Upper Compartment Coolers (Annulus)
Fieldwork was started and remains in progress.
ECN 6689 - Relocation of Mainsteam PORV The mechanical workplan was written and approved, and fieldwork is ready to begin.
Conduit, cable, and tubing work is in progress.
ECN 6693 - Primary H 0/ Control Air Interaction 2
Fieldwork was completed.
ECN 6698 - Repull 120-Volt Cables The workplan writing has been suspended in order to start fifth diesel generator workplan writing.
ECN 6700 - Concrete Edge Distance Hangers Fieldwork was started.
ECN 6701 - Modify Foxboro Recorder Latches Fieldwork was started.
ECN 6706 14 Support Enhancement A workplan was written and approved, and fieldwork was started.
SMI-0-317-24--The number of hangers requiring inspection now totals 350 fer unit 2.
Preliminary inspections are complete on all supports on unit 2 and 1,653 supports on unit 1.
Forty unit 2 supports require fieldwork, while 51 unit i supports have fieldwork required to date. Discrepancies totaling 86 on unit 2 are being evaluated. Work is continuing.
ECN 6707 - Replace System 74 Flow Switches Workplan writing is in progresJ.
ECN 6710 - Diesel Generator and SIS Supports A workplan was written and approved, and fieldwork was started.
- .a
O ECN 6712 - Turbine-Driven Auxiliary Feedwater Room DC Exhaust Fan Conduit and cable work is in progress.
ECN 6717 - Stub Bus Fuses Workplan writing is in progress.
ECN 6718 - Postaccident Sampling Facility Modification for Hydrogen Analyzee The workplan has been written and placed in the approval cycle.
ECN 6723 - Diesel Generator Exhaust Piping Supports A workplan was written and approved, and fieldwork was started.
ECN 6758 - HVAC Supports The workplan has been written and approved, and fieldwork has been started.
ECN 6759 - Waste Disposal Support The workplan has been written and approved, and fieldwork has been completed.
ECN 6999 - Remove Caps and Valve Stems Work was completed.
Dry Active Weste Building (DCR 1898)
All siding is complete. The roofing work is approximately 75 percent complete. Some roofing panel installation will be delayed because crane access will be required to align the compactor. Work will also continue on the trim, dock levelers, and metal doors.
Additional Office and Medical Facility Building Buildings A and B are complete, except for the installation of the window blinds, which will be available September 2 for installation, and the insulation of the attic area in building B, which is scheduled for completion by September 1.
i The yard area fire-protection pipe to the new hydrant locations is complete, except for the rotation of the pump flange scheduled for completion this period. General grading work is in progress.
The modification to the fire detection panel is being held pending the receipt of the panel and parts. The vendor is attempting to obtain internal parts needed to complete the assembly. 12
~., -
e Work on the medical facility is continuing this period. Completion is scheduled for September 18, pending further modifications requested by Medical Services employees.
Additional Office Building at Power Operations Training Center All work is complete, except for the window blinds, which are scheduled to be received by September 2.
Paving Activities All paving activities and lane striping scheduled at this time are complete. Final curb work for intermediate aisles is in progress, including outside curbs at the Power Operations' Training Center parking lot.
Storage Building at Power Operations Training Center Clearing and grade work for the storage building are in progress.
Wort has been hampered by recent rains but was back in progress at the end of this reporting period.
Welding Proiect Support was provided to Welding Project personnel as requested.
Alternate Analysis Walkdown Work is continuing.
SCR Resolution Many man-hours were spent resolving SCRs.
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MODIFICATIONS ECN DCR SYS UNIT DESCRIPTION L5925 F1615 320 2
Remove dogging latch and replace with a special nut that needs a special wrench to open the door.
L6031 D1246 063 1
Add snubber to valve. System 63, NCR SQN WP 8313.
L6482 D0972 000 1
Valves not requiring operation changeout as a result of Revision 7 of NCR SQNMEB 8201 will be returned together with pre-issued ECN L5824 status, except for those valves which were changed before.
L6501 F3795 032 1
Delete isolation valves 1950, 1951, 1953, and change 2-inch pipe to 1/2-inch tubing.
L6508 F3812 005 2
Piping associated with valves II-FSV-5-94, 96, and 98 needs to be changed from carbon steel to stainless steel.
L6600 F3976 030 1
Reflect flow measurements of CRDM equipment room cooler in accordance with TI-50 and TVA-9C flow data. Revise unit 2 duct configuration. This is to replace disapproved FCR.
L6616 D0972 030 2
Replace a fuseable link in fire damper.
Modify ductwork in pipe chase.
L6669 D0972 030 1
Replace limit switches 1-ZS-30-296, -297,
-298, and -299 (units 1 and 2) with fully qualified limit switches.
L6671 F4301 077 2
Add the following note to drawings 47W479-1: All drains in nonradioactive buildings drainage systems (NBDS) may have wire mesh strainers (1/4-inch by 1/4-inch) instead of under drain covers.
L6726 F4313 031 2
Delete a 60-minute time delay relay from FS-31C-439 and -465 on drawings 47W611-31-3 and 47W611-31-4 which should have been shown deleted by ECN 2614 and Workplan 5227. '
ECN DCR SYS UNIT DESCRIPTION L6731 D2259 363 2
Modify beam end connection for typical 47A056-85 as required to a roller-type connection that resists lateral loads only, and allows longitudinal growth.
L5640 D0972 001 1
Delete PDIS-1-17 and FDIS-1-18.
Reference TACF 81-0321.
L6369 D0972 030 2
Replace 1 and 2 PDT-30-44845 with transmitters with accuracy acceptable to FSAR limits.
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ENVIRONMENTAL QUALIFICATION (E.Q.)
SUMMARY
P
9 Estimated Date of Ccreletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 h - nts EQP 8501 Disconnect I-and 2-HS-62-61 6524 Peters 11901 C
C U-2 QlR suttnitted.
EQP 8502 Replace penetrations 23 and 48 6490 Peters 11001, 11802, C C
Conplete QlR submitted.
11810, 11811 EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Cowplete field verification sheets are in binder. No QlR needed.
i EQP 8504 5plice methods not correct N/A Stockton 80 MRs C
C Complete QIR sutanitted.
EQP 8505 Drawing N/A N/A N/A N/A N/A EQP 8506 Seal containment isolation 6514 Kimsey 11880 C
C valve EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C
EQP 8500 JB weepholes (press) 6523 Alas 11898 C
C Capplete QIR submitted.
EQP 8508R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C
EQP 8509R2 Conduit seals 6615 N/A N/A N/A No field work remaining.
EQP 8510 Disconnect local handswitches 6527 Peters 11901 C
C EQP 8511 Submerged JB inside 6549 Peters 11901 C
N/A containment 1*
1
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9 Estimated Date of Canaletion SCR No.
Description ECN Engineer Workplan No. U-l U-2 Cannents EQP 8512R2 Rewire J8 N/A Ant > urn 11855, 118 % C C
All boxes rewired.
EQP 8513 Weep holes (moisture) 6547 Alas 11898 C
C Capplete QIR submitted.
EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C
C Canplete QIR submitted.
EQP 8514 Motor insulation 74-1, -2 6540 Branham 11906 N/A C
Canplete QIR submitted.
J EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C
C EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C
Maint.
EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C
EQP 8518 Submerged cables 6533 Various/6 various C
C EQP 8519 Tec drains N/A Electrical N/A C
C Canplete QIR stdanitted.
- Maint, i
EQP 8520 Expired cables 6553 Gonzalez 11902 C
C EQP 8521 Delete TB and rework splices 6550 Stocktoa 11914, 11915 C C
EQP 8521R1 Delete TB and rework splices 6551 EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C
EQP 8522R2 Rewire local panels N/A Instrument 12016 C
C Maint.
~de,
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Estimated Date of Cgnoletion SCR No.
Description ECN Engineer bbrkplan No. U-l W2 Conments l,
EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C
and misplaced brackets EQP 8524 Change setpoints 6551 Instrument 11916 C
C Maint.
EQP 8525 Reterminate hydrogen N/A Electrical N/A C
C Completed by Electrical Maint, reconbiner (HR)
- Maint, EQP 8526 Replace FSVs, U-1 1, U-2 11 6552 Mechanical 11897 C
C
- Mods, i
l EQP 8527 Coat TB, U-1 3, U-2 8 N/A Stockton 11914, 11915 C C
t (MR) 4 h
EQP 8528 Solder strain gauge Barton IMI Instrument N/A C
C QIR submitted 1/24.
transmitters Maint.
EQP 8529 PDT-30-42, -43 6554 Legg 11912 C
C l
EQP 6530 Gasket, Namco L/S N/A Electrical N/A C
C (MR)
Maint.
1 q:
EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C
?
EQP 8532 Delete L/S 1, 2-43-201, 6630 Alas N/A N/A No longer an issue.
-202, -207, and -208 EQP 8533 Delete dJal voltage splice N/A Rutledge 11866, 11853 C C
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Estimated Date of i
Coneletion SCR No.
Description ECN Engineer Workplan No. WI -
W2 Comments i
l, EQP 8534 Resplice valve positioner N/A Maxwell MR C
C Conplete QIR submitted.
l 3-174 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927 W 2 C
C I
U-l 10 U-2 12 11928, W1 I
EQP 8536 Valve room submergence 6561 Mechanical 11939 C
C Cap drains 6632 Mods.
C C
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EQP 8536R1 Valve room submergence 6612 Electrical C
C Mods.
I EQP 8537 Rebuild or replace J8 3078 6579 Auburn N/A C
i EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C
FCO-31-475, -476 l
EQP 8539 Replace capacitors N/A Instrument C
C Maint.
I EQP 8540 Replace pigtails to Target 6649 Peters C
C Rock solenoid valves l
EQP 8541 Delete brakes 6582 Branha 11980 C
N/A i
EQP 8542 Replace unqualified cables 6680 Hall 9/30 N/A Two cables will be replaced in accordance with a new issue.
N EQP 8543 Replace JB wire N/A Asburn 11855, 11856 C C
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..e Estimated Date of Cmpletion SCR No.
Description ECN Enraineer Workplan No. U-l U-2 Coments EQP 8601 Replace 1, 2-PT-1-2A, -27A; 6588 Elkins 12014 C
C upgrade 2-PT-1-28, ~278 EQP 8602 Reroute control cables for
" Gaeaaaaaaaaaaaaaaaaaa"aau u aaaaaa"AAAA No longer an issue, 1, 2-FCV-70-87, -89 EQP 8603 Replace portion of PP7118 6627 Kimsey N/A C
EQP 8604 Cable IPL3241A not qualified a a " A A " a a a a u " A a -****** No longer an issue.
EQP 8605 1, 2-TS-74-43, -44, -45, 6589 Branham C
C
-46 not qualified EQP 8606 Undervoltage concern on 6611 Rutledge 10/15 9/30 feedwater isolation valve 6676 7
brakes EQP 8607 Delete TB for 1, 2-PT-1-2A, 6626 Instrument 12014 C
C
-27A Maint.
EQP 8608 Enable / disable MOV brakes 6621 Rutledge 9/8 C
Holding for motors for 6622 1-FCV-74-33 and 1-FCV-74-35.
6665 6686 EQP 8609 Replace cable IV7973B 6618 C
N/A EQP 8611 JB has weephole in top N/A Anburn N/A C
EQP 8612 Replace zone switches 6669 N/A C
i.
9 Estimated Date of Cmpletion SCR No.
Description ECN Engineer Workplan No. U-1 U-2 Connents EQP 8614 Weep holes in JB 6652 C
C EQP 8615 Replace FT-72-13, -34 EQP 8617 Junction box internal wiring Auburn Writing workplan.
EQP 8618 Relocate arc suppression 6795 network EQP 8619 Valve room submerged cables Holding for corrective action i
determination.
]
EQP 8620 Relocate stcan generator Instrument Will roll transmitters 1800 i
level transmitters Maint.
EQP 8621 Resolve conduits and tittings Holding for corrective action that may be submerged in determination.
4 Auxiliary Building 1 EQP 8622 Replace terminal blocks with spliced cables No longer an issue.
EQP 8623 Replace limit switch on FCV-3, -21 1
1 1
EQP 8624 Junction box 2145 may be No longer an issue, submerged, unit 1 i,
EQP 8625 6.9-kV nondivisional cables in trained trays i
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Estimated Date of Completion SCR No.
Description ECN Engineer Workplan No.
U-l U-2 Comnents N/A Move surge suppression 5773 Kimsey 11883 C
C network for PORV EEB 8523 Penetration overcurrent 6606 Legg C
C 1
N/A Work FCR to delete 1,
5883 Hall C
C Need SI-166.
I 2-PS-3-160A, -1608, -165A, and -165B N/A Replace 1-FT-1-3A, -38, -10A, 6347 Instrunent N/A C
N/A
-108, -21A, -21B, -28A, -28B Maint.
3 3
NEB 8510 Relocate LT-68-320, 6439 Carrasquillo various C
C PT-68-323. -320 Peters Remount 63-71,68-308 64 %
Legg 11865 C
C Replace LS-65-4, -5 6504 Legg 11865 N/A C
MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C
Delete brakes FCV-62-61 6521 Branham 11905 C
C EEB 8517 Replace pressure transmitter 6488 Branham 11931 C
C PDT-65-80, -82, -90, and -97
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9 THIS PAGE INTENTIONALLY LEFT BLANK P
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TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 September 15, 1986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - AUGUST 1986 Enclosed is the August 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Manager Enclosure cc (Enclosure):
Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, Georgia 30323 (1 copy)
Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. A. Rubio Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 (1 copy)
INPO Records Center Suite 1500 1100 circle 75 Parkway
(
Atlanta, Georgia 30339 (1 copy)
I I
Mr. K. M. Jenison, Resident NRC Inspector O&PS-2, Sequoyah Nuclear Plant gezf An Equal Opportunity Employer