ML20081M513

Monthly Operating Repts for Sept 1983

ML20081M513
Person / Time
Site:	Sequoyah
Issue date:	09/30/1983
From:	Dupree D, Eddings M, Nobles L TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8311170285
Download: ML20081M513 (22)

Text

w +_ 1w A u- - - - - e

-g._ . et TENNESSEE VALLEY AUTHORITY DIVISION OF NULL 7AR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION SEPTEMBER 1, 1983 - SEPTEMBER 30, 1983' UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Um ed By.

M ower Plant Superintendent 3%htk'e?PSS$h a 5 I1#f .

1* .. .

I 3

4 TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . 1-4 i.

PORV's'and Safety Valves Summary . . . . . . . . . . . . . . . . 5 Licensee Events and Special Reports . . . . . . . . . . . . . . 5-6 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . 6 Cperating Data Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . 7-9 Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . 10-12 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . 13-18 I

l i

?

t

,. , - - - e ,,-m , , - ,n,-.,, ,.p.,.. , - -4 ,,.,-,-,,-,-r,. - , , . ~ . - - - ,-,- - , .. ,. , , -,- ,,,n,., .,, , , , >,--, , - .,

t. r' Operations Summary September, 1983 The following summary describes the significant operational activities for the month of September. In support of.this summary, a chronological log of significant events is-included in this report.

Unit 1 Unit I was . critical for '390.6 bours, produced 367,940 MWH (gross),

resulting in an average hourly gross load of 971,031 kW during.the month.

There are 73.92 full power days estimated remaining until the end of cycle 2 fuel. With a capacitf factor of 85 percent, the target EOC exposure would be reached December 27, 1983. The capacity factor for the month was

<43.2 percent.

There was three reactor scrams, there were no manual shutdowns, and there was one power reduction during September.

Unit 2 The refueling / modification outage continues.

Significant Operational Events Unit 1 Date Time Event 09/01/83 0001 Reactor in mode 4 and cooling'down to mode 5 to clean-up the condensate and steam generators.

0830 Reactor entered mode 5.

09/02/83 1640 Reactor entered mode 4.

2150 Reactor entered mode 3.

09/03/83 1915 Began cooldown. Reactor to be

.taken to mode 5 to drain the steam generators to remove the contaminates.

2308 Reactor entered mode 4.

09/04/83 0850 Reactor entered mode 5.

09/10/83 0533 Reactor entered mode 4.

Significant Operational Evants Unit 1 (Continued)

Date Time Event-09/11/83 1824 Reactor entered mode 3.

09/12/83 0635 Rod M-14 failed to move on demand.

0840 Shutdown band B group 1, control bank B and control bank D would not operate.

0903 During the performance of SI-11 some rods in shutdown bank A failed to step on demand. The reactor trip breakers were' opened.

A reactor trip was declared by the shift engineer.

1810 Began cooldown. Reactor.to be taken to mode 5 to repair the shutdown rod lift coil.

F 2300 Reactor entered mode 4.

09/13/83 0220 Reactor entered mode 5.

1915 Reactor entered mode 4.

2340 Reactor entered mode 3.

09/14/83 1151 . Reactor taken critical.

1418 Reactor at 4% Power.

1424 Began increasing reactor power.

1613 Tied the generator on-line.

1639 Reactor tripped on.a Lo-Lo level in #3 steam generator due to feedwater flow / steam flow mismatch during power ascension.

1908 Reactor taken critical 2151 Tied the generator on-line.

09/15/83 0130 Reactor at 30% power producing 310 MWe and holding due to steam generator chemistry.

1104 Began power ascension.

_. . ~ _ _ . , _ . .. . _ . - . . . _ _ _ - _ . _ _ _ . _ , . - . . _ . . _ _ _ _ _ , _ , _ .

., a Significent Operational Events (Continued)

Unit 1 Date Time Event 09/16/83 1445 Reactor at 50% power. Began reducing power to 30% due to steam generator chemistry.

1640 Reactor at 30% power, producing 330 MWe and holding due to steam generator chemistry.

09/17/83 0405 Began power ascension.

0601 The reactor tripped after MFPT-A tripped due to low injection water.

0904 Reactor taken critical.

1341 Tied the generator on-liae.

1422 Reactor at 30% power and holding due to steam generator chemistry.

2250 Began power ascension.

09/18/83 1000 Reactor holding at 49% power to repair an oil leak on "B" condensate booster pump.

1142 Began power ascension.

09/18/83 2225 Reactor holding at 85% power for additional maintenance on condensate booster pump.

09/19/83 0135 Resumed power ascension.

0507 Reactor at 100% power producing 1160 MWe.

09/30/83 2359 Reactor in Mode 1 at 100% power producing 1160 MWe, Unit 2 Date Time Event The refueling / modification outage continues.

. . _ . - . . ~ _ . _ _ . - . . __ __ _ . . _ _ . ._ _ . ____.. . - _

)y .-

Fuel Performance ,

+

Unit 1 The core average fuel exposure accumulated during September was 520.61 MWD /MTU with the total accumulated core average fuel exposure of 8320.81. MWD /MTU.

Unit 2 The scheduled ~ outage continues. Reloading the core-began again on

. August 31, 1983 after temporarily being suspended in mid-August due to the clarity of the water. Reloading the -core was completed on September .4,1983.

The core verification mapping (TI-45) was performed via camera / videotape system on September 4, 1983. Also,'an inventory was performed via camera / videotape on

! 136 fuel bundles (units 1 & 2) located in the spent fuel pit.

1 4

f.

i I

l e

1 l

-4

. . . - . . . . .. . . . , -- _ . . ~ ~ . - - --_. - . - .- -.

s e

• PORV'S'and Safety Valves Summary No PORV's or. safety valves were challenged during the month.

Licensee Events'and Special Reports 1 The following Licensee Event Reports (LER's) were.sent during September

~

1983, to.the Assistant Director of' Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.

, , Unit 1 LER SUBJECT SQR0-50-327/83110 During the performance of SI-136, EGTS cooldown valves FSV-15-47A and 47B failed to close.

4 SQRO-50-327/83111 During the performance of SI-102 oil was found in the. glycol coolant expansion tank on diesel

generator 1A2. t

, SQRi}-50-327/83112 Both trains of the reactor trip automatic actuation logic was inoperable when the reactor trip breaker undervoltage coils were jumpered

. out and the breakers were closed.

SQP0-50-327/83113 Steam generator effluent line radiation monitor 1-RM-90-120/121 was declared inoperable due to

, loss of effluent flow. >

SQR0f50e327/83115 Auxiliary building gas treatment system damper g 1-FCV-30-146A was found with its operator

< disconnected.

SQRO-50.1/7/83119 Containment internal pressure limit of +0.3 psig

'4 relative to the annulus pressure was exceeded.

SQRO- f d-327/83120 During the performance of SI-166.3 when containment sump isolation valve 1-FCV-63-73 was stroked all ice condenser doors opened.

Unit 2 LER SUBJECT SQR0-50-328/83114 During the performance of SI-260 safety injection pump 2A and both centrifugal charging pumps failed to meet the minimum head curve requirements.

Also the CCP boron injection tank and the cold leg injection lines could not be balanced.

v -- r y, --ym & g y .y,,,

yv3 y -.-,r,* +-,ev,..v-v+rw,. **ree' e- +- - - -

• cw-' - - w 'e ve *- --*'w=w'-=r'**ta--*ww-*-get----~e- +r--~9-~*rde*--*-**me"

e.

Licensee Evrnts and Special Report =.

(Continued)

Unit 2 LER SUBJECT SQRO-50-328/83118 SI-214 was not. performed within its required 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. frequency. When it was performed it confirmed that the combination C valves were closed and had been closed with an administrative hold order issued from 09/01 - 09/05/83.

SQRO-50-328/83121 Lower containment airlock failed SI-159.1 -

Overall leak rate test. The condition was found in mode 5 but'may have existed in the applicable modes per LCO 3.6.1.3.

Special Reports There were no special reports transmitted during the month of September.

Offsite Dose Calculation Manual Changes There were no changes to the Sequoyah Nuclear Plant ODCM during the month.

t.

e i

l l' t

% J OPERATING DATA REPORT DOCKET No. 50-327 DATE OCTOBER 12 1983 COMPLETED BY M. G. EDDINGS TELEPHONE (515) 870-6248 0PERATING STATUS

1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES:

-2. .

REPORT PERIOD: SEPT. 1 THRU SEPT. 30 1983

3. LICENSED THERMAL POWER (MWT): 3411.0

4. NAMEPLATE RATING (GROSS MWE): 1220.6 5.. DESIGN ELECTRICAL RATING (NET MWE): 1148.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH.7)SINCE LAST REPORTi GIVE REASONS:__._________

9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):..______

10. REASONS FOR RESTRICTIONSrIF ANY:____________________.._

THIS MONTH YR.-TO-DATE CUMULATIVE 11.; HOURS IN REPORTING PERIOD 720.00 6551.00 19728.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 390.60 5593.81 13129.51

13. REACTOR. RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 378.90 5481.60 12801.10

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENfRATED (MWH) 1106760.35 17761699.15 41044441.15 17.. GROSS ELECTRICAL ENERGY GEN. (MWH) 367940.00 6101460.00 13858996.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 350538.00 5878336.00 13314340.00-

19. UNIT SERVICE FACTOR 52.62 83.68 64.89

20. UNIT AVAILABILITY FACTOR 52.62' 83.68 64.89

21. UNIT CAPACITY FACTOR (USING MDC NET) 42.41 78.16 58.79

22. UNIT CAPACITY FACTOR (USING DER NET) 42.41 78.16 58.79

23. UNIT FORCED OUTAGE RATE 47.37 9.94 14.62

24. SHUTDOWNS 6CHEDULED OVER NEXT 6 MONTHS (TYPE, DATER AND DURATION OF EACH):

_Refyg li,ng/h4,1f ig g,t_ign _De_cggl e_r_ 2 l s ,.ljM _(qy_ QQ, gipyg , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

25. ii iEUiB5ws Ii is5 57 Rii3Hi eisi35- iiiiiiii5 5Ifi 57 siliiUPi"~~~~~~

NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.

__- . - ._ ,_ . - . . . ~ . . _ _ _ _ _ _ _ ___ _ __.__..____ _

\.

AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50-327 UNIT Sequoyah One DATE 10-04-83 COMPLETED BY M. paainea TELEPHONE (615) 870-6248 MONTH SEPTEMBER, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 192 2 0 18 624 3 0 19 1086 4 0 20 1109 5 0 21 'E 1109 N.

6 0 22 1110 'M 7 0 23 1112 8 0 24 1084 9 0 25 1119 10 0 26 1119 11 0 27 1118 12 0 28 1118 13 0 29 1081 14 21 30 1111 15 257 31 16 327 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah one . '-

DATE October 4.1983 COMPLETED BY M. Eddinsts _

REPORT tIONTH SEPTEMBER TELEPHONE (615)870-6248 i

%o a te em u yw Licensee g g,_ Cause & Corrective

% .S 8 @ .o ,C g Event o.g g,g Action to R y8 8 ,8 " g Report # gg g. g Prevent Recurrence

$5 E US O a

xm[a 22 830831 F 328.2 H 1 Condensate demineralized waste evaporator dumped to the condensate system steam generator water chemistry above limits, i

? 23 830914 F 5.2 H 3

1. 3 Steam generator Lo-Lo level due to steam flow /feedwater flow mismatch, r

24 830916 F 0.0 H 5 Reduced reactor power from 50% to 30% due to steam generator chemistry out of specification.

I 25 830917 -F 7.7 A 3 "A" Main feed pump turbine trip on low injection water.

i 1 2 3 4 l F: Forced Reason: Method: Exhibit G-Instructions i S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee

.! C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 i (9/77) H-Other (Explain) Exhibit I-Same Source t

2 OPERATING DATA REPORT DOCKET NO. 50-328 D ATE 10-12-83 COMPLETED BY D.C.DUPREE TELEPHONE (615)a70-6543 OPERATING STATUS

1. UNIT NAME: SEQUOYAH' NUCLEAR PLANT, UNIT 2 NOTES:

2. REPORT PERIOD: SEPTEMBER 1 THRU 30,1983

3. LICENSED THERMAL POWER (MWT): 3411.0

4. NAMEPLATE RATING (GROSS Mt'E): 1220.6

5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1163.0

7. MAXIMUM DEPENDA9LE CAPACITY (NET MWE): 1128.0

8. IF, CHANGES OCCUR IN CAPACITY. RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:____________

9. POWER LEVEL TO WHICH RESTRICTEDrIF ANY(NET MWE):________

~

10.R555555~iBRkk5iRiciiBN557~U55_~(((((((((([_~(((([~_((((~

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD- 720.00 6551.00 11688.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL ~0.00 4750.77 8639.47 13.: RE ACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 0.00 4715.95 8522.70

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 15401769.43 27556360.23

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 5299490.00 9381340.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00. 5113057.00 9039347.60

19. UNIT SERVICE FACTOR 0.00 71.99 72.92

20. UNIT AVAILABILITY FACTOR 0.00 71.99 72.92

21. UNIT C APACITY: FACTOR (USING MDC NET) 0.00 69.19 68.56

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 67.99 67.37 23.. UNIT FORCED OUTAGE RATE 0.00 1.14 8.84

24. SHUTDOWNS SCHEDULED OVER NEXT'6 MONTHS (TYPE, D ATE, AND DURATION OF EACH):

25. ii isuiB5ss IV is5 Bi iie5ii piiiBB- iiiisifi5 5Iii 57 iiiiiUPi-------

_osisttr_32s_1982___________________________________________________

NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.

-10_

a AVERAGE DAILY UNIT POWER LEVEL

' DOCKET NO. 50-328-UNIT Sequoyah Two

^

DATE 10-4-83 COMPLETED BY ' David Dupree TELEPHONE (615)870-6543 MONTH September, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(MWe-Net) (MWe-Net) 1 0 17 0 -

2 0 18 0 3 0 19 0 I

4 0 20 0

- ~

5 0 21 0

l 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 l 15 0 31 .

16 0

~ -

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) l

_. l UNIT. SHUTDOWNS AND POWER REDUCTIONS ^ DOCKET NO. 50-328

' UNIT NAME '-

Seouovah Two DATE 10-04-83 COMPLETED BY David Duoree REPORT MONTH SEPTEMBER ~ TELEPHONE (615)870-6543

% .u No. Date e, n yg o Licensee g, gg Cause & Corrective

~

.S @ y .S g Event o.g g,g Action to R yg g j"y Report # gg gg Prevent Recurrence

}5 $ U.E

c w c[

O 13 830719 S 720 C 4 Refueling Outage Continues.

1 2 3 4 F: Forced Reason: Method: Exhibit G-Inscructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)

E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source

~ 9( -

~ Plant Maintenance Summary

~

The following significant maintenance items were completed'during the

~

month of. September.1983:

. MECHANICAL MAINTENANCE

~

1. Installed.a new; element on 2BB centrifugal charging pump.

. 2 .' Performed SI-108 on th'e-ice condenser doors, SI-106-ice weighing and

SI-107 on the ice condenser floor drains to complete work in unit 2

~

' ice condenser.

. 3. l Repaired body weld on main. steam power operated relief valve 2-PCV-1-12.

4. Repaired the CRDM dampers'on unit 2.

5. Repaired 2-VLV-62-174 by repacking it with the factory representative present.

6. Aligned all four reactor coolant pumps on unit 2.

7. Replace'the' gaskets on'2-FE-63-170.

~ Electrical Maintenance

1. Replace the. motor bearings in the unit 2 reactor coolant pumps.

2. Replace _ the- motor windings 'in the unit 2 #3 heater drain tank pump motors with high temperature windings.

. !3. Re-worked all of the unit 2 rod position indicator connectors and

' control rod drive connectors.

Instrument Maintenance

. Unit 1-

1. _ Changed out 2 incore neutron monitoring detectors.

2. Added silicon oil to " top off" the fill system for containment sump level transmitter 1-LT-63-178.

3. ? Repaired 1 failed CRDM connector and 2 power supplies on the rod control system.

. 4. Stroked and performed maintenance on the main feedwater reg valves during the forced outage.

5. Supported Westinghouse Test Engineer in preparing to set up for the

! field acceptance test on T.S.C. Hardware.

j[

Plant Maintenance Summary (Continued)

Instrument Maintenance Unit 1 (continued)

6. Performed monthly testing of the UHI accumulator level switches.

All switches were within . tolerance for the fourth consecutive month. . The prototype static-o-ring switch which has only' been installed for 1 month was also found to be within tolerance.

Unit 2

1. Completed scheduled calibrations and response time test for the refueling outage.

-2. Installed the reranged steam flow transmitters and completed associated recalibrations.

3. Completed installation and checkout of the new area radiation monitors.

4'. . Completed installation and calibration of the reactor vessel vent system. Post modifice. tion testing will be performed during startup.

5. Replaced the bellow and added silicon oil to " top off" the fill system in containment sump level transmitter 2-LT-63-176. Added oil to " top off" 2-LT-63-178.

6. Replaced the amplifier, power supply and accumulator bladder on 2-PCV-3-122.

Condenser Vacuum Exhaust Flow Monitoring Units 1 and 2 Problems with the flow elements have become a significant concern.

Condensation in the annubar seem to be the major problem. However the design range is a contributing factor. Backpressure caused by the HEPA filter essentially prohibits use of the bypass loop. We have submitted 2 LERs on unit I and 2 LERs on ur.it 2. We have had 2 PR0s on unit 1 and 1 PRO on unit 2 during thi.i month. We have initiated daily surveillance to blow down the lines and have installed heat trace to control condensation. These measurte have helped but are not adequate. ENDES has -been informed and are e aluating arrective action under ECN 5058 and DCR 1710.

• l

' Plant Maintenance Summary (Continued)

_ Field Services Group

1. 'ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2)

' Work continued on the installation of duct for the HVAC systems~

serving the PASF. ' Work continued in the accumulator. room to route the seven sample tubes serving lower containment.and one sample tube serving upper containment for unit 2. This tubing was routed through the unit 2 shield building wall penetrations this month. The steel containment vessel penetration modification to route sample tubing through the vessel was not done this outage. . Installation of unit 2 containment conduit continued. ~The equipment pads have.been set and are ready for equipment installation on El. 706 in the auxiliary building.

12. ECN 5429--Containment Hydrogen' Mitigation System (Units l'and 2)

All installation work is complete. Several breakers were replaced in the distribution panels when they failed during the post-modification testing. 'The system was retested and passed. The installation work-is now field complete. Removal of the old unit I system and restoration of both units containment lights in the old systems electrical sockets remain to be done.

3. ENC 5009--ERCW Piping Changeout (Units 1 and 2)

The ERCW piping changeout was completed for piping serving the SIS pump 2B-B room cooler and the supply piping serving charging pump 2A-A room cooler and oil cooler.

4. ECN 5645--Steam Generator Blowdown (SGBD) (Units 1 and 2)

SGBD piping serting the unit 2 SGBD heat exchangers has now been tied into the cooling tower-blowdown piping. Work to tie-in the SGBD piping from the condensate demineralizer to the main condenser "A" is complete.

Work to make the unit 2 SGBD piping tie-ins upstream of the SGBD flashtank for the SGBD heat exchangers is complete. All outage mechanical work is now complete. Non-outage mechanical work is continuing. The electrical work has not started.

5. ECN 5596--Batch Neutralization System (Unit 0)

The system is in operation with temporary air to the solenoids. Some hanger work remains to be completed . The outstanding work continues.

, 6. ECN 5198--Technical Support Center (TSC) (Units 1 and 2)

The TSC computer systems have been energized and the site acceptance test is underway. Conduit installation was completed inside unit 2

[ containment during the outage. Work is complete for the TSC fire detection system. Various cable pulls are continuing in the control

. building.

Plent M:intentnce Summary (Continued)

Field Services (continued)

8. ECN 5642--Add 2N Regulating Station To Supply N2 To Deaeration Distribution System Inside Condensate Storage Tanks /and To Steam

~

Generators (Units 1 and 2)

The installation of the nitrogen sparger and associated piping is complete in both condensate storage tanks and the final tie-in outside the tanks is~ completed.

9. ECN 2773,2775,2779,2923--Post Accident Radiation Monitoring (Unit 2)

Wiring inside the main control room panels 2-M-30 and 2-M-31 was completed.

Field cable connectors have been installed and all cables have been terminated. Instrument calibration and post-modification testing are underway.

10. ECN 5449--6.9kV Shutdown Board Degraded Voltage Circuitry (Units 1 and 2)

The 6.9kV shutdown boards IA-A and 2A-A were modified and post-modification testing was completed. Field work is now complete for this ECN.

11. ECN 5684--RCP Motor Oil Spray Shields (Units 1 and 2)

The unit 2 RCP motor oil spray shields were completed during the outage.

-All field work is now complete for this ECN.

-12s ECN 5847--Plant Fire Dampers (Units 1 and 2)

Eighty-six of 89 plant fire dampers have been modified. Work also

. remains on this ECN to change out 15 plant fire dampers.

13. ECN 5647--Main Feedpump Turbine Condenser (MFPT)

Condenser Air Removal Piping-(Units 1 and 2)

This piping reroute is field complete for unit 2. Unit I work continues.

14. ECN 5608--Pressurizer Manway (Units 1 and 2)

- Scarifying of the unit 2 pressurizer enclosure area and installation of the manway insert (sleeve) is complete. The manway cover will be installed and leak tested prior to mode 4.

15. ECN 5856--Pressurizer Loop Seal Drain (Units 1 and 2)

Installation of this piping and the new pipe hangers is field complete for unit 2. This piping is valved out of service until the pressurizer safety valve seats can be modified. Prefabrication of pipe and pipe supports is scheduled to begin for unit 1 in October.

.. , m _. . . -. _ _ _ ~ . . . . . . _ . - - _

L*. i --:

Plant Maintensuce Summary

_(Continued)

Field Services .(continued) 1'6 . ECN 5773--Pressurizer Power Operated Relief Valve (PORV)' and Piping 7

. Changeout (Units 1 and 2)

The ' unit 2 valves were received, installed, cables terminated, and ,

functional tested early in the month; however they had to be

~

reorientated in accordance with the' vendor recommendations. Cable

, termination and functional-testing continues. -The unit 1 portion of this ECN remains to be done.

17. ECN 5743--Improved Access to Pressurizer' and Steam Generators (Units 1 and 2)

Work is complete on'the platform inside the top of the unit 2 pressurizer. enclosure.

Installation of ladders, platforms, and a catwalk in the unit 2 lower 1 containment to. provide better access to'the steam generators and the l pressurizer is complete. Minor painting and QC signoffs. remain for the job to be field complete for unit 2. Substantial work remains for unit 1.

1.8 . ECN-2777--Reactor Pressure Vessel Head Vent (Unit'2) ,

All ' remaining lower'compartmentipiping and pipe supports were installed this month; including the entire reactor cavity portion of the system.

All' remaining electrical work was completed this month except where-indicated below. One valve was replaced when it failed during functional- ,

testing. The I/I converters have been installed. Cable and I/I converter.

i. nonconformances' have been cleared. Diode nonconformances remain to be .

. cleared. The post-modification valve leakage test data is being evaluated for acceptability. Final system valve leakrate testing will. t

- be performed when the unit reaches full operating temperature and pressure.

19. ECN 2776--Containment Pressure Monitoring (Unit 2)

Unit 2 work is field complete except for the main control room pressure

. indicators. Non 1-E pressure indicators have been temporarily installed in main control room panel 2-M-9. Delivery of 1-E pressure indicators is expected by the first of next year.

2

20. .ECN-5769--Feedwater Chemical Feed Tie-in Relocation (Units 1 and 2)

The unit 2 work is field complete. The remaining existing tubing

.w as removed and rerouted to the new tie-in locations on the auxiliary feedwater system this month. This completes the ECN field work.

4 .

r s e v - ey e. - -

,.--r----ye--m,e,-r-

• c  :

Plant Maintentnce Summary (Continued)

Field Services (continued)

21. ECN 5370--Replacement of EGTS, ABGTS, and Ventilation Fan Motors (Unit 0)

EGTS, ABGTS,7and pipe chase cooler fan motors have been changed out.

The ABGTS fan housings-_were modified to accomodate the new motors.

'. Vendor representatives modified two pipe chase cooler motors to correct improper rotation direction problems. Thermal overload protection device functional testing is underway.

22. ECN 5125--Fluid Dynamic Flow Element Replacement During the unit I forced outage two "A" train flow elements, 1-FS-65-25 and 1-FS-65-31, were replaced. Replacement of several flow elements 3 for various plant ventilation systems remians.

23. ECN 5595--EGTS Filter Housing Drain Reroute During the unit 1 forced outage drains serving both the "A" and "B" train EGTS filter. housings were rerouted in order to facilitate system operation. All required field work for this ECN is now complete.

24. ECN 5106--Reactor Pressure Vessel Level Indication System Two 3"_ diameter holes were core drilled through th unit I shield

, building wall during the unit I forced outage. In addition, conduit and cables were installed in the penetrations prior to sealing them.

, 25. ECN 5713--Steam Generator Secondary' Side Manway Port Access Platforms (Units 1 and 2)

Work was completed during the unit 2 refueling outage to install platforms

.for all four unit 2 steam generators, providing access to all secondary side manway ports.

t l

[-

I t

I i

l L

.,. m

s. ~ .

TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379

' OCT I 51983 -

Nuclear Regulatory Commission

' Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

' Enclosed is the September 1983 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY' AUTHORITY

. k Y

.W C. C. Mason Power Plant Superintendent Enclosure cc (Enclosure):

Director, Region II Director, Office of Management Nuclear Regulatory Commission Information and Program Control 101 Marietta Street Nuclear Regulatory Commission Suie 3100- Washington, DC 20555 (2 copies)

Atlanta, GA 30303 (I copy)

INPO Records Center Director, Office of Iaspection Suite 1500 and Enforcement 1100 Circle 75 Parkway Nuclear Regulatory Commission Atlanta, GA 30339 Washington, DC 20555 (10 copies)

Mr. A. Rubio, Director Electric Power Research Institute P..O. Box'10412 Palo Alto, CA 94304 (1 copy)

Mr. R. C. Goodspeed MNC 461 Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, PA 15230 (1 copy)

I \

An Equal Opportunity Employer j

i ).

Sequoyah Nuclear' Plant P. O. Box 2000 Soddy-vaisy, Tennessee 37379 Nuclear Regulatory Commission Office of Management Information

'and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the September 1983 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY C. C.' Mason Power Plant Superintendent CED)

RWF:GRW:SFH Enclosure cc (Enclosure):

Director, Region II Director, Office of Management Nuclear Regulatory Commission Information and Program Control

_ Office of. Inspection and Enforcement Nuclear Regulatory Commission

~101 Marietta Street Washington, DC 20555 (2 copies)

Suite 3100

. Atlanta, GA 30303 (1 copy) INPO Records Center Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway and Enforcement Atlanta, GA 30339 Nuclear Regulatory Commission Washington, DC 20555 (10 copies) NUC PR ARMS, 1520 CST 2-C C. L. Breeding, 1270 CST 2-C Mr. A. Rubio, Director H. L. Abercromb'.e, 1760 CST 2-C Electric Power Research Institute H. N. Culver, ';49A HBB-K P. O. Box 10412 J. P. Darling, 546 CST 2-C Palo Alto, CA 94304 (I copy) J. P. Delong, 1200 CUBB-C G. H. Kimmons, W12A9 C-K Mr. R. C. Goodspeed L. M. Mills, 400 CST 2-C MNC 461 Radiological Hygiene Br, ROB-M Westinghouse Electric Corporation Steve Butler, NRC, SNP P. O. Box 355 Pittsburgh, PA 15230 (1 copy)

._.... _ . _ ,___