Text

Monthly Operating Repts for Sept 1986
	ML20207F655
Person / Time
Site:	Sequoyah
Issue date:	09/30/1986
From:	Wallace P; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8701060173
	Download: ML20207F655 (59)
	v • d • e

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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT

, MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION

" SEPTEMBER 1986"

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UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 1 g UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by: P -

p P. R. Wa m ee, m a Manager 1

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TABLE'0F CONTENTS I. Operational Summary _P,a te 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 2-5 Offsite Dose Calculation Manual Changes 5 II. Operating Statistics A. NRC Reports Unit One Statistics 6-8 Unit Two Statistics 9-11 B. TVA Reports Nuclear Plant Operating Statistics 12-13 Unit Outage and Availability 14-15 Reactor Histograms 16 III. Maintenance Summary A. Electrical Maintenance 17-19 B. Instrument Maintenance 20-25 C. Mqchanical Maintenance 26-29 D. Modifications 30-39 i IV. Environmental Qualification (EQ) Summary 40-46 l

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e OPERATIONAL

SUMMARY

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9 PERFORMANCE

SUMMARY

September 1986 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.

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 1 has been off-line 404 days. Unit 2 has been off-line 405 days.

SIGNIFICANT OPERATIONAL EVENTS Unit 1 Date Time Event 09/01/86 0001C The reactor was in mode 5. The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.

09/30/86 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 Date Time Event 09/01/86 0001C The reactor was in mode 5. The administrative shutdown due to design control review, configuration control updating and resolution of significant employee concerns continues.

l 09/30/86 2400C The reactor was in mode 5. The administrative i shutdown due to design control review, configuration

, control updating and resolution of significant l employee concerns continues.

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, FUEL PERFORMANCE Unit 1 The core average fuel exposure accumulated during September was 0 MWD /NTU with the total accumulated core average fuel exposure of 0 MWD /NTU.

Unit 2 The core average fuel exposure accumulated during September was 0 MWD /NTU with the total accumulated core average fuel exposure of 8097.51 MWD /NTU.

SPENT FUEL PIT STORAGE CAPABILITIES The total storage capability in the spent fuel pit (SFP) is 1,386. However, I=

there are five cell locations which are incapable of storing spent fuel.

i 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.

SPENT FUEL PIT INVENTORY A complete inventory via cassette tape of.all 348 spent fuel bundles was

! performed on September 17 and 18, 1986. This inventory both resolved a i discrepancy report and met a requirement in Plant Instruction TI-1 to

! perform an inventory of fuel at least every twelve months. No discrepancies l were observed.

l NOTE: An inventory of fuel in the new fuel storage vault was performed on August 5, 1986.

PORVs AND SAFETY VALVES SUNNARY i

No PORVs or safety valves were challenged in September 1986.

LICENSEE EVENT REPORT (S)

The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in September 1986.

l LER Description of Event 1-86034 On August 14 and 15, 1986, it was noted that Surveillance Instruction (SI) 238.1, " Diesel Generator Battery System Weekly Inspection," and SI-302.2, " Vacuum Switch And Controller Performance Check For Radiation Monitoring Gas Sample flows (Monthly)," were not performed within their allowable timeframes. These instructions are required by Technical Specifications (TSs) 4.8.1.1.3 and 4.3.3.10, respectively. The due dates were missed as a result of personnel error. However, both surveillances were performed immediately upon discovery of their tardiness.

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LER- Description of Event-1-86035 On August 7, 1986, it was discovered while revising Instrument Naintenance Instruction (INI) 99, Response Test 699, " Response Time Testing Of Enginested Safety Feature Actuation-Safety

' Injection Signal With Station Blackout," that this instruction did not totally test for diesel generator (D/G) start on loss of voltage to the shutdown boards. As written, it bypasses the loss of voltage start signal causing the D/G to start by a safety injection signal. This event is caused by a procedural error. Response Test 699 will be revised to allow for both conditions.

1-86036 During a review of Plant Operations Review Committee (PORC) minutes on August 20, 1986, it was discovered that a quorum for the May 27, 1986 meeting was not. documented. The cause of this event was failure to properly document the names of PORC members present during the meeting. Technical Specification 6.5.1.5 requires the minimum quorum of PORC to consist of the chairman or his designated alternate and four members including alternates. Items reviewed on May 27, 1986, were reviewed and approved again by another PORC meeting on August 20, 1986.

j 1-86037 i Item 1 On August 26, 1986, SI-244, " Periodic Functional Tests of

Radioactive Effluent Monitoring Instruments (Quarterly)," was l not performed with the allowable NRC timeframe. Ihis SI tests i for numerous radioactive effluent monitoring for both units and is required in accordance with TS 4.3.3.9. The instruction was

! immediately performed, however, two items (flow indicator 0-FI-77-230 and level transmitter 0-LT-27-225) were discovered out of specification. These components were calibrated and

l. returned to service. This event was caused by personnel error.

Item 2 On August 29, 1986, three sis (SI-430 "Nonthly Radiochemical Analysis," SI-409, " Quarterly Radiochemical Analysis," and SI-422.1, " Monthly 10 CFR 50 Appendix I Dose Calculations Liquid Effluents") were not performed within their allowable time limits. The deadlines were not met due to improper sampling techniques and equipment being out of specification. The equipment was corrected and the sis in question were performed again, meeting all requirements.

1-86038 Two inadvertent D/G starts occurred on August 26, 1986, and September 8, 1986, respectively.

Item 1 While performing SI-60, "6.9 kV Unit Board Manual And Automatic Transfer," on August 26, 1986, on the "2D" unit board which was deenergized, personnel mistakenly deenergized "2C" board. This caused the D/G to start and D/G 2A-A to load. The relays of these unit boards are located next to each other.

Identification labels will be printed to distinguish each board.

t Item 2 At 1542 CDT, September 8, 1986,'while attempting to transfer start bus "2B" from alternate to normal, the normal breaker tripped, which caused a loss of voltage on the associated unit and shutdown boards. This resulted in the D/G 2A-A loading.

The trip contacts on the close trip switch were found to be allowing the D/G control voltage to are and trip the breaker.

Apparently, the arcing was due to the vibration of the charging spring motor. The manual close trip switch on the front of the breaker was replaced.

1-86039 Two surveillance requirements were not performed due to inadequate procedures:

Item 1 On August 25, 1986, it was discovered that two of the five functions of P-4 (main turbine trip on reactor trip, main feedwater valve closure on low reactor coolant system average temperature with reactor trip) were not being tested every eighteen months as required by TS Surveillance Requirement (SR) 4.3.1.1.2. This requirement is performed by SI-90.8,

" Reactor Trip Instrumentation Monthly Functional Test." A new procedure will be written to perform all five functions of P-4.

NOTE: P-4 is a permissive (reactor trip logic-solid state protection system) which trips the turbine on a reactor trip and subsequent opening of reactor trip breakers.

,l' All P-4 circuits and associated egulpment have never failed to function properly during a reactor trip.

' Item 2 On August 27, 1986, it was discovered that SI-108, " Ice Condenser Doors," does not verify the inlet door position at the local panel as required by SR 4.6.5.3.1. The indicator in the main control room has been verified operable; however, the 1 channel test requires the whole channel to be operable. SI-108 i

will be revised to terify signals at the local panel.

1-86040 A deficiency was determined on August 26, 1986, that existed in l

SI-158.1, " Containment Isolation Valve Leak Rate Test." It was discovered that credit could not be taken for a water seal for essential raw cooling water (ERCW) and for leak testing of these isolation valves as specified in SI-158.1. This procedure is inadequate and is not consistent with TS 3.6.1.2. This deficiency failed to include leakage of the ERCW isolation valves with the combined leakage rate. The above stated t procedure will be revised to air-test the subject valves and include their leakage in the combined leakage rate.

l ABBREVIATIONS f 1. D/G - Diesel Generator

2. TS - Technical Specification

3. SR - Surveillance Requirement

4. SI - Surveillance Instruction i - ,-- - - _ - . _ - _ _ - . . - . - - _ _ - - _ - . _ . - . - . . - . _ - - . -

-. .. . .a+.. .

SPECIAL REPORT (S)-

There were no reports submitted to the NRC in September 1986.

OFFSITE DOSE CALCULATION MANUAL CHANGES, No changes were made to the Sequoyah offsite dose calculation manual during the month.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-327 UNIT NAME __Sequoyah One DATE October 3. 1986 COMPLETED BY D. C.-Dupree REPORT MONTH SEPTEMBER 1986 TELEPHONE (615)870-6544

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S i iiti 5.. DESIGN ELECTRICALSRATING (NET.- MWE): 1148.O YY e d MAXIMUM DEPENDADLEMA'PACITY !(GROSS MWE)il',; 1185 0 >M+

O , e . . .x."N i; e 67. 2

.(NET MWE): hi148. O gjg

<4 ;nIF. CHANGES OCCUR ?IN.. CAPACITY. RATINGS (ITEMS NUMBERS

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"12.4 NUMBER OF1 HOURS REACTOR WAS CRITICAL" ' O. 00 . ^

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l0.001 l ji3dREACTOR RESERVE ' SHUTDOWN HOURS <

'O.00' 314n HOURS GENERATOR ON-LINE O.00 .. a O.00 ., ,2149_4.42:

7 15h UNIT RESERVE [ SHUTDOWN HOURS . O.' 00 ' 1 ?O.00 [ l O."003 M;16.HGROSS THERMAL: ENERGY GENERATED.,(MWH)

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' 20; UNIT AVAILABILITY FACTOR O.00 ~ O. 00 ~ V '56.58 g 21.ll UNIT CAPACITY FACTOR (USING MDC NET) O.00 O.00 51.78j W,.22.-UNIT CAPACITY 7 FACTOR (USING DER NET) O.00 O.00 51.'78 i

@123i UNIT FORCED OUTAGE RATE 100.00 100.O'O 35.07

24. . SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Mq

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25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: a THE STARTUP OF UNIT-2 HAS DEEN SCHEDULED FCR MARCH 1987.

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I' UNIT SHUTDOWNS'AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME' seanovah Two

' DATE October 3. 1986 COMPLETED BY D. C. Dupree REPORT MONTH SEPTEMBER 1986 TELEPHONE (615)870-6544

% u en c4 Y eo O Licensee E.: En Cause & Corrective No. Date

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e 00 5 5SN Event 0$ oE Action to I

$ N5 0 .0 U $ Report # $O

$0 Prevent Recurrence.

l $5 0 US

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9 850821 F 720 F 4 Design Control, Configuration Updating,:

and Employee Concerns.

1F: Forced 2 Reason: 3 Method: 4 Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-tfanual 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 & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source II-Other (Explain)

F 4

OPERATING STATISTICS (TVA REPORTS)

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TVA M82A (DNP4 84 NUCLEAR PLANT OPERATING STATISTICS Seouoyah Nuclear Plant Period Hours 720 Month September 19 86 Item No. Unit No. Unit One Unit Two Plant 1 Averaae 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 646 6,857 7,503 E 7 Net Electrical Gen., MWh -646 -6,857 -7,503

$ 8 Station Use, Percent N/A N/A N/A 9 Accum. Core Avg. Exposure. MWD / Ton 1 0 0 0 10 CTEG This Month,106 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 0800 15 Capacity Factor, Percent 0.0 0.0 0.0 y 16 Turbine Avail. Factor, Percent 0.0 0.0 0.0 g 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 t' 18 Turbooen. Avail. Factor. Percent 0.0 0.0 0.0

$ 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 0 20 Unit Avail. Factor. Percent 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 j 25 Net Heat Rate, Btu /kWh N/A N/A N/A

$ 26 Y 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 g 31 Intake Water Temp., F N/A N/A N/A

>- 32 33 Main Feedwater, M lb/hr N/A N/A N/A E 34 35 36 37 Full Power Capacity, EFPD 404.86 360.65 768.51

38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 j 39 Oil Fired for Generation, Gallons 2,904 2 40 oit Heatina value. Btu / Gal. 138,000 41 Dieu! Generation. MWh 44 47 Max. Hour Net Gen. Max. Day Net Gen- Load MWh Time Date MWh Date Factor, %

a 43 N/A N/A N/A N/A N/A N/A O Remarks: A For BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.

8 2(t) indicates T hermal Energy.

3 U1 ,

Date Submitted N Date Revised Plant Superintendent g ,

. TVA 7382A (L,..P4-811 NUCLEAR PLANT OPERATING STATISTICS Sequoyah Nuclear Plant Period Hours 8,760 Month Fiscal Year 39 86 Item No. Unit No. Unit One Unit Two Plant 1 Averaae Houriv 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 8 5 Gross Electrical Gen., MWh 0 0 0 5 6 Station Use, MWh 32,471 54,393 90,607

$ 7 Net Electrical Gen., MWh -32,471 -54,393 -90,607

$ 8 Station Use, Percent N/A N/A N/A 9 Accum. Core Avg. Exposure, MWD / Ton 1 0 0 0 10 CTEG This Month,106 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. 0500 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 g 17 Generator Avail. Factor. Percent 0.0 0.0 0.0 e 18 Turboaen. Avail. Factor. Percent 0.0 0.0 0.0

$ 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 0 20 Unit Avail. Factor. Percent 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 3

j 25 Net Heat Rate, Btu /kWh N/A N/A N/A

E 26 5 27 g 28 Throttle Pressure, psig N/A N/A N/A

& 29 Throttle Temperature. "F N/A N/A N/A d 30 Exhaust Pressure, InHg Abs. N/A N/A N/A E 31 Intake Water ftgnp., F N/A N/A N/A H 32 33 Main Feedwater, M lb/hr N/A N/A N/A i I 34 l

( 35 36 37 Full Power Capacity, EFPD N/A* N/A* N/A*

38 Accum. Cycle Full Power Days, EFPD N/A* N/Ax N/A*

j 39 Oil Fired for Generation, Gallons 69,696 2 40 Oil Heatina Value. Btu / Gal. 138,000 41 Diesel Generation. MWh 1,056 d?

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 WBNP this value is MWD /MTU.

j 2(t) indicates Thermal Energy.

, 3

Item subject to change during the fiscal year.

! sn ,

Date Submitted Mhh Date Revised Plant Superinter. dent

1 8

TVA 6560C (PP 3 76)

UNIT OUTAGE AND AVAILABILITY , .

SEQUOYAll Nuclear flant Licensed Reactor Power 3.411 MW(th) Unit No.

nw Generator Rating 1220.5 MW(e) Month / Year SEPTEMBER 1986 Design Gross Electricat Rating 1.183 MW Period Hours 720

'"' METHOD OF UNIT Time Not Available CORRECTIVE ACTION T6tne Unit Available Totae cen. Not Used Tuttwne Gen. Reactor Unst N DURI G EP T T N REACTOR OUTAGE Day Mrs l Men Hrs l Min Hrs [ Man Hrs j Min hrs ! Min Mrs l Min Hrs l Man Hrs ! Men Mrs ' Min 1 00s 00 00 ; 00 ; 248 00 24e00 24 iOO 24 iOO i e Desien Control. Configuration N/A Mode 5 2 00 3 00 00 i 00 t 24 ' 00 24 l 00 24 e00 24 !00 ! ! Undatine. and Employee Conceriis 3 00l 00 00 e00 e 24i 00 24e 00 24 300 24 ;00 l ;

4 00 i 00 00 l 00 l 24a 00 24' 00 26 !00 24 s00 e 5 00100 00 e00 i 24 8 00 24l 00 24 l 00 24 !OO 8 '

6 008 00 00 :00 1 24! 00 24iOO 24 800 24 iOO ! ,

7 00 ' 00 00 8 00 ! 24: 00 24! 00 24 l 00 24 800 l e 24: 00 24 i 00 24 s00 24 l00 8

,1 8 00 l 00 00 ' 00 l t T 9 00: 00 00 i 00 e 24 ! 00 24' 00 24 ! 00 24 iOO e ,

10 00i 00 00 ' 00 1 24i 00 24 l 00 24 i OO 24 !00 l e 11 001 00 00'00 j _248 00 24e 00 24 100 24 t00 t l 12 00 8 00 00l00 . 24 : 00 24! 00 24 l00 24 000 t i 13 00I 00 00iOO ? 24 ? 00 24l 00 24 iOO 24 !D; e i 24 l 00 24i 00 2 QI 24 l00 ' '

14 00; 00 00 8 00 .

15 00; 00 00 ! 00 i 24' 00 24 ,' 00 24 iOO 24 t00 i i 16 001 00 00l00 i 24' 00 24a 00 24 ! 00 24 000 0 8 17 001 00 00!00 ! y i 00 24800 24 l00 24 !00 e 18 00! 00 00t00 i 24? 00 24; 00 24 800 24 l00 8 19 00 l 00 001 00 e 24i 00 24 i 00 24 iOO 24 i OO ! ?

20 00; 00 00 1 00 ? 24! 00 24! 00 24 !OO 24 e00 ; ,

21 00 00 00 l 00 l 24; 00 24 i 00 24;00 24 000 i ,

22 000 00 00t 00 e 248 00 24 ! 00 24 800 24 l00 i i 24 ' 00 24 ;00 i 23 00' 00 001 00 8 24! 00 24 i 00 e

' 24i 00 24! 00 24 iOO 24 iOO 24 00! 00 00 ! 00 8 25 00; 00 00i00 i 248 00 24 ' 00 24 *00 24 100 i 26 00i 00 008 00 1 24; 00 24 i 00 24 l00 24 400 , i 27 00t 00 00 ! 00 l 248 00 24e 00 24 s00 24 !00 t i 28 001 00 00 i 00 t 24! 00 24! 00 24 ;00 24 ;00 6 6

29 00! 00 00 ! 00 i 24i 00 24 00 24 !00 24 ;00 l 30 00 j 00 00i 00 l 24l 00 24 i 00 24 i 00 24 400 i i 31 I e i e 3 i e Total 00! 00 00 30 ! 720! 00 720! 00 720 i OO 720 .00 ><iXXX __

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SUMMARY

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MAINTENANCE

SUMMARY

(ELECTRICAL)

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1

' ELECTRICAL MAINTENANCE MONTHLY

SUMMARY

10-02-86 PAGE 1 COMP

,MR. COMP U ~FUNC SYS ADDRESS. DATE....-DESCRIPTION............................. CORRECTIVE ACTI0N.......................

9 :, -i ~ . . .# A .' 4 W A561025; 2'HS. 313 . 0522D 08/21/86 2-HS-313-0522D-A, REPAIR OR REPLACE ' WATER IN JUNCTION BOX. REPLACED SWITCH % 'y

[ SW.JBOX SW IS MOUNTED IN IS FILLING UP AND OPERATOR. CDATED JBOX WITH RTV 3140 h.7hT[hv./ . , . g.u 4 lBOTTOMOFJBOXW/WTRISUGGEST DRILLING WEEP 'j HDLES ] .

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-"4 yp BOTTOM 0F JBOX l M A561028 l2 HS $ 313 '0497D 08/21'86 / 2-HS-313-0497D-B, REPAIR OR REPLACE ~ ; WATER IN JUNCTION BOX. REPLACED SWITCH q>4 s SW.JBOX SW IS MOUNTED IN IS FILLING UP AND OPERATOR C0ATED JBOX WITH RTV 3140 -p 3

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0152 02/10/86 2-MV0P-063-0152-As[*10CFR50.498 tNPRD*], REPLACED TORGUE SWITCH AND PERFORMED N B103130 2 MV0P 063 ,

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. ELECT W/ CORRECT LIMIT SW TO BE INSTLD IN LIMIT SWITCH.

yb Q . CLOSED PGS.0N WP11904/ECNL6529. LIMIT SW

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" B126067 2 GENB 082 TRIPPED .

0002A 08/29/86 2-GENB-082-0002A-A,[*NPRD*],*It 2A-A7 O TO .120 OHMS. WR B-124786.

SPEED SETTING KNOB WAS BINDING ON THE r

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DIESEL GEN. D/G WILL NOT LDAD UP OVER FACE PLATE. ADJUSTED THE FACE PLATE TO ,

.3d 1800 KW INVEST AND FIX . ,RELEIVE BINDING. WR B-126067..

1 8126099 1 MV0P 063 0047 08/28/86 1-MV0P-063-0047-A,C*NPRD*], SIS PUMP GREASE, GASKETS 8 SEALS WERE BAD "V Y^ ! INLET VLV AUX 669 A PUMP RM. OPERATOR PREVENTING STEM MOVEMENT. REBUILT

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WILL NOT NOVE VLV STEM MOTOR WILL DRIVE OPERATOR REPLACE!NG GREASE AND GASKETS ..'..

VM d ' M GEAR DRIVEM LIMITS AND SEALS AND RETURNED TO SERVICE. WR M . W . '. . , , -

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', % z.W qN B12619171 MTRB 082 0001A2A 08/01/86 1-MTRB-082-0001A2A-A,[*NPRD*3,AC OIL PMP PUMP MOTOR BEARINGS WERE FT ' '

W -ON ENGINE 92 IS MAKING ALOT OF NOISE . NORMAL WEAR.' REPLACED MOTOR BEARINGS. WR , ,M' 4 , di , , ..

B-126191. g4@ '

B126286 2 GENB 002 0002B 08/22/26 2-CENB-082-00028-Be[*NPRE*],2B-B D/G. FUSE HOLDER WAS NOT GRIPPING THE FUSE THE LOAD WENT TO APPROX 4MW INITALLY TIGHT EN0 UGH TO MAINTAIN PROPER

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' LOAD WAS RAISED TO 2 4 NW AND SWITCH ~ FUSE TIGHTER. WR B-126286. y d RELEASED LOAD WENT TO 2 5 MW THE ACB WAS TRIPPED M..

~ B126615 -2 BCTD 003 0047 09/16/86 2-BCTD-003-0047-Br[*NPRL*), LOOP 2 S/G THE OPEN CONTACT HAD A BURR ON IT DUE TO FDWTR ISO VLV U-2 EAST VLV RM AFTER MANUFACTURERS STAMP.

G0ING TO THE CLCEED POSITION WITH j l HS-3-47A FCV-3-47 WENT TO THE CLOSED ))

POSITION . AFTER REACHING THE CLOSED l POSITICN FCV-3-47 CAME BACK OPEN WITHOUT _'}) -y f

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,..m ,y.fh..a .t jjgg% 2:iM OIL MANIFOLD GASKET WAS,.Th#N . . JDUE

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N h yp,i? % 3 d,p-- ., ; " @p+ sX 700 PER MI-27. DISASSEMBLE AND REPAIR RETURNED TO NORMAL TO SERVICE. WEAR. j,Jg REPAIRED WR B-2001 GA PW.

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p 2; ' TIMER. AUX PLDG 734'-0'. ADJUST AGASTAT ADJUSTED RELAY TO 20.1 SECONDS. ;>, M, A' q

.s TIMER CCS-ST TO 20 f 1 SECONDS. THIS , . . .

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d. p . w- : SPRING ENGINE 61 DC FUELOIL PUMP MOTOR. BRUSH . ADJUSTED S IS NOT HOLDING BRUSH IN HOLDER NO. BRUSHES. WR B-203606. . . . ,

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MAINTENANCE

SUMMARY

(INSTRUMENTATION)

~ _

INSTRUMENT MAINTENANCE MONTHLY REPORT FOR SEPTEMBER 1986 CONMON Completed preparation of 10 of 14 maintenance instructions for backfilling the transmitter sense lines for the reactor trip and engineered safety features instrumentation channels.

, Completed field work for Workplan 11129R1. This workplan incorporated an upper level discriminator efecuit for radiation monitoring channels 1-R-90-62, 2-R-90-62,.and 0-R-90-138.

Prepared and submitted preventive maintenance instructions (PMIs) on 1 ,

2-FIS-70-81; 1 , 2-PDIS-67-490, -491; 0-PDIS-313-305 -340; and 0-LIS-39-36 (reference CATS item numbers 86297, 86298, 86299, and 86300). These instructions will establish a threo month calibration cycle to ensure that the Barton Model 288 switches do not drift out of tolerance.

Responded to Experience Review Item WBN-NCR-W-390-P concerning problems with meeting and maintaining calibration values on the Air Monitor Corporation panels at Watts Bar Nuclear Plant. Sequoyah Nuclear Plant has not experienced problems of the same magnitude, but has experienced an undesirable amount of calibration drift. Our response indicated we would separate these instruments into a separate procedure and increase the calibration frequency from 18-months to 9-months. This new procedure should be implemented by June 10, 1987.

Initiated a reply memorandum requesting the Division of Nuclear Engineering

-(DNE) to evaluate the output shift of the containment sump level transmitters during venting of lower containment. The memorandum requested DNE to evaluate the effects of environmental transients during a postulated accident inside containment on the transmitter's operability. Copies of recorder charts showing transmitter outputs shifting high were included.

Responded to Employee Concern Report No. 303.02 SQN (MATS 9133) regarding redundant level indicating channels not indicating the same level on the cold leg accumulator tanks and the refueling water storage tank (RWST) narrow range channels. The report also identified a high maintenance i history on transmitters in both applications. Our reponse stated that Sequoyah has already corrected the problem with inconsistent indications on redundant channels by taking fleid measurements and changing the transmitter scaling to con.pensate for the different sensor elevations. Corrective action for the high maintenance history is to replace the cold leg accumulator transmitters in accordance with ECN L6358, and PMI-1678-063 and 1679-063 have been initiated for the RWST transmitters to obtain more trending information and to ensure operability is maintained.

During review of surveillance instructions, it was discovered that the current procedures do not perform a calibration of ter perature sensors as required by the technical specification definition for channel calibration (reference PRO-1-86-238). Current plans are to perform a Westinghouse cross-calibration procedure for the reactor coolant system resistant temperature detectors (RTDs) and incore thermocouples. Before startup, a calibration verification method will be established and implemented for the remaining temperature channels.

INSTRUNENT MAINTENANCE MONTHLY REPORT FOR SEPTEMBER 1986 UNIT 1 Initiated and obtained approval for Field Change Request (FCR) 3652, which-will enable completion of Workplan 11225. This workplan will clear nuisance alarms by changing various instrument setpoints.

Completed preparation of PMIs to check the calibration of auxiliary feedwater pressure transmitter 1-PT-3-122 which has been found consistently out of calibration by.the instrument trending program.

UNIT 2 During performance of Surveillance Instruction (SI) 96.1 and SI-581, three compliance instruments were found outside the required tolerances specified in Technical Instruction (TI) 54. PR0s 2-86-084, 2-86-089, and 2-86-090 were initiated for evaluation. The instruments were recalibrated and returned to service.

Prepared and planned work reqeusts to rotate the mounting position of four steam generator level transmitters. This was needed to satisfy the submersion requirements of Environmental Qualification Binder No. INTR-001.

During performance of PMI-1653-063 and SI-98.4, containment sump level transmitter 2-LT-63-176 was found outside the technical specification allowable tolerance (reference PRO-2-86-093). The transmitter was

,recalibrated and returned to service.

1 TI-54 : Compliance Instruments l SI-98.1: Channel Calibration for Engineered Safety Feature Instrumentation l

SI-98.4: Channel Calibration for Engineered Safety Feature Instrumentation i for Containment Sump SI-581 : Periodic Calibration of Main Steam System f

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7 STATE OF CPER REPAIR CR PEPLACE CONTRDLLER SN 0133340-40 8112106 0 TC 234 37 09/09/06 0-TC-234-3?-P,FND P3!KT 1 CKT CfP i CEFECTIVE CONTROLLER. REPLACE u!TN SPARE- ,?

INDICATING )200 DEG F UN O TR 234 5008' 3ERIAL 613337-47 -

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, SPARE SERIAL $8133-100932-01 3 PARE 07/09/86 0-TC-234-3 PARE , GREEN LIGHT CU2MED OUT . BU5!NED OUT CULC. REPLACED CULS. .<> W_. AN' d' N' 4

B126568 2 in 068 44 07/18/86 2-TM-068-44-E,HNILE R'JNNING A DTNAMIC 4 ALL GF THE OUfPUT TRAN313 TORS IN THE lou

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CHANGES AREA STEADILY CEr0FE AND AFTER TN!3- DEFECTIUE. RLPLACED THE TRAN31310R3 AND 1 THE DIODES RECALIBRATED Tile D!UICE AND -b

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SPARE 07/07/86 0-TC-234-3 PARE ,TROUCLE3HOGI AMD REPAIR _ CEFECTIVE C14 CAPACITOR. 2EPLACED

{ :8128644f0 TC 234 '

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CONTRCLLER <

-CAPACITOR >

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. ;B12864T O TC 254 135557-T 07/09/C6 0-TC-254-133337-T ,FETLACE IN-UP GREEM CEFECTIVE GREEN LIGHT AND DUTPUY REI AY.- ,

LAf:P & REPA!R AMPLIFIER CIRCUIT FOR FULL RE/ LACED GREEN LIGHT AND CUTPUT RELAY, , O

l SU SPAM PER In!-234.1 STEP 4.5.15 3M ,

e 133337-76 .

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8128650 0 TC 234 SPAPE Of/09/C6 0-TC-234-3 PARE ,3N 8133-54705-_13 TEND .. CEFECTIVE GREENLIGHT.. REPLACE! . . .

CIMPO CONTROLLER WILL NOT 3 WITCH STATES, GREENLIGHT T4 Y

RER3UED FROM CIRCUITj-TC-234-0397 PEfr ' +

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C129609 2 LT 068 '

USING n&TE 54514 WHICH WA3 FOUND OUT,DF OUT OF CAlltRATION.2RECALICRAIED THE CALIERATION AT THE LA0; .. y <

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' B130349' 0 TC 234 CEFECTIVEC14 CAPACITOR.7REPLACEDC14 m'

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.J d, Ulk V t. - Su!PECT C-14 CAPICITUR. , REPAIR A3 m CAPACITOR. REPLACED RELAY AND CePACITOR

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r FRONT OF TEMP CONTROLLER 3N 13337-39 E

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M@7 h' [ CIBCDMTROLLER WAS REMOVED FRDn CIRCUIT CREEN LIGHT 01 TRAN313 TOR AND C4 ,. "

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'!p s e. > GREEN LARP3 ARE CURNED, GUT ,

U L2130457 0 TC '23413339-92 09/10/86 0-TC-234-13339-92 ,TC HAS BUTNET RELAYc ' BURNED RELAY CONTACT 3.. Reft ACFD C14

. hyAND GREEN LIGHT. REPLACED PARIS . t ,fO ' Q~, f

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D p.a e9- 4- CONTACT! REPAIR /REPLAdCANDFUNCTIONAL(Y'CAPACITORDUTPUT,RELAYSAND.REtrLARP m

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GREEN AND RED !!CNT! ON SIMULANCDUSLY N/ $PARC 3Cf!AL 813339-f2. . N -

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IPAPE 09/13/86 0-TC-234-3 PARE ,CONTCLLER FAILED DURING CURNED UP POWEE TRAN3FORMER.;FEPLACEO.

i[ [ 130437. O TC PER CT IMI-234.1 8 STEP 6.3.10. 3USPECT POWER TRAN!FORMER '

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CAD TRANSFORMER SN 8133-32677-14

] U , 3130470, o TC 234 .. c 174 09/02/C6 0-TC-234-174 , CONTROLLER 00E3 NOT CHANGE DEFECT!YE CONTROLLER. REPLACE 0 ,

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'A ITATES. INDICATED CIRO TEMP PT 14=1700EG CONTROLLER HITH 3 PARE 834703-13 J <

f W/TC 3ETP0 TNT 2 500 G f ,

MI C130487 0 TC 234 122P 09/02/S6 0-TC-234-122P ,TC $0TFDINT'=180DE5'r ' ',^

i 7,5 CEFECTIVE CONTROLLER.' INSTALL 10 3 HOP CHUGE STATES 2 APPROX 205-210 DEG r 3PARC. 3ERIAL 813330-f 2. WEOS 120407 '

! 6 2130489 0 TC 23413338-93 09/02/06 0-TC-234-13338-95 ,00?PUT RELAY CHATTERS DEFECTIVE C14 CAPACIT0f. FEPLACCD C14.

UHEN TC ENERGIZED IN 13338-93 CA'ACITOR i'- 8130491 0 TC 23413338-77 09/09/C6 0-TC-234-13338-77 , REPLACE IMOP RED CEFECT!YE RED' LIGHT CURM. REPLACE 0 RED LAMP. FAILED ATTER RCMOVAL FROM CET LIGHT.

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102P DURING PERT OF 15!-234.1 SN 133 n.77 4 $

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C~ NCT LIGHT 3N13337-06

!",k,8130494 0 TC 234 O! ODE 24. REPLACE 0 LAGP3 AND ZENER O! ODE '

$PAFE 09/02/86 0-TC-234-3 PARE ,CREEN LAMP !! IR-OP'. i

'W REPAIR SNC133-34203-07 BURNED OUT GREEN LAMP. REPLACE ifEEN LAMP

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N, 3131947 0 TC 234 .

38P 07/02/06 0-TC-234-38P , TEMP CONTROLLER CH4TTERS $ UNKNOWN UGULD NOT ACT UP. MONT. - ' ,

INTEFNAL RELAY CONTACTS ,, j WR86-131967

m. 2131984 0 TC 23413338-62 09/03/06 0-TC-234-13338-62 ,3N19338-62 OUTPUT:

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CRITERIA 0F IMI-234.1 TROUBLESHOOT AND . '

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63P 09/12/86 0-TC-234-63P ,TR INDICATE! > 200 i TC

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63P CHANCE 3 STATE 3 LE!! THAN SETPCINT E 3Ef!AL 98133-34703-06. NRfC-131*?4 120 F TC 63 3 CHANCE STATES ABOUE n 'i p 7 : SETPOINT ) 200 f < -*

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i$3131??3 3 PARE 09/13/86 0-TC-234-3PARC ,3N19337-34 TEMP ' s iY CUNTROLLERS RELAT CNATTERS DEFECT!YE OUTPOT RELAY AND CAPACITOR.

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!bt200033 0 TC y 234 3 Pour 07/0?/36 0-TC-234-3 FARE , REPAIR CCNTROLLEE ;;,

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jhB200$$3 0 NTCK 234 31P 09/09/86 0-HTCF-234-31P ,31P NEAT TRACE 7

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CONTROLLER AUX 469 Tall. CONTROLLEE !! $ SERIAL 613338-77. / -

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'i MAINTENANCE

SUMMARY

(MECHANICAL)

p. -.- -- - -, .,.7 ,,, - -- ,... -- - - ,. -

MECHANICAL MAINTENANCE MONTHLY REPORT FOR SEPTEMBER 1986 COMMON

1. The hanger bolt tightening program continues. To date appecximately 400 of 1,000 hangers are complete.

2. Continued damper repairs to allow successful completion of SI-149, Auxiliary Building Gas Treatment System Vacuum Test.

3. Completed shaft sleeve / packing replacement on the essential raw cooling water (ERCW) pumps.

4. Completed review of all technical specification-related surveillance instructions.

5. Replaced aftercoolers on "B" statien service air compressor.

6. The upper pump shaft on "MB" ERCW pump was replaced.

7. Replaced rupture disk on "B" boric acid evaporator package.

UNIT 1

1. Disassembled and began repairs to the unit 1 main generator.

2. Disassembled and inspected 1-FCV-63-40 due to high thrust reading during a MOVATS test.

3. Began main steam valve ring setting changes on unit 1.

UNIT 2

1. completed unit 2 main steam safety valve ring setting changes.

2. The stem in 2-FCV-63-172 was replaced due to damage in the packing gland area.

3. Repaired tube leak in 2A condenser.

4. Removed two hydro pins found in two main steam header hangers,

5. Disassembled and inspected 2-FCV-70-90.

.jxRECHMICAL GINTENMCE MDHTHLY SunnARY 10-0944 PACE 1 A m .. a . s ._. ,. _ egpp _ _ - - - - , . .ae ,

m ,

MR. HIST U FUNC SYS ADD RESS. DATE . . . . DESCRIPTIDH. . . . . . . . . . . . . . . . . . . .. . . . . . . CDRRECTIVE ACTICN. . . . . . . .. .. .

B117117f. 0 EU 042 : 103109/13/84 0-ULY-042-1031, REPLACE DISPHRAGM 2" WDRH DIAPHRAGn. INST 6LLED NEW DIAPHRAGM. M

-u

&s R -

ggyg yIIg gjj.ddOP VLVS AK LEAKING AT-r-

T.M . .h

'. dNZ :@ + , p : BDHNET .. ,

, _ ,. , p .

9

.V,;q ' %g 9M B117110 ~ 1 RU "042 1031 OV13/841-YLU 042-1031, REPLACE DIAPHRAGM 2" ULV WDRN DIAPHRAGM. INSTALLED PG DIAPHRAGM.

{ MM a + j, ,.

B11713d 0 EV 047 ' ' 7%A OV13/84 0-ULU-047-7%A-A,EuMPRDu3,WHEN a pTIC AJJ-440P ULUS ARE LEAKING AT BDMET

. , ;m ,g a,. .. A

WORM D-RING DUE TO NDR'tAL KAR.'

. c .

~ '

['1 ,

,. , SMI-0-67-5 WAS PERfDRnED D-RING WAS INSTALLED HEW D-RING, PERfDRMED L Q.. .$ ',9 m # - . . FDUND TO BE DEFECTIVE

- SURYEILANCE INSTRUCTIDH 33 MD 45.1, AND .

-M n .. c.:/ - . . . RETURED TU SERVICE.

k B120430 1 CMP 082 - 0100 09/15/841-CMP-082-0180 ,EuMPRDw3,CDnPRES!DR HAS WDRN GASKET DUE TD HDRMAL DPERATIDN.

M '1 My ' -

! AIR LEAK ARDUND DISCHARGE FLANGE INSTELED NEW GASKET, CHECKED FDR LEAKS J' AND RETlflNED TO SERVICE.

W 3

B1h3138 1 DISC 042 ';[0192 OV13/841-DISC-042-0192

, REPLACE RUPTURE DISC . DUER Y PRE

.?f y, W gN . ,

w . 2 DISC.< .' A ' ,,

B123473 0 ULY 024 1007 OV14/86 0-ULV-024-1007 , DRIP CHECK VLV 4-24-1007 , 1

%f

?

70 1 " 1, 'l* LEAKS REAL BAD WHEN THE HEADER IS "

ll&& $c >

CHARGED .- +

3' '

<f "

B123d?4 ~0 EV 024 ~ - 1005 09/1d/84 0-VLV-024-1005-lTNIS DRAIM CHECK

.wf' 0-24-1005 DH 0-FCV-24-191 LEAKS THRU 02410V09/84 2-CMP-082-0241,EnNPRDm3, SAFETY VLU DN WDRH HIGH PRESSEE INTAKE %VE DUE TO .

MM B125233 2 CMP 082

$if 1. ' CDnPRESSDR SLIGHTLY LIFTING. CDfFRESSDR NORMAL DPERATIDN. -INSTALLED NEW HIGH ] h, '

o IS KNUCKING UERY HEAVILY. CRANK CASE CK PRESSURE INTAKE UALUE MD C6!KET!.

O . 37 CHECKED AND FULL. PERFDRMED FUNCTIDNAL CHECK 6HD RETUf>ED : s 4 8 8y ea . '

TD SGVICE. ' 2' j B124706. O PMP 313 . 0303 09/18/841-FnP-313-0303 , REPAIR CR REPLACE TO WDRK ECH. SEALS. INSTALL NEW SEALS. q

. J. 6 ,, INSURE ND LEAKAGE FRDn PunP ,- w .. . ,

1 . ..

. s %q%s 8129305f, 2. ENC, 082 0002A2 09/02/84 2-ENG-082-000282 ,CuMPRDn),ENG DRIVEN : WDRN ECHMICAL SEAL'IN FKL DIL PunP. d Q!

FUEL DIL PHP NAS LEAK WITH ENG RUNNING ' INSTALLED NG KCHANICAL SEAL IN PunP, C M Wy h 1 1' << f^

PERfDRMED SI-7 MD RETURED TO SERVICE 0030 CV09/841-PCV-001-0030-B,E*HPRDn3,VLV FAILED _ .,' WDRN PACKING ANI DIRTY IPTERNALS DUE TD

' *M$

VM B129790 1 PCU - 001 .

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STRDKE TIflE SI idd. STFDKE TIME ERRATIC NDRMAL DPERATIDN. INSTALLED NEW PACKING Iff ;g@ 0 ,

Id 3. '. '

.' ADN CLEANED YALUE INTERNALS PERfDRED SURVEILLANCE INSid.CTIDH idd.d AND 1 e q' ;; j'i ,

?

a . .< - , , . . ., .

RETURNED TO SERVICE.'B-179790 . ,

^

B131428 'l AHU Cd1 00100 09/04/861-AHU-041-C010B ,ENNPRDx], A.H.U NDTOR ' BELT STRETCHED DUE TO MUdnAL UPERATI"H.

4 0lg g . HAS THROWN ITS l'ELT; INVESTIGATE AND INSTALLED NEW BELT,PERfDRMED FUNCTIDNAL ,

REPLACE AS HEEDED CHECK AND RETURNED TD SERVICE.

B202201' 1 E V 462 10514 09/04/841-YLU-062-10548-B,UALVE IS LEAKIhG WDRH DIAPHRAGn. INSTALLrD NEW DIAPEAGM.

I ~ 8202104 0 LCY 077 00%A c9/06/a4 0-LCU-077-00950 ,UMTE CAS CDnfRESSOR A WDRN DIAPHRAGM. INSTALLED NG MDISTURE SEPAPATD2 LEVEL CONTRCL UALUE DIAPIRAGM

,- 0-LCV-77-95A HAS A WDRM DUT DIAMAGM g' ,

THAT HEEDS TD BE PEPLACED; 14 recorh list =d,

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.. .MECHMImL NAIH1EHANCE MUMTHLY %"-

SUMMARY

10-09-86 '. PAGE 1 .. .

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- 4 E SEALS IN LDUP 4 MSIU SDLENDID.- -

%HEW ,..a,,1/ 0-RINGS

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MECMNICAL RAINTEEANCE MDHTMLY Surr.ARY 10-09-84 PAGE 1 ,

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'4 :W4 l 0594158_ 2 FSV M1 : YARIDUS 02/2V84 2-FSU-001-VARIDUS ,Eul0CFR50.49d],REPLAC PER 10CFR50.49. INSTALLED HEN 0-RING '

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'T123474" not Found. -

"B173233" not Found.' . . ."'r .

"B124708" not Found.

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4-b MAINTENANCE

SUMMARY

(MODIFICATIONS) h

.o y

i

r

SUMMARY

OF WORK CONPLETED NODIFICATIONS SEPTEMBER 1986 NUREG 0588 ECW 6231 - Remove Interferences All identified work is complete.

APPENDIX R ECN 5435 - Fire Doors The installation of weatherstripping continues as resources permit.

ECN 6300 - Additional Sprinklers and Draf t Stops The draft stop workplan was approved, and the sprinkler workplan is

in the approval cycle. Questions concerning the design have been raised by Operations. A workplan for the electrical portion is in the approval cycle.

. ECN 6311 - Operator Extension on POEV

'This work has been completed except for final cycling at startup.

OTHER ITEMS ECNs 2783 and 5202 - Installation of Fifth Diesel Installation of the fifth diesel generator has been deferred i indefinitely.

ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of isolation valves was approved.

Some insulation activities remain incomplete. DNE completed the USQD revision.

. ECNs 5034 and 5743 - Various Platforms in Lower Containment Because of new weld inspection requirements, Modifications Group B is waiting on DNE to furnish inspection requirements on tack welds to hold down grating.

j ECN 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 5599 - Conduit Supports for Fifth Vital Battery and Waste Disposal Area Workplan 12186 in approval cycle for fifth vital battery area.

Workplan for waste dispoal area held for approval of FCR 4753.

ECW 5609 - Air Compressors Makeup Water Treatment Plant Air compressors and mechanical piping complete except for tie-in to -

headers which is held for issue of electrical drawings.

ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete.

ECN 5703 - Reinforcement of Block Walls Unit 1 is 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 remains incomplete--work is in progress.

ECN 5880 - UNID Tags for Class 1E Fuses

~

DNE revised fuse listing and drawings. Five workplans have been approved, and field verification of Class 1E fuses and penetration cable protection has begun.

ECNs 5938. 6305. and 6571 - Replace Feedwater Heater and Eroded Pipe 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 in preparation for the changeout of feedwater heaters 3 and 4.

Structural steel reinforcement has begua on unit I heaters 3 and 4.

t

-:,-_ ,- - . . - - , -,- - , . - _ . , - .n,

e ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced. The extent of cable tray cover requirements are being reevaluated by DNE.

ECN 6147 - Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete (prior to mode 4).

ECN 6145 - Offsite Paging System Functional tests of the remoto mobile units remain to be completed.

ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete and scheduled for startup.

ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete.

Modifications Group A is waiting for a technical specification change to place the circuits in operation.

ECN 6237 - Modify Snubbers Work was started and is in progress.

ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement Cleanup, flushing, and reinsulation is continuing.

ECN 6380 - Replacement of Barton Pressure Transmitters Unit 2 installation is 50 percent complete.

ECN 6357 - ERCW Roof Access and Rails for Security Equipment Workplan 12238 being written to perform work.

ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Two heaters completed on workplan 12005. Workplan 12223 is being issued for five remaining heaters.

ECNs 6402 and 6439 - Pressurizee Instrumentation Relocation All work is complete. In-service tests will be performed when the system is brought up to temperature and pressure.

ECN 6459 - Declassify Certain Class 1E Equipment Conduit tags and nameplates have been changed out.

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 Replacing of anchors 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 is incomplete.

ECNs 6631 and 6683 - Snubber Replacements / Modifications An additional support was added to 6683. Work on the support is in progress.

ECN 6636 - Replace Cable in Valve Room The first variance has been approved and work will restart immediately.

ECN 6637 - Control Air Drawing Discrepancies Work was completed.

ECN 6648 - Time-Delay CCS Pump All work is complete.

ECN 6661 - Upgrade ERCW Piping Work remains in progress. All large pipe installed, hydroed, and returned to service.

ECN 6667 - Delete Torque Switch MOVs Work is approximately 80 percent complete on both units.

ECN 6681 - Supports for ERCW to Upper Compartment Coolers (Annulus)

Fieldwork was completed.

ECN 6689 - Relocation of Mainsteam PORV All conduit cable and tubing are complete on unit 2. Relocation of controls is expected shortly. Unit 1 conduit is in progress.

ECN 6698 - Repull 120-Volt Cables Resolution of DNE comments on workplan and PORC approval remain prior to commencement of work.

ECN 6700 - Concrete Edge Distance Hangers Field work is in process.

ECN 6701 - Modify Foxboro Recorder Latches Fieldwork is continuing. Several FCRs have been required.

ECN 6702 - Upgrada of ERCW Valves Workplan written and approved. Awaiting valve tags for completion.

ECN 6706 14 Support Enhancement Field work continues on both units. Inspections for unit 2 are complete. fotals to date are 396 for unit 2 with 72 requiring work and 23 complete. Totals to date are 1784 for unit 1 with 31 requiring work and 17 complete.

ECN 6707 - Replace System 74 Flow Switches Resolution of DNE comments on workplan and PORC approval remain prior to commencement of work.

ECN 6710 - Diesel Generator and SIS Supports Field work for all supports but one complete. A pipe clamp is on order for the last support and is due early October.

ECN 6712 - Turbine-Driven Auxiliary Feedwater Room DC Exhaust Fan Conduit and cable work is complete, termination is in process.

ECN 6717 - Stub Bus Fuses ECN has been returned to DNE for further work on USQD.

ECN 6718 - Postaccident Sampling Facility Modification for Hydrogen Analyzer Field work was completed.

ECN 6719 - Volumetric Intrustion Detection Systems

^

Final civil drawings were received September 30, 1986. Workplan 12186 for civil and architectural features submitted for approval i cycle.

ECN 6723 - Diesel Generator Exhaust Piping Supports All field work completed.

ECN 6739 - Alternate Analysis Two workplans were written and approved and work started in excess of 200 supports are anticipated. Approximately 70 are complete.

Work continues on others.

ECN 6749 - Replacement of Bussman KAZ Replacement with MIS-5 has begun.

ECN 6752 - Modification of P.D. (Anchor Problems)

Workplan written, approved, work started and is continuing.

ECN 6754 - Penetration Supports Workplan written and in the approval cycle.

ECN 6758 - HVAC Supports Unit 2 field work complece. Unit I workplan remains in the approval cycle.

ECN 6761 - EVR Blowout Panels o

Workplan was written and placed in the approval cycle.

ECN 6769 - Auxiliary Air Compressor Traps Workplan was written and placed in the approval cycle.

ECN 6770 - Water Spray Workplan written and placed in approval cycle.

ECN 6781 - Hanger Pipe Clamps Workplan was written and placed in the approval cycle.

ECN 6790 - Medium Energy Pipo Break Workplan written and placed in approval cycle.

Dry Active Waste Building (DCR 1898)

The roofing work is complete. Some roofing ranels will require removal for crane access to align the compactor. Work continues on the trim, dock levelers, and metal doors. Remaining work on inside wall and mechanical features held for dcawings and material. In addition, no interface drawings have been released.

Additional Office and Medical Facility Building All faciliciss complete. Fencing along railroad area and west side helit for installation of the South Central Bell environmental un'it.

Additional Office Building at Power Operations Training Center Complete.

Paving Activities

_ Complete.

Storage Building at Power Operations Training Center g Building erection complete. Outside trim and inside mechanical and electrical activities in progress.

e ADP Additional Lights to Parking tot No. 2 (DCR 2260)

Workplan 12208 written but held for design drawings.

Install Electrical to Sump Pumps in Manholes 42 and 46 FCRs 4534 and 4572 approved by DNE. Workplan issue for approval held for drawing issue.

Welding Project Support was provided to Welding Project personnel as requested.

Procedure Revisions Many manhours were spent revising procedures.

e

NODIFICATIONS ECN DCR- SYS UNIT DESCRIPTION 15827 D1705 244 0 Provide power line carrier terminal and microwave channel equipment for transmission of interchange readings to the alternate Power Station Control Center at Volunteer, Tennessee 500kV substation.

L5899 'D1384 01'3 0 Change drawing to reflect contact change from.normally closed to normally open (45N1699-33). Fire protection panel 0-L-531 2B relay. Document change only.

L6405 D2183 085 2 Replace the existing Crouse Hinds connectors with a more reliable type connector.

L6553 D0972 000 2 Replace the class IE cables identified on SCR-SQN EQP8520 with cables qualified in accordance with 10 CFR 50.49.

Systems 30, 31, and 70.

L6570 F3958 000 1~ Correct drawings to show the pressure setpoint for valves62-505 and 63-511 is 220 psi.

L6590 F4066 003 2 Hardface internal gasket seating surface with Stellite No. 21 of steam traps on terry turbine (auxiliary feedwater pump) located between 2-VLV-3-916 and -917, and 2-VLV-3-914 and -915.

L6637 F4176 032 0 To correct drawing discrepancies and to get additional design information added i to drawings as identified in Quality Surveillance Survey No. 21-86-S-003 on i auxiliary control air system.

L6641 F4261 099 2 Change the description for the RCP 62 timers to ATC timers (Model 317K,

. specification F3791. Also install new timers.

L6649 D0972 317 1 Replace the field wiring inside solenoid valves with qualified wiring. This ECN supersedes ECN L6581 which is voided.

L6672 F4332 026 2 To facilitate valve maintenance need to modify existing hanger 47A491-44-7.

f

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ECN DCR SYS UNIT DESCRIPTION I

L6675 F4408 317 2 Division of Nuclear. Engineering (DNE) to issue a design controlled document specifying all penetration Trotective I devices and all non-lE load breakers fed from 1E buses that require testing.

L6693 D2259 081 2 Restrain existing seismic category 1(L) piping to prevent or limit horizontal movement during a seismic event in accordance with resolution of Gilbert-Commonwealth Technical Issue Number II.

L6703 F4475 012 1 Show correct plant configuration of piping for auxiliary boiler system.

Major piping location: from steam trap on elevation 669 ABW to tie-in on elevation 653.

L6723 D2259 082 1 Perform analysis, component qualifications, and support evaluation, and document for eight diesel generator exhaust lines.

L6730 F4349 012 0 Revise drawings to reflect current plant configuration of 1/2-inch tubing between nitrogen supply and pressure indicator PI-12-107.

L6732 D2257 000 1 Revise main steam flow diagram for higher pressure on steam dump piping.

L6747 F4503 001 1 Reverse the valve tag order for all four loops of the main steam safety valves on units 1 and 2 on drawing 47W801-1.

Document change only.

L6753 F4448 046 2 Show configurations change to control air lines in accordance with sketches to match as-constructed status for feedwater control system. Document change only.

L6759 D2259 077 2 Evaluate all attachments made to 1/4-inch plate on crane wall and all supports mounted with concrete expansion anchors .

installed by drilling through plate, and modify as required.

L6772 F4327 027 2 Delete circulating pump drain valves.

Units 1 and 2-27-716 -717 -738. -739,

-760 -761 from the flow diagram drawing. Document change only.

Not Required D2215 003 2 Remove and replace original carbon steel J-nozzles with new incone J-nozzles.

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6 D

ENVIRONMENTAL QUALIFICATION (E.Q.)

SUMMARY

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. Estimated Date of Con 1pletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Conments EQP 8501 Disconnect I- and 2-HS-62-61 6524 Peters 11901 C C U-2 QIR submitted.

EQP 8502 Replace penetrations 23 and 48 6490 Peters 11801, 11802, C C Complete QIR submitted.

11810, 11811 EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Conplete field verification sheets are in binder. No QIR needed.

EQP 8504 Spilce methods not correct N/A Stockton 80 Ms C C Conplete QIR submitted.

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 8508 JB weepholes (press) 6523 Alas 11898 C C Couplete QIR submitted.

I EQP 8508R2 JB weepholes 6709 Alas EQP 8509R1 Conduit seals 6529 Kimsey 11903, 11904 C C E0P 8509R2 conduit seals 6615 N/A N/A N/A No fleicherk remaining.

EQP 8510 Disconnect local handswitches 6527 Peters 11901 C C EQP 8511 Submerged JB inside 6549 Peters 11901 C N/A containment

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, Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Canments EQP 8512R2 Rewire JB N/A Anburn 11855, 11856 C C All boxes rewired.

EQP 8513 Weep hoics (moisture) 6547 Alas 11898 C C Conplete QIR st.bmitted.

EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C C Caplete QIR submitted.

EQP 8514 Motor insulation 74-1, -2 6540 Branham 11906 N/A C Conplete QIR submitted.

EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C C l

1 EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C Maint. )

l EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C EQP 8518 Submerged cables 6533 Various/6 various C C

, o EQP 8519 Tee drains N/A Electrical N/A C C Conplete QIR submitted. 1 Maint.

EQP 8520 Expired cables 6553 Gonzalez 11902 C C EQP 8521 Delete TB and rework splices 6550 Stockton 11914, 11915 C C EQP 8521R1 Delete TB and rework spilces 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.

I

(

Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Conments 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 Reter1ninate hydrogen N/A Electrical N/A C C Conpleted by Electrical Maint.

reconbiner (M) Maint.

EQP 8526 Replace FSVs, U-l 1, U-2 11 6552 Mechanical 11897 C C Mods.

EQP 8527 Coat TB, U-l 3, U-2 8 N/A Stockton 11914, 11915 C C (M) w EQP 8528 Solder strain gauge Barton IMI Instrument N/A C C QIR submitted 1/24.

! transmitters Maint.

i

! EQP 8529 PDT-30-42, -43 6554 Legg 11912 C C l

) EQP 8530 Gasket, Namco L/S N/A Electrical N/A C C (m) Maint. -

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.

j -202, -207, and -208 i'

EQP 8533 Delete dual voltage splice N/A Rutledge 11866, 11853 C C

)

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e Estimated Oate of

Concletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Comments i EQP 8534 Resplice valve positioner N/A Maxwell Nt C C Conplete QIR submitted.

3-174 and -175 i

EQP 8535 Replace limit switches, 6556 Gtockton 11927, U-2 C C j U-l 10, U-2 12 11928, U-1 EQP 8536 Valve room submergence 6561 Mechanical 11939 C C

Cap drains 6632 Mods. C C EQP 8536RI Valve room submergence 6612 Electrical C C Mods.

EQP 8537 Rebuild or replace JB 3078 6579 Anburn N/A C

, . EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C C FCO-31-475, -476 EQP 8539 Replace capacitors N/A Instrument C C Maint.

EQP 8540 Replace pigtails to Target 6649 Peters C C Rock solenoid valves ,

EQP 8541 Delete brakes 6582 Branham 11980 C N/A EQP 8542 Replace unquallfled cables 6680 Hall 12/30 N/A Two cables will be replaced in

! accordance with a new issue.

l EQP 8543 Replace JB wire N/A Anburn 11855, 11856 C C 4

6

Estimated Date of Concletion SCR ho. Description ECN Engineer Workplan No. U-l U-2 Coments EQP 8601 Replace 1 , 2-PT-1-2A, -27A; 6588 Elkins 12014 C C i

upgrade 2-PT-1-28, -27B EQP 8602 Reroute control cables for No longer an issue.

1 , 2-FCV-70-87, -89 EQP 8603 Replace portion of PP7118 6627 Kimsey N/A C I

EQP 8604 Cable IPL3241A not quallfled "auaaaaaaaaa"aa"aiAaaaaaaaaaa" ";" Gaaaa No longer an issue.

EQP 8605 1 , 2-T5-74-43, -44, -45, 6589 Branham C C 1 -46 not quallfled EQP 8606 Undervoltage concern on 6611 Rutledge 11/1 11/1 Holding for drawing issue.

, feedwater isolation valve 6676

$ s brakes I EQP 8607 Delete TB for 1 , 2-PT-1-2A, 6626 Instrument 12014 C C 1 -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 IV79738 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 l

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Estimated Date of -

Cmpletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Conments EQP 8614 Weep holes in JB 6652 C C EQP 8615 Repl:ce FT-72-13, -34 EQP 8617 Junction box internal wiring Anburn Workplan in appmval cycle.

, EQP 8618 Relocate arc suppression 6795 Holding for drawings.

network i

EQP 8619 Valve room submerged cables Holding for corrective action detennination.

EQP 8620 Relocate steam generator Instrument Will roll transmitters 1800.

level transmitters Maint.

EQP 8621 Resolve conduits and fittings Holding for corrective action that may be submerged in determination.

Auxiliary Building i

EQP 8622 Replace tenninal blocks with Holding for drawings.

spliced cables EQP 8623 Replace limit switch on No longer an issue.

TOV-3, -21 EQP 8624 Junction box 2145 may be ************ No longer an issue.

submerged, unit I EQP 8625 6.9-kV nondivisional cables Holding for drawings.

in trained trays i

s 9

^ _ _ _ _ _ _ _ _ _

-e Estimated Date of

Concletion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Conments N/A Move surge suppression 5773 Kimsey 11883 C C .

network for PORV EEB 8523 Penetration overcurrent 6606 Legg C C N/A Work FCR to delete 1 , 5883 Hall C C Need SI-166.

2-PS-3-160A, -1608, -165A, and -165B N/A Replace 1-FT-1-3A, -38, -10A, 6347 Instrtsnent N/A C N/A

-108, -21A, -21B, -28A, -28B Maint.

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 L5-65-4, -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 e

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TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 October 15, 1986 Nuclear Regulatory Commission Office of Management Information and Program Control

- Washington, DC 20555 Gentlemen SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - SEPTEMBER 1986 Enclosed is the September 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY Y

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 Nucl<.2 : 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)

Mr. K. M. Jenison,JResident NRC Inspector -d O&PS-2, Sequoyah Nuclear Plant {(', b f II An Equal Opportunity Employer

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

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