ML20107A360

Monthly Operating Repts for Dec 1984

ML20107A360
Person / Time
Site:	Sequoyah
Issue date:	12/31/1984
From:	Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8502190436
Download: ML20107A360 (33)

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~N' TENNESSEE VALLEY AUTHORITY DIVISION'0F NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION December 1, 1984 - December 31, 1984 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 f

I I B502190436 841231 PDR ADOCK 05000327 R

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,. C' TABLE OF CONTENTS ~

. P, age Operations Summary.

1 Significant.: Operational Events.

1-3 PORVs. and LSafety Valves Summary...

4 Reports Licensee Events.

5-8 Diesel Generator Failure Reports.

7 Special Reports 7-8 Offsite Dose Calculation Manual Changes.

8 Operating Data i

Unit 1..

9...........................

Unit'2..

12-14 Plant Maintenance Summary.....

15-29 i

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- Operations Summary

.. )

December'1984 The _ following summary describes the significant operational activities

,for,the month of December.

In support of this summary, a chronological:

log of significant events'is' included in-this report.

Unit 1 Unit I was critical-for 744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 862,510 MWH (gross), resulting in an average hourly gross load of 1,159,288 kW during the month. There are 170.8 full power days estimated remaining until the end of cycle 3 fuel.

With a capacity factor of 85 percent, the target EOC exposure would be-reached July 20,-1985.

The capacity factor for the month was 98.0 percent.

During the month, the unit experienced no reactor scrams, manual shutdowns, or power reductions.

Unit 2 i

Unit 2 was critical for 209.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, produced 39,000 MWH (gross), resulting in an average hourly gross load of 304,997 kW during the month. There are 362.0 full power days estimated remaining until the end of cycle 3 fuel.

With a capacity factor of 85 percent, the target EOC exposure would be

, reached March 2, 1986.. The capacity factor for'the month was 4.4 percent.

During the month, the unit experienced one reactor scram, two manual shutdowns and no power reductions.

Significant Operational Events Unit 1 Date Time Event 12/01/84 0001 The reactor was in mode 1 at 100%

power producing 1165 MWe.

12/18/84,

1420 Began a load reduction to test the 500 kv.intertie breakers.

1 1530 The reactor was at 82% power and holding. The unit load was 964 MWe.

2335 Began power ascension.

l 12/19/84 0415 The reactor obtained 100% power.

12/31/84 2359 The reactor was in mode 1 at 100%

power and producing ~1165 MWe.

i l

i j '

Y-Significant Operational Events (Continued).

Unit 2 Date Time Event 12/01/84 0001 Cycle 2 refueling / modification outage continues..

g 112/03/84 1306 The reactor entered mode 4.

12/05/84 1250 The' reactor entered mode 5 for RPI repairs, inoperable RCP #3 and leaking 7,

1..

(

primary check valves63-641 and -644.

J12/13/84 2155 The reactor entered mode 4.

12/_14/84 2053 The reactor entered mode.3.

P 12/15/84 '

0326 The 500 kv Watts Bar 2 (PCB 5064) CT exploded. The fire was extinguished within 5 minutes.

12/16/84 0826 While attempting to stop PZR safety valve 68-330 from leaking a reactor trip and safety injection occurred on a Lo Pressure SI signal. The reactor was not critical at the time.

12/17/84 0050 Pressurizer safety 68-564 opened.

0130 68-g64wasrescated. RCS was'at 547 F and 1800 psi.

4 12/18/84 2020 The reactor entered mode 2.

2147 The reactor was taken critical.

12/19/84 1735 Control bank A, rod H-10 dropped.

~2200 The reactor was in mode 2 and suberitical (Keff < 1 >.99).

12/20/84

'0140' Control bank A, rod H-10 repairs were completed.

0300 The reactor was taken critical.

1725 Control bank D, rod H-4 dropped while stepping in D bank.

2310 Began cooling down to mode 5 for i

control rod problems.

l 2339 The reactor entered' mode 3.

12/21/84 0453 The reactor entered mode 4.

1131 The reactor entered mode 5.

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Significant' Operational Events (Continued)

Unit 2 Date Time Event 12/23/84 1230-Began RCS heat-up.

1505 The reactor entered mode 4.

2025 The reactor entered mode 3.

12/24/84 2255 The reactor' ntered mode 2.

2258 The reactor was taken critical.

'12/26/84 0046 The reactor entered mode 1.

0433 The unit was tied on line. 'The cycle 2 refueling / modification outage ended (88 days).

1350 The reactor obtained 30% power producing 290 MWe and was holding for secondary chemistry and the turbine overspeed trip test.

12/29/84 1355 Began reducing load for the turbine overspeed trip test.

1532 The reactor tripped due to a Lo-Lo

1. 4 steam' generator level.

The reactor entered mode 3.

12/30/84 0008 The reactor was taken critical.

0115 The reactor entered mode 1.

0306 The unit was tied online.

0405 The reactor obtain 30% power and-was holding for secondary chemistry.

12/31/84 2359 The reactor was in mode 1, holding at 30% power due to secondary chemistry and producing 300 MWe.

'(.

PORVs and Safety Valver Summary-

. Licensee Events and Special Reports The following. licensee event reports (LER) were sent during December 1984 to the Nuclear Regulatory Commission.

LER DESCRIPTION OF EVENT 1-84071 On November 21, 1984, with unit 1 in mode l' at 100% power and unit 2 in mode 5, during a review of Surveillance Instruction (SI)-6, " Containment Building Ventilation Isolation," it was noted that the radiation monitors for containment ventilation isolation were not being adequately verified in accordance with the technical specifications. The.SI was verifying containment ventilation isolation from only the gaseous channels of the upper and lower. containment radiation monitors, and did not include the particulate channels during core alterations or movement of irradiated fuel (as described in LCO 4.9.9) only.

This proccdure deficiency was discovered after the unit had returned to a nonapplicable mode. The'SI is being revised to include both channels.

Both channels of the radiction monitors were operable during the time that SI-6 was required as verified.

1-84072 On December 7, 1984, Sequoyah Instrument Maintenance personnel idenfified a functional discrepancy for postaccident radiation 4

monitors for the RCnT discharge piping, and the RBFES discharge piping from containment.

It was noted that the RCDT monitors were located on the RBFES piping and the RBFES monitors on the RCDT piping. This would have resulted in the inability of the monitors to close their designed containment isolation valves in the event of high radiation through the-discharge lines.

Upon event discovery, the monitors were revised to provide adequate and correct isolation capability. This is an item of noncompliance with License Condition 2.C.22.F for unit 1.

1-84073 A fire door inspection was performed at Sequoyah Nuclear Plant, using UL guidelines from a Watts Bar inspection. This inspection resulted in finding 110 fire doors that fail to meet Underwriters Laboratory (UL) Standards. Thirty-six (36) of these doors have been evaluated as being nonfunctional,s and L.C.O. 3.7.12 was entered at 1040 CST on December 12, 1984 for these doors. Fire j

watches required per Action (a) of L.C.O. 3.7.12 were satisfied by using existing watches in this area, previously established I

by other Appendix R commitments. Failure of the 110' doors can be attributed to maintenance and modifications activities per-formed on these doors.

l l 1

I-Licensee Events and Special Reports (continued)

LER DESCRIPTION OF EVENT l-84074 Inspections at Sequoyah Nuclear Plant have_ identified the following additional items of noncompliance with Appendix R of 10 CFR 50.

These inspections are part of an ongoing project to ensure compliance with Appendix R.

1.

1-FCV-68-332 cable IV2449B interacts with 1-PCV-68-340A cable IV5612A in the auxiliary building on elevation.734 in the 6.9kV shutdown board room

'A' at A3-6/R-S line.

2.

2-FCV-68-333 cable 2V2455A interacts with 2-PCV-68-334 cables 2V5593B and 2V5594B in the auxiliary building on elevation 734 in the 6.9kV shutdown board room 'B' at A11-13/R line.

3.

1-PCV-68-334 cable IV55988 and train 'A' power to 1-FCV-68-333 interact on elevation 748 in the auxiliary building in the 480 volt transformer room '1A'.

4.

2-PCV-68-340A cable 2V5610A interacts with train

'B' auxiliary power cables to block valve 2-FCV-68-332 in the auxiliary building at elevation 714 on A8/Q line.

5.

2-PCV-68-334 cable IV5596B interacts with train 'A' auxiliary power cables to block valve 2-FCV-68-333 in the auxiliary building at elevation 714, A6-8/Q-R line.

6.

2-PCV-68-340A cable 2V5612A interacts with train 'B' auxiliary power cables to block valve 2-FCV-68-332 at elevation 759 in the auxiliary building in the CRD equipment room.

7.

Cables for

'A' train valves 0-FCV-70-193 and 0-FCV 197 and 'B' train valves 0-FCV-70-194 and 0-FCV-70-198 interact on elevation 714 in the auxiliary building with the IAA, 2AA, IBB, 2BB, and C-S CCS pumps.

8.

2-FCV-74-1 cable 2V2780A interacts with 'B' train auxiliary power for 2-FCV-74-2 in the auxiliary building at elevation 759 in the CRD equipment room at A13/V.

9.

In the auxiliary building at elevation 734 in the' unit I reverse osmosis room, cables for 1-FCV-74-2 interact with cables for normal and excess letdown. For a fire involving normal and excess letdown, the shutdown Jogic requires that 1-FCV-74-1, -2 be open within 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

10.

Interactions exist between 1-LCV-62-132 (cables IV2761A, IV2764A, IV2765A) and 1-LCV-62-133 (cables IV2771B, IV2774B, IV2775B) such that spurious operation of either valve could be caused by a fire in the auxiliary building at elevation

+

i 690..

4 Licensee Events and Special Reports (continued)

LER-DESCRIPTION OF EVENT 1-84074 (continued)-

11.

Cables for 1, 2-FCV-70-156 (IV2562A,~ IV2565A, 2V2562A, 2V2565A) train

'A' and 1, 2-FCV-70-153 (IV2556B, IV2559B, 2V2556B, 2V2559B) train

'B' interact with each other and cables associated with CCS pumps IAA, 2AA, IBB, 2BB, and CS.

These interactions exist in the auxiliary building on elevations 690, 714, 734, and 749.

12.

Common power supply and common enclosure cables were analyzed per Appendix R criteria. Four hundred and six (406) circuits failed this criteria due to lack of proper fuse and breaker coordination. More in-formation will be forthcoming per confirmation of action letter from J. P. O'Reilly to H. G. Parris dated August 10, 1984.

The action statement for Technical Specification 3.7.12 was satisfied by utilizing fire watches in the affected areas that were established by other Appendix R commit-ments. This action included the establishment of a roving fire watch in areas with fire detection and a dedicated fire' watch in areas without fire detection.

1-84075 On December 1, 1984, at 0000 CST, with unit 1 in mode 1 at 100% power and unit 2 in mode 5, the fire watch assigned to route "C" (outside) on November 30, 1984,

.from 1500 CST to 2300 CST, failed to await proper relief prior to assuming an overtime watch on route "B" (inside). -The replacement for route "C" failed to show up for work as-scheduled. This condition remained unknown until the assistant unit operator 4

(AUO) outside realized that-the fire watch truck had not moved during the shift. The shift engineer immediately re-established the fire watch on route "C" (at 0510 CST) by utilizing the outside AUO.

s Licenses Events and Special Reports (continued)

Diesel Generator Failure Reports There were no; diesel generator failure reports transmitted during the month.

4 Special Reports

- The following special report was transmitted during the month.

DESCRIPTION 84-08 Sequoyah Nuclear Plant has been performing a sprinkler system walkdown during the Appendix R reverification program to ensure full compliance with License Condition 2.13.(a) of the Unit 2 Facility Operating License. These walkdowns have identified sprinklers in the Auxiliary Building that.do not comply with the literal requirements of NFPA Standard No. 13, as committed tc in the Fire Protection Program submittal and the SER Supplement I submittal. All sprinklers identified have been evaluated as being operable, and will function to prevent both redundant divisions of safe shutdown equipment from being damaged. The-locations of'these sprinkler heads have been summarized in the following table by elevation. The table 4

also categorizes the sprinklers into different areas of corrective actions required to bring the sprinkler system into compliance with NFPA Standard No. 13.

i Elevation (Aux Bldg)

Relocate Plug Add (Note 1)

(Note 2)

(Note 3) 669 53 90 25 690 78 25 31 714 123 0

116 734 111 185 27 749 34 20 18 759 19 29-0 418 349 217 (Note 1) -~These sprinkler heads must be relocated to bring into full compliance with NFPA-13.

(Note 2) - These sprinkler heads have been evaluated as not being required for NFPA-13, and will be plugged or removed. _. -

2 Licenses' Events and Special Reports (continued)

DESCRIPTION (Note 3) - These sprinkler heads must be installed to bring the' system into compliance with NFPA-13, and ad-dress intervening combustibles. The majority of these must be added, due to' obstructions between the ceiling mounted sprinkler heads and floor level e

equipment.

' 84-10 Fire door A-77 was open without-a fire barrier breaching permit and the required roving _ fire watch. This door is located on elevation 690

.between the containment airlock doors and the 690 penetration room. Unit 2 was in a refuel-ing outage, and door A-77 is located in the passageway used for access to the annulus and lower containment.

4 Offsite Dose Calculation Manual Changes There were no changes in the Sequoyah Nuclear Plant Offsite Dose Calculation i

Manual (ODCM).

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OPERATING' DATA REPORT:

DOCKET NO. 50-327-

'DATE JANUARY 10,1985.

COMPLETED BY M.

G.'

- EDDINGS j,

TELEPHONE (615) 870-6248 OPERATING STATUS c1. UNIT NAME:. SEQUOYAH NUCLEAR PLANT, UNIT 1

NOTES:

.2.--REPORT PERIOD:. DECEMBER--1984

3. - LICENSED :. THERMAL POWER (MWT ) :

3411.0;

4. NAMEPLATE: RATING'(GROSS:MWE)::

1220.6 5.zDESIGN ELECTRICAL RATING'(NETEMWE):

1143.0 15.-- M A X I M U M D E P E N D A B L E C A P A C I T Y (GROSS MWE):

' 1183.0

~

7.'-MAXIMUM DEPENDABLE; CAPACITY (NET MWE):

1148.0-l.11F CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS' 8

4

'3-THROUGH 7)SINCE LAST REPORTv GIVE REASONS:______

_=-.

9. POWER LEVEL TOlWHICH-RESTRICTED.IF ANY(NET MWE):___-

i

=

10. REASONS FOR: RESTRICTIONS'IF ANY:----

- =___

1

- =--

THIS MONTH YR.-TO-DATE CUMULATIVE i

11. HOURS IN REPORTING PERIOD 744.00 8784.00 30721.00 2

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 6206.10-20647.66 113. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE.

744.00 5995.80 20108.95 4

- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 16._ GROSS THERMAL ENERGY GENERATED (MWH) 2525283.37-19185835.65 - 64677685.95

'17.. GROSS ELECTRICAL ENERGY GEN. (MWH) 862510.00 6357280.00 21736416.00

{18.; NET. ELECTRICAL ENERGY GENERATED (MWH)

'827991.00

~6104702.00 20881630.00

'19. UNIT SERVICE FACTOR 100.00 68.26 65.46 i20. UNIT AVAILABILITY FACTOR' 100.00 68.26 65.46 l21. UNIT CAPACITY FACTOR (USING MDC NET) 96.94 60.54

-59.21 122.LUNIT CAPACITY FACTOR (USING DER NET) 96.94 60.54-59.21 j23. UNIT FORCED OUTAGE RATE O.00

-19.22 18.34 124. SHUTDOWNS. SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

i j

j25.-IFSHUTDOWNATENDbFREPORTPERIOD.

ESTIMATED DATE OF STARTUP:

i

. _ICLNEIGRING-_. APRIL,. 26 1985,._.:_.11L DAYS i

7 NOTE THAT THE THE YR.-TO-DATE AND.

CUMULATIVE VALUES HAVE BEEN.U? DATED.

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UNIT SHUID0 % AND POWER REDUCTIONS DOCKET NO.

50-327 c,

UNIT NAME... Sequoyah One U_

DATE January 10. 1985 COMPLETED BY M. G. Eddinns REPORT HONTH December TELEPHONE Ia si a7n %>An -

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cyu Licensee Cause & Corrective No.

Date E.

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NO SHUTDOWNS OR POWER REDUCTIONS DURING MONTH 4

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4 F: Forced Reason:

Method:

Exhibit G-Instructions 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

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I AVERAGE DAILY UNIT POWER LEVEL

?.

DOCKET NO.

50-327 UNIT ONE DATE January 10, 1985 COMPLETED BY M. Eddings TELEPHONE (61s) 870-6248 HONTil necember 1984 DAY-AVERAGE DAILY POWER LEV 5L DAY AVERAGE DAILY POWER LEVEL

'(MWe-Net)

(tNe-Ne t) 1 1129.1 17 1125.0 2

1122.0

-13 1073.4 3

1124.5-19 1087.2 4

1123.8 20 1127.8 5

'1124.3

'1b9.3 21 7

6 1125.6 22 1129'.'2 7

1125.4 23 1127.3-8 1126.2 24 1127.2 9

1127.0 25 1126.6 10 1126.4 26 k

1126.5 11 1125.5 27 1125.2 12 1126.9~

28 1122.8 13 1123.6 29 1120.4 14 1127.3 30 1120.0 15 1128.5 31 1120.5 16 1128.9

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INSTRUCTIONS

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Onthisformat,listjheaveragedailyunitpowerlevelinMVe-Netforeachdayin the reporting month.

Compute to the nearest whole megawatt.

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(9/77)

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OPERATING DATA REPORT DOCKET.NO. 50-328 DATE JANUARY 10, 1985 COMPLETED BY D.C.DUPREE TELEPHONE (615)S70-6248

_ g, OPERATING STATUS

1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2

NOTES:

2.

REPORT PERIOD:. DECEMBER 1-31, 1984

3. LICEtNED THERMAL POWER (MWT):

3411.0 4.

NAMEPLAL' RATING (GROSS MWE):

1220.6 5.

DESIGN ELECTRICAL RATING -(NET MWE):

1148.0 6.-MAXIMUM DEPENDABLE-CAPACITY (GROCS 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 REPORT, GIVE REASONS:-__---_--_--

9.' POWER LEVEL TO WHICH RESTRICTED,IF.ANY(NET MWE):_-------

10. REASONS FOR RESTRICTIONS,IF ANY:

THIS MONTH YR.-TU-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.00 8704.00 22601.00

12. NUMBER 0F HOURS REACTOR WAS CRITICAL 209.30 6334.05 16695.12

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURG GENERATOR ON-LINE 127.87 6115.86 16270.18

15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

16. GROGS THERMAL ENERGY GENERATED (MWH) 131365.76 19530943.06-51999010.87

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 39000.00 6659740.00 17691680.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 29582.00 6403271.00 1702100G.60

19. UNIT SERVICE FACTOR 17.19 69.62 71.73

'20.

UNIT AVAILABILITY FACTOR 17.19 69.62 71.73

21. UNIT CAPACITY FACTOR (USING MDC NET) 3.46 63.50 65.37

22. UNIT CAPACITY FACTOR (USING DER NET) 3.46 63.50 65.37

'23. UNIT-FORCED OUTAGE RATE 8.30 7.44 8.59

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

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

__-_---=-

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

UNIT SH'JTD0Vhs A:iD POWER REDUCTIONS.

DOCKET NO.

gn.31g UNIT-NAME

---hequoyah Twa DATE 3anuary in ions COMPLETED BY n,nria

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REPORT MONTH nacamhar 1984 TELEPHONE (61si a7n-6106 1

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517 "a

cy" Licenste Cause & Corrective Mo.

Date E

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t 13 840928 S

604.55 C

4 Refueling Outage Continues

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14 841229 F

11.57 A

3 Reactor Tripped on Lo-Lo S/G Level While Re-ducing Power-For.The Turbine Overspeed Trip Test

=

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1 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions 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 m

~ a aQ F.

5VERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-328 UNIT

'Sequoyah Two DATE January 10, 1985 COMPLETED BY D. C.

Dupree TELEPHONE (615) 870-6196 MONTH noi,mher 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

'(MWe-Net)

(MWe-Net)

I g7 go RO 2

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n 3

19 ft 4

20 5

I 21 6

22 3 '

7 23 n

8 24 s

9 25 10 26 nn 11 27 321 12 28 324

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29 224 14

-30 264 15 31 318 16 INSTRUCTIONS Onthisformat,', list'jComputetothenearest'wholehe average daily unit powe e

the reporting month.

megawatt.

i (9/77)

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Plant Maintenance Summary

The plant maintenance summary for significant maintenance items completed' during the month of December 1984 are listed in the following order:

Construction Activities Electrical Maintenance.Section Electrical Modification Section Instrument Maintenance Section Mechanical Maintenance Section Mechanical Modification Section f

I d..

Construction Activities December 1984' ECN L6241 - Raise yard drainage pond skimmer 5 feet. EPA commitment mod-ification.

This modificat'on was completed on December 21, 1984 and complied with i

the EPA. commitment date-of December 31, 1984.

ECN L5503, 5111 - Office and Power Stores facility.

I The project is' approximately 94 percent complete. During thislaonth work continued on the top floor, EL.740. : Installation of heating and ventilating units,- carpet, glass windows, energ7 management systems,' duct insulation, painting, ceiling installation, doors and office partition etc.

Continued material delivery of glass windows, the arrival of the ceiling installation contractor and changes in the offices laycut caused a 2 week delay of the January 1st occupancy date. Work continues on the other floors.

i ECN L5609,' 5610 - Make-up Water Treatment Plant.

The project is approximately 70% complete. During this month work continued on the installation of piping, cable trays, protective coatings, and. yard piping.

Installation of pump foundations in the Turbine Building continued.

j Workplans for interfacing work in the Turbine Building have been approved.

The schedule for preoperational testing of the systems has been given to Construction to complete the systems required to facilitate pre-op so that the plant can be-operational by March 31, 1985.

Construction may start multi-shift work on this building.

ECN L5599 - Fifth Vital Battery

+

The project is approximately 85 percent complete. Construction is scheduled to be completed by January 21, 1985.

Discharge testing on the new batteries to.begin on January 21, 1985. Discharge test on existing-vital batteries to begin on January 28, 1985.

ECN L5841~- Hot Machine Shop The project is 99 percent complete. Health Physics laboratory deconning machines, electric shop, snubber shop, and hot machine shop were in use during the unit 2 cycle 2 outage. Work continued on communication and fire detection cable pulling and equipment installation. Monorail and. hoist over electro-polishing equipment in the decon room will be done later.

ECN L6182 - Cooling Tower Repair Custodis:Ecodyne.- The contractor finished ice damage related work on both cooling towers and left the site. They will come back later to complete the remaining two punchlist items (concrete louvers and nozzles).

+

08.00:30 01-03-85 ELECTRICAL MAINTENAM:E MENTM.Y REPGtT FOR DECEPEBER PAGE 1

'g DATE....

(I)WOENT.....

FAILL5tE DESCRIPTION......

CAUSE OF FAILIRE.........

CORRECTIVE ACTION........

Nt,NO..

12-03-84 0-CMt-311-0141 CONTROL ROOM CHILLER NOT KNOWN AT THIS TIE WENT TO CECK UNIT FOLN)

A293628 PACKAGE "B" WANT START IN SERVICE ( NO WORK PERFORtED) 12-03-94 M W-003-0142 STEAM GEERATOR BLOWOOWN POSGIBLY HAIG SUITCH IN CECNED OPERATION OF A294559 VALVE WILL leT ISOLATE lat0NG POSITION CIRCUIT PER DRAWING 45W646-6 HAD OPERATOR STRONE THROTTLE VALVE 2-FCV-1-151 SYSTEM I

WORKING PROPERLY AT THIS-TIE

'12-03-94 2-FCV-062-0084 SUSPECT LIMIT SWITCH BOLTS ON LIMIT SWITCH TIGHTEED BOLTS ON LIMIT A288974 PROBLEM VALVE W:U. SHOW BRACMET LOOSE ON SWITCH BRACKET FE LY OPEN BUT WILL NOT AUXILIARY SPRAY VALVE TO SHOW FLA.LY (1.0 SED ON RCS AUXILIARY SPRAY TO RCS i

! 12-04-84 0-HTCK-234-040 TEFFERTURE CONTROLLER BAD TEf9ERTUtE CONTROLLER REPLACE 0 TEMPERTURE A295922 4

WOLA.D NOT W(ftK ON C.V.C CONTROLLER 1

ELECTRICAL EAT TRACE

12-04-04 2-HTCK-234-041 APPERAGE ON CIRCUIT 411 DEFECT IN HEAT TRACE WIRE SPLICED EAT TRACE A232467 1

WILL NOT PEET ACCEPTANCE CMDCNED CLNtRENT NOW 2.3 i

CRITERIA AfFS

?

f12-04-84 0-HTCK-234 VERIFY PROPER OPERATION HD FAILURE PREVENTIVE WORK PERFORfED AS A247635 0F E AT TRACE CIRCUITS fMINTANCE REGLESTED DE F5t tat 0TE (N l-PRESSURE FIRE Pt#FS ASSOCIATED WITH TE HIGH CIRCUIT #176 j 12-04-94 (H Ht-311-0141 INSPECT RELAYS Ale NO FAILURE PREVENTIVE REMOVED COVER APS) CLEAED A284834 i

CONTACTORS FOR BURED OR 11AINTANCE fMIN CONTACTORS.

i PITTED ColfTACTS AM) LOOSE INSPECTED ALL RELAYS i

COMECTIONS ON CONTROL BUILDING CHILLER (B) 12-04-84 1-CMt-311-0156 INSPECT RELAYS AM)

NO FAILURE PREVENTIVE INSPECTED RELAYS AM)

A284838 CONTACTORS FOR BURED OR 11AINTANCE CONTROLS AS REGUESTED PITTED CONTACTS AM) LOOSE C(NECTI(MS (M ELECTRIC BOARD ROOM CHILLER (A)

08:00:30 01-03-85 ELECTRICAL MAINTENANCE FD m LY REPORT FOR DECEFBER PAGE 2.

• C DATE....

(IlrF0ENT.....

FAILlRE DESCRIPTION......

CAUSE OF FAILlRE.........

CORRECTIVE ACTION........

79t.NO..

t i 12-04-84 2-IGN-268-0248 IGNITER 248 FAILED SI IGNITER BREAKER TRIPPED REPLACED IGNITER NO 248 A297874 305.2 BREANER 138 PER MI 4.20 j

A m M8AI 12 RAN SI 305.2

~

DN IGNITER 24 PLLLING -

J 8.0 AMPS 12-04-84 2-IGN-268-0238 IGNITER 238 FAILED SI IGNITER BPEANER TRIPPED REPLACED IGNITER 238 A297875 305.2 BREAKER 15 8 PER flI 6.20 M Pf8AI 12. RAN SI 305.2 ON IGNITER 238 PlLLING 8.1 Af1PS 12-04-84 2-IGN-268-0200 IGNITER 208 FAILED SI IGNITER BREANER 1 RIPPED REPOLACED IGNITER 208 PER A297870 305.2 ON BREAMER 13 A MI 6.20 AND f18AI 12. RAN SI 305.2 PULLING 8.9 Af9S

12-04-84 2-IGN-268-0207 IGNITER ON B9EANER 13 A BREAKER 13 A TRIPPED CHECKE0 BREAMER 13 A A284453 FAILED SI 305.2 FOUM IGNITER 207 TO BE GOOD AND IGNITER 208 UAS BAD j 12-04-84 1-Crp-313-0458 LARGE AMOLMT OF BUBBLES NO FAILURE CECKED OPERATION OF A296459 i

IN SIGNT CLASS ftAY BE LOW UNIT, OPERATING PROPERLY, ON FREON ADJUSTED PRESSURE CONTRG.

OPERATOR i 12-05-84 2-FCV-003-0090 CECM ELECTRIC WIRING TO NO FAILURE PREVENTIVE CECNED ELECTRIC A233899 SOLOMOID ON FEED WATER F1AINTANCE WIRING-WORKIONG REGlLATOR VALVE PROPERLY-NO WIRES LIFTED.

TIGHTEED CHASF NIPPLE GOING TO "C" CONDUIT 12-05-64 2-FCV-003-0048 CECK ELECTRIC WIRING TO No FAILURE PREVENTIVE CHECKED ELECTRIC A233900 SOLONDID ON FEEDWATER F1AINTANCE WIRING-WORKING

Q REGlLATOR VALVE PROPERLY-MO WIRES LIFTED.

TIGNTEED CNASE HIPPLE GOING TO "C" CONDUIT 12-13-84 1-CMt-313-0433 INSPECT RELAYS M NO FAILURE PREVENTIVE INSPECTED RELAYS M A287744 CONTACTORS FOR BURED OR ftAINTANCE CONTACTORS AS REGLESTED PITTED CONTACTS M LOOSE -

08:00:30 01-03-85 ELECTRICAL MINTENMCE IDmLY REPORT FOR DECEISER PAGE 3 DATE....

GRP00ENT.....

FAILURE DESCRIPTION......

CAUSE OF FAILlRE.........

CORRECTIVE ACTION........

19t.ND..

COBECTIONS ON 490 VOLT

. BOARD ROOM CHILLER 1-A 12-13-84 2-CMt-313-0458 INSPECT RELAYS AM)

NO FAILURE PREVENTIVE INSPECTED RELAYS Ale A287745 CONTACTORS FOR BtAtED OR 11AINTANCE CONTACTORS AS REelESTED PITTED CONTACTS Ale LOOSE COMECTIONS DN 490 VOLT BOARD ROOM CHILLER 2A 12-13-84 2-CMt-313-0503 ' INSPECT RELAYS Ale NO FAILURE PREVENTIVE INSPECTED RELAYS Ale A287747

-8

. CONTACTORS FOR BLRIED OR 11AINTANCE CONTACTORS AS REGUESTED PITTED Ale LOOSE COMECTIONS (M #0 VOLT BOARD ROOM CHILLER 2B 12-13-84 1-CMt-313-0453 INSPECT RELAYS AM)

NO FAILURE PREVENTIVE INSPECTED RELAYS AM)

A287746

-8 CONTACTORS FOR BLRED OR 11AINTANCE CONTACTORS AS REGE STED 4Q PITTED AM) LOOSE l

COMECTIONS (Di 40 VOLT j

BOARD ROOM CHILLEP 1B 12-13-64 2-CMt-311-0171 INSPECT RELAYS AM)

N0' FAILURE PREVENTIVE INSPECTED RELAYS Ale A284839 CONTACTORS FOR BURIED OR 11AINTANCE CONTACTORS AS REGUESTED PITTED CONTACTS AM) LOOSE CONECTIONS ON ELECTRIC BOARD ROOM CHILLER "B" 12-13-84 1-ZS-030-0056 STATUS LIGHTS ON VALVE DIVIDER MISS ALIEGIED REPLACED DIVIDER BETWEEN A288667 1-ZS-030-0056 SHOWING ALLOWING LIGHT TO SHOW IN RED AND GREEN WINDOWS IN BOTH RED AM) GREEN IN BOTH WINDOWS PROPER POSITION STILL j

CLOSED POSITION.

WOLA.D NOT PREVENT LIGHT FROM SHOWING TMt0 UGH BOTH WIIGOWS. REPLACED FIXTUIE 12-13-84 2-LOCL-013-063 REl10VE FIRE DETECTORS NO FAILURE INSTALLED JUMPERS IN A287520 1

CABLE Ale CGWUIT ABOVE FIRE DETECTOR PAIELS TO 4

R.C.P MOTOR #3 INSTALL PREVENT EERGIZING FIRE JtN9ERS IN TIE FIRE WYSTEM. REl10VED Ale DETECTION PAIELS TO RE-INSTALLED CONDUCTS i

PREVENT EERGIZING TE OVER RCP #3 INVOLVING H

J FIRE SYSTEM 9011AINTANCE FIRE PROTECTION. WIRES WORK CAN BE PERFORED ON REl10VED-AM) RE-INSTALLED m

A}Q

. 08

00:30 01-03-85 ELECTRICAL MINTENANCE M(DmLY REPORT FOR DECEFBER PAGE 4 DATE....

(DF0ENT.....

FAILURE DESCRIPTION......

CAUSE OF FAILtRE.........

CORRECTIVE ACTIDN........

FR.MO..

F RCP MOTOR #3 PER NI 6.20 12-13-84 0-HTCK-234-028 CIRCUIT 28P LIGifT WILL CtRRENT RELAY OUT OF ADJUSTED CURRENT RELAY A285864 P

NOT CLEAR ADJJSTENT CDI CVC ELECTRIC E AT TRACE CIRCUIT 28P 12-13-84 2-FCV-001-0025 BOTH LIMITS ARE LIT WITH ROLLER WORN OFF ARM ON REPLACED ARM ON CLOSED A288819 VALVE IN BOTH OPEN AIO r1 rwarn LIMIT SWITCH OF LIMIT SWITCH CLOSE POSITION STEAM GEERATOR BLOlE0W LOOP N3 OUTSIDE ISOLATION 12-14-84 2-FCV-062-0070 LOOP N3RCS LET DOWN VALVE LIMIT SWITCH OUT OF ADJUSTED. LIMIT SWITCH A297441 WILL NOT OPEN ADJUSTENT NOUNTING BRACKET 12-14-84 0-CtR-031-0008 CHILLER PACKAGE B-B IS LOW ON FREON ADJUSTED HEAD PRESSURE, A296675 NOT COOLING MIN CONTROL SIGHT GLASSES CLEAR ROOM 12-14-84 2-FCV-026-0240 WILE PERFORMING SI 166.6 VALVE IS CAUSING TORGE OPERATED VALVE SEVERAL A289259 DN 2-FCV-26-240 TE GREEN SWITCH TO T(ReUE OPEN TIMES BY HALO WORKING LIGHT EVER GOES OUT CAUSING GREEN LIGHT TO PROPERLY AT THIS TIE STAY ON 12-14-84 2-FCV-001-0022 BLUE LIGHT WILL NOT CLEAR LIMITS ARE SLOW FROM EAT CECKED ALL CIRCUITRY A297445 LA1EN VALVE IS FLLL OPEN AlO MOISTLRE, VALVE WAS INCLUDING DIODES Ale ON UNIT 2 LOOP 3 MIN STROKED TOO FAST TO ALLOW RELAYS ALL WIRING AND i

STEAM ISOLATION VALVE PROPER LIGHTS TO RESP 0lO CIRCUITRY WERE RIGHT Ale ON UNITY 2 LOOP 3 MAIN IN C000 WORKING ORDER i

STEAM ISOLATION VALVE IN OPERATIONS STROKED VALVE EAST VALVE ROOM 12-3-84 ALLOWING e

SUFFICIENT TIE FOR LIMIT OPERATION, EVERY THING OK 12-14-84 M CTD-003-003 RELAY CHATTERING ON CLOSE CONTACTORS DIRTY AIO CLEANED IRON LANIMATION A296232 3

CDIL TO 2-FCV-3-33 STICKING OF CONTACTOR CECKED AlO WORKING PROPERLY AT THIS TIE 12-14-84 0-HTCK-234-304 CVC ELECTRIC EAT TRACE CURRENT TRANSFORER (J)DED ONE TURN OF WIRE 04 A285845 P

CIRCUYIT WANT CLEAR CIRCUIT NOT PULLING TE CURRENT TRANSFORMER.

08:00:30 01-03-85 ELECTRICAL F1AINTENANCE FOmLY REPORT FOR DECEF9ER PAGE 5

,~',

DATE....

(EPP0 LENT.....

FAILURE DESCRIPTION......

CAUSE OF FAILURE.........

CORRECTIVE ACTION........

FIR. NO..

ENDUGH AtFS CIRCUIT IS PLLLING.5 7

12-14-84 2-ZS-062-0115 SIS ACCUMLATOR TA>5( li1 LIMIT SWITCH OUT OF TIGHTEN A0 JUSTING ROOS A286117 FILL VALVE NOT TO CLEAR ADJJSTFENT AlO READJUSTED LIMIT SWITCH 12-14-84 2-MTR B-077-000 REACTOR COOLANT DRAIN f10 TOR BAD REPLACED t10 TOR A294409 2-8 TAM ( Purp 28 WILL NOT RUN 12-14-84 0-MTR B-026-011 PERFORM 1000 VOLT PEGGER NO FAILURE PERFORrED MEGGER TEST PER A006359 A

TEST ON FIRE Pl#9 20-8 MI 10.20-LOCATED 480 VOLT SNUTDOWN BOARD 28-8 C0FFT. 3C c

~

! 12-1N14 1-BATB-250 GROUM) ON UPPER DEAD GR0lH)

LOCATED GROUND PER MI A288898 I

C0tFARTFENT ISOLATION 10.13 (SUBMITTED 2 MRS (N VALVE 2-FSV-30-52 AM) 12-10-84 TO CLEAR UP j

2-FSV-30-10 (SHOWS 130 GROUlO VOLT GROLN) ON 125 VITAL BATTERY BOARD III 12-17-84 2-FIV0P-070-013 PERFORM ROUTIE t1AINTANCE NO FAILURE PREVENTIVE WORK PERFORPED PER A298362 i

4-8 DN LIl1ITOROLE OPERATOR FIAINTANCE ROUTIE 11AINTANCE PRECEDlRE ATTACHED SIGN OFF SNEET I

12-17-84 2-ZS-090-0107-REPLACE TOP COVER GASNET NO FAILURE PREVENTIVE REPLACED TOP COVER CASKET A287630 1

ON NArlCO SERIEC EA180 f1AINTANCE AS REQUESTED LIl1IT SWITCH (TDP COVER GASNET REPLACE!ENT MIT IS A NAMCO EA18110102 TIIC 0188T5268) 12-17-84 2-ZS-090-0117-REPLACE TOP GASNET COVER NO FAILURE PREVENTIVE REPLACED TOP COVER GASKET A287653 1

DN NAMCO SERIES EA180 11AINTANCE AS REGUESTED-lit 1IT SWITCH (TW COVER GASKET REPLACEPENT MIT IS A NAMCO EA18110102) 12-17-84 2-ZS-090-0111-RCPLACE TOP COVER GASNET NO FAILURE PREVENTIVE REPLACE 0 TOP COVER GASNET A287639 1

DN HAl1CO SERIES EA180 MAINTANCE AS REQUESTED M

-21'

l 08:00:30 01.-03-85 ELECTRICAL MAINTENANCE PDmLY REPORT FOR DEEFEDER PAGE 6 DATE....

(Ilrp0 ENT.....

FAILURE DESCRIPTION......

CAUSE OF FAILlRE.........

CORRECTIVE ACTION........

f9t.ND..'

LIMIT SWITCH (TtF COVER f.

i l

GASNET REPLACEE NT MIT IS l

A NAMCO EA18110102)

)

12-17-84 1-ffTR B-077-000 TERMDAL OVERLOAD NEEPS OVERLOADS BAD REPLACED OVERLOADS A288727 6

TRIPPING OUT ON REACTOR j

COOLANT DRAIN TAM ( Plfp 1B 12-19-84 2-PCV-068-0340 LIMIT SWITCH.WAS GIVING LIMIT SWITCH ARM OUT OF ADJUSTED LIMIT SUITCH ARM A296608 RED AM) GREEN LIGHT ADJUSTFENT TO OBTAIN PROPER Il@ICATION l4EM VALVE WAS OPERATION CLOSED 12-19-84 2-FSU-061-0122 YALVE WILL STRONE TO OPEN LIMIT SWITCH LEFT LODSE TIGHTEEN LIMIT SUITCH A296248 POSITION ID ALLOW FLOW FROM FIELD SERVICES WORK AM) TIRED FOR OPERATION BUT CLOSED LIMIT SWITCH PLAN WILL NOT CLEAR 12-19-84 2-FCV-001-0011 BLLE LIGHT (10 PERECENT)

HD FAILURE FOLH) AT THIS CECKED OUT CorpLETE A297444 CLOSED IN CCHTRG. ROOM TITE CIRCUIT FOUle HD PROBLEM WILL NOT CLEAR l#EN VALVE APC FUNCTIONALLY CHECKED IS FILLY OPEN VALVE AM) LIGHTS ALL l

OPERATING PROPERLY 12-19-64 2-PCV-065-0007 GREEN LIGHT WILL NOT CLOSED LIMIT SWITCH OUT ADJUSTED LIMIT SWITCH A302057 CLEAR IAEM UALVE IS OPEN OF ADJUSTFENT 12-19-64 2-RCV-068-0340 PRESSURE OPERATED RELIEF NO FAILURE PREVENTIVE REWIRED AS REQUESTED A040299

-A VALVE EEDS REWIRING f14INTANCE 12-19-84 24fTCK-234-012. RED LIGHT ON TERf10 STAT TEFFERTURE CONTROLLER BAD REPLACED TEFFERTLRE A296617 2-P NOT TO COPE ON latILE ON CVCS EAT TRACE CONTROLLER I

PERFORMING SI 16 12-19-84 1-GENB-082-001 IFERSION EATER WILL NOT OYER LOAD RELAYS BAD REPLACE 0 OVER, LOAD A296660 l

9-8 Core ON IN 1B-8 DIESEL RELAYS j

GEERATOR 12-19-94 2-GENB-082-000 DIESEL CDERATOR 2A-A ACTUATOR PLUG ON COVERNOR CLEAED ACTUATOR PLUG ON A289322 2-A TRIPS FR0ff REVERSE poler WAS DIRTY GOVERNOR AND CECNED FOR 32 RELAYS OPERATION -

08:00:30 01-03-85 ELECTRICAL 11AINTENANCE PEDmR.Y REPORT FOR DECErBER PAGE 7 DATE....

Gif90ENT.....

FAILlRE DESCRIPTION......

CAUSE OF FAILlRE.........

CORRECTIVE ACTION........

FR. ND..

P 12-19-84 2-FCV-090-0114 CONTAIlfENT ism.ATION LDfILE DOING WORK PLAN ADJUSTED LIMIT SWITCH FGt A296594 VALVE FOR 2-Rft-90-112 FIELD SERVICES KNOCNED PROPER OPERATION ON AIR WOLLD HOT UPEN LIMITS DUT (F ADJUSTfENT VALVE ON CONTAIPRENT ISCLATION VALVE 12-19-84 0-LOCL-013-060 FIRE DETECTOR IN PAINT BAD FIRE DETECTOR REPLACED FIRE DCTECTOR A121906 ag 1

STORAGE WAS NOT TIGHT

~

CAUSING 20ES 401 Ale 339 ON MOTRONICS PAEL 0-L-601 i' BE IN ALARM i 12-19-84 2-BATB-082-VE-GREEN LIGHT SOCNET ON IlGICATING LIGHT SOCNET REPLACED DIALCO A121936 l

B 2B-8 DIESEL GEERATOR BAD INDICATING LIGHT SOCNET I

BATTERIES IS BAD Ale SHOWING 130 VOLT GR0t#O i.

12-19-84 2-FCV-001-0029 CABLE 2V79684 WAS SHORT EAT IN WEST VALVE ROOM REPLACE 0 WIRE AND ColOUIT A29Wu TO GROUlO ON MAIN STEAM FLEX TO JUNCTION BOX 401 ISOLATION VALVE IN WEST VALVE ROOM OF LMIT 2 12-19-84 2-FSV-026-0223 INVESTIGATE CAUSE OF NO FAILURE SYSTEM CECKED OUT PER SI A244744 2-FSV-026-0223 0F LMIT 2 234.7 USING MI 6.20 TO R.B. CABLES WATER SPRAY LIFT TE WIRES SYSTEM CIRCUIT BEIts EIGERIZED WORKING PROPERLY AT THIS WITH Ole.Y ZOE 374 IN TIRE ALARM 12-19-84 0-CtR-311-0171 ELECTRIC BOARD ROOM NO FAILURE UNIT LT)ULD NOT START A302020 CHILLER "B" WILL NOT BECAUSE OF LOW SUCTION RESTART PRESSURE

12-19-84 1-ZS-030-0057 OPEN LIMIT SWITCH ON LIMIT SWITCH OUT OF ADJUSTED LIMIT SWITCH F0t A293589 j

CONTAI> TENT VENT DAFFER ADJUSTFENT PROPER LIGHTS HAD VALVE IS NDT TLRNING OFF OPERATIONS STROKE VALVE 1

T E GREEN LIGHT Ale RAN SI 166.6

) 12-19-84 0-Clet-031-00/2 FREON LOW IN 6.9MV SIUT LEAK IN EXPANSION VALUE REPAIRED LEAK AT A2T6693 D-A DOLM BOARD ROOM CHILLER A EXPANSION VALVE TIGHTEFED j

TE CHILLER WOLLD START FLARE FITTING AND 4

___ ~

08:00:30 01-03-85 ELECTRICAL FIAINTENANCE FD m LY REPORT FOR DECEf9ER PAGE 8-DATE....

(DrF0ENT.....

FAILlRE DESCRIPTION......

CAUSE OF FAILlRE.........

CORRECTIVE ACTION........

f9t.MO..

M RLM FOR 10 OR 15 PROPERLY. CHARGED UNIT-5 SEColeS TEN TRIP OFF WITH R-22 REFRIGERENT 12-20-84 2-ZS-077-0017 VALVE LIrlITS SHOW CORROSION INSIDE LIMIT LIFTED WIRES OFF LIMIT A296244-tnt 0TTLED lAEM VALVE SWITCH SWITCH CLEAED OUT LIMIT SHOULD BE CLOSED ON SWITCH CHECNED OPERATION REACTOR C0KANT DRAIN OF VALVE HAD OPERATIONS TANK TO GAS Alel.

STROKE VALVE Ale RLM SI ISOLATION IN LMIT 2 PIPE 164.6 CHASE 690 i

i-12-20-84 0-LOCL-013-060 LIGHT BLIl4(ING IN POWER POWER LITE BAD REPLACED. PLUG IN TYPE A288880 2

POSITION ON PAEL OF POWER LITE. NO PYROTRONICS 0-L-602 TERMINATIONS MADE 6

AUXILIARY BUILDING 12-20-84 0-RM-090-134/1 RAD FIONITOR NEEPS BAD F10 TOR REPLACED fl0 TOR PERFORPED A296685 41 TRIPPING BREANER AT 1-11 SI206 f

BREANER 7 BATTERY BOARD 7.

12-20-84 2-PEN-302-0036 CABLE CUT ON OlflBOARD

$10 FAILURE PREVENTIVE SPLICED OUT80ARO CABLE F A298785 8

SIDE OF PFETRATION THAT FIAINTANCE PEETRATION 36 CABLE

\\

SUPPLYS R.C.D.T ISOLATION R2V8914 PER MEAI 7 AND UALVE 2-FCV-77-415 DWG. 45A-860-36 59 records listed.

i i

4 3

i j ;

. +.

't

- ~ '

SUMMARY

OF WORT COMPLETED ELECTRICAL MODIFICATIONS SECTION DECEMBER 1984 DCR 1739 - VAACS Panel wiring continued during this period.

ECN 5194 - Iodine Monitors Work remaining consists of installation of door locks and new door frames.

Security wiring is in hold until another ECN is executed.

ECN 5198'- Technical Support Center Changes to the annunciator: system are in process.

ECN 5202 - Fifth Diesel Generator Cable pulls and splices are in process.

ECN 5712 - Evacuation Alarms Major cable pulls in the auxiliary building are in process.

ECN 6018 - Installation of Space Heaters, Auxiliary Feedwater Pump Motors Unit 1 conduit is being istalled.

ECN 6055 - Fourth Wide-Range Pressure Transmitter All nonautage work is complete.

Appendix R Work continues on the first five interactions. An implementation schedule has been developed.

1 b

i i

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

• e

'L Instrument Maintenance Monthly Report December 1984-Unit 1 1.

Pressurizer level channels L-68-320, -335, and -339 have been operating within the five percent channel deviation as required. All channels have been in service all month.

2.

During the monthly calibration of the UHI level switches'all switches were found within technical specification tolerance.

3.

We supported CDWE cleanup and replacement of the density element due to solidification.

4.

The P-250 process computer was declared inoperable twenty times during the month. The computer was restarted and returned to service without appreciable down time. The P-250 will be removed from service and cleaned during the next unit outage of sufficient duration.

5.

NCR SQN-NEB 8407 was issued on 12/6/84 to report possible mislocation of Class IE equipment. Radiation detectors RE-90-275 and -276 were specified in the instrument tabs as monitoring the reactor coolant drain tank discharge lines and RE-90-277 and -278 were specified as monitoring the reactor building sump discharge lines. Visual in-spection and testing on 11/20/84 revealed that the monitoring de-tectors were functionally reversed.

The problem was corrected by TACF 1-84-123-90 on 12/7/84. FCR 3110 was written to revise the drawings.

Unit 2 1.

During the monthly calibration of the UHI level switches all switches were found within technical specification tolerances.

2.

NCR SQN-NEB 8407 was issued on 12/6/84 to report possible mislocation of Class IE equipment. Radiation detectors RE-90-275;and -276 were specified in the. instrument tabs as monitoring the reactor coolant drain tank discharge lines and RE-90-277 and -278 were specified as monitoring the reactor building sump discharge lines. Visual in-spection and testing on 11/20/84 revealed that the monitoring de-tectors were functionally reversed. The problem was corrected by TACF 2-84-122-90 on 12/7/84. FCR 3110 was written to revise the drawings.

3.

During startup from the outage 6 RPI connectors failed. Causes were determined to be open wires in the connectors and water in the connectors. Seven rod control connectors also failed due to wiring problems at the connectors.

4.

Other work is sho a on the attached list. -_,

3 INSTRltENT MAINTENA6CE *10pmLY SLRflARY, 01-08-85 I

PAGE 1 C0w

+

r5t.C0r58 U FUNC SYS ADDRESS. DATE.... DESCRIPTION.'.................................... CORRECTIVE ACTION....................... ?

A230521 2 LT 068 339 12/18/84 2-LT-068-339,ItDICATOR 6% HIGH TRANSilITTER WAS DUT (F CALIB. RECALIB..

./

AFD BACNFILLED LEGS (N TRANSMITTER.

A233292 1 LT 068 320 12/03/841-LT-068-320,BACK FILL PZR LVL XMITTER LOST FILLED LEG. BACIFILLED LEG A234389 2 XX 302 1?/17/84 2-XX-302, MIN 3 OPEN PEFETRATI(NS(1 INCH)

RUN SI233' INSTALL CONOUIT PLUGS. tRJST BE COMPLETE WITHIN 7.

I DAYS A285794 2 1M 068 318 12/03/84 2-Tif-068-318 INSTALL NEW F1000LE INPLACE OF OLD F10DULE WAS FOUPD TO BE DEFECTIVE.110DULE i

OE. NEW F100ULE OUTPUT IS LIEAR A6C OUTPUT WAS REPLACED 1 THE SETPOINT WAS ADJUSTED WILL #40T FLUCTI! ATE WITH AC POER FLUCTUATIONS.

TO PROPER SETTING.

A286980 2 LIC 003 164 12/07/84 2-LIC-003-164,S/G #1 LEVEL CONTROLLER-CODBECTOR PLUL; ON SIGNAL CABLE IS BROKEN, POSSIBLY j

PLUG ON BACK OF CONTROLLER IS BROKEN DUE TO STRESS. REPLAED CO>tECTOR PLUG.

I AND VERIFIED PROPER (PERATION.

A288954 2 FI 063 173A 12/10/84 2-fI-063-173A,RF5t HOTLEG INECTION-LAEN FLA.L ALIGM1ENT PROBLEM ON ULV. LIElp.

FLOW TtstU 63-172-10 FLOW IS IPDICATED.

REALIGNED VLVS.

A288970 2 FCV 062 143 12/11/84 2-FCV-062-143, NIN WEN IN AUTO FCV-143 OPE >ED HO PROGRArt FOUbD. PRCPER OPERATION i

SEVERAL TIRES FOR HD APPARENT REASON.

VERIFIED.

l A289263 2 XI 085 5106A1 12/01/84 2-XI-085-5106A1, STEP COUNTER FAILING (D1 DOWN BAD STEP COUNTER. REPLACED STED COUNTER t

CattlAFD A289271 1 FCV 087 11 12/04/841-FCV-087-11, FLOW CONTROL VLV HAS AIR REGLA.ATINt BAD REGULATOR. REPLAED REGULATOR.

l LEAKING AIR ON BOTTOM OF REGULATOR

.3289279 2 PI 001 19C 12/07/84 2-PI-001-19C,uIn GUAGE IS READING APPROX. 400

. INDICATOR DUT OF CAL. TE IPDICATOR WAS PSI LAEN IT SHOLLD BE APPROX.10 PSI REPAIR.

REPAIRED AND RECAL.

MODE 3 ITEM

~

A289293 2 LIC 003 156 12/14/84 2-LIC-003-156,2 LCV 3156 A>D 2 LCV 3156A WILL SUPPLY AIR REGULATOR WAS OUT OF CALIB.

NOT OPEN-ADJUSTED SUPPLY AIR REGLA.ATOR TO 23PSIG Atc FUNCIONALLY TESTED.

A289392 2 092 5001 12/10/84 2--092-5001,N-31 HAS LOSS OF DETECTOR VOLTAGE THE HIGH VOLTAGE PX LMS DAt1 AGED.

REPAIR REPLACED TE PX AFD N) JUSTED TO PROPER SETTING A294777 2 PI 030 311 12/05/84 2-PI-030-311, WIN INDICATOR HAS OPEN Il@UT PRESS. INDICATOR AFD TFE DIODE ERE BAD.

y CIRCUIT THE DIODE AFD PRESS.16DICATOR WERE REPLACED AFD TE IFDICATOR WAS RECAL.

A294B14 2 PX,003 122C 12/03/84 2-PX-003-122C, REPAIR / REPLACE POLER SUPPLY t100LLE BRONEN-WIRE FR011 cop #ECTOR TO PX AS PECESSARY RECTIFIER CIRCUIT. REPAIRED WIRE A294866 2 )E 068 334 12/11/84 2-XE-068-334, REPLACE ACCELR0rETER PROBE NONE. ACCELEROFETERS WERE CHANGED TO HEW 2-XE-68-334 TYPE. REPLACED ACCELER0rETER A294995 2 PDT 065 80 12/07/84 2-PDT-065-80,CONTAINrENT A>HJLUS DP -

LEAKING TEST FITTING. REPLACED FITTING l

TRANSilITTER-PARMER TEST TEE ON HIGH LEG PEEDS REPLACNG l

A296199 2 LCV 003 156 12/15/84 2-4.CV-003-156,VLV LEAKING TF5tU VLV. SEAT BAD. TECH. REPAIRED ON ANOTHER rft Ale WE RESTROKED M.V.

I f

s

'INSTRUENT MAINTENANCE MONTM Y SLNIARY 01-08-85

?

PAGE 2 COW rgt.C0fp U RMC SYS A00REGS. ' DATE.... DESCRIPTION.'.................................... CORRECTIVE ACTI0N....................... * :

../?

f.296628 1 LI 077 410 12/11/841-LI-077-410, uIn CALIB., IM)ICATING LOER TRANSMITTER'0UT OF CA.IB. RECALIB TRANSMITTER.

7#

A296672 1 TI 068 398 12/11/841-TI-068-398,1-TI-68-398 IM)ICATING APPROX POSSIBLY LOOSE CONECTION. CECKED LOOP, R

160-1850EG F, IM)ICATOR DRIFTING.8 NO OTER NO PROBLEM FOUM) l PARAtETERS IM)ICATING LEAKAGE A296732 1 LCV 003 174 12/17/84 1-LCV-003-174,VLV UILL NOT STROKE IN F1AMJAL OR SOLENDID STUCK. TAPPED SOLENDID TO FREE J

AUTO LP.

A299002 2 FI 003 170A 12/15/84 2-FI-003-170A, LOOP M4 FLOW IM)ICATOR READS 10-15 YRANSf1ITTER WAS OUT F CALIB. RECALIB.

GPfl FLOW WEN Pt9S ARE NOT RUM 4ING TRANSilITTER I

A301066 2 FI 003 170A 12/21/84 2-FI-003-170A, INSTR. READS 15GPM WITH ALL VLVS TRANSMITTER WAS DUT F CALIB. CAUSING l

(LCV'S) r1 rwn AM) NO FLOW THE VLV. TO BE PARTIN.LY OPEN.

i l

TRANSrlITTER UAS RECALIB.

A301068 2 FI 003 147A 12/20/84 2-FI-003-147A, FLOW IM)ICATOR STICKS ON BOTTOM POINT BENT ON INDICATOR. STRAIGHTEED i

WILL NOT INDICATE FLOW UNTIL IT IS PECKED ON POINT AM) RECAL.

l t

A301083 2 FM 062 139A 12/21/84 2-Fil-062-139A, FLOW IM)ICATOR WILL NOT IM)ICATE THE F10DIFIER WAS rIUT UF CALIB. RECALI8.

FLOW WITH BORIC ACID VLV OPEN f10 DEFIER A302035 2 LCV 003 90A 12/07/84 2-LCV-003-90A, min VLV IS NOT SEATING OFF LOW LIMIT ON TE VLV. CONTROLLER WAS CG9LETELY 8 IS LEAKING THROUGH

,HIGH. ADJUSTED CONTRG.LER A302040 2 LI 068 321 12/11/84 2-LI-068-321, min (IILD CAL. INSTR. HAS A HIGER - TRANSf1ITTER DUT OF CA.IB. RECALIB.

READING THAN TE MIT CAL. PZR LVL IM)ICATION.

'. TRANSMITTER.

l A302055 2 PI 001 26C 12/06/84 2-PI-001-26C, PRESS. INDICATOR PEGGED OUT BOTTW1. _ BAD INDICATOR. REPLAED INDICATOR..

A302065 i LIC 003 156 12/15/84 1-LIC-003-156,VLV 156 IS OPERATING ERRATICALLY LIrtIT SWITCH WAS SET WRONG. TE

~ ELECTRIC ANS RESET TE SWITCH AM)

I OPERATION WAS VERIFIED.

A302169 2 PDIS 067 491/E/F 12/18/84 2-PDIS-067-491/E/F. FILTER 2A CONTINUOUSLY SWITCN OUT OF CAL. IIECAL. SWITCH BACKWASES-SUSPECT 2-PDIS-67-491 E/F flALFUNCTIONING A302177 2 PS 003 171 12/15/84 2-PS-003-171. WEN S/G PRESS IS LESS THAN 500 PRESS. SWITCH WAS OUT OF CALIB. RECALIB.

PSIG TE LCV WILL NOT Core OPEN PRESS. SWITCH A302182 2 LR 068 339 12/18/84 2-LR-068-339,PZR LVL SETPOINT IS TOO HI FOR RCS TElf. CONTROLLER WAS OUT OF CALIB.-

~

PRESS m

RECALI8. TE TEt9. CG4 TROLLER A302196 2 Pt9 003 142 12/17/84 2-Pf9-003-142,TURB TRIPS ON ELECT OVERSPEED SIGNAL CONVERTER BOX WAS OUT OF-ADJJSTFENT. READJUSTED SIGNAL CONVERTER 8100lE.E AM) VERIFIED PROPER OPERATION.

/

32 records listed.

.77 A -

't.

4-Mechanical Naintenance Section December 1984 A

Unit 1 i

1.

Leaks from valves.1-VLV-3-891 and -829 were stopped by Furmanite.

Unit 2 1.

Primary check valves 2-63-641 and -644 failed to seat during SI-166.10.

The seats and flappers were blued and lapped. They'were retested on 12/14/84.

2.

2-LCV-62-118.was replaced.

3.

The main turbine was balanced on 12/27/84.

f 4.

The inboard mechanical seal was replaced on 2B-b charging pump.

5.

The seats and trim were replaced in 2-LCV-3-148 and -164.

1 6,.

The missile shield was set, caulked and' smoked tested.

7.

The mechanical seal on 2B-B RHR pump was replaced.

8.

The RCP's were balanced.

9.

The 2B-B Auxiliary Feedwater Pump burned out a bearing and it was re-placed. Due to excessive clearance between the balancing drum and the balancing sleeve, the new bearing ran hot and required replace-ment.

In addition, the clearance was corrected.

Common I

1.

The diesel generators were inspected per SI-106.

2.

Crystallization was cleared from the CDWE heate 'and work continued clearing the 16-inch line.

i.

D

,I.

't Mechanical Modification Section December 1984 ECN 2768 - REVLIS PMTs were completed with no problems. Work documentation was completed.

Work began on the preparation of work for the " improvements" for unit 1.

This includes modifying the seal table tie-in and the unit I vessel head attachment.

ECN 5773, 6196, 5856 Pressurizer Work Due to leakage during start-up the loop-seal drain valves were closed. An additional hanger was modified.

ECN 2780 5200 - PASF PMTs were completed. Painting is underway. Workplans were prepared for several discrepancies for unit 1.

ECN 5842 - Cavitating Venturi PHTs were completed. Some additional hanger work is anticipated.

ECN 5938 - FW Heater Replacement Work was started on the relocation of ductwork, building structural mod-ifications, the piping modifications, and the modification of the Hartsville Heater Nozzles.

ECN 6362 Additional supports for the ERCV to the diesel generators were installed.

ECN 6302 Additicnal support was provided to Auxiliary Building block wall to qualify the wall for a siesmic event.

ECN 6289 Work was started to replace the concrete blow-out panels for the valve rooms. Two plugs were poured but not installed. Approximately 14 panels are to be replaced.

" Appendix R" - Initial walkdowns of the sprinkler location was completed.

Schedules were developed for implementation.

EN DES in working on the preparation of ECNs and purchasing materials. Field work is scheduled to begin on these items April 1, 1985. Additional walkdowns are scheduled to start on January 7, 1985.

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1.}F 3.f-TENNESSEE. VALLEY AUTHORITY t-.

Sequoyah Nuclear Plant'

. P..O. Box 2000 Soddy-Daisy,: Tennessee '37379 XI 41985l Nuclear-Regulatory' Commission-

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

SEQUOYAH NUCLEAR PLANT - MONTHLY. OPERATING' REPORT - December 1984

-Enclosed is the' December 1984 Monthly Operating Report to the_NRC for Sequoyah Nuclear Plant.

Very truly yours,.

TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Manager 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 30323 (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)

Mr. A. Rubio, Director Electric-Pouer Research Institute P. O. Box 10412 Palo. Alto, CA 94304 (11 copy)-

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

Y y_

l 1-1 An Eq'ual Opportunity Employer s

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