ML20100L190

Monthly Operating Repts for Oct 1984

ML20100L190
Person / Time
Site:	Sequoyah
Issue date:	10/31/1984
From:	Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
References
NUDOCS 8412110492
Download: ML20100L190 (42)

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION OCTOBER 1, 1984 - OCTOBER 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 8412110492 841031 PDR ADOCK 05000327 A R pyg ..

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TABLE OF CONTENTS i.

i Operations Sn= mary . . . . . . . . . . . . . . . ... .. . ... . 1 i .

l . Significant Operational Events . . . . . .. . ... .- . . . .. .. 1-2 PORVs and Safety Valves Summary. . . . . . . . . . . . . . . . . . 2'

. Reports l'

Licensee Events . . . . . . . . . ... . . . . . .-. ... . 2-14 I

Diesel Generator Failure Reports. ... . .. . . . . . .. . 14 Special Reports . . . . . . . . .. .. . . . . . . ... . . 14-15 t

l Offsite Dose Calculation Manual-Changes. .. . .. . . . ... . . 15

-Operating Data-t Unit 1 . . .. . . ... . . . . . .. .. . .. . . .. . . 16-18 l

e Unit 2 .. . . ... . . . . . . . . . . . ... . .. .. . . 19-21

' Plant Maintenance Summary. .... . . . . . . ... . . .... . 22-39 i

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45 Operations Summary s <

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' October 1984

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.The following summary. describes-the significant operational'activitiesL

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< for the month'of October. 'In support of this. summary, a-chronological: -

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

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Unit 1 Uniti1;was critica1'for 745.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, produced 843,080 MWH (gross), resulting'

in an average hourly gross load of 1,131,651 kW during the month. There'are

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.231.6 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 31, 1985. The capacity factor for the' month was'95.7 percent.

, IThere were no reactor scrams or manual shutdowns, and one power reduction

during-the month.

Unit 2 The. unit 2 cycle 2 refueling / modification outage continues. The estimated

. return-to-service date is November 30, 1984.

Significant Operational Events Unit 1 Date Time Event 10/01/84 0001' The reactor was in mode 1 at 69% power and increasing.- The unit load was 795 MWe.

10/17/84 0540 Condensate booster pump 1B tripped-due to' low oil level. The RO performed a-

- , manual runback to 60% reactor power. ,

0545 Began power ascension.

10/18/84 0300 The reactor obtained 100% power.

10/31/84 2359 The reactor was in mode 1 at:100%,

producing 1140 MWe.

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t Significant Operational Events i Unit 2 Date Time Event i

10/01/84 0001 Cycle 2 refueling / modification 10/31/84 2359 outage continues.

PORVs and Safety Valves Summary No PORVs or safety valves were challenged during the month.

Licensee Events and Special Reports The following licensee event reports (LERs) were sent during October 19?4 to the Nuclear Regulatory Commission.

LER DESCRIPTION OF EVENT 1-84053 With unit 1 at 100 percent power and unit 2 in mode 3 (hot standby), both trains of the auxiliary building gas treatment system were declared inoperable due to an uncontrolled breach of the ABSCE boundary. During a routine safety inspection of the auxiliary building and west valve room for unit 1, the inner door was noted to have been breached, using the proper administrative controls; however, the outer door was inadvert-ently left ajar allowing a breach of the ABSCE boundary. This configuration would have prevented the ABGTS from maintaining a minus k-inch water gauge pressure with a vacuum relief flow of greater than 2000 CFM as required per technical specificatica

3. 7.8, surveillance 4. 7.8.d. 3.

1-84057 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. Power and local control cables for 1A,1B, 2 A, and 2B RilR pump room coolers interact such that all four (4) could be lost in a single fire. Cables involved are:

1PP3031A,1PP3033A,1PP3041B,1PP3043B, 2PP3031A, 2PP3033A, 2PP3041B, and 2PP3043B.

2. The A-A and B-B main control room air handling units and compressors have cables which interact such that a fire could take out both "A" and "B" trains. Cables involved are:

1PL4500A, 1PL4501 A, IPL4520A , 1PL4527A, 1PL4510B , 10L 4511B ,

1PL4512B , 1PL4540B , 1PL4547B , 1PL4512B , 1PL4501A, 1PL450 2A, IPL4520A, and IPL4527A.

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Licensee Events .and ' Special' Reports (continued)

- LER ~ DESCRIPTION OF EVENT 1-84057 3. . Cables which supply allifour RCS;1oop temperature (continued) J indications interact at one location on elevation 714' in the auxiliary building. ~ Cables involved are:

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1PV330K and'1PV320J.

4. Interactions exist between "B" train 6900 volt shutdown boards and' cables for various "A" train. valves. Valves and cables involved are:

2V1963A (2-FCV-3-136B), 2V1953A (2-FCV-3-136A),

2V2953A (2-FCV-3-1168), 2V2952A (2-FCV-3-116B),

• 2V2931A (2-FCV-116A), 2V2200A (2-FCV-67-125),

2V2201A (2-FCV-67-125), 2V2203A (2-FCV-3-125),

i 2V2211A (2-FCV-67-126), 2V2422A (2-FCV-67-146),

2V2423A (2-FCV-67-146),-2V2425A (2-FCV-67-146),

2V2968A (2-FCV-67-223), 2V2969A (2-FCV-67-223),

2V1983A (2-FCV-67-81), and IV2425A (1-FCV-67-146)' .

5. Interactions exist between "A" train 480 volt. shutdown boards and cables for various "B" train valves and "B" train ERCW pump cables.- Cables involved are:

2V2941B (2-FCV-3-126A), 2V2961B (2-FCV-3-126B),

2V2083B (2-FCV-3-179A), 2V2131B (2-FCV-3-1798),

2V2807B (0-FCV-67-152), 2V2791B (0-FCV-67-152),

2V2794B.(0-FCV-67-152), 2V2160B (2-FCV-67-123),

2V2792B (0-FCV-67-152), 2V2173B (2-FCV-67-124),

2V2160B (2-FCV-67-123), 2V2431B (2-FCV-67-147),

2V2170B (2-FCV-67-124) -2V2161B (2-FCV-67-123),

2V2429B'(2-FCV-67-147), 2V2003B (2-FCV-67-82),

2PP704B, 2PP706B (ERCW Pump:M-B), 2PP716B, 2PP718B (ERCW Pump P-B), 1PP704B, 1PP706B (ERCW Pump L-B), IPP716B, 1PP718B (ERCW' Pump N-B).

6. Interactions exist between "B" train 480 shutdown boards and cables for various "A" train valves and~"A" train components.- The cables and components are listed below.

IV2951A (1-FCV-3-1168), IV1953A (1-FCV-3-136A),

IV1960A (1-FCV-3-136B), IV1983A (1-FCV-67-81),

IV2200A (1-FCV-67-125), IV2211A (1-FCV-67-126),

IV2423A (1-FCV-67-146), IV2431A (1-FCV-67-147),

1V2971A (1-FCV-67-223), IV641A (1-FCV-67-424),

2V2971A (2-FCV-67-223), 2PLW227A (2-FCV-67-492),

IV2792A (0-FCV-67-151), 1PP679A (ERCW Pump J-A),

IV681A (ERCW Pump K-A), IV691A (ERCW Pump R-A),

IV691A (ERCW Pump Q-A), IPLW203A (A, ERCW Traveling Water Screen), 2PLW211A (D, ERCW Traveling Water Screen).

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/ t1 L'icensee-Events and Special Reports (Continued)

'LER DESCRIPTION OF EVENT-

,, 1-84057 . 7..' Interactions exist between train "A" 6900 volt shutdown -i y- '

(continued) boards"and train "B" cables for valves and components. .

• Involved cables are:

1V2941B (1-FCV-3-126A),'1V2961B (1-FCV-321268)', ,

IV2081B (1-FCV-3-179A),-IV2130B'(1-FCV-3-1798),- ,

1V2003B'(1-FCV-67-82),E1V2163B (1-FCV-67-123),

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! 1V2173B (1-FCV-67-124), 2V2428B (2-FCV-67-147),

I 2PLW233B (2-FCV-67-489), IV3350B.(1-FCV-67-478),

-1PLW223B (1-FCV-67-489), 1PLW190B (ERCW Screen Wash; Pump B), 2PLW180B (ERCW Screen Wash Pump C), 1PLW211B (ERCW Traveling Screen B), 2PLW203B (ERCW Traveling Screen C).

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8. . Unit;1 - In.the auxiliary building on elevation'714 at A6Q and in the auxiliary control room on elevation 734lat RA6, the control cables for containment _ isolation valves, l for normal letdown path, interact and fail'to meet the 20-foot separation criteria required by Appendix R.

Cables involved are:

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IV4423A, IV4435A, IV4473A, IV4488A, and IV4503A.

9. Unit 1 - A fire at location A3 to AS/R to T'on elevation 690 in auxiliary. building could take out'the following-cables due to interactions with less than 20-foot separation.

(1) Train At Handswitch for 1A-A AFW pump'(cable 1PP652A) -i and 6s00 volt to 1A-A AFW pump (cable 1PP650A).

(2)- Train B: Handswitch for 1B-B AFW pump (cable 1PP6648) and 6900 volt to 18-B AFW pump and IB-B AFW pump.

and motor.

(3) Steam-driven AFW pump cables:

1SC461 and 1SC481 (LCV status light), 1PV105A i (vital AC supply to' l-L-381), ISG240A (vital AC to 669 transfer switch, normal). 1M811A (1-PS-3-138A), r 1M1450A, IM1452A (steam supply transfer), IV2623A, IV264A (1-FCV-1-17), 1PV185B (vital AC to 1-L-381),.

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and 1SG221B, ISG241B (alternate transfer' switch).

10. Unit 1 and unit 2 - A fire at A12-A13/r line wall could involve the following "A" train components and "B" train reactor MOV board. Train "A" cables ares-IV2425A (1-FCV-67-146), 2V1955A (2-FCV-3-136A),

2V1965A (2-FCV-3-1368), 2V1985A'(2-FCV-67-81),

2V2200A, 2V2201A, 2V2203A (2-FCV-67-125), 2V2211A (2-FCV-67-126), 2V2422A, 2V2423A, 2V2425A (2-FCV-67-146), ,

2V2931A (2-FCV-3-116A), 2V2951A, 2V2953A (2-FCV-3-116B), s 2V2968A, 2V2969A (2-FCV-67-223).

Train "B" eables are reactor MOV board 2B2-8 and associated l cable trays.

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( Licensee Events and Special Reports (Continued)

LER DESCRIPTION OF EVENT l-84057 11. Unit 1 - A fire at location A3 to A10/Q to U on elevation (continued) 714 in the auxiliary building could involve cables for both motor-driven and turbine-driven auxiliary feedwater pumps along with their-associated level control valves.

(Listed below are the TDAFWP cables involved.)

1V3250A, 1V3251A, IV3253A (1-FCV-1-15), 1M1452A, IV3240A, IV3243A, IV3241A, 1M1450A, IM1451A (1-FCV-1-16), IV2624A, 1V2620A, IV2621A, IV2623A (1-FCV-1-17), IV2633B, IV2634B, IV2635B (1-FCV-1-18), ISG480, ISG481, ISG461, ISG250S, ISG251S, ISG252S, ISG229S (control cables, TDAFWP).

The action statement for technical specification 3.7.12 was satisfied by utilizing firewatches in the affected areas that were established by other Appendix R commitments. 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.

Corrective Actions An implementation schedule for corrective actions will be submitted to the NRC by January 1, 1985. The fire watches established will remain in effect until full compliance with the requirements of Appendix R can be achieved.

1-84058 A high radiation alarm was actuated at 0109 CST on September 17, 1984, while unit I was in mode 1, which caused a containment ventilation isolation (CV1) to occur. Investi-gation revealed that due to a leak in the manway cover on steam generator number one, steam entered the containment atmosphere and the resulting increase in moisture saturated the particulate filter and caused the iodine sample flow alarm to actuate. The contacts on the flow switch were very noisy and generated electromagnetic interference (EMI) which caused the high radiation alarm to actuate. There was no actual high radiation level in containment and no personnel were contaminated.

( Licensee Events and Special Reports (Continued)

LER DESCRIPTION OF EVENT 1-84059 Inspections at Sequoyah Nuclear Plant have identified the following 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. Units 1 and 2 - Certain areas of the plant requiring operator action for the safe shutdown of the plant were surveyed using Abnormal Operating Instruction (AOI) 27, Control Room Inaccessibility. Areas requiring lights for operation of equipment specified by the shutdown logic are currently being evaluated. Also, the battery packs at Sequoyah are not rated for eight (8) hours.

2. The reactor coolant pump oil collection system does not fully comply with the requirements of 10 CFR 50, Appendix R, i.e., seismic design and capacity.

Each reactor coolant pump (RCP) holds 240 gallons of oil in the upper bearing system and 26 gallons in the lower bearing system. The RCP oil piping is seismically qualified (the piping installed on the pump), and the drain piping is Class 1 (L). Should one of the pump's oil systems fail, approximately 240 gallons of oil will be collected by the

" pocket sump" and associated drain piping. The piping holds 140 gallons and the " pocket sump" holds 200 gallons. In the event that the " pocket sump" is full of water, the excess oil will overflow to the containment floor.

3. Inadequate separation (less than 20 feet) exists between the following valves:

a. Location - 480V transformer room 2B, valve 2-FCV-67-81

("A" train) interacts with same system "B" train equipment.

b. Location - 480V transformer room 1A, valve 1-FCV-67-82

("B" train) interacts with same system "A" train equipment,

c. Location - 480V transformer room 2A, valve 2-FCV-67-82

("B" train) interacts with same system "A" train equipment.

d. Location - 480V shutdown board room, valve 2-FCV-67-489

("B" train) interacts with same system "A" train equipment.

e. Location - Auxiliary control room, valve 1-FCV-67-147

("A" train) interacts with same system "B" train equipment.

f. Essential raw cooling water (ERCW) pumps J-A, Q-A, K-A, R-A, and units 1 and 2 valve FCV-67-492 intecnct with 1, 2-FCV-67-489 ("B" train).

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ILER- 'DESCRIJZION OF/ EVENT' Y i  ; ,,(

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1-84059- "T. iLocation v Unit l'P4metration room,' valve- 1-FCV-67 g -(continued), . .r',("A" trpiti) interacts wi!)h'{-FCV-67-82 ("B" train).

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'. tya' Q r- ~ Jir. / Locationt Unit 2 pcpatration room, valve 2-FCV-67-81 :

3 ("(" train)

. interact'sI'hi*hDFCV-67-82 ("B" train).

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! i,~ vitae $ M CV-67 M d"A" train) interacts with-1NCV-67-82

!- ("h" Arain)'tiodcolumn line A1. through A6= and wall 11ne

. .Q through,J g41eYation 690. w,, ..

s . . v vf s L .J. Valve 2-FCV-67-%1 ("A" trti r- , - - '1, 2-FCV-67-82 1"B". train)jn) ~nown interacts column with line All through u., A15 and wall.lipp Q through U, elevation'690..

'.k. Valves 1, 2-FCV-67-81 ("A" train) interact with

• 17 2-FCV-67-82 ("B" train), s elevation'669.

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4. Less than 20-feet of sepatation exists, causing RHR pump 1A-A

-(cables 1PP575A 1PP577A, IPP578A, and IPP580A) to interact

,witt; RHR pump 18-B pump, room cooler fan (cables 1PL4098B/

-lPL3043h 1PL4097B/IPi.3041B)+on elevation' 714, column A3/R.~

t . %l S. Less than 20-feet of separation ex3 es J bdween the RHR pump cooler 2A-A (cab'le 2PL3033A) and the .2B-8 RHR pump,'(cables -

i 2PE587B,.2PP589B, 2PP5905, and 2PP592B). _A,1so, the 2A-A RkF' pump cooler (cable 2PL3033A) interacts with 2B-B 6900V shEdown board on, elevation 734,'evlumn A13/R. ,,

6. L$ss'thgn20-fettofseparationevists, causing'15-BRHR

' pump ro<m gooler (es)1e 1PL30428) to interact with,the IA-A RHR ptenp (cables IrJ575A, IPP577A, IPPQ78A, and 1PP580A) on elevation.734, column'A3/y.  ; w, ,

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I- 7. Lessa than 29-fmt of steparation, exists,+ 64using 2A-A RHR pump. rooia, ces111, (cables ?JL3032A and 2PL3033A)'to interact -

with 28-B'RHR pump.(cables 2PU 678, 2PP5895p 2PP5908, and-2PP592B) .,

on glevation 734, cotan s.

{ A12/Q.- ,.

-8. Less 17an 29-fuet of separatiori ellats, causi 24-A RHR pump rocia cooler'/ cables 2PL30'31Atand 2PL3033A) /o interact with25knjulF,pqjN(cables 2PP587B,2PP589B,2PP5908,and' 2PP5323)20if elevation 714, .wlumn A13/R.

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9. Cables and conduit that pro' vide level indication forgthe.

automatic level control valves (LCVs) on the potou, driven ugh.a potencial auxiliarV fire zorkon'feedwater' elevation 714, pumps< olnen '($DAWP)A6-A14/4- pass th(U (condult/ cab s

f MC1099/21'et1223K; C226/2 Pill 232% "2PM1241K, 2PM1251K). The level indication is re.wsired forAanual. level control.

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4 L'icensee: Events and'Special Reports (Continued)

LER. DESCRIPTION OF EVENT 1-84059 10. Less than 20-feet- of - separation exists,' causing a. common (continued) power cable -for channel I temperature loops -(2PV320J) to interact with a common power cable for channel II temperature loops (2PV330K) on elevation ,714, ' column A4-A8/Q-R.

11. ~Less than 20-feet of separation exists.between theitwo pressure loops P-68-69 and P-68-66. .The cables are 2PV320J and.2PV135II,'respectively, on elevation 714,'-

columa A4-A12/Q-R.

12. Less than 20-feet of separation exists between the two pressure loops P-68-69 and-P-68-66. -The cables are 2PM4801 and 2PM481, respectively, on elevation 714,.

column A12-A14/Q-X and elevation 690, column A12-A13/X.-

13. Cables for backup heater A-A pass on one side of a' metal hatch and cables for backup heater B-B are on the other side of the metal hatch.- The cables are 2PL4627A through 2PL4633A -

and 2PP820B, respectively, on elevations 749 and'734, column A11-A12/V. The hatch could conduct heat from a fire on elevation 734 to the control rod drive equipment room on elevation 749.

14. Unit 2 ~In the' auxiliary building on elevation 714 at A8/Q line, the 2A-A RHR pump cables interact with the 2B-B RHR pump cables and fail to meet the 20-foot separation criteria required by Appendix R. '(Cables-involved: 2PP578A, 2PP580A, 2PP590B, and 2PP592B.)

15. Unit 1 - In the auxiliary building on elevation.734 at A3/Q-R line; a fire in this area would require manual level control and the use of motor-driven AFW pump 1B-B. This condition '

also requires the use of the, wide range level indication, whose cables pose an interaction of less_than 20 feet.

(Cables involved: IPM1241K,1PM1251K, and '1PM1223K for 3 LI-3-56, -98, -111, and -43, respectively.)-

16. Units 1 and 2 - In the auxiliary building on elevation 653 at A8/T line on either side'of the elevator enclosure. The following RHR conduit and' cables interact as.they run.from' the floor to the ceiling on this elevation. . '(Cables involved: "A" train - 1PP575A (U1), 2PP575A (U2) interact-with "B" train - 1PP587B (U1), 2PP587B (U2).

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%/ Licensee Events and Special Reports (Condin'ubd) .

LER DESCRIPTION OF EVENT g

• J 1-84059? . . 17. Units 1 and 2 - In the a,uxiliary building.on elevation 669 (continued) at A8/S to R-line, the following cables for the "A" train RHR pump 1A-A interact with the "B" train RHR pump 1B-B.

-(Cables involved: "A"-train - 1PP577A, IPP575A and

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"B" train - 1PP589B, 1PP587B.) Th!.s same interaction applies to unit 2. (Cables involved: ="A" train - 2PP575A, 2PP577A, and."B" train - 2PP587B,.2PP589B.) -

18. Units l'and 2 - On elevation 734 in the 6.9 kV shutdown. ~

board rooms. train "B" shutdown board interacts (less than-20-foot separation) with cables IV2432A-(1-FCV-67-147) and-IV2965A (1-FCV-67-223). For this interaction, it'is assumed that-the "B" train shutdown board is lost due to a fire.

This fire would also cause 1-FCV-67-223 to fail,~ making the -

"A" component cooling heat exchanger inoperable. Also, 1-FCV-67-147 opening would crosstie the 2B and'1A~ essential,

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rawcoolingwaterpeaders.

'19, Units 1 and 2 - On elevation 714 of the auxiliary building, please note the following table which indicates the "A" t

train interaction.(less than 20-fcot separation) train l-'"B" for the cables to the, listed valves.

Unit 1 ,

"A" Train "B" Trsin 1-FCV-3-116A 1-FCV-3-126A 1-FCV-3-116B. .

1-FCV-3-126B 1-FCV-3-136A 1-FCV-3-179A 1-FCV-3-136B 1-FCV-3-179B 1-FCV-67-81 J 1-FCV-67-82 l 1-FCV-67-125 1-FCV-67-123 1-FCVl67-126 1-FCV-67-124 1-FCV-67-146 1-FCV-67-478 1-FCV-67-147 1-FCV-67-489' 0-FCV-67-151 0-FCV-67-14 ,

1-FCV-67-223 0-FCV-67-364 h 0-FCV-67-365 ERCW Pump L-B ERCW Pump N-B 1-FCV-67-424 1-FCV-67-492 Traveling Screen B j

ERCW Pump Q-A ERCW Pump J-A Traveling Screen A Y

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Licensee Events and Special Reports (Continued) a-LER DESCRIPTION OF EVENT 1-84059, 19. (continued)

(continued)

Unit 2 "A" Train "B" Train 2-FCV-3-116A 2-FCV-3-126A 2-FCV-3-116B 2-FCV-3-126B 2-FCV-3-136A 2-FCV-3-179A 2-FCV-3-136B 2-FCV-3-179B 2-FCV-67-81 2-FCV-67-82 2-FCV-67-125 2-FCV-67-123 2-FCV-67-126 2-FCV-67-124 2-FCV-67-146 2-FCV-67-147 2-FCV-67-223 0-FCV-67-152 2-FCV-67-492 2-FCV-67-489 ERCW Pump R-A ERCW Pump M-B ERCW Pump K-A ERCW Pump P-B Traveling Screen D Traveling Screen C Corrective Action Taken or Planned Ttem 1 Portable lighting has been supplied outside the main control room, by the shift engineer's office, to be used by the operators. Operators in the plant usually carry flashlights.

Portable lighting is also supplied by the auxiliary control room in a cabinet by its entrance. TVA will reverify compliance with 10 CFR 50, Appendix R, Section J in accordance with the confirmation of action letter from O'Reilly to Parris dated August 10, 1984.

Item 2 System Operating Instruction (SOI) 55 was revised to include operator response to an RCP oil level alarm to pump down the sump if the level is greater than 45 percent. In addition, Surveillance Instruction (SI) 137.1 requires the pocket sump to be pumped down at least once per shift. TVA will reverify compliance with 10 CFR 50, Appendix R, Section III.0 in accordance with confirmation of action letter from O'Reilly to Parris dated August 10, 1984.

Items 3 through 19 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 commitments. 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. An implementation schedule for corrective actions will be srbmitted to the NRC by January 1, 1985. The fire vatches established will remain in effect until full compliance with the requirements of Appendix R can be achieved.

r Licensee' Events and Special Reports'(Continued)

LER DESCRIPTION OF EVENT

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1-84060 This report describes seven inadvertent auxiliary building isolations caused by spikes on the spent fuel pool radiation monitors. For all incidents,-the spent fuel pool. area was surveyed by Health Physics, and no indication of abnormal radiation levels were found. Operations personnel reset the signal, realigned all affected dampers to their normal position, and returned the ventilation systems to normal operation. .The event dates included in this report are:

y (1) 1906 CST on September 21, 1984 from RM-90-102; (2)'1115 CST on September 23, 1984 from RM-90-102; (3) 1730 CST on September 24, 1984 from RM-90-102; (4) 0039 CST on September 28, 1984 from RM-90-102; (5) 0228 CST on September 28, 1984 from RM-90-102;;

(6) 2205 CST on September 29, 1984 from RM-90-103; and (7) 0114 CST on September 30, 1984 from RM-90-103.

l The two spent fuel pool radiation monitors are Geiger-Mueller i tubes manufactured by General Atomic (Models RD-1 and RP-1) mounted above the fuel pool and are designed _to monitor the.

air spaces above the pool area. ' A high radiation signal initiates auxiliary building isolation and is designed to limit releases to the environment in the event of a fuel handling accident._ For a11' events ~ described, the auxiliary _ building isclations were caused from noise and/or background spikes reaching the monitor setpoint resulting in the autogatic isglation.' The range of these monitors is from 10 to 10 mr/hr, and the technical. specification allowable setpoint is 15 mr/hr. The spikes causing the isolations peaked at-

, approximately the setpoint value for the events described.

The noise was from normal EMF on the monitor signalicable and the background radiation was from contaminated waste-i material passing near the monitors or fuel pool water radiation levels.

The following corrective actions have been taker. to reduce the number of inadvertent auxiliary building isolations:

A onc-second time delay was added to the high' radiation

~

1.

isolation circuit to help discrimit. ate _between an1 inadvertent spike and an. actual high radiation condition.

A

2. The spent fue1~ pool water was cleaned through its own filtering system to reduce the background levels to the monitors.

3. Contaminated waste material near the spent fuel pool monitors has been moved to reduce background' levels and efforts are being made to maintain this area clear of contaminated waste.

~

e O' . Licensee' Events and Special Reports (Continued) r LER DESCRIPTION OF EVENT 1-84060 4. ~A. technical' specification change is being pursued to

, (continued)- increase the allowable isolation actuation setpoint from .the present 15 mr/hr to a higher value.

It/is expected that corrective actions one through three,.

will limit.the number of ABIs; however, until the technical specification setpoint change is obtained, inadvertent isolations from these monitors are expected to continue. For L the events in this report, there was no effect upon'public ihealth and safety.

4 1-84061 On September 27, 1984, at 1219 CST, the reactor coolant system (RCS) pressurizer relief tank (PRT) pressure indicators located in the unit 1 and 2 auxiliary control rooms (ACRs) were discovered to have a range of 0-10 psig instead-of 0-100 psig as required per technical specifications. The indicators were discovered to have the wrong pressure range . ,

while maintenance was being performed. The pressure' indicators in the main control room read correctly. The unit one indicator was modified to read 0-100 psig and the unit two indicator will be modified during the present refueling outage.

1-84062 This Lrt involves two separate incidents. The first control room isolation (CRI) occurredlat 0930 CST on September 18, 1984 while unit.1 was in acde 1 (100 percent power, 2235 psig, 579 degrees F),'and unit 2 was in mode 1 (100 percent power, r 2235 psig, 578 degrees F). The CRI was reset and the chlorine L detector was returned.to service at 0935 CST on September 18, 1984.

L The second CRI occurred at 2310 CST on' September 29, 1984 while unit 1 was in mode 1-(30 percent power, 2235 psig, 557 degrees F),.

and unit 2 was in mode 4 (0 percent power, 375 psig, 332. degrees F).

The CRI was reset at 2320 CST on September 29, 1984. The radiation monitor (RM) chart drive motor was repaired at 2320 >

CST on October 10, 1984. The RM was operable-during this time.

I In the first incident, an assistant unit operator (AUO) pushed the test button on the chlorine detector without first placing-the chlorine analyzer in the t'est position. The AUO was attempting to correct the drip rate on the detector. The AUO immediately realized what had happened and notified the unit operator to reset the CRI and realign the ventilation system.

Instrument Maintenance was notified to correct the drip. rate

.- on the detector and verify the detector's operability. No problem was found'with the chlorine detector. Instructions are written and a warning signal is posted to warn personnel about this type of error. Personnel failed to heed the warning in this instance. A yellow caution sign-is being added to the detector that is more visible and gives a more explicit warning to personnel.

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I is  %<  :-.___.______..-__L----_..--__-_-_.. . - _ - _ _ _ _ - . _ -- _ _ _ - _ _ _ _ _ _ _ _ - _ _ . _-- ____ .__ - --_ . _ - - _ - .

1-- . _ _ _ _ _ _ . . . -_ _ - _ _ - - _ .

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Licensee Events and Special Reports '(Continued)L

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'LER . DESCRIPTION OF EVENT ,

,1-84062 In'the'second incident, the high radiation alarm on the-

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'(continued) radi9 tion monitor-(RM) was actuated by a spike. The spike was caused by the generation.of electromagnetic interference-(EhI) when the. recorder chart drive motor was moved. 'The recorder is periodically pulled out:from the RM to changelthe

' chart paper. The EMI was generated due to a lead on a capacitator.being'1oose. The-loose capacitator lead ~ caused and 'ntermittent connection when the recorder was moved. The operation of the RM was not affected as long as'the recorder was not moved.. The capacitator: lead.was resoldered to correct.

the EMI problem. No other problem was found, and the RM was returned to service.

.1-84064 While -in mode 5 (cold shutdown). at 2148 CST on September 25, 1984,

- and with' reactor trip breakers closed, the unit experienced a trip on low-low steam generator level on loop 1.--The main steam isolation valve was cycled for testing, releasing pressure on.the steam generator, resulting in a swell, then a shrinkage, of level on the secondary side. This effect had not been anticipated ~

before the test. Steam generator level was recovered'after the trip, due to automatic start of the auxiliary feedwater.

2-84015 Unii 2.was in mode 1 (2235 psig, 579 degrees.F)- at 100 percent -

reactor power on September 5, 1984. At 0523C, the operator received a turbine generator electrohydraulic control system.

(EHC) high-low level alarm. An assistant unit operator was.

immediately dispatchad to the-EHC tank to investigate the problem. ' At 0529C, the operator received an EHC. low. oil pressure alarm. At 0530C,.the reserve-EHC pump automatically started. At 0532C, the generator turbine tripped on ECH low--

low pressure and level resulting in'an' automatic reactor. trip.

2-84016 On September 9, 1984 at 0803C, a reactor trip occurred due to-a turbine trip'which was caused by the generator neutral over--

voltage relay actuating. The relay operation was verified as valid, and a megger test of the generator, isolated-phase. bus,.

and main and unit station service transformers indicated a

" I ground on the system. The ground was found to be caused by a neoprene gasket / isolating strip that had fallen down onto the isolated phase (IPB). All the strips in the IPB were inspected,.

removed, and reinstalled with RTV as an adhesive. A preventive.

maintenance program is being implemented to inspect the' isolated phase bus at each refueling outage. The unit stabilized at

^ 547 degrees'F following the reactor trip.

w

s . . _

' i wco Licensee Events and Special Reports (Continued)

LERq  : DESCRIPTION OF EVENT 2-84017, During startup.following recovery from a reactor trip'(see. a SQRO-50-328/84015), unit.2 experienced another reactor-trip.

j Just prior to the event which occurred at 1000C on September 6, 1984,-unit-2 was in mode 1.(2235 psig, 551-degrees F)

.at 22 percent reactor power. The balance of plant operator was in the process of-switching control of steam generator levels 1

from manual to automatic. During tha switchover, the number I' three (3) steam generator level began increasing.and at 60

, . percent level feedwater was isolated to loop 3.. The: reactor operator reduced reactor power.in an attempt to slow the swell of'the number 3 steam generator. .With reactor power at 18 percent, the steam generator level shrink;due to the feedwater 1

isolation resulted in a low-low level in the number.four (4) atcam generator, which tripped the' reactor. The unit stabilized at 547 degrees F following the reactor trip.

J 2-84018 On September 10, 1984, three reactor trips occurred due to

, steam generator low-low level. These occurred at_0412 CST, 0901 CST, and 1253 CST, and all involved operators attempting to manually control steam generator levels on the feedwater

bypass valves while trying to transfer to automatic controls. i Diesel Generator Failure Reports- +

There were no diesel generator' failure reports transmitted during the month.

Special Reports

- The-following special reports were transmitted during.the month.

SPECIAL

. REPORT NUMBER DESCRIPTION.

..84-04 A penetration fire barrier breaching permit was issued on August 16, 1984 for fire. door A-33 due to the' door panel' splitting at the welded seam. This-door is located on' elevation 669 between the refueling water purification pump and filter area (safety-related area) and the cask decon collector tank, pump, and filter area (nonsafety-related).

The cause of the split panel has been attributed to hard~

closing forces due to the high differential pressure across the. door.

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

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• Licensee Events and Special Reports (Continued)

SPECIAL REPORT

- NUMBER. DESCRIPTION

~ 84-05' The biological shield blocks have been removed.from unit 2 reactor building equipment hatch for the unit 2' refueling outage. This condition has been identified as a breach of a fire barrier penetration and will remain nonfunctional for

,the duration of the refueling outage.

84-06 Event Description Door A-92 Door A-92 was found to be inoperable by a fire watch on October 7, 1984. Penetration fire barrier breach permit number 1830 was written and the controls of technical specification 3.7.12 were placed in effect. Maintenance request (MR) number A121506 was written and sent to be loaded into the MR tracking system. The MR was not loaded into the system, and no work was performed'on the door during the seven days that breach permit number 1830 was in effect.

On October 14, 1984, permit number 1830 expired, and a second permit, number 1907, was written along with a new MR, number A121508. The craftsmen received the MR on October 15, 1984, and the door was repaired the same day. A postmaintenance surveillance was performed to verify.. operability of the door and breaching permit number 1907 was closed out.

Event Description Door DE-3 On September 24, 1984 at 2140 COT, the penetration fire barrier breach permit (PFBBP) for door D3-3 expired. The door had been breached to allow ventilation to the CDWE building since the air conditioning unit was inoperable. A fire watch had been.

established and remained in effect throughout the door breach..

On September 26, 1984 at 1030 CST, an audit of the breach permit book by an ASE revealed the permit had expired. The door was immediately closed.

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

. OPERATING DATA REPORT DOCKET NO. 50-327 DATE NOVEMBER 8 1984

'- COMPLETED BY M. G. EDDINGS TELEPHONE (615) 870-6248 OPERATING STATUS

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

2. REPORT PERIOD: OCTOBER 1984

3. LICENSED THERMAL POWER (MWT): 3411.0

4. NAMEPLATE RATING (GROSS MWE): 1220.6

5. DESIGN ELECTRICAL RATING-(NET MWE): 1148.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0

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

__=_ - ----

____=- _- - _ _ - - _ - _ _ _ - _ _ _ - - - - - - - _ . --_______

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

= _ _ _ _ _ = - - -. ._____-----______ _ - - . --- _________---

10. REASONS FOR RESTRICTIONS,IF ANY:_____________--________

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745.00 7320.00 29257.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL 745.00 4742.10 19183.66

13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00

14. HOURS GENERATOR ON-LINE 745.00 4531.80 18644.95

15. UNIT RESERVE SHUTDOWN HOURS O.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 2509115.23 14213187.07 59705037.37

-17; GROSS ELECTRICAL ENERGY GEN. (MWH) 843080.00 4662940.00 20042076.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 814661.00 4472070.00 19248998.00 19.' UNIT SERVICE FACTOR 100.00 61.91 63.73

20. UNIT AVAILABILITY FACTOR 100.00 61.91 63.73

21. UNIT CAPACITY FACTOR (USING MDC NET) 95.25 53.22 57.31

22. UNIT CAPACITY FACTOR (USING DER NET) 95.25 53.22 57.31

23. UNIT ~ FORCED OUTAGE RATE O.00 23.94 19.50

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..

L

W AVERAGE DAILY UNIT POWER 1.EVEL DOCKET No. 50-327 UNIT 'Seauovah One DATE November 1. 1984

, COMPLETED BY, M. G. Eddings TELEPHONE (615) 870-6248 NONTH OCTOBER 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (We et) 1 1017 17 .

931 2 1104 18 1089 3 1084 19 1101 4 1105 20 1104

~

5 1107 21 ~~S103 6 1105 22 1201'

-7 1106 23 1103-8 1104 24 1105 g 1105 25 1093 10 .1106 26 1102

~

11 1104 27 1097 l

12 1102 28 1100 13 .1103 29 1098 14 1105 '30 1099 t

15 1103 31 1100 i ,

16 ' 1102 1

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INSTRUCTIONS .

l' - On this format,ilist ghe average daily unit power level in MWe-Net for e'sch day in l the reporting month. ICompute to the nearest whole megawatt.

l l (9/77) j (.

-17 .

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UNIT'SHUTDOWNSANDPOWERREDNCTIONS' DOCKET NO. 50-327 -

. UNIT NAME Sequoyah'One DATE November 6. 1984 -

COMPLETED BY .M. G. Eddings REPORT MONTH. OCTOBER 1984 TELEPHONE (615) 870-6248 q ~

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- @q "a e ge t Licensee y Cause & Corrective No. Date 8, t$ 8 '8 t @ Event $% 8% Action to y 2e g 5g* Report # M'8 8,] Prevent Recurrence 5" $$$ N* 5" 8

15 841 17 F N/A A 5 . Manual runback to 60%.

Condensate booster pump-tripped on low oil level.

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. 1 2 3 .

4 -

l F: Forced Reason: , Method: Exhibit G-Instructions

S

Schedul,ed A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry. Sheets for Licensee 1 C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-

D-Regulatory Restriction 4-Cont. of Existing 0161) i 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 d

e

1 OPERATING DATA REPORT DOCKET NO. 50-328 DATE NOVEMBER 7,1984 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6248 OPERATING STATUS

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

2. REPORT PERIOD: OCTOBER 1-31,1984

3. LICENSED THERMAL POWER (MWT): 3411.0 4.' NAMEPLATE RATING (GROSS MWE): 1220.6

5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0

.7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0

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

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

10. REASONS FOR RESTRICTIONS.IF ANY:_____--------___-------

THIS MONTH YR.-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745.00 7320.00 21217.00

12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 6124.75 16485.82

13. REACTOR RESERVE SHUTDOWN HOURO O.00 0.00 0.00

14. HOURS GENERATOR ON-LINE O.00 5987.99 16142.31

15. UNIT RESERVE SHUTDOWN HOURS O.00 0.00 0.00

16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 19449577.30 51867645.11

17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 6620740.00 17652680.00

18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 6373689.00 16991426.60

19. UNIT SERVICE FACTOR O.00 81.80 76.08

20. UNIT AVAI. LABILITY FACTOR O.00 81.80 76.08

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 75.85 69.76

22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 75.85 69.76

23. UNIT FORCED OUTAGE RATE O.00 7.42 8.59

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

=-----------__. -------------__. -- - ___----

25. IF SHUTDOWN AT END OF REPbRT PERIOD ESTIMATED DATE bF STARTUPS

__N_gtep h G _1914_______.__ 4 ______________________________________

NOTE THAT THE THE YR.-TO-DATE AND 1 CUMULATIVE VALUES HAVE BEEN UPDATED.

f I

4 AVERACE DAILY UNIT POWER LEVEL

,' DOCKET No. 50-328 UNIT -Sequoyah Two DATE November 6, 1984

, COMPLETED BY, D. C. Dupree TELEPHONE (615) 870-6248 MONTH OCTOBER 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

'(We-Ne t) (We-Net) 1 0 17 . 0 2 0 13 0 3 0 -

19 0 4 -

.0 20 0 I 0 5 O 21 *:.

6 0 22 3*' D 7 0 23 0 8 0 24 0 s

9 0 25 0 10 -

0 26 0 i 11 0 27 0 12 0 28 0 13 -

0' 29 0 14 0 '30 0 l

15 0 31 0 ,

16 0

INSTRUCTIONS .

l On this format,[ list he average daily unit power level in We-Net for each day in the reporting mouth. Compute to the nearest whole megawatt.

. . (9/77)

(.

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. - - ~ - . , . , , , - . - - - - . - . . , ....r--, - - , . - - , . - , , ,

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UNIT' SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO. 50-328 -

UNIT NAME Sequoyah'-Two DATE November 6, 1984 COMPLETED BY .D. C. Dupree REPORT HONTH OCTOBER 1984 TELEPHONE (615) 870-6248 r .

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- @g "a c E tj Licensee y Cause & Corrective Ns. Date 8, t$ 8 ~8 0 8 Event g% 8% Action to y 8e @ $y* Report ! g'8 gi Prevent Recurrence E# #

?$$ N*

• 8 13 840928 S 745 C 4 Refueling outage.

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1 2 3 -

4 -

, Fr Forced Reason: Method: Exhibit G-Instructions i

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data

. B-Maintenance or Test 2-Manual Scram. Entry. Sheets for Licensee

! C-Refueling' 3-Automatic Scram. Event Report (LER) File (NUREG-

D-Regulatory Restriction 4-Cont. of Existing 0161) j E-Operator Training & License Examination Outage l F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 j (9/77) H-Other (Explain) Exhibit I-Same Source k,

%- s f ., . .

7

' Plant Maintenance Summary

- The plant-maintenance. summary for significant maintenance l'tems completed during the month of October 1984 are listed in the following order:

Construction Activities Electrical Maintenance Section Electrical Modification Section Instrument Maintenance Section Mechanical Maintenance Section Mechanical Modification Section =

s e

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- elm ,,.[ .-s, wee-n,-r--m--rn,-r-sw,-e-.=~--c--- ,,-w--. >e,***c-++,-+-*-r-re----,m- _m~~-e-*---n---- *-r-~~~ "v*-'v-'-

-- 5

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' ~ ' ' Construction ActivitiesL ECN L5599 - Fifth Vital Battery

.The project is approximately 55 percent complete. The fif th vital battery .

-board has.been placed in-the battery. room.through a' hole cut in_the concrete roof. JWork continued to set the batteries and theiboard," installation of, fire protection piping and HVAC fans. . Electrical' tie-ins to battery boards ~I Land.IIIihave been completed, and preparations are being made to make tie-ins s 1to the other two boards during the. unit 2 cycle 2 outage. -!

LECN'L5841'- Hot Machine Shop The project is 99 percent complete. Health Physics laboratory, deconning machines . electric shoo, snubber shop, hot machine shop are in use.during

^

-unit'2 cycle 2 outage. Work . continued on communication' and fire detection-

< . Lcable pulling and equipment installation. Monorail and hoist over electro -

- - polishing. equipment in_the decon room will be done later when material and design drawings are available.

ECN L6182 Codling Tower Repair ,

Custodis Ecodyne - The contracdor' finished ice.'damag'e related work on bcth cooling towers and le:f t the ' site. They will come:back:the latter part of

' November: to complete the ' remaining two punchlist items (concrete louvers -

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and. nozzles).

ECN L5503,-- 5111 - Office and Power Stores Facility The project is approximately 90 percent comp 1'eted. During this month,. work-continued on pulling cable, insulating ductwork and piping, architectural-painting, and drywall installation. Work'was completed on the east entrance-way,:all fa* a were installed, hydrostatic testing of fire protection piping -

^

-was completed, and permanent power cable was pulled to the1 building. The

' installation of toilet ' fixtures, toilet' tile work, and electrical connection of heat pumps and-air handling units has begun.

< > ECN L5609, 5610.- Makeup Water Treatment Building The . project is approximately 68 percent completed. During this month, work continued on. installing TVA-supplied piping, cable, trays, protective.

coating application, and yard piping. Work was. completed on the replace-1 ment.of damaged instrumentation. tubing on vendor-supplied equipment. Heat-traced process piping was-started in order to expedite as-built drawing

. preparation which is necessary prior to ordering heat trace cables.

PLANT MAINTENANCE

SUMMARY

' Page 1 of~3 M.;'. ELECTRICAL MAINTENANCE SECTION  : , r ' -

~.1 ,

DATE.... Gir>0ENT. . . . . FAILlRE DESCRIPTION...... CAUSE OF FAILlRE. . . . . . . . . CORRECTIVE ACTIOK ....... FR.NO. . .< >

10-16-84 0-FAN-030 FIEL HADOLING EXHAUST HI-RAD MONITUR- ADJUSTED TRIP UNTIL SET :A294545- .

FANS WILL NOT TRIP UNTIL - (0-RM-90-103) OPERATES POINT WAS ACHIEVED.. RESET RELAY ON HI RAD F10NITOR RELAY WHICH AUTOMATICALLY HI-RAD Ale LETT DPERATI$

RESETS REIETS WEN HI-RAD IS ^NORMALLY RErWYED THUS TE FUEL HAleLING EXHAUST FANS WILL NOT TRIP LDITIL RELAYS RESET 10-16-04 1-CDR-313-0433 1B-B 400 VOLT BOARD ROOM LOOSE ADJUSTE NT BOLTS TIGHTENED ADJUSfflENT' A234140

-B CHILLER IS NOT COOLING BOLTS AND ADJUSTED HEAD LIKE IT SHOLLD PRESSURE 10-25-84 2-ZS-063-0064 LIrlIT SWITCH OUT OF LIFIIT SWITCH OUT OF ADJUSTED LIMIT SWITCH A294343 ADJUSTENT CAUSING TE ADJUSTrENT Hale SWITCH IN CONTROL ROOM'TO SHOW BOTH RED Ale GREEN LIGHTS L10-25-84 0-LOCL-013-063 ALARM KEEPS COMING IN ON RESET ON ALARMS OUT OF CECKED DURING A294461 7 0 PYTRONICS PAEL (PRIMARY ADJUSTrIENT PERFORMANCE OF SI 234.7 POWER FAILURE PAEL SYSTEM IN NORrlAL RELAYS DISABLED) CONDITION RESET ALL ALARrtS 10-25-84 1-RE-090-0120 NDTOR ON STEArt GEERATOR MONITOR HAD NO FLOW CHANGED FIOTOR ROTATION A121955 BUILDING LTe SAPPLE USING tl8AI 12 PERFORPED FIONITOR IS ROTATING SI 206 CLEAED ROTOR BACKWARD- f1ETER Ale SAPPLE CHAFIBER LEFT IN SERVICE 10-25-9'. 14E-090-0121 FIOTOR ON STEArt GEERATOR FIONITOR HAD NO FLOW CHANGED fl0 TOR ROTATION' A121956 BUILDING LTG SAPPLE. _ USING M8AI 12 PERFORrED FIONITON IS ROTATING SI 206 CLEAIED ROTOMETER BACKWARD Ale SArFLE CHAPBER LEFT IN SERVICE.

10-25-84 0-Rf1-090-0212- ON STATION SUFF FIONITOR BAD fl0 TOR REPLACED fl0 TOR CLEANED A286870 A HI RAD ALARM ADO FLOW SWITCH APO LEFT IN INSTRUrENT FIALE ALARM SERVICE WILL COPE IN ADO CLEAR.

TEN FEW MIlWTES LATER

PLANT' MAINTENANCE

SUMMARY

-ELECTRICAL MAINTENANCE SECTION

- P,rge.2 of.-3 DATE....' CDf90NENT..... FAILURE DESCRIPTION,..... CAUSE'0F FAILURE........ CORRECTIVE ACTION.,....... 11R.NO. . s

. IT WILL CO E IN.AGAIN .

212 SUCTION VALVE WILL NOT OPEN PROPERLY .

RESTRICTING FLOWL 10-29-04 2-BCTA-072-001 TIER ON CONTADR1ENT AGASTAT TIER BAD REPLACE 0 AGASTAT TIl1ER d6 A232741 0-B SPRAY Puff 28-B CAN NOT REQUESTED A!O SET TIFIER BE ADJUSTED PER SURVELLANCE INSTRUCTIONS 220.2 10-29-84 1-FCV-072-0013 ' LOOSE CO N CTION ON LODSE CO N CTION TIGHTENED AND A293544

-A BUCHAl#4AN PLUG ON CONTROL FUNCTICHALLY TESTED R0011 HA6e SWITCH CONTROL R0011 HAND SWITCH I10-29-84 1-HST-079 UNIT 211ANIPtLATOR CRAE NOT KNOWN AT THIS TIE BORROWED UNIT 1 A246787 AUXILIARY HOIST WILL NOT t1ANIPULATOR CRANE WORK AUXILIARY HOIST FOR USE

. ON UNIT 211ANIpULATOR l CRAE DURING U2C2 OUTAGE da DOCul1ENT ON TACF Pf 1-94-105-79 HOLD ORDER 1411

, 10-29-84 0 RLY-026-OFPS WHILE TESTING FIR RELAY FAILED TO RESET CECKED FPS RELAY AND FPS A284821

! DETECTORS IN TE LAUPORY TIr1ER RELAY AIO PS 235-AREA 690 FLOW SWITCH RELAY ALL CECKED OK WE-

! RELAY FAILED TO RESET FUNCTIONALLY TESTED ZOE

, 349 & 350 ALL RELAYS

RESET PROPERLY

10-29-84 2-OXF-068-0341 PRESSURIZER EATER DOES SCREEN DIRTY Ale FUSE REPLACED SCREEN AND FUSE A293662 l -F NOT LOAD PROPERLY TO BLOWN CECKED LOAD OH 6.9 K.V.

t1AINTAIN PRESSLAtE . BREAKER Ato IS BALANCED

. AT 26 Af9S PER PHASE (374 1

ALPS PER PHASE AT 480 VOLTS) 10-29-84 0-XS-013-0144- Sl10KE DETECTOR EAR PIPE BAD DETECTOR REPLACED Sl10KE DETECTOR ,A288596

, D GALLERY BEHIle ELEVATOR WILL NOT WORK 10-29-84 2-HST-079 t1ANIPLA.ATOR CRAE UP8(NOWN AT THIS TIE INSTALLED AUXILIARY HOIST A245788

. . -_ _ . ~ ~. . .

PLANT MAINTENANCE SUMMAR Page 3 of~3 ELECTRICAL MAINTENANCE SECTION .

DATE.... GIMPO>ENT. . . . . AILtRE DESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION........ twt.NO,. .. .<

AUXILIARY HOIST HAS BEEN ON UNIT 2 THAT WAS . .

REMOVED FROM LhlIT 2 BORROWED FROM UNIT 1 ON istA246787 10-29-84 2-BCTB-030-003 Af9TECTOR WAS BAD IN AN TECTOR BAD REPLACED ANTECTOR IN A234147 8-A ' CIRCUIT BREANER (SB. WESTINGNDUSE BREANER.

2A1-A COUP LOC) DF SNUT '

WEN TE CURVE WAS DOWN BOARD. TE CURVE WAS REFIGURED BREAKER 30-38A FIGtRED WR0lC ON SI258.2 WAS APPLIED TE PROPER TE If9UT CLRRENT WAS.TOO CURRENT AND PASSED THE LOW REGUIREENTS OF SI 258.2 10-29-84 2-LOCL-013-063 . UNABLE TO RESET FCV-26-223 WILL NOT RESET . REPLACED DETECTOR ON ZOE A295005 0- FCV-26-223 DUE TO ALARM 3748 RAN SI 234.7 ON ZOE -

IN FROM ZOE 3741 374 CECKED OPERATION AM)

RETURtED TO SERVICE 10-31-84 2-CRN-079 LIMIT SWITCH ON LIMIT SWITCH ARM UAS RESET LIMIT SWITCH ARM A285730 11ANIPULATOR CRAE NOT ACCIDENTLY TRIPPED 4 MAKING CONTACT T -

17 rwcords listed.

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, s Electrical Modification'Section

.0ctober 1984-

'DCR 1739 - VAACS Panel wiring has continu'd:this e period at a slow pace. -Material shortages

.still impede completion of this work. The Public Safety Service will meet November 1 with field engineers to ~ establish the availability of-ren.aining material needs.

-DCR 2072 - Local DCR to Improve Reliability of Stud Tensioner Hoists

. The original limit switches were -replaced with geared limit ' switches. The (480-volt connectors were not available to be installed in this time period.

The' hoists were hard-wired in place. .If'the connectors arrive before the lend'of the outage, they will be installed.' In any case, the_ stud tensioner hoists will be removed before the en'd of the outage and stored outside-

-of containment.

ECN'2768 - RVLIS All conduit inside and outside containment was completed during this period.

All rework associated with this ECN was completed. All cable inside and.

'outside containment was pulled. Terminations are underway inside and outside~

-containment. All main control room work is complete with the exception of-installing four level indicators, which are expected to be onsite in early. November.

-ECN 2780 - Postaccident Sampling Facility c

DAll electrical modification work asso'iated with the ventilation system

^

has been completed. Communication equipment in the facility is nearing completion. At'the present time, there are four valves that are not wirec

..pending resolution of leak-rate testing deficiencies. Installation-of heat trace has begun and is expected to be completed in early November.

All lighting is complete.

_ECN 5194 - Iodine Monitors All electrical work associated with the monitor was completed.early this

- period. The monitor has been analyzed and turned over to Instrumentation for initial checkout. Work remaining consists 1of keycardfreaders in both

-PING rooms. The workplan is still in the approval cycle.

ECN 5198 cTechnical Support Center

-The Ayden. display generator was received onsite and installed early this period. All conduit work was completed -this period. Approximately

.95 percent.of the cable has been_ pulled,'and terminations are underway. The

'old SMS cabinet was removed from the main control room and is being reworked

to accommodate the SPDS monitor. Work is on schedule, and there are no anticipated delays.

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-3 Electrical Modification Section (Continued).

ECN 5640 -~ Deletion of PDIS 1-17 andL1-18 nt The inst'ruments were-removed and associated pipes-capped. All electrical work is: complete.

'ECN 5645 Steam Generator Blowdown-All conduit and cables-have been completed on this ECN. Terminations are hi progress in the main control room and in local panels.

The system is expected to be ready for postmodification tests early in-November.

.ECN 5712 - Evacuation Alarms -

Conduit,and' cable have-been installed in the unit 2 letdown' heat exchanger

-room. Conduit'has been installed in the east valve room, and 90 percent of.

'the conduit ha's been installed in the west-valve room.

ECN 5765f- Deletion ~of Seal-in Limit Switches All work was completed in this period for this ECN.

ECN 5770 - High-Range Radiation Monitor Work completed this period consisted of remaining panel. wiring in 2-M-30.'.

All work is complete.

ECN 5823 - Pressure Switch Replacement Four pressure switches were replaced this period, for a total of ten associated with unit 2. There are four more pressure switches en order,.

and they'are expected to arrive onsite October 31. They will be installed in'early November.

ECN 5824 -- Replacement of Valve Operators Thirty-four valve operators were replaced this period. Four more operators remain.on this ECN.

ECN 5842 - Removal of PCV-3-122 and.PCV-3-132 Electrical work this period consisted of lif ting leads on a maintenance request to facilitate removal of the valves. Workplan 11239 is awaiting

'information from the Instrument Maintenance Section. This information is expected to be finalized shortly, releasing the workplan'for work.

ECN 5865 - RcJocation of LA-77-129 All. conduit and cable associated with this ECN are complete. We are presently waiting until the coolant system is brought back down below elevation 693 to remove the annunciator from service for-relocation.

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. Electrical Modification Section (Continued)~

ECN 5867 - Fuel Transfer- System All work was completed on this ECN at the beginning of' this period.

Postmodification testing was performed and found to be satisfactory.

.However, during initial fuel movement, the Red Lion counter continually reset during the transfer of fuel. Westinghouse.was notified of this problem and recommended two field changes be made. The FCNs were imple-

- mented, and the transfer system has since performed satisfactorily.

ECN 5881 - Limit Switch Replacement Twenty-eight of fifty-two limit switches have been replaced this period.

There are no anticipated problems at this time.

ECN 5882 - Temperature Switch Replacement Twenty-two System 30 temperature switches have been replaced and are functional at this time. Eighteen System 12 temperature switches have been installed in the field. Field wiring is complete. We anticipate final connection to the control circuit in early November.

ECN 5883 - Replacement of Various Instruments Conduit and cable associated with the relocation of four flow elements and flow switches have been completed. Terminations are underway. Conduit and cable work associated with the relocation of six pressure switches has begun. Work involving the direct replacement of nine pressure switches will commence in early November.

ECN 5884~- Replacement of Flow Transmitters Work has commenced to replace five System 3 flow transmitters. This is expected to be completed this period. Two System 72 flow transmitters required redesign of mounting brackets. Approval of this redesign is in hand, and the replacement of these flow transmitters is expected to start this week.

- ECN 5898 - Deletico of Seal-in Limit Switches Cable pulling for this ECN is complete. Workplan 11227 was PORC'd on October 30. Installation of relays and wiring changes will commence this week. This work involves five-valves.

ECN 5970 - Replacement of Valve. Operators

'Two System 72 valves are waiting for final pipe relocation to facilitate

- their replacement. The four feedwater isolation valves have arrived onsite. Planning is underway to determine the most efficient way of delivering the valves to the worksites. There are no anticipated problems at.this time.

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.' '. c Electrical Modification Section (Continued) cECN'5971 - Replacement of Valve Operators

-Replacement of valve 63-172 started late in the period. It is expected to be back in service by October 31. The two PORV block valves had their operators changed out early in the period.

ECN 5995 - Replacement of'Various-Instruments The four PDTs have been replaced, and limit switches have been replaced on three valves. All field work on this ECN is complete.

ECN-6018 - Installation of Space Heaters, Auxiliary Feedwater. Pump Motors At the present time, we are waiting for a redesign of the installation of the heaters. The original design called foru boring two 3-inch . holes into

~

the motor casing. We are requesting a design that will incorporate the use of vent openings to provide access'for the heaters.

ECN 6032 - Relocation of Hydrogen Analyzers

'All conduit and cable work is complete on this ECN. Trains of analyzers have been turned over to Instrumentation for functional testing.

ECN 6053 - Replacement of Acoustic Monitor Charge Converters

.The new converters have been mounted, and conduit work is in progress.

-There are no anticipated delays.

ECN 6055 - Fourth Wide-Range Pressure Transmitter Conduit and cable work inside containment is nearing completion.

ECN 6108 - Replacement of Valve Operators This ECN has been superseded by ECN 6245. We have received instructions i on modifying a unit 1 valve operator to replace the unit 2 valve operator.

i The writing of the workplan is in progress.

EC21 6200 - Relocation of Pressure Transmitters Conduit and cable are approximately 50 percent complete on this ECN. The

.six pressure transmitters and their associated panels have been relocated.

ECN 6204 - Installation of Fuses The majority of this work is on hold pending technical specification revision. The. work that is available will commence in early November.

.Electrica'l Modification Section (Continued)

ECN'6207 - Conax Connectors Workplans involving other ECNs that require Conax connectors have been revised to incorporate the use of the connectors. The remaining devicee

. that require the connectors will be addressed on a separate workplan,

' which'is now in:the approval cycle. There are no delays expected.

Appendix R Work continues on~the first five interactions, w

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4 'l 9'~ Instrument Maintenance Section.

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-October 1984 O, ,

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- ' Unit 11 .

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1. The unit ex'erienced p a. turbine runback'to 60 percent wh'en 1B condensate (booster pump tripped on-.0ctober 17,'1984 during a-transient with_the level lin'the hotwells.- It was.found that the NPSH pressure switch had drifted high causing an inadvertent actuation during the transient.--The-f- 1 switch' was replaced, and the unit returned to full: power.

2. fDuring the monthly calibration of the UHI-level switches, lone switch I

.was found outside of technical specification tolerance.

L- 3. The TACF on the pressurizer _ relief tank remote monitoring pressure channel, 1-PT-68-311C, was cleared. In September, the channel was l changed from 0-10 PSI to 0-100 PSI to agree with technical.specifi .

cations. The ECN and drawing were received this month to clear. the TACF.. The modification is being implemented on unit 2 during the current refueling outage.

Unit 2-

1.' The' unit has been in cycle 2 refueling. outage this month. Response time

' testing and refueling calibration continue. -Modifications for installation of TSC,' RVLIS, new post accident radiation monitors, and harsh environment instruments to meet 10 CFR 50.49 requirements have been started.

Other work is shown on the attached list.

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Plant Maintenance Summary INSTRU1ENT MAINTENANCE n0Mitu SU@ARY 11-09-64 NE 1 of 3 ,

COnP MR. CON U FUNC SYS ADDRESS. DATE. . . . DESCR IP T I ON. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CCR RECT IVE AC T ICH. . . . . . . . . . . . . . . . . . . . . . . ,

A040293 1 RM 090 121 10/05/841-Rn-090-121, FLUSH nONITOR TO REDUCE BACKGROLRO. CCNTAMINATED SArWLE OMMBER. FLUSHED WITH RAW SERVICE WATER ,8 RAN SI-206 FOR CAL 1.A096162 2 LT 077 411 10/15/84 2-LT-077-411,XnTR RESPONSE IS InPAIRED dud TO TRANSMITTER LOW ON FILL FLUID. REFILLED SUSPECTED LOSE OF FILL FLUID IN SENSING ELEMENT. TRANSMITTER & VERIFItD CALIBRATION. e A233390 2 FCV 062 93 10/03/84 2-FCV-062-93, CHECK STROKE OF VALVE CHARGItC HE@ER FLOW CONTROL VLV STROKE

, WAS ALTERED BY MAINTENANCE PERFORNED ON A PREVIOUS fR. VLV Uf6 RESTROKED.

A233392 1 TI 083 5001 10/29/841-TI-083-5001,NO INDICATION-CECK OUT ADO REPAIR BAD CA8LES. REPAIRED BY ELECTR PER MR N234150.

A234140 1 Oft 313 433 10/11/84 1-CHR-313-433,ufu INVESTIGATE AIO RESOLVE LOOSE ADJUSTnENT BOLTS. ADJUSTED HEAD

-- PR08 LENS WITH 4800 BD ROOn CHILLER 18-6 PRESSURE (TICHTENED ADJUSTMENT BOLTS)

A234146 0 BATD 250 10/16/84 0-BATD-250 , min PREPARE THE EW 5TH VITAL NO FAILURE. PREPARE THE NEW 5TH VITAL

BATTERY FOR INITIM. EQUALIZE CHARGE BATIERY FOR INITIA". EDUALIZER CHARGE.

CHECKED BATTERY CONtECTIONS, VERIFIED WATER LEVEL TO BE 1" ABOVE CELL PLATES APO LASEL CELLS 1 THROUGH 60.

10/11/84 2-MTRA-003-0128, REPLACE LUBRICATING OIL ON NO FAILt'RE. REGLACE L1;8RICATING OIL OH J A237705 2 MTRA 003 0128

J AUXILLARY FEEDWATER PUm MOTCR. AUXILARY FEEDWATER PTP MOTCR 8. DRAINED r " A>O REFILLED WITH 4 GJARTS OF STO-2 OIL E A237708 2 MTRA 003 0118 10/11/84 2-f1TRA-003-0118,REDPLACE LUBRICATING OIL ON NO FAILURE. REPLACE LtBRICATING OIL ON AUXILLIARY FEEDWATER PUN MOTgt. AUXILARY FEEDWATER Pi9 N0 TOR A. DRAINED AND REFILLED UITH 4 GJARTS CF STD-2 OIL A239443 0 RM 090 102 10/01/84 0-RM-090-102,NIn CHECK CALIBRATION OF n0HITOR. THE FUEL POOL RADIATION MCHITOR WAS 2

SHOWING HIGHER ACTIVITY THAN HP SURVEY.

INVESTIGATED AND FOUr0 NO APPARENT E PROBLEN.

10/28/84 2-FCV-062-93, VERIFY 2-FCV-62-93 IS STROKING POSITIONER OUT CF CAL., VLV OUT OF

[ A282234 2 FCV 062 93

~

STROKE. CALIBRATED POSITIONER, STROKED i PROPERLY FR0n CONTROLLER vtv.

A285082 2 ICR 074 483 10/12/84 2-HGR-074-483, HANGER 2-RHRH-483 - PAINT WELDS NO FAILURE. HAfGER WELDS CCRRODED AND

. APO HANGER AS RE8UIRED NEEDS PAINTING. CLENED CCRROSION FR0n l( ,

10/12/84 2-HGR-074-492,HAbeGER 2-RHRH-492 - PAINT WELDS HAtCER WELDS ETC AND PAINTED BLACK

!/ A285084 2ICR 074 492 NO FAILURE. HA*.CER LTLDS CCRRODED AND .

AIO HANGER AS REQUIRED NEEDS PAINTING. CLEAPED CORROSION FR0n

!~

HANGER WELDS ETC AND FAINTE0 SLACK lT l' A285086 2 FOR 012 8-14 10/12/84 2-HGR-012-8-14,HA>EER 47A431-8 PAINT UELDS NO FAILURE. HAtCER W 1DS CORRODED AND -

!I; A O HANGER AS REGUIRED NEEDS PAINTING. CLEANED CCRROSION FROM iM HANGER WELDS ETC AND PAINTED BLACK Y.A285097 2 tCR 062 416 10/12/84 2-HGR-062-416. HANGER 2-CVCMH-416 - WELDS NEEDS NO FAILU9E. HA.uCER U10$ CCRRCDED 1

M ,

PAINTING NEEDS pap.rtnG. CtE M D CORROSIOtt FF03 y-

?

] Plant Maintenance Sur. unary i- IN5TRtt ENT nAIH1ENANCE n0NTHLY SUmARY 11-09-84 PAGE 2 of 3 -

ii COMP '

' rs.COnP U FUNC SYS ADDR ESS. DATE. . . . DESCRIPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CCRRECTIVE ACTION. . . . . . . . . . . . . . . . . . . . . . .

It -

HANGER, UELDS ETC Ah0 PAINTED BLACK

'. A285899 1 LIC 003 174 10/15/841-LIC-003-174, uIn pLEASE CALIBRATE ABOVE PROBLErl UITH SERVO r10 LOR 1 VARIABLE ll MENTIONED LIC RESISTOR. REPLACED C04 TROLLER WITH SPARE.

i A288557 2 #1TRA 062108A 10/15/84 2-f1TRA-062-108A,2A CENTRIFUGAL CHARGING Pl#F NO FAILURE. OIL ON OUT8OARD n0 TOR -

l MOTOR - ADO DIL TO OUT80ARD f10 TOR BEARINGS. BEARINGS ON 2A CENTRIFIEAL CHARG!lG Pl9 110 TOR. ADOED 1/4 PINT OF STD-5 OIL TO l OUT8OARD MOTDR BEARIrGS 0 QR 313 725-8 10/17/84 0-CF5t-313-725-8,8 TRAIN 69 SHUTDOWN 80. ROOM NO FAILURE-IND& TOR LIGHT SHOWING ll;A288684  ;

l CHILLER-HIGH MOISTURE CONTENT IN FREON CAUTION ON 81xAIN 4.9 KV SPRIT 00W j BOARD Rf1 CHILLER (NIGH f10!STLRE CONTENT). CHECNED AS REGESTED, FOLAG TO 8E IN GOOD GPERATION, SIGHT GLASS CLEAR ADO ALL PRESS. FOUPS TO BE FIDE.

i NO WORK PERFORrED A291755 0 Rr1 090 125 10/11/84 0-RM-090-125, INVESTIGATE SPIKING PROBLEM (DI LEAD ON CAPICATOR BRGCEN. RESOLDERED WHICH LEADS TO CONTROL ROOM BLDG VENT ISOLATION LEAD f6A2928112 tGR 001 310 10/15/84 2-HGR-001-310, RUSTY SNUB 8ER NO FAILURE. RUSTY SNLBSER FDLDO IN UEST T

t VLV RM. CLEASED APC PAINTED SMA8ER PER ._

MI 10.14 -

H

[ A292831 2 FGR 001 10 10/15/84 2-HGR-001-10, HANGER E EDS PAINTING NO FAILtRE. NANGER NEEOS PAINTItC IN UEST VALUE RM. CLEAED 8 PAINTED HANGER 1 AS RE7 JESTED.

l A293505 1 Nr1 090 120 10/05/841-Rl1-090-120, FLUSH OUT MONITORS TO REDUCE CONTAMINATED SAf1PLE 04ArWER. FLUSED i BACKGROUPO AIG CLEAR ALARnS. WITH RAW SERVICE WATER 8 RAN SI-206 FOR I CAL A293519 0 RI1 090 122 10/07/84 0-Rft-090-122.CE11ICALLY CLEAN RAD 110HITOR TO SAr1PLE CHAn8ER CONTAf1INATEO. CLEAN REDUCE BACKGROUte TD (10 TO STH POWER CPM SArPLE CHAMBER & VERIFY CAL 2 FCV 074 24A 10/15/84 2-FCV-074-24A,THIS VLV CYCLES SUITCH OUT OF CAL. REEALIBRATED SUITCH.

l A293680 DPEN(PARTIALLY) WILE ON RHR 8 TRAIN 4 FLOW CO>DITION IS >2500GPM WTIL VLV OPENS UP. TEN DROPS BELOW 2500GPM(TECH SPEC)

A293715 0 Ret 090 212 ,

10/06/84 0-itn-090-212," INSTRUMENT MALFlklCTION ALARM" UILL FL0u SUITCH STUCK. CLEANED SUITCH &

~~

NOT CLEAR. FLOW DRUi1 STAYING IN UEN Sul9 Pur9 FLUSHE0 M0?lITOR, PERFORrED SI-206 -

IN SERVICE.

i A293716 2 F11 030 273A 10/I2/84 2-Frt-030-273A, uIn TE Ff1 IS NOT FOLLOUING A.S. FAULTY DELTA P TRANSnITTER. REPLACE f PRESS. WILL NOT fMINTAIN A.B. PRESS. IN NORl1AL TRANSf1ITTER.

i, aaact 4 A294256 2 f1TRA 074 0010- A 10/04/84 2-f1TRA-074-0010-A,TE UPPER SITE GLASS ON 2AA' NO FAILL9E. DIL LEVEL LOW. ADOED OIL TO

! RFft PUMP HEEDS DIL ADDED UPPE9 SIGHT CLASS ON 24-A RHP Pr1P 1 PINT

! 0F STC-2 l

Plant Maintenance Summary INSTRtITNT f1AINTENNCE f10NIHLY SUf71ARY 11-00-84 PAGE 3 of 3 C0f1P

.A rio.C0r9 U FUNC SYS ' ADORESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . COR RECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . .

A294520 2 PT- 070 17A 10/01/84 2-PT-370-17A. PRESS SUI 1CH STARTS CCU PlR1PS THAT C0(1P0fENT COOLING SYSTEf1 Pf1PS 2A-A A@

AR IN AUTO BEFORE LEADER PRESS APPROACIES 40 28-B DISCHARGE LOU PRQiS. SUITCH UAS OUT

1. SIC , OF CALIB. C0r1PONENT COOLING SYSTEr1 PriPS

. _ _ 2A-A AM) 28-B DISCHARGE LOW PRESS.-

SUITCH UAS RECALIB. .

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A294542 0 Rr1 090 132 10/09/84 0-Rft-090-132,NIn FLOW LOW WON'T CLEAR, HAD ALL FILTS PAPG NOT INSTALLED PROPERLY 3 FILTERS CHANGED-STILL WOULD NOT CLEAR LID ON FILTER BOX NOT TIGHTDEO DOWN.

INSTALLED PAPER CORR CTLY 8 TIGHTEIED

- FILTG BOX LID.

A295006 0 BATB 250 10/15/84 0-BATB-250 ,NIN SPECIFIC GRAVITY READING 1.195 NO FAILLRE. CIECK SP. GRAVITY OF CELL, THIS IS T.S. LIIIIT IF BELOU 1200 PLACE Of EQUALIZG CHARGE. IF SP. GRAVITY IS BELOW 1195, / .,

REPORT IfRIEDIATELY TO SE D/G 28-8 BATTERY. PLACED BATTERY 28-8 0F DIESEL I

GENERT0R ON 7 CAY EGUM.IZER CHARGE.

29 records listed. / -

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Mechanical Maintenance Section-

~ . .

.0ctober 1984

1. ERCW scab plate' work onLthe third and fourth locations was completed,

! thereby completing .this project..

2. .The boric acid transfer pump seal was. replaced.

3. ~The 2B1 MSR tube'. bundle was pulled and replaced with a stainless.

steel bundle.

~4. ~ Pinhole leaks on the ERCW piping at 1-FCV-67-146 above the'CS heat exchanger resulted in the installation of a scabplate.-

5. Monthly. inspections of 1A-A and 2A-A diesel generators were completed per SI-102.

6. FCV-1--18 was threaded and capped due to steam blowing from the gland leak-off line.

7. The floor drain collector tank line was drilled'and drained due to-blockage in the line.

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Mechanical Modification Section o ~

October 1984 ECN 6047

., A temporary reactor vesael level indicator for unit 2 was installed and is operable.

DCR 2032 The reactor coolant pump seal leak-off lines were capped.

1

-ECN 5773, Pressurizer Work, ECN 6196 Final designs were received for all but three hangers. All three pressurizer safeties were replaced with three modified valves. The Nu-con insulation for

. the loop seals is on site.

NUREG 0588 ECN'6231 Several piping reroutes on the fire protection, CVCS and waste disposal systems were completed allowing the new motor operators to be installed.

ECN 6032 - Relocate H Analyzer 2

This work has been completed except for postmodification testing.

ECN 5895 - Solenoid Replacement A11'but five solenoids have been replaced.

ECN 5457 - Solenoid Replacement only one solenoid remains to be replaced.

ECN 5883 - Auxiliery Feedwater Pressure Switches Work continues on the relocation of these switches.

ECN'6200 - Auxiliary Feedwater Transmitter Relocation The-instruments have been relocated. The repiping work has not : started.

Other Work Me chanical support was provided to the Electrical Section in the replacement of the 0588 instruments.

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4 Mechanical Modification Section (Continued)

ECN'5644 - Auto Dump Back.to the Condenser

Some-painting and insulation activities remain.

ECN 5645 - SGBD

' Painting, sinsulation, and final testing will be performed during startup.

ECN 5770 - Turbine Building Radiation Monitor Final tie-ins were made and postmodification testing has begun.

ECN 6002 - CST Check Valves The diafloat check valves have'been installed.

ECN 5024 - Steam Generator Wet Layup SGBD tie-ins were completed. The feedwater bypass check valves and the discharge tie-in were completed. Work. remaining includes tie-ins to the

- chemical feed-lines, hanger work, painting, and insulation.

ECN 5842 - Cavitating Venturi All tie-ins have been completed. Hydro testing is in progress and hanger work continues.

ECN 6060 The upper internal lift rig platform was installed prior va floodup.

ECN 5534 The under vessel access cage was installed and painted.

ECN 5751 Penetration X117 was installed.

ECN 5713 - Paul Monroe Snubber Monorail Work continues. Two steam generator enclosures are complete except for painting.

DCR 1935 - Turbine Generator Platform The turbine generator platform has been installed on unit 2.

ECN 5743 - Steam Generator Platforms and Ladders This work is 90 percent complete.

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Mechanical' Modification Section (Continued)-

b- DCR 1729 - MSR Doghouse:HVAC LWork continues in this area. 1 Work is being coordinated with other MSR work.

ECN 6243 - Penetration X87 -

The workplan was written and approved.

~ECN 6206 - CST.B "The tank has been sandblasted and the first coat of' paint applied. Application-of the final coat remains. The. Williams Company HVAC equipment is being used-'

.to maintain the temperature and humidity within -the allowable limits during-work.

.ECN 6256, 6257,-6262 - Turbine Building Side Performance Improvement Modifications Workplans hcve been written and are in the approval cycle. . Material is being located.

ECN 2768 - RVLIS

-All containment unistrut and sensor installation was-completed. Some paint-work remains. All capillary tubing ~was installed. . Tie-ins to the hot legs and the reactor head remain prior to pressure testing and postmodification

-~

testing. Westinghouse personnel are on site to assist in these activities.

ECN 2780 - Post Accident Sampling All penetration isolation valves were installed-and tested. All valves are being procured from Watts Bar Nuclear Plant. Tubing work inside containment and in the PASF room continues. Postmodification testing was started on the HVAC and parte of.the tubing.

ECN 5939 - MFPT Condenser Retubing

.The condensers were opened, old tubes removed,~and new tubes installed. Harris Tube Pulling and Foster Wheeler have completed their work. The first tube is presently being reinstalled. Both expansion joints 'have been replaced.

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l TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant Post Office Box 2000 Soddy Daisy, Tennessee 37379 NOV 141984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - OCTOBER 1984 Enclosed is the October 1984 Mcnthly Operating Report to the NRC for Sequoyah Nuclear Plant.

Very truly yours, TENNESSEE VALLEY AUTHORITY c ;;A 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 l Atlanta, GA 30323 (1 copy) INPO Records Center l Suite 1500 l Director, Office of Inspection 1100 circle 75 Parkway and Enforcement Atlanta, GA 30339 Nuclear Regulatory Commission Washington, DC 20555 (10 copies)

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

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

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