ML20113F443
| ML20113F443 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1984 |
| From: | Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8501240022 | |
| Download: ML20113F443 (59) | |
Text
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- i TENNESSEE VALLEY. AUTHORITY' i
DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT ;
f MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION NOVEMBER 1, 1984 - NOVEMBER 30, 1984 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 i
DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by P. R. Wallace, Plant Manager 8501240022 8411 JQ PDR ADOCK 05000327 R PDR
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TABLE OF CONTENTS Page Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . 1 PORVs and Safety Valves Summary. . . . . . . . . . . . . . . . . . . 2 l Reports I Licensee Events . . . . . . .e. '. . . . . . . . . . . . . . . . 2-17
( Diesel Generator Failure Reports. . . . . . . . . . . . . . . . 18 l
l Special Reports . . . . . . . ... . . . . . . . . . . . . . . . 18 l
Offsite Dose Calculation Manual Changes. . . . . . . . . . . . . . . 18 Operating Data Unit 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19-21 Unit 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22-24 Plant Maintenance Summary. . . . . . . . . . . . . . . . . . . . . . 25-50 Appendix A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51-56 i
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17 3
ik Operations Summary November 1984 n
A
, The following summary describes the significant operational activities for the month of November. In support of this summary, a chronological log of significant events is included in this report.-
Unit l'
' Unit I was critical.for 720.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, producca 831,830 MWH,(gross),.resulting
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- in an average hourlyfgross load of 1,155,319 kW during the month. There are 201.7 full power days. estimated remaining until the end'of cycle 3 fuel.
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With a capacity factor of 85 percent', the target EOC' exposure would be reached ~ July 24,-1985. The capacity factor for_the month was 97.7 percent.
There were no reactor scrams, manual shutdowns, or power reductions j during the month.
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Unit 2
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The unit 2 cycle 2 refueling / modification outage continues. The estimated return-to-service date is December 18, 1984.
Significant Operational Events Unit 1~
l l Date Time Event
!- 11/01/84 0001 ' The reactor maintained 100% reactor 11/30/84 2359 ' power the entire month. The-average hourly load was'1155 MWe..
Unit 2 i
11/01/84 0001 Cycle 2 refueling / modification outage 11/30/84 2359 continues. The unit return-to-service date is December-18, 1984.
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~PORVs and Safety Valves Summary No PORVs or safety valves were challenged' during the month.
I Licensee Events and Special Reports The following licensee event reports (LER) were sent during November 1984 to the Nuclear Regulatory Commission.
1 l
. LER DESCRIPTION OF EVENT '
1-84063 Inspections at Sequoyah Nuclear Plant have identified the e 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. The listed train 'A' cables interact with unit 2 2B 480 volt transformer room (train 'B').
Train 'A' cables: 2V2233, 2V2232A (2-FCV-62-98),
2V2070A, 2V2071A (2-LCV-62-135), 2V2326A, 2V2327A (2-FCV-63-7), 2V2680A, 2V2681A (2-FCV-63-26), 2V2695A, i<
2V2696A (2-FCV-63-39), 2V2292A, 2V2993A (2-FCV-70-143).
- 2. The listed train 'A' cables interact with unit 2 train .
'B' MOV board room. L l -i.
Train 'A' cables: 2PL3002A (CCP Room Cooler A-A), !
2PL4729A (CCS Pump 2A-A), 2PL6145A, 2PL6148A, 2PL6149A (CCP 2A-A Auxiliary 011 Pump), 2V2235A (2-FCV-62-98), :
2V2073A.(2-LCV-62-135), 2V2329 (2-FCV-63-7), 2V2683A 1 (2-FCV-63-26), 2V2698A (2-FCV-63-39), 2V2787A (2-FCV-74-1), i 2V2295A (2-FCV-70-143), 2V2423A,.2V2424A, 2V2425A (2-FCV-67-146),
- 3. The listed train 'B' cables interact with train 'A' 2A 480 volt transformer room.
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Train 'B' cables: 2V2240B, 2V2241B (2-FCV-62-99),
2V2100B,-2V2101B (2-LCV-62-136), 2V2320B (2-FCV-63-6),
l 2V4934B (2-FCV-63-24), 2V28408, 2V2842B (2-FCV-74-2),
( 2V4371B (2-FCV-62-55), 2PM-132 (2-FCV-62-56). ,
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- 4. Interactions exist for each channel such that all four i RCS temperature indicators could'be made_ inoperable due
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to one fire. Cables involved are:
Channel I: 2PM5911 (T-68-1), 2PM7781 (T-68-18),
2PM6861 (T-68-24), 2PM8711 (T-68-41).
Channel II: 2PM59511 (T-68-43), ' 2PM78411 (T-68-60),
2PM69111 (T-68-65), 2PM87611 (T-68-63).
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Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84063 5. Unit 1 RCS pressure instrumentation loop P-68-66 (continued) (cables 1PM481II, 1PV135II) interacts with pressure instrumentation loop P-68-69 (cables IPM4801, 1PV320J) at three locations in auxiliary building (elevation 690 U-W/A3-A4, elevation 714 Q-W/A2-A4, elevation 714 Q-R/A4-A11). In addition to cables, the pressure transmitting equipment is located less than 20 feet from each other at elevation 690 at A3-A4/V line.
- 6. Secondary side pressure control cables for all three channels of pressure indication for each steam generator interact with less than 20-foot separation. Also, cables for 2-L-381 pressure indicator are involved. Cables involved are:
SG-1: 2PM13351 (PI-1-2A), 2PM1347II (PI-1-2B),
2PM13601V (PI-1-5).
SG-2: 2PM1474I (PI-1-9A), 2PM148011 (PI-1-9B),
2PM1490111 (PI-1-12).
SG-3: 2PM1595I (PI-1-20A), 2PM1607II (PI-1-20B),
2PM1613III (PI-1-23).
SG-4: 2PM17151 (PI-1-27A), 2PM1723II (PI-1-27B),
2PM17291V (PI-1-30).
2-L-381: 2PM1340J, 2PM1475J, 2PM1601J, 2PM1717J.
- 7. Interaction exists in the 480 voit reactor MOV board rooms between 1A-A and 2A-A 480 volt reactor MOV board room air handling units (cables 1PL2958A and 2PL2958A) and numerous cables for the 1B-B and 2B-B 480 voit reactor MOV board room air handling units and compressors.
- 8. The following interactions exist for 480 volt reactor MOV board rooms at elevation 734 in the auxiliary building.
- b. Cable 1PL2947V (1B-B compressor) crosses R line wall and interacts with 'A' train 6.9 kV shutdown boards.
compressors. Also, cable 2PL2958A crosses R line into 'B' train 6.9 kV shutdown board room.
Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84063 9. At elevation 749 in the 2B 480 volt MOV board room in (continued) the auxiliary building, cables 2PL2945A, 2960A, 2961A, 3503A, 3504A, 3505A (2A board room AllU/ compressors) interact with cable 2PL2947B (2B compressor).
- 10. At elevation 749 in the auxiliary building (2A 480 volt transformer room, 2A 480 volt HVAC equipment room) cables 2PL2966B, 2PL3514B, 2PL3516B pass through two rooms listed above and interact with transformers /HVAC equipment on train 2A.
- 11. A fire in auxiliary building at elevation 690 All-A15/Q-S would result in the loss of automatic level control for the turbine-driven auxiliary feedwater pump and the wide range level indication cables (2PM1233K, 2PM1244K, 2PM1226K) required for manual operation of level control valve.
- 12. At elevation 669 in auxiliary building at A11-A12/S-T DC control power for the turbine-driven auxiliary feedwater pump, cable 2SG220A interacts with the 'A' and 'B' motor-driven auxiliary pump on elevation above, due to stairway opening.
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.
1-84064 While in mode 5 on September 24, 1984, at 2148 EST 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.
1-84065 Two separate auxiliary building isolation (ABI) events occurred on October 9, 1984, with unit 1 in mode 1 at 100 percent reactor power and unit 2 in mode 5. Both events occurred as a result of personnel carrying mops and buckets used for cleaning of the transfer canal too close to the spent fuci pool radiation monitors. The first event occurred at l
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r Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84065 0307 CST when the material was taken near radiation monitor (continued) 0-RM-90-103, causing a 10 mR/hr spike of the monitor. The second event occurred at 0340 CST when the material was taken near radiation monitor 0-RM-90-102, causing a 55 mR/hr spike of the monitor.
1-84066 During performance of surveillance instruction (SI) 258.2,
" Inspection of Molded Case and Lower Voltage Circuit Breakers," personnel manually opened a breaker without an alternate power source to supply its loads. This action caused diesel generator (D/G) 2A-A to start on loss of power to its emergency start circuit. The other three D/Gs started due to the common emergency start circuitry. The breaker was closed and the D/Gs were stopped and reset fifteen minutes after the incident. There was no effect on public health or safety.
1-84067 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. A fire in the corridor near the number six (6) stairway on elevation 669 could interact with controlling cables for the component cooling system (CCS) pumps that maintain reactor coolant pump seal integrity. Affected equipment -
CCS pump A-A, cables 1PL4727A, IPL4731A, 1PL4732A; CCS pump B-B, cables 1PL4742B, IPL4743B, 1PL4744B, 1PL4748B, IPL4749B; instrument loop 70-63A, cables 1PV288 and 1PH2236. The listed cables are located on elevation 714, 45 feet above the lower elevation.
- 2. In the common area on elevation 714, an interaction exists between two paths of cables for reactor coolant system (RCS) inventory control.
Path I Centrifugal charging pump (CCP) A-A, cables IPP550A, 1PP552A, IPP554A, IPP556A.
CCP A-A cooler fan and FCV-67-168, cables 1PL3001A, IPL3003A.
CCP A-A auxiliary tube oil pump, cables 1PL6145A, 1PL6148A.
Instrument loop 70-63A, cables 1PM2236, IPV288.
CCS pump A-A, cables 1PL4727A, 1PL4731A, IPL4732A.
CCS pump B-B, cables IPL4742B, 1PL4743B, 1PL47448, IPL4 748B, 1PL4749B.
I Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84067 Path II (continued)
CCP B-B, calbes IPP562B, 1PP564B, 1PP566B, 1PP568B.
CCP B-B cooler fan and FCV-67-170, cables 1PL3011B, 1PL30138.
CCP B-B auxiliary lube oil pump, cables 1PL6155B, IPL6156B, 1PL6152B.
Instrument loop 70-99A, cables IPV 386, 1PM2435.
CCS pump C-S, cables 1PL4735S, IPL4736S.
Pressurizer level loops68-339 (cable 1PV161),68-335 (cable 1PV13511) and 63-320 (cable iPV255111).
- 3. In the common area on elevation 714, the auxiliary control room, and the auxiliary instrument room, interactions exist between all three paths of letdown (RCS inventory control) .
Cables Common Area Aux Control Rm Aux Inst Rm Valve ECV-62-54 IV4414 1V4413 1V4411, IV4412, IV4413, IV4415 FCV-62-55 IV4320 IV4367 IV4369 FCV-62-56 1PV56 1PM133 1PM132,1PM133, IPM134
- 4. A fire in the corridor near the number six (6) stairway on elevation 690 could damage cables for the RCS makeup.
Valves FCV-63-41 (cable IV4798B) and FCV-63-42 (cable IV4830A).
- 5. In the common area on elevation 690, column A2-AS/T-U, and in the pipe gallery on elevation 690, column A3-A4/U-W.
both level control valves (LCV) for the volume control tank (VCT) interact. LCV-62-133 (cable IV2770B) and LCV-62-132 (cables IV2764A and IV2760A).
- 6. In 6900V shutdown board room 'A', all three paths that accomplish normal letdown isolation interact (RCS inventory control).
Path I FCV-62-69, cables IV4420A, IV4421A, IV4425A.
Path II FCV-62-70, cablos IV4432A, IV4433A, IV4437A.
Licensee Events' and Special Reports (continued)
LER DESCRIPTION'OF EVENT f
1-84067 Path III (c ntinued)' FCV-62-72. , cables IV4470A, IV4471 A, IV4477A FCV-62-73, cables IV4485A, IV4486A, IV4492A FCV-62-74, cables IV4500A,'1V4501A, IV4507A
-7. In 480V shutdown board room 182, interaction exists between both paths of centrifugal charging pumps (CCP).
Path I CCP A-A: cables IPP550A, 1PP552A, 1PP556A.
CCP A-A auxiliary lube oil pumps cables IPL6145A, 1PL6148A.
CCP A-A cooler fan and 1-FCV-67-168, and instrument loop 30-83: cable 1PL3003A.
Instrument loop 70-63A: cable 1PM2236.
Path II CCP B-Bt cable 1PP5648.
CCP B-B auxiliary lube oil pumpt cables 1PL6152B, 1PL6155B, 1PL6156B.
CCP B-B cooler fan and 1-FCV-67-170, and instrument loop 3-182 cables IPL3012B,1PL30138.
Instrument loop 70-99: cable 1PM2435.
- 8. In battery board room I, an interaction exists between all three paths of cables for RCS inventory- control.
Path I FCV-62-79: cables IV4420A, IV4421A Path II FCV-62-70s cables IV4433A, IV4432A Path III FCV-62-72: cables IV4470A, IV4471A FCV-62-73: cables IV4485A, IV4486A FCV-72-74: cables IV4500A, IV4501A
Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84067 9. In 6900V shutdown board room A, an interaction exists (continued) for both paths of CCPs.
Path I CCP A-A: cables IPP550A, 1PP552A, IPP553A, 1PP554A, IPP556A, IPP557A, 1PP555A CCP A-A auxiliary lube oil pump: cables 1PL6145A, iPL6146A, 1PL6147A, 1PL6148A CCP A-A cooler fan and FCV-67-168: cables 1PL3002A and IPL3003A CCP pump A-At cable 1PL4725A Instrument loop 70-63A cable 1PM2236 Path 11 CCP B-B cable 1PP564B CCP B-B auxiliary lube oil pump: cables 1PL61528, 1PL6155B, IPL6156B CCP B-B cooler fan and FCV-67-170: cable 1PL3013B CCS pump C-S cables 2PL4733B, 2PL4734B, 2PL4737B Instrument loop 70-99A cable 1PM2435
- 10. In 480V transformer room 1A, an interaction exists between both CCPs.
CCP A-A auxiliary lube oil pumps cable 1PL6149A CCP B-B auxiliary lube oil pumps cable 1PL6152B
- 11. In the common area and corridor of elevation 669, column Al-A14/S-T, ar. interaction exists between both paths of CCP.
Path I CCP A-At cables IPP550A, IPP552A CCP A-A auxiliary lube oil pumps cables IPL6145A, 1PL6149A CCP A-A sooler fans cables IPL3001A, IPL3003A, 1PL3004A FCV-67-168: cables IPL3001A, IPL3003A, IPL3004A Path II CCP B-B cables IPP562B, 1PP564B CCP B-B auxiliary lube oil puinpa cables IPL61528, 1PL6156B CCP B-B cooler fan and FCV-67-170 cables 1PL3011B, IPL3013B, IPL3014B 8-
Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84067 12. In 480V shutdoan board room 2A, interactions exist (continued) between the following equipment for RCS inventory:
CCP B (cables IPP568B, IPP566B,1PP562B), thermal barrier booster pump B (cables 1PL6134B, IPL6133B, 1PL6131B, 1PL6132B), CCP B auxiliary lube oil pump (cables IPL6153B, 1PL6154B), 1-FCV-63-5 (cable IV2335B control).
- 13. On elevations 714, 734, and 749, unit 2 initial reactivity control (reactor trip) cables interact with each other.
Elevation 714 - cables 2PS181B and 2PS184B interact with 2PS161A and 2PS164A.
Elevation 734 - cables 2PS181B, 2PS184B, 2B37B interact with 2PS161A, 2PS164A, 2B23A, and 2B36A.
Elevation 749 - cables 2PS181B, 2PS184B, 2B37B interact with 2PS161A, 2PS164A, 2B23B, and 2B36A.
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- 14. On elevations 714, 734, and 749, unit 1 initial reactivity control (reactor trip) cables interact with each other.
Elevation 714 - cables 1PS161B and IPS184B interact with 1PS161A and IPS164A.
Elevation 734 - cables IPS181B, IPS184B, 1B24B and IB37B interact with 1PS161A,1PS164A,1B23A, and 1B36A.
Elevation 749 - cables 1PS181B, 1PS184B, 1B24B. and 1B37B interact with IPS161A, IPS164A, 1B23A, and 1B36A.
- 15. In the 6900V shutdown board room 2B-B, cables for all the auxiliary feedwater pumps, the icyc1 control valves, ,
and the steam supply valves interact with each other.
Wide range indication cables for unit 2 also pass through this area. This equipment is for steam generator inventory control.
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- 16. On olevation 734 in the emergency gas treatment room, the following list of 'A' and 'B' train cables interact.
These are valves providing reactor coolant system inventory control.
Train 'A' FSV-68-394: cable 2V5681A and 2-FSV-68-397:
cable 2V5685A.
Train 'B' FCV-63-24: cable 2V4934, 2-FCV-63-174:
cable 2V5131, 2-FCV-74-2: cable 2V28403 and 2V2842B, 2-FSV-68-395: cabic 2V5661B, 2-FCV-62-56: cable 2 Pit 132, 2-FCV-62-55: cable 2V4371, 2-FCV-62-85:
l cable 2V4461.
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ELicensee Events and Special' Reports (continued)
~LER' -DESCRIPTION OF EVENT
- 1-84067. 17. In 6900V shutdown board _ room 'B' train, the following-(continued) -list of train 'A' cables interact with 'B' train. This equipment is associated with reactor coolant system inventory control'.
Train 'A' CCP A-A room cooler: cable 2PL3003A
, ,e CCP'A-A' auxiliary lube oil pump: cables 2PL6145A, 2PL6148A, 2PL6149A l 2-FCV-62-98: cable 2V2235A l 2-FCV-67-146: cables 2V2422A, 2V2423A, 2V2425A 2-LCV-62-135: cable 2V2073A
- _ 2-FCV-63-7
- cable 2V2329A 2-FCV-74-1: cable 2V2787A
[
2-FSV-68-394: cable 2V5681A l 2-FSV-68-397: cable 2V5685A l Thermal barrier booster pump A-A: cabla 2PL6123A l 2-FCV-70-143: cable 2V2295A l
- 18. Less than 20-foot separation exists between the 2A2-A 480V shutdown board room (train 'A') and the listed train 'B' cables.
l l 2 Pit 2435 (LI-80-99A), 2PL3013B (CCP B-B room cooler),
l 2PL6152B, 2PL6155B~(CCP B-B auxiliary' lube oil pump),
i 2PP562B, 2PPS63, 2PP5648, 7PP5665, 2PP568B (CCP B-B),
2V2243B (2-FCV-62-99), 2PM108, 2PM110 (2-FCV-62-93),-
, 2V21038 (2-LCV-62-136), 2V23235 (2-LCV-62-6), 2V26908 L (2-FCV-63-25), 2V2706B (2-FCV-63-40), 2V47938, 2V4794B (2-FCV-63-41), 2V49305, 2V49315, 2V4934B (2-FCV-63-24),
l 2V28478 (2-FCV-74-2), 2V56615 (2-FSV-68-395) , 2PM134 l (2-FCV-62-56) , 2V4411 (2-FCV-62-54) , 2V4412 (2-FCV-62-54) ,
l 2V4367, 2V4368 (2-FCV-62-55), 2PL6131B, 2PL61338, 2PL6134B I
(RCP TBBP B-B), 2V44578, 2V4458B (2-FCV-62-85) .
- 19. The following train 'A' equipment interacts with train 'B' l equipment in the 480V shutdown board '182-5 at elevation j 734 in auxiliary building.
l Train 'A' cables: 2PL612A, 2PP550A, 2PP552A, 2PP554A, 2PP556A.- ,
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Train 'B' cables: 2PL4737B. 2V23218.
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-Licensee Events and Special Reports (continued) s - LER' LDESCRIPTION OF EVENT
. 'l-84067 20. Interactions exist between the following 'A' train (continued) cables such that a fire could prevent isolation of
. normal letdown path. Cables involved are: 2V4423A, 2V4425A (2-FCV-62-69), 2V4435A, 2V4437A (2-FCV-62-70),
2V4473A, 2V4477A. (2-FCV-62-72) , 2V4488A, 2V4492A .
(2-FCV-62-73), and 2V4503A, 2V4509A (2-FCV-62-74) .
- 21. Interactions exist between shutdown logic panels 1A-A and 2A-A and the 'B' train cables listed below.
l Cables involved: IB251I, 1B3011, B3411, B16II, 2B26II, 2B311I, 2B32II, -1B2611, '1B311V,1PP765B,1PP753B,1PP7628.
4 22.
Interactions exist between 'A' and 'B' train cables located in the auxiliary building on elevation 734 in the 480V' shutdown board room 2A2-A. A fire at this location could take out all 480V 'A' train shutdown boards and all 480V 'B' train shutdown boards. Cables involved are:
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! Train.'A' - 2PP756A, 2PP750A, 2B11III, 2B161V, 2B121, j 2B17I, 2PL4978A, 2PL4913A, 2PL4925A, 2PL4958A, 2PL5055A, 2PL5056A, 2PL5057A,,2PL505SA 2PP759A, 2PL4935A, 2PL4938A.
Train 'B' - 2PP483B, 2PP4808, PP377B, PP477B, 2PP460B, PP738, 2PL4914B, 2B251V, 2B301V, 2B26II, 2B31II.
- 23. Interactions exist.such that a fire could cause the loss
- i
- i. Cables involved: IB121II, 1B171II, 1B111, 1B161 interface l with B13IV, 1P L4901B , 1B 261V, 1B 311V , 1PL5075B , 1PL5076B ,
i 1PL5078B , 1PL4982B , 1PL4985B , 1PL4965B , 1PL4926B , ' 1B251I ,
1B301I, 1PP762B, IPP7533, 1PL4942B, 1PL50678, IPL5068B, i
1PL5069B, 1PL50708, 1PL50638, 1PL5064B, 1PL5065B, 1PL5066B,.and 480V shutdown board 1B1-B.
- 24. Interactions exist such that a fire could cause the loss of 'A' and 'B' train 480V shutdown boards. These inter-actions 'are located in auxiliary building on ' elevation '
734 in 480V shutdown board room 1B2-B. Cables involved are:
Train 'A' - B30I, PP373A, PP374A, PP468A, PP469A, 2PP478A, i
1PL4900A, PP378A, 1PP475A,'1PP478A, 1PP454A, 2PP498A, p 2PP454A , 1B11I , 1B16I ,1B12111, IB17III, 1PP493, 1PP496, j 1PP498, 2PP493, 2PP496, '2PP498.
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t Licensee Events and Special Reports (continued)
LER' DESCRIPTION OF EVENT 1-84067 .
Train 'B' - IPL4901B, 1PL4914B, 1PL4945B, 1PP765B,
.(continued) 1PL4966B , 1PP 753B , 1PP762B , 1PL5071B , 1PL5072B ,
1PL5073B , 1PL5074B , 1PL4965B , 1B 25II , 1B 30II , B131V ,
~ 1PL5067B , 1PL5068B , 1PL5069B , IP L5070B , 1PL5075B ,
1P L5076B , 1PL4985, . 1PL5077B , 1PL5078B ; equipment : 'C-A vent board 1B1-B, 480V shutdown board 1B2-B.
- 25. Interactions between 'A' and 'B' train cables exist in auxiliary building on elevation 714 at A8-Q. A fire at this location could cause the loss of breaker control to breakers.1922,'1914, 1924, and-loss of operation for ACB 1912. (This could. prevent the diesel generators from being put on line.) . Cables involved: 1PP475A,~2PP454A, 2PP475A, 1PP460B, 1PP480B, 2PP480B.
- 26. Interactions exist between 'A' and 'B' train cables!and a fire could render both 'A' and 'B' train 480V shutdown boards inoperable. Cables involved are:
Train 'A' - 2PL4975A, 2PP750A, 2PL4957A, 2B11III, 2B121, 2PL5051A, 2PL5052A, 2PL5053A, 2PL5054A, 2PL5059A, 2PL5060A, 2PL5061A, 2PL5062A, 2PP756A, 2PL5047A, 2PL5048A, 2PL5049A, 2PL5050A, '2B17I, 2B161II.
Train 'B- 2B251V, 2B30IV, 2B2611, 2B31II.
- 27. Interactions exist between 'A' train 6.9 kV shutdown
~ board and 'B' train component cables. Cables involved:
2PL4733B, 2PL4734B, 2PL4737B (CCS pump C-S), and 2V2321B (2-FCV-63-6) .
x 28.
Interactions exist betweenz'A'-and 'B' train cables which could prevent
- isolation of' excess letdown line.
' Cables involved: . 2V4411', 2V4412,'2V4414'(2-FCV-62-54),
2V4367, 2V4368, 2V,4370 -(2-FCV-62-55), . and 2PM133, 2PM134
- (2-FCV-62-56) . v ,
29.. Interactions exist between control cables, 'A' and 'B,'
train, for operating auxiliary feedwater terry turbine.
. Cables involved are 1SG220A and 1SG221B.
Y r
1
p.
Licensee Events and Special Reports (continued)
LER DESCRIP' TION OF EVENT 1-84067 _ ' 30. Interactions exist'in auxiliary building at elevation (continued) ~ 714 between 'A' and 'B' train cables. Cables involved are:
4 Train ' A' - 2PL4725A, - 2PL4726A,- 2PL4727A, 2PL4731A, 2PL4732A, 2V5685A, 2V5690A,.2V5691A, 2V4595A, 2V5696A.
- Train 'B' - 2PL4738B,-2PL4739B,:2PL4742B, 2PL4734B,
. 2PL4744B, 2PL4748B, 2PL47498, 2V5676B, 2V5670A, 2V5671B, 2V5675B.
- 31. Interactions exist'between 'A' and 'B' train cables .:ba the auxiliary building at elevation 741. These cables are part of the RCS inventory control safety function. Cables involved are:
Train ' A' '- 2PL3001A, 2PL3003A, 2PL4725A, 2PL4726A, 2PL4727A, 2PL4731A, 2PL4732A, 2PL6145A, 2PL6148A,-2PL6149A, 2PM10411, 2PM1046, 2PM1053, 2PM1086III, 2PP550A, 2PP551, 2PP552A, 2PP554A', 2PP555A,.2PP556A, 2V161, 2V25?III, 2V2235A, 2V2422A, 2V2423A, 2V2424A, 2V2425A, 2V2073A, 2V2329A, 2V4828A, 2V4830A, 2PV43A, 2V2787A, 2V4423A, 2V4435A, 2V4473A, 2V4468A, 2V4503A, 2V5680A,'2V5681A, 2V5685A, 2V5690A, 2V5691A, 2V5695A, 2V5696A, 2PL6120A, 2PL6122A, 2PL6123A, 2V2295A, 2V4448A, 2V4596.
Train 'B' - 2PL30llB, 2PL3013B, 2PL4738B, 2PL4739B, 2PL4742B, 2PL4743B, 2PL4744B, 2PL4748B, 2PL4749B, 2PL6152B, 2PL6155B, 2PL6156B, 2PM1070II, 2PM1076K, 2PV135II,-2PV386, 2PP562B, 2PP563, 2PP564B, 2PP566B, 2PP568B, 2V2243,-2PM108, 2PM110, 2PM111, 2PM112, 2PM115, 2PV50, 2V2103B, 2V2321B, 2V2323B, 2V2690B, 2V2706B, 2V4796B, 2V4798B, 2V4933, 2V5130, 2V5131, 2PV163B, 2V2847B, 2V5660B, 2V5661B, 2V5670B, 2V5673B, 2V5675B, 2V5676B, 2PM134, 2PV56, 2V4370, 2V4414, 2PL6131B, 2PL6134B, 2PL6133B, 2V5743B, 2V5745B, 2PV56.
- 32. An interaction exists between nuclear source range detector NC-31 (cables 2PV111, 13I, 2NM211, 23I, 261, 27I, 281, 29I, 301) and source range detector NC-32 (cables 2PV131II, 2PV133II, 207II, 208II,- 209II, 21011). This interaction is located at A8-812/Q-X in the auxiliary-building on elevation 714.
- 33. At various locations in the auxiliary building on elevations 669, 690, 714, and 734, the floors have'not been sealed to provide a fire barrier between elevations (ventilation duct penetrations, conduit / pipe penetrations / stairways).
E
- e v
' Licensee Events and Special Reports (continued)
LER : DESCRIPTION OF EVENT 1-84067 34. An interaction exists between nuclear source range (continued) detector NC-310 and NC-320. Cables involved are:
1PV11I, 1PV131, 1NH261, 27I, 28I,-291, 301, and 1NM201II, 203II,_20611, 207II, 208II, 209II, 210II, -
1PV131II, and 1PV133II. These cables are located on elevation 714 of the auxiliary building.
- 35. Interactions exist betweenA' and 'B' train cables and components in the auxiliary building on elevation ,
690. Cables involved are:
Train 'A' -'2PL3001A, 3003A, 4725A, 4726A, 2731A, 4739A, 6145A, 6149A, 2PM1041I, 1046, 1053, 1086III, 2PP550A, 2PP552A, 2V2232A, 2233A,'2070A, 2071A, 2326A, 2327A, 2680A,.2681A, 2695A, 2696A, 4830A, 2292A, 2293A.
Train 'B' 2PL3011B, 3013B, 4739B, 4742B, 4743B, 4748B, 6152B,'6156B, 2PM1070II, 1076K, 2PP562B, 2PP564B,-
2V2240B, 2PM108,1111, 112, 115, 2V2100B, 2101B, 2320B, 2321B, 2687B, 2688B, 2703B, 2704B, 4798B, 5745B.
Common (train 'A' and 'B'): 1PL4735S, 4736S.
- 36. Interactions exist between 'A' and 'B' train cables in the auxiliary building on elevation 669. Cables involved are:
Train 'A' -'2PL3001A, 3003A, 3004A, 3006A, 6145A, 6149A, 2PM1053, 2PP550A and 552A.
Train 'B' - 2PL3011B, 3013B, 3014B, 3016B, 6152B, 6156B, 2PM108, 111, 112, 115, 1076K, 2PP562B, 564B, 2V2321B.
'37. Interactions exist between 'A' train and 'B' train cables in the auxiliary building on elevation 690 in the unit 2 penetration room. Cables involved are:
Train 'A' - 2V2292A, 2326A, 2680A, 2695A, 2232A, 2293A, 2681A, 2696A, 2233A, 4830A, 2327A,-2070A, 2071A.
Train 'B' - 2V2100B, 2101B.
- 38. Interactions exist between 'A' train and.'B' train cables in the auxiliary building on elevation 690 in the unit 2 pipe chase. Cables involved are:
Train 'A' - 2V2327A, 2326A,'4830A, 2293A,_2681A, 2696A, ;
2233A, 2292A, 2680A, 2695A, 2232A.
Train 'B' - 2V2320B, 2688B,-2704B, 2687B, 2703B, 2240B, 4798B, 5745B, 2242B, 2241B.. .
i
. i n,
- Licensee Events and Special Reports (continued)
~
LER DESCRIPTION OF.EVENTe An interact' ion exists between' cables for diesel
~
1-84067 39.
. (continued) generators 1B and 2A from the 480V shutdown boards to the 480V diesel-auxiliary board. Cables 1PL4982B and 4985B interact with cables ~2PL4975A and 4978A.
These cables are separated by greater than thirty-one (31) feet; however, no suppression-exists in the large area of concern. These cables are-located in the-auxiliary building on. elevation 749, column A8 near the ceiling of the refuel. floor, t
- 40. Interactions exist between cables for diesel generators lA and 2A (cables 1PP477A and 2PP477A) and for diesel
- - generators 1B.and 2B (cables 1PP482B and 2PP482B) in the auxiliary control room on elevation 734 of the auxiliary building. These cables provide indication (red and green light) of breaker position.
- 41. Cables contained in cable trays PO-A, PN-A, and PM-A.
pass through the auxiliary. control room and. interact with cables in cable tray PA-B. These cables are involved
. with the normal to auxiliary transfer of control from the main control room to the auxiliary control room of both redundant divisions and cables associated with vital battery board II and III loads. The cables and cable trays are located in the auxiliary control room on elevation 734 of the auxiliary building.
- 42. General interactions exist between onsite electrical I supply cables 1PP478, 2PP478A, 373A, 374A, 378A,_468A,' .
469A, 498A, 1PP475A, 2PP454A, 475A, 1PP454A, and most
{ -- of the 'A' train and 'B' train reactor coolant system inventory control cables. These cables are located on elevation 714 in the auxiliary building at A36A8 and Q to R.
- 43. Potential interactions exist in the auxiliary building
. on elevations 669, 690, and 714 in a twenty-foot area around the elevator, stairwell, and hatch between 'A'
- and 'B' train reactor. coolant system inventory control
- cables. Cables involved are
Train 'A' - 2PL6120A, 6122A, 2V5691A, 5696A.
- Train 'B' - 2PMll5, 2V2321B, 2V2240B, 2241B, 2320B, 2687B, 2688B, 2703B, 2704B, 4798B, 2P26131B, 2PL6133B,.
f 2V5671B, 5676B.
4 i
s a
y en - T-----
- w , . - - - , - ,. -w,e m -c- w - * - - - , -&-, e
Licensee Events and Special Reports (continued)
LER DESCRIPTION OF EVENT 1-84067- 44. Potential ~ interactions exist in the auxiliary building
' on elevations 669, 690, 714, and the unit 2 stairwell (continued) between 'A' and 'B' train reactor coolant system inventory control cables due to open areas between the floors. Cables involved are:
i Train ' A' - (Elevation 669) 2PL3001A, 6145A, 2PM1053, 2PP550A, 552A, (Elevation 690) 2PL4731A, 2PM10411, i 2PM1046, 2PM1053, (Elevation 714) 2PL4725A, 4726A, 4732A, 2PM1041I, 10861II, 2V2422A, 2423A, 2424A, 4830A, 2PV43A, 2V5690A, 5691A, 5695A, 5696A.
-1
- 45. Interactions exist within.the onsite electrical supply l- in the vital battery board room I on elevation-734 of the auxiliary building. The following EQUIPMENT: 125 volt vital BBI, 120 volt vital instrument panel I; CABLES:
.B15I, 2B12I, 2B17I, 2PVII, B10I, 1PVII, 1 Bill, 1B161, B5SI, B561, B57I, B30I, B57I, 1B12III, IB17III; and CONDUIT: _2B151, lB2, 1B15III interact with the following
-CABLES: IB261V,~1B311V, 1B25II, 1B30II, and CONDUIT: 1B2911, 1B34IV. This interaction could cause the loss of both unit 1 ' A' and 'B' train 480V shutdown boards and cable'lPL4914B associated with the normal f feed to battery charger II.
- 46. An interaction' exists in the' common area on elevation 690 of the auxiliary building between 'B' train ERCW cables and 'A' train CCP-cables.- Cables involved are:
^
ERCW 'B' Train - 1PP700B, 712B,- 2PP700B, 712B.
CCP 'A' Train - 1PP550A, 1PP552A, 1PL6145A, 6149A, 3001A, 3003A, 4725A, 4726A, 4731A.
An interaction also' exists between path 1 and path 2
{' for the CCPs in this same area. Cables involved are:
. 1 Path 1 - 1PL6149A.
., Path 2 - 1PP564B, 1PL6152B, 6156B,,30llB, 3013B, 4739A,.
4735S, 4736S, 2PL4739B.
The action statement for technical specification 3.7.12 was ,
i satisfied by utilizing fire watches in the affected areas that
. were established by other Appendix R commitments. This action I
included the establishment of a roving fire watch in areas 4 with fire detection and a dedicated fire watch in areas without fire detection.
u
, pi j
~
' Licensee Events and'Special Reports (continued) s LER ' DESCRIPTION OF EVENT.
-. 1-84068: An inadvertent relay' actuation caused an auxiliary building ventilation isolation (ABI) to occur at 1228 CST on November 4, 1984,*while unit 1 was in mode 1 and unit 2
-was in mode 6. Investigation revealed that a relay was jarred while-personnel were working inside a . cabinet in the main control room. The relay.was found to be not fully
-seated in its tenminal block. .This relay.gives a high radiation signal for the spent-fuel pool radiation monitor, which causes
- an'ABI. Radiation monitors were checked and no abnormal levels or spikes were found. The ABI was reset and the system
~
' returned to normal. Radiation. levels were not above normal during.this time.
I l-84069 During performance of surveillance instruction (SI).9,
[ " Actuation of--Automatic Valves.via SI Signal for Non-testable.
- Boric Acid and ECCS Flow Path Valves," essential raw cooling '
water-(ERCW) valve'TCV-67-66 to' diesel generator (D/G) 2A-A
.w as found in'its normally closed position, but-its thermal overload was not reset. This ERCW valve ('A' train) supplies cooling water for D/G.2A-A'and would not have opened if i required. The' thermal overload was found 'not reset' from a previous SI (251.2).. The thermal overload was reset, and the
- valve operated corre'ctly. SI-251;2'wa's revised to check the
~
thermal overloads before the actual = performance of the SI, but the revised SI had not yet been. issued to personnel to use.
i All other overloads.that had been tested per SI-251.2 before it-was revised were verified to have reset, properly.
! 2-84019 Surveillance instruction. (SI) 260.2, " BIT Cold -Leg Injection .
Flow Balance, Pump Performance -and Check Valve Test," is performed to satisfy technical specification surveillance requirement 4.5.2.h.2.a for the centrifugal charging pumps (CCP).
The requirement basically states that with one charging pump i running, the sum'of'the injection line flow rates, excluding the highest flow rate, must be greater than or equal to 346 gpm. ,
2A-A CCP was-tested on October 17,~s1984, with the "as found" flow rate found to be 336 gpm. -The system throttle valves ~
were repositioned in order to obtain the proper flow rate of 346 gpm. The'new throttle positions for the valves were documented and the valves then returned to their "as found"
!. position to allow for testing the 2B-B CCP in its "as found" condition. With the valves returned to their original positions,
- the 2B-B CCP was tested on October 18, 1984, and.found to have a simulated "as found" flow rate of 331 gpm. The system valves were repositioned to obtain the required 346 gpm flow; rate-
- j. required flow rate was still met.
i l-( wg g y 9 --vr-' - = *Trv ^+*W -
- - * *e v ' - - - w r br- - - - -e *e' t -" - W"'w=-v '-
Licensee-Events and Special Reports (continued)
Diesel Generator Failure Reports There were no' diesel generator failure reports transmitted during the month.
Special Reports The following special report was transmitted during the month.
SPECIAL REPORT NUMBER DESCRIPTION 84-07 Mechanical penetration door A75 in the auxiliary building (elevation 690) was breached for a period greater than seven (7) days. The penetration was breached by Public Safety at 1945 CST on October 4, 1984, and was not closed out until 1225 CST on October 12, 1984.
Offsite Dose Calculation Manual Changes Changes in the Sequoyah Nuclear Plant Offsite Dose Calculation Manual (ODCM) are described in Appendix A in accordance with Sequoyah technical specification 6.14.2.
p-r
, OPERATING DATA REPORT DOCKET NO. 50-327 DATE DECEMBER 6, 1984 COMPLETED BY M. G. EDDINGS TELEPHONE (615) 870-6248
-OPERATING STATUS
- 1. UNIT
- NAME:1SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES:
- 2. REPORT PERIOD: NOVEMBER 1984
- 3. : LICENSED THERMAL POWER (MWT): 3411.0 o4.-NAMEPLATE RATING (GROSS MWE): -1220.6
- 5. DESIGN ELECTRICAL-RATING.(NET MWE): 1148.0 6.7 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0
- 13. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:--
9..PbWER LEVEb TO WHICH RESTRICTkD IF ANY(NET MWhhI___-
10..REASbNS'FOR RESTRICTIbNS.IF ANY: z--
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD- 720.00 8040.00 29977.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.00 5462.10 19903.66
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE 720.00 5251.80 -19364.95
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS. THERMAL ENERGY GENERATED (MWH)- 2447365.21 16660552.28 62152402.58
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 831830.00 5494770.00 20873906.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 804641.00 5276711.00 20053639.00
- 19. UNIT SERVICE FACTOR 100.00- 65.32 64.60 t20. UNIT-AVAILABILITY FACTOR 100.00 65.32 64.60
,21.-UNIT CAPACITY FACTOR (USING MDC NET) 97.35 57.17- 58.27
~22. UNIT CAPACITY. FACTOR (USING DER NET) 97.35 57.17 58.27
- 23. UNIT FORCED OUTAGE RATE O.00 21.36 18.91
'24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE,'AND DURATION OF EACH):
l25. 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' SHUTDOWNS AND POWER REDUCTIONS ~ DOCKET NO. 50-327
. UNIT NAME Sequoyrh On'e DATE December 7,1984 .
. COMPLETED BY M. G. Eddings REPORT HONTH NOVEMBER 1984 TELEPHONE (615) 870-6248 q -
W O ,
Eq "8 e c ll t Licensee y Cause & Corrective No. Date 8, t $_ @ ] O g- Event g% 8% Action to p -E e g cy" Report ! g'8 gi Prevent Kecurrence
. $" $65 N* 8"
. 8 No shutdown or power reductions during the month.
4 L
7 1 2 3 -
4 -
Fr Forced -
Reason: . Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain)
- 1-Manual -for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry, Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Op.erational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source l
y; ,
AVERACE DAILY UNIT POWER LEVEL j , DOCKET No. 50-327 UNIT Sequoyah one
- DATE December 7, 1984
, COMPLETED BY, M. G. Eddings TELEPHONE (615) 870-6248 NONTH NOVEMBER 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
~(MWe-Net) (MWe-Net) 1 1096.3 17 . 1126.9 2 1090.6 13 1124.4 3 1092.5 19 1124.5 4 1092.0 20 1125.8 5 1096.6 21
~
11;!5.0 6 1085.8 22 112$.0 7 1108.2 23 1128.8 8 1106.0 24 1129.7 9 1106.'8 25 1128.8 10 1111.3 26 1122.5
~
11 1116.3 27 1127.3 1
12 1118.6 28 1128.2
. I 13 . 1121.5 29 1121.7 !
14 1121.0 '30 1119.3 15 1120.9 31 ,
16 , 1124.6 INSTRUCTIONS .
On this format,' list he average daily unit power level in HWe-Net for e's-h day in the reporting month. Compute to the nearest whole megawatt. .
, ,, (9/77)
(.
l
OPERATING DATA REPORT DOCKET NO. 50-328 DATE DECEMBER 7,1984 COMPLETED BY D.C.DUPREE TELEPHONE (615)S70-6248 OPERATING STATUS
.1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 2. REPORT PERIOD: NOVEMBER 1-30,1984
- 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 18 . 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)I$- __
_ _ _ . _- ____=- --___ ____- -
- 10. REASONS FOR RESTRICTIONS IF ANY:______ _________-----
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.00 8040.00 21937.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 6124.75 16485.82
- 13. REACTOR RESERVE SHUTDOWN HOURS 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.OO 74.48 73.58
- 20. UNIT AVAILABILITY FACTOR O.00 74.48 73.58
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 69.05 67.47
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 69.05 67.47
- 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 REPORT PERIOD, ESTIMATED DATE OF STARTUP:
____Deum@st_11L_LUL4 ________________________________ _____
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
i-
~
UNIT SHUTDOWNS AND POWER REDUCTIONS- DOCKET NO. 50-328 UNIT NAME Snquoyah Two'-
DATE December 7,1984 COMPLETED BY D. C. Dupree REPORT MONTH NOVEMBER 1984 TELEPHONE (615) 870-6248 e -
W O .
E7 "e0 c p tj Licensee Cause & Corrective No. Date i ty '8 % $ Event $% 8% Action to y 8j g f, y " Report ! g'8 g'8 Prevent Recurrence 5" $d5 N* "
8 13- 84/09/28 S 720.0 C 4 . Cycle 2 refueling outage continues.
i U$
i 4
I 2 3 -
4 -
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 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-Op.erational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source d
e
w ,
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Sequoyah Two
. DATE December 7,1984
, COMPLETED BY, D. C. Dupree TELEPHONE (615) 870-6248 HONTH N0'VEMBER 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
'(We-Net) (MWe-Net) 1 0 17 -
0 2 0 18 0 3 0 19 0 4 - 0 20 0 5 0 21 7 ~;. 0 6 0 22 .'O 7 0 23 0 8 0 24 0 s
- 0. 0 9 25 10 -
0 26 0 11 0 27 0 12 '0 28 0 13 - '0 29 0 14 0 ~30 0 15 0 31 16
. O t
~ .
INSTRUCTIONS ,
! On this format,, list ghe average daily unit power level in We-Net for each day in l the reporting month. ' Compute to the nearest whole megawatt .
l l , , (9/77)
(.
4 4
Plant Maintenance Summary The plant maintenance summary for significant maintenance items completed during the month of November 1984 are listed in the following order:
Construction Activities
, Electrical Maintenance Section Electrical Modification Section Instrument Maintenance Section Mechanical Maintenance Section U
4 Mechanical Modification Section i
1 f
1 j
Construction Activities November 1984 ECN L5503, 5111 - Office and Power Stores Facility The project is approximately 92 percent . completed. During the month, work continued on pulling cable, insuleting ductwork and piping, architectural painting, and drywall installation. Work was completed on the east entranceway, all fe.ns were installed, hydrostatic testing of fire protection piping was completed, and permanent power cable was pulled to the building. The installation of toilet fixtures, toilet tile work, and electrical connection of heat pumps and air handling units was started.
Also, installation of the drop ceiling has begun. Top floor (elevation 745) will be available for occupancy by December 31, 1984.
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-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.
ECN L6241 - Raise Yard Drainage Pond Skimmer Five Feet This modification is required to comply with EPA requirements and shall be completed by December 31, 1985. Preparations are being made to complete the work by December 31, 1985.
ECN L5599 - Fifth Vital Battery The project is approximately 65 percent-completed. The fifth vital battery board has been moved into the battery room through a hole cut in the concrete roof of the. battery room. The hole has been closed. New batteries have been installed in the room and are on charger. Installation of fire protection piping and HVAC fans continued. ' Electrical tie-ins to existing battery boards I and IV:have been completed. This modification is scheduled to be completed .by January 28, 1985.
ECN L5841 - Hot Machine Shop -
The project is 99 percent completed.
The Health Physics laboratory deconning machines, electric shop, snubber shop,.and hot machine shop are 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 when material and design drawings will be available.
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 the latter part of November to complete remaining two punchlist items (concrete louvers and nozzles).
PLANT MAINTENANCE SmefARY ,
- 00
- 17:51 1>11-04 ELECTRICAL MnINTEMA$CE temLY REPWT FOR WWEMER PAGE 1 of 10 '
iDATE.... GN900ENT . . . . FAIL 15tE DEBMIPTION...... CAUSE OF FAILL5tE. . . . . . . .. CORRECTIVE ACTION........ M.lG..
I 11-45-64 FCRN-309-J/9 INBPECT MANIPLLATOR CRAIE ND FAILURE PREYENTIE GREASED ADO INSPECTED A250009 El PER MI 9.3 MAINTANCE MANIPLLATOR CRANE AS i REttESTED !
i *
- 11-05-64 HTV-067-0152 REPLACE T E ftISSIls CAP W FAILURE YALYE NAS DEEN REPL. ACED A236521
-9 SCREWS (31 TE WIRIE WITH A LIMITORetE. ALL COYER OF T E ELECTRODYE CAP SCREWS ARE IN PLACE OPERATER
,11-05-84 0{tet-031-0338 SDRIT Donel BOARD ROOM ANTI-CYCLE TIfER BAD REPLACED ANTI-CYCLE A294298
-4 CHILLER PACNAGE B-B WILL TITER, CIECNED FOR PROPER ;
leT START FR(NI (MIT OPERATION Ale RETLRIED 10 ColmML ROOM A8 OESIGED SERVICE i C-1,C-2,C-3,C-4 RELAYS STAY DEERI2ED. ANTI CYCLE TIVER LIGHT STAYS ON EYEN LAEN CfB91tE981R PACNAGE IS RLSetDC 11-05-64 2-CON -363-2RM3 FLEX ColOUIT 2A-2RM-384A NO FAILURE REPAIRED SEAL TIGHT A290001 SH ON RAD IWBlITOR FITTIIC BY TIGHTHING
, i 2-E-90-106 IS LDOGE ADO CODCUIT Il#IDE OF FITTDC ,
]y PtLLED OUT (F TE KAL j
TIGHT FITTDG ,
i11-09-94 2-SCCTB-030-01 AUXILIAltY BUILDING CIRCUIT OREANER FAILED SI REPLACED Al91EC10R MODEL A121953 04 GEN.StPPLY FAN 24 WILL 275.2 ON AUXILIARY L1 RECECNED Ale RETLNttED W T OPERATE BUILDING GEN. StPPLY FAN TO SERVICE l 24 i11-09-94 1-XFD-313-090:s FIRE DAl9ER WILL DDT OPOl BAD FUBE LIle( IN FIltE REICYED OLD FUSE LINK A296278 SO 90 AIR FLDU WAS DAl9ER FROM FIRE DAMPER Als GETTDC TietElGN TO 125 INSTALLED EU OE CIECNED l YCLT VITAL BATTBtY BOARD FOR Pit 0PER OPERATION Ale l
ROINI 1 RETLNtED TO SERVICE ,
11-08-44 2-FCV-090-0116 VALYE WILL leT IPEN WI1H D9ROPGt AIR PitE98LNtE OPDED AIR RECtLATOR TO A29441 NADO SWITCH (PERATION IN PROPER POSITION 11AIN CIBfTROL R0lNI Ntit-090-0225 LOOSE .AR9ER WIRE WAS LOOSE JJtpER WIRE TIGHTDED LOOSE WIRE ON A WJ568 l11-09-94 l CAUSDC RAD fEMITOR WT JLR9ER 80TTON SIDE OF l
PLANT MAINTENANCE
SUMMARY
!00:17:51 12-11-84 ELECTRICAL MAINTENUCE ISBmLY REPWT FtR WWEISER PAGE 2 of 10
- OATE.... (IN900ENT. . . . . FAILLRE DESCRIPTION...... CAUBE OF FAIL 1RE. . . . . . . . . CORRECTIVE ACTION........ PR.lG..
TO ISG. ATE URLVE SUITCH OF CON 0-FCV-14-360 (R A40RL. HI DEMItERLIZER EFFLLENT R4 RAD ISEN RAOIATION MONITOR PERFORfED SI 281 MONITOR TRIPS AND RETURIED TO SERVICE
,11-0844 0-Cf9-311-0156 AIR ColOITI(DER IN LOAD CONTROL OUT OF ADJUSTE0 LOAD CONTROL A294759
' CorpUTER CONTROL ROOM ADJJSTfENT WILL DET NEEP ROOM TEl9ERTLRE AT 70 DEGREES i11-0944 N3R-3114126 CONTROL BUILDIls CHILLER NO PROBLEM FULSD AT THIS FLDCTIONALLY C6ECNED A121520 I A-A IS teT IERNIE TRIPS TIfE FOIAC le PROBLEM RETLRIED
&#EN STARTED TO SERVICE
,11-1444 2-MTRB467-012 IAtILE TIMISC AUKILIARY YALUE WAS OUT OF TIfE RETIPED YALUE Afm UAS A294369 9-9 BUILDIE AIR Sl# PLY LESS THAN .02 SEC LEADER ISII.ATI M VALVE FOR SI 166.4 LOCAL TILE 59 SEC. REMOTE TIfE MAS
. l$' 53 IEC. FRJBT BE WITHIN 1 j SEC. TO PA88 SI 11-14-84 0-CON-363 ColGUIT ON 000R A56 IS NO FAILURE PREVENTIVE REPLACED PIPE SUPPORT A291467 RIPPED OFF MAINTANCE i
11-14-94 1-29-061-0193 OPEN (RED) LIMIT NOT 95T NNOWN AT THIS TIfE NO PROBLEM FOU W A286875 i GOIts OUT l#EN GLYCOL RETLRN 19tLATIt31 UALUE POSITI M SWITCH IS CLDBED l11-15-64 O C R-311-0141 CtplTROL ROOM CHILLER NO PR00LEft FDL90 DECNED CHILLBt PACKAGE A295175 PACNAGE 5-8 TRIPS ON LOW NO WORK PERFORfE0 SL89 OIL LEVEL 11-1544 2-FSU-030-0056 LIMIT SWITCH IS teT DIRTY CONTACTS CLEAfED DIRTY CONTACTS A247213 4 IleICATIls A GREEN LIGHT WORKIM PROPERLY AT THIS ON LolER CONTAIleENT TIRE i
EXHAUBT 190LATIM YALVE 11-15-64 2-FCV-062-0022 ACTUATOR ARM ON L0lER ACTUATOR ARM SENT ADJUSTED LIMIT ACTUATOR A285830 CONTAlleENT EXHAUST ARM ISOLATION YALYE LIMIT
PLANT MAINTENANCE
SUMMARY
i08:17:51 12-11-84 ELECTRICAL MINTENAICE lEBmLY REPWT FtR leWEMER PAK 3 of 10 lDATE.... GH80 DENT. . . . . FAILARE DESCRIPTION...... CAUSE OF FAILtRE......... CORRECTIVE ACTION........ 19.08..
SUITCH UA8 BENT CAUBils SUITCH NOT TO RELEASE ,
,11-15-84 2'fCV-067-0095 INBTALL "T" DRAIN IN TE le FAILURE PREVENTIVE INSTALLED "T" CRAIN AS A297854
-A ELECTRIC ICTOR DG MINTAICE REttESTED BELLAT TIE LSEST POINT TO REPLACE TIE EXISTIls '
SOLIO PIPE PLIE IN LGER
- - CMTAlltENT 2C C0(LER DISCNARE ISELATIM UALUE INBIDE CMTAIl#ENT 11-15-84 2fCV-074-0002 IISTALL GREASE RELIF SC FAILURE PREUENTIVE INSTALLED "T" DRAIN Ale 4297862 j 4 UALVE IN T E ELECTRIC MINTAfCE GREASE RELIEF AS fBTOR WERATOR IGUBIlt REGESTED AIS DSTALL "T" DRAIN IN TIE ELECTRIC ICTOR DS BELL AT TIE LOREST POINT I h DF TIE Rift SYSTEM j y ISOLATION VALVE 11-15-84 2-FCV-067-0111 IIETALL "T" DRAIN IN TE NO FAILURE PREVENTIVE INSTALLED "T" DRAIN AS A297856 4 ELECTRIC IWTER DG SELL MINTA6CE REGESTED l AT TE LGEST POINT TO REPLACE TE EXISTDC SOLIO PIPE PLIE IN LOIER CMTADRENT D Com.ER DISCNARGE UALVE DEIDE I CMTAIl8ENT 11-15-64 MTV-067-4103 INSTALL "T" DRAIN IN TE PC FAILURE PREVENTIVE INSTALLED "T" DRAIN AS A297855 4 ELECTRIC ISTOR DO BELL MINTAICE REetESTED AT TE LOREST POINT TO REPLACE T E EXISTING
. SILIO PIPE PLIE IN LOIER CONTADGENT g rnm re DISCHARGE VALUE 2-FCV-067-0298 INSTALL "T" ORAIN IN TE le FAILURE PREVENTIE INSTALLED "T" DRAIN AS A297860
!11-15-84 4 ELECTRIC feTGt De BELL MINTANCE REGLESTED AT TE L0lEST POINT TO j REPLACE T E 9 OLIO PIPE
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1 5'LANT MAINTENANCE SU)DfARY i08:17:51 12-11-84 ELECTRICAL MINTEMAfEE lEBmLY REPWT FGt NDUEMER PAE 5 of 10 <
DATE.... (IN900ENT. . . . . FAILWE DESCRIPTI(36...... cal 2E OF FAILtRE. . . . . . . . . CMRECTIVE ACTION........ 19.08..
NO FAILURE PREUENTIVE ItETALLED "T" PLUG DRAIN A297861 l11-1 M 2-FCV-0744001 INSTALL GREASE RELIEF Ale GREASE RG.IF7 UALUE
- -A YALVE IN T E ELECTRI7 MINTADCE i FST(R (DERATIR letB1DC AS RE0 TESTED '
AfG IISTALL "T" DRAIN IN TE ELECTRIC IEmR DO l
- DELL AT TE LOLEET POINT I
j (F RlR SYSTEM IS(R.ATION i UALUE CIRCUIT BREANER TLNttED TURED CIRCUIT BREANER (M A297868 11-15-84 2-IGN-2E-2518 HYOROGEN IGNITERS ON B 252 TRAIN WILL IST DERCIZE OFF #18 CECNED AP98 ON i BREANER LEFT ON CIRCUIT BREANER TtRIED TURED CIRCUIl BREANER 9A A297869
'11-15-84 2-IGN-22-2358 NYOROGEN IGNITERS ON '
2M TRAIN "A" WILL DDT (FF DECNED Af98 ON SitEANER EERCIZE LEFT ON l '
0-PS-39-0057 PRES 9L5tE SWITCN SHOWilG PRESSIRE SWITCN NOT SET RESET PRESSIRE SWITDES A29468 >
11-15-64 CO2 EADER IS CHARGED TO le WIRES LIFTED
& Lime OIL PtRIFIER ROON T' (OUT IT ISN'T)
DISABGEMLE TE (PPER 60 FAILURE PREYENTIVE DISAGEMLED LPPER A297864 i11-15-84 2-HTRO-068 BEARIIC, NADE REPAIRS 10 l BEARIts (N4 RCP ISTOR #3 MINTAICE '
FOR INBPECTION Ale ItEPAIR BRONE OIL LIES ,
l 0F TIE OIL LIFT SYSTEN REASSDELED LPPER SEARIlG OECNED FOR OIL LEANS. ,
l REFILLED LPPER OIL POT l WITH SND-824 OIL Ale
! RETINttED TO SERVICE 2-NTCK-234-012 CitEEN LIGNT ON CONTR(n.1ER BAD CONTROLLDt REPLACED CONTROLLER Ale A245474 11-15-84 6-S OF TE DEAT TRACE CIRCUIT DECNED OPERATION OF EAT 3
I TtERN08 TAT WILL leT COE TRACE PLUG IN TYPE ON Colmt0 List j _
0449 -074 PAINT StPPORT ASSEM LY OF De FAILURE PREVENTIVE SADO BLASTED AfD PAINTED A230632 .i l11-15-84 SPACE Rigt MR9 AfD fBTOR MINTANCE AS REQUESTED +
i IN MINTAfCE SEP WITH l PROTECTIYE C04TIls (LEVEL ID
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1 PLANT MAINTENANCE
SUMMARY
i00:17:51 12-11-04 ELECTRICAL NAINTD4AfCE IEBmLY REptRT FtR MM79ER PM 7 of 10 -
- DATE.... (IB90leff. . . . . FAIL 1RC DESCRIPTIEN...... CAIM
- OF FAILARE. . . . . . . . . CORRECTIYE ACTION........ FR.le... ;
! mACEED: 84 148 FAILTY FILTER CARD WAS REPAIRED FILTER CARD I BAD (M "B" N2 REXXNSDER CECNED Ale RETURDED TD f j SERVICE i
111-19-04 04CTD-313-06 PLACE AR9ER BETLEEN 60 FAILURE PERFORN TI-71 PLACED J#9Elt FOR TEST A102361 0 rERnINALS rox AND 7D3 TO wTDt TEST aRoER uAS 4 PItEYENT BATTERY ROON II REMOUED f l
I EXNAtBT FAN FRtNI I
STtpPDE ISEN PRESERIZIIC FAN IS i STtpPED LNED Ftm l PERFORMAhCE F TI-71 FTER TEST REPME JL29ER ON THIS f9t 2 i
2-808-201-00-A 4 0 YOLT StJTD0684 90ARD BLop!i FUEES PREBASLE REPLACED FUBES ON A2943P6 l 11-21-04
! 2A2-A YtLTIETER SELECTION TA18E FRENI REGE IN poler PETERING TRANIFolttER
! SWITCH DOES teT DGICATE TESTED FOR OPERATION ADO
! VOLTAGE SETuEEN 8 AND C TRREETIVE ACTION l PNAGES RO U CED FUBES ON l . PETDtIt3 TRAMBFORIER :
i
$' TESTED FOR OPERATION Ale l RETLRED TO SERVICE l 11-21-44 1-ffTRA-072-001 OIL LEYEL LOW IN DSOARD le FAILuftE ADDED OIL TD Pit 0PDt LEYEL A293531 j 0 BEARING OF CONTAINtIENT USIE STO-1 APPROK 4 OZ
- SPRAY Pt#9 IEm R i i 11-21-44 2fCV-04F0001 CAMST GET GAS SAf9LE PREESLRIZBt GAS 1911ATIEW STRolcED UALUE SFUERAL A000003 ;
FRtm PRE 98tRI2ER CAS UALYE WILL IST OPEN TIfEB 60 PROBLEM FtXAO ;
i 1911.ATION URLUE IN ICT l
9ArpLE ROEM i 11-21-64 4-FCV-063-0071 1" FLEX CEBSUIT Dit01EN ON De FAILilRE SAFETY NAZARD REPAIRED ON A PREVIOUB IR A287705 i BOTH DOS F SIS DEIX l UALUE ISELATIGI EADER FLSI ISELATIEM UALYE
, 11-21-44 2-ONRC-0P9-404/ If8PECT BYPASS BREAIER 60 FAILURE (PBt DCIDENT VISUALLY DePECIED BY A24P937 29-T "B" NAftlAL Q.08DE AT TLRitEY PODif) TWiMAN SMITH le PRtBLBf IECHANIWI FtB POBBISLE FotAC AT THIS TIfE BEARDE DAMAGE (R BUWfils l
i ___ _ __ ___ _ _ _ _ _ ___ _ __ __ _ __ __ __ ___ _. __
i PLANT MAINTENANCE
SUMMARY
l 08:17:51 12-11-04 ELECTRICAL MAINTDWEE IWmR.Y REPWT Fim WWUSER PM S of 10
!OATE.... (3900 GIT. . . . . FAIumE ' r
- IPTI(M. . . . . . CAU K OF FAIURE......... CORRECTIYE ACTION........ 19t.le. .
f ESP (RT BRADIET FAILARE 11-21-04 2WHl-061 ET TIE DEFROBT TIfERS TO De FAILURE LEAK RATE TEST RESET DEFROST TIfERS A8 A296157 T E IR REGUIRED POSITION REGLESTED l
AS LISTED IN SI 156 i APPDOIX E RR TIE C(BITADRefT INTEERATED
! LEAK RATE TEST 11-21-44 1-NTCK-23N REPAIR lEAT TRA(E ON BA le FAILURE PREMENT CLEA6ED MR9 leuSDS AfG A291464 4
F TRA05'ER PLR91H ADO FREEZDE REIMTALLED lEAT TRACE GI t j 15-8 IEAT TRACE CIRCUIT PLRDS 1AA Ate 188 '
90 Ate & REMIVEL'l CIRCUITS 87P,878,90p,908 j
11-21-44 1-4.T-0D-4053 DECK lEAT TRACE ON RUBT NO FAILURE PREWENT lEAT TRACE WAS CEDED A279383 .
LEVEL TRA0METTER SDK FREEZIlE AfD IS MLLDE PRtpER LDES TO ME F ITS Af98 ptALIls PR(FER Af98 i
l 11-21-44 1-LT-0E-0050 DECK EAT TRACE ON RUBT 90 FAILURE PitEWENT lEAT TRACE MA3 QED (E0 A279361 !
j LEVEL TRA05MITTER SEME FREEZDG MO IS PLLLUS PittpER .;
ArpS i u LDES TO IEE F ITS '
l i PLLLDE PRipER AIDS l
< 11-21-04 1-LT-063-0046 DECK EAT TRACE (W RIST le FAILURE PREUDIT lEAT TRACE DEDED ABC B A279359 LEWEL TRAfSIITTER M FREEZIM PLLLIls PROPER Arps '
i l LIES TO SEE F ITS I MA.LDE PROPER Af98 l
'11-21-04 1-LT-0G 0049 DECK IEAT TRACE ON RUBT 95 FAILURE PREWENT DEAT TRACE WAS QED (ED A279360 i
LEYEL TRApSETTER SDK FREEZDE Ale IS PLLLDE PROPER d 4
LIBES TO ME F ITS ArpS MLLDE PR(DER Af9S j l
!11-21-04 1-LT-00-0051 DECK IEAT TRACE C4 Rl5T le FAILUE PREWENT EAT TRACE WAS CEDED A279381 LENEL TRAletITTER IB M FREEZDC AfD IS PLLLDC PR(NER LDES TO ME F ITS Arps MLLDE PRipER Af9S i
i 11-21-94 1-LT-0G 0052 DECK IEAT TRACE (M RIST le FAILURE PREMENT lEAT TRACE WAS QEDED A279382
! LEYEL TRAlW RTTER M M FREEZDG Ale IS PLLLUS PR(NER
! LDES TO SEE F ITS Af98 l
- . . - - . __ _-_ .- . - - - - . , - - . - . . - - -_ - - - . - _ _ _ _ . - - . - . -. =-
PLANT MAINTENANCE
SUMMARY
00:17:51 12 11-94 ELIETRICAL MnINTDIADEE FDmLY REPWT HR ISGSER N E 9 of 10 DATE.... GN900GE. . . . . FAILARE DESERIPTIW...... CALBE OF FAIL 12E......... COMECTIVE ACTION... ..... Igt.le. .
MAllts PRWER Af9S 1
11-21-94 2-NTCM-234-012 DEFECTIVE RED LIGNT IN IG FAILURE REPLACED CONTROLLER A345&3 ,
1-9 CIDfTRIX.LER (F DEAT TRACE TIERISBTAT IN PN1 CYCS-Al A12 Ale U 11-21-04 2-fffRS-0&-018 UALUE IS ALL TE MAY LIMITS OUT (F ADJJSTleft. CLEAIED CONTACTS, ADJUSTS A2WF54 1 CL M D, LIMIT SUITCN CIBfTACTS DIRTY ON NIEN LIMIT SUITCN, RNCTION IlGICATE IT IS TIGOTTLED P88 BAN STUM SEAL YALUE ADO WORKING i BYN 88 UALUE PCU- M -191 PROPDtLY AT THIS TIfE 11-21-44 2-HTCM-234-223 CIRCUIT 229 A READDC 0.0 SLolet FUSES IN CtBffRE.LER REPLACED RIBES IN A232750 '
i M Af98 taEN TERIESTAT IS OF TIERMOSTAT (36 EAT CONTROLLER a
l CALLDE RR EAT TRACE ICE Ct3 M M4IN 1 -DRAIN LIDE CIRCUIT 229A :
l 11-21-94 0-TC-23NMap CUC ELECTRICAL EAT TRACE CONTROLLER CUT OF ltESET CONTROLLER 468 TO A2B21& l j TEf9ERTLRE CONTansasu gg ADAISTIENT 170 DEEREES F. SECGIGARY ;
PADEL A4-1 DGICATES 150 CONTRE.S SET AT 200 ;
i
, twen85# F. nsrnense DEEREES F.
i u DOICATES IREATBt TNAN T 200 '2-ist F.
i
- 11-21-44 6-lGR-142 PAINT NYDRAILIC SIRBOERS 95 FAILURE pitEWENTIVE PAINTED AS REGUFSTED A285139 IN WRESER SUNF IERVICE fl4INTAICE BUILDDE 11-26-94 2 NTCK-234 DETALL EAT TitACE le FAILURE PitEWENTIVE RETAPED lEAT TRACE TAPE A297879
- CIRCUITS tl4INTADCE AS PER DSTRUCTED (M ,
l 405,406,408,409,410,412 FRESH UATDt LIE S
- GN Tm resD unTet SEMBE d
LDES ,
- 11-26-94 2-XS-013 ItE!WWE FIRE Ale SLOE le FAILUltE It99UED SM0llE DETECTOR A24996 DETECTER CaeUITS AfD XX-13-1994,XX-13-1990 Apis ,
DISC 30ECT CABLES FR0ff TB-13-1994 REDETALLED i ABOUWE RCP IUTER 113 IN SfDE DETECTOR AIO j REACTOR SUI'.DDC IA4IT 2 PGtFORtED SI 234.7 a '
l 11-26-44 6-TC-234 0035- CENTRG.LER REETS AT 20 TIERfeCUPLE WIRES rannasn REVERSED LEADS TO PROPER A231826 S DEEREES F. (31 CYC ENT Plt IN "T" C0Dem.ET POLARITY. CONTR&lER
l PLANT MAINTENANCE
SUMMARY
l 40:17:51 12-11-94 ELECTRICAL MAINTDWM:E PEBmt v REptRT FM WWEMER PAE10 of 10 CAtBE OF FAILLME......... COINtECTIVE ACTION........ fR.fC..
lOATE.... GB90fefT. . . . . FAILARE DEBERIPTIG4...... d I B3>-1 UITH SET POINT 145 WORKIIC Pit 0PERLY AT THIS nnzmt T!fE 11-M44 0-TC-2344404 munra DRIFTIls ON ENT LUG EDI CGfTRG.LER BAD REPLACED LUG ON A23996
- TB 9ERTLRE m CONTROU.ER l
!11-2744 0-OR-3114126 DWECT RELAYS AfD M FAILURE CLEAE D CONTACTS ON tmIN A29433 I CtpffACTORS FM BURED OR CONTACTOR Afe INSPECTED i
PITTED CONTACTS AIS LOOK RELAYS -
CGGECTIGS EDI GBITRG. ;
BUILDIE OGLLER "A" -
(
NffCK-234-040 MAT TRACE CABLE APPEARED 00 FAILURE REPAIRED SEVERED EAT A287727 l 11-27-64 l 7 TO DE DAMAGED BY OTER TRACE CASE
) CRAFT IRRKIls IN AREA l
11-27-64 1-TC-003 T/C CABLE 1PL1070 ON 1A-A BAD CASLE IN PDERATIG4 CABLE WAS REPAIRED ON A232626 H2 RECGSIIER WAS SAD 33 AISTER fR -
11- D 44 1-HTRh-083400 HVOROGEN RECDf3DetS FAILED SI 151 THIS WORK WILL SE A247188
, 1 TfERfECINILES DIA00E.81 C0f9LETED ON FRA26908 l
i y AfD 3 ARE GREATER THnN 50 i
i nnu mtAPART I
j11-3-04 1-4fTRS-067-013 AMKILIARY CGITACTS Of BAD INTEllLOO( CONTACTS REPLACED BAD INTBtLOCK A29762 -
4 ARROM HART CGITACTER WAS CONTACTS PDt MI 6.20 i
BAD CALSDE INIPER DEDED FOR PROPER
}
CIBffADDENT UENT OpetATION AfD SI 146.6' i
l DISCH4kE ISELATIIBt UALVE
! IST TO CLOK FRGt Hale j SUITCH IN MAIN CG4TREL
! RolNI 1
1-GENS-082-001 ItELAYS 42K AIS G52834 IN BAD RELAYS ItEPLACED SOTH ltELAYS A121921 l11-2D-94 1 4-A 14-A DIEEL GDERATER i CGITRG. CIRQlIT LOADS A69
] tat. DADS ERRATTICALLY i
! 71 records listed.
b Electrical Modification Section November 1984 DCR 1739 --VAACS Panel wiring has continued during this period.
DCR 2072 - Local DCR to Improve Reliability of Stud Tensioner Hoists Connectors did not arrive this period. Hoists were removed upon completion
'of refueling.
ECN 2768 -'RVLIS All work was completed during this period, s
ECN 2780 - Postaccident Sampling Facility All work was completed during this-period.
ECN 5194 - Iodine Monitors Work remaining consists of installation of door locks and new door frames.
ECN 5198 - Technical Support Center All scheduled work was completed during this period.
ECN 5640 - Deletion of PDIS 1-17 and 1-18 All unit 2 work was completed this period.
ECN 5645 - Steam Generator Blowdown All work was completed this period.
ECN 5712 - Evacuation Alarms Major cable pulls to valve rooms and unit 2 annulus were accomplished this period.
.ECN 5770 - High Range Radiation Monitor All work was completed this period.
ECN 5823 - Pressure Switch Replacement All work was completed this period.
4
> ' t ElectricalModificationbection-(continued)
LECN 5824~- Replacement of Valve Operators Allrequiredunit2andunitl0motoroperator~valveswerdreplace'dthis
-period.
ECN 5842 - Removal of PCV-3-122 and PCV-3-132 All' unit 2 work was compieted this period.
T.CN 5865'- Relocation of LA-77-129 All unit 2 work was completed this period.
ECN 5881 - Limit. Switch ~ Replacement All unit 2. work was completed this period.
ECN 5882 - Temperature Switch Replacement All work was completed this period.
ECN 5883 - Replacement of Various Instruments All unit 2 work was completed this period.
ECN 5884 - Replacement of Flow Transmitters All work was completed this' period.
ECN 5898 - Deletion of Seal-in Limit Switches All unit 2 work was completed this period.
-ECN 5970 - Replacement of Valve Operators All unit 2 work was completed this period.
ECN 5971 - Replacement of Valve Operators All unit 2 work was completed this period.-
ECN 6018- Installation of Space Heaters, Auxiliary Feedwater Pump Motors-All unit 2 work was completed this period.
ECN 6032 - Relocation of Hydrogen Analyzers All unit 2 work was completed this period.
.ECN'6053 -' Replacement of-Acoustic Monitor Charge Converters-All. work was completed this period.
Electrical Modification Section (continued)
E_CN'6055 - Fourth Wide Range Pressure Transmitter All outage work was completed this period. Nonoutage work continues.
ECN 6200 -' Relocation of Pressure Transmitters All unit 2 work was completed this period.
ECN 6204 - Installation of Fuses All unit 2 work was completed this period.
ECN 6207 - Conax Connectors All unit 2 work was completed this period.
Appendix R
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Work continues on the first five interacdions.
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- Instrument-Maintenance Section November 1984 Unit l'
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- 1. .During the month, several problems were encountered with pressurizer level channel-1-LT-68-320. uThe~ channel was declared' inoperable on
- November 3,1984, because it was reading higher 'than the other two channels. -It was determined .that -the reference leg condensate pot .
was not operating properly.--During the investigation, a ferrule type fitting on the sense line was found to be leaking. The pressurizer enclosure was entered, the root valve closed, and,the fitting replaced.
This repaired the leak, and the-channel was declared operable on November 10.. The channel went' high again.on November 12 and was declared inoperable. The condensate pot was backfilled and the channel
~ declared operable on. November'14. The channel drifted high again the
~
next day. :The pressurizer enclosure was entered on November 19, and-insulation was added to the sense line to the condensate pot. . Lines were inspected for leaks, but none were found. The channel was declared operable'and remained so until November 27 when it drifted-high. The channel was recorded for stability with the condensate pot dry and no perturbation wasffound. The~ condensate pot was backfilled and. declared operable on November 30. . The channel has been continuously' recorded' since, and no perturbation has occurred. Modifications to increase the line' size are planned to enhance-performance.of the' reference leg.
- 2. Pipe-break detection switches'for unit 1 auxiliary feedwater turbine-driven pump were disabled by Temporary-Alteration 1-84-713-3 on'.
November 1~, 1984. This was-the result of a Justification for Continued Operation Evaluation performed by'the Office of Engineering. The unit 2 switches.were replaced with environmentally qualifie'd switches and relocated
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to_the_ auxiliary building from.the valve rooms during this current refueling outage on unit 2. . The unit'l switches will remain out of service until'a similar modification can:be performed.
- 3. During the monthly calibration of the UHI level switches, all switches were found within~ technical specification tolerance.-
14 . The P-250 process computer was declared inoperable three times during the month on November 6,' November 14,'and November 29,'1984. 1 Common problems are. parity errors andlp'ower supplyfglitches. The-computer was restarted and returned to service without appreciable down time.
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Instrument Maintenance Section (continued)
Unit 2'
- l. Response time testing and refueling calibrations were completed.
Modification for installation of the Technical Support Center, RVLIS, new postaccident radiation monitors, and harsh environment instruments to meet 10 CFR 50.49 requirements have been completed. Other work completed during the refueling outage was to replace source and intermediate range detectors for the NIS system. The remete shutdown monitoring source range detector was also replaced. Two of the four.
containment sump level transmitters, 2-LT-63-176 and 2-LT-63-178, were upgraded to a double 0 ring model to improve reliability.
- 2. During the-monthly calibration of the UHI level switches, 2-LS-87-22 was found outside technical specification tolerance. -Valve 2-LCV-87-24 was found out of tolerance during the refueling outage response time surveillance testing. Maintenance was performed, and the valve retested successfully.
Other work is shown on the attached list.
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' INSTRtfENT MAINTEM,ADEE MONTtB.Y EM1ARY 06-W4' PLANT MAINTENANCE
SUMMARY
Page 1 of 4 y
PR.CWF U FlMC SYS ADORESS. DATE.... DESCRIPTION..................................... CORRECTIVE ACTI0N.......................
A118790 0 PS -032 62 11/19/84 0-PS-032-62, CALIBRATE SET POINT FOR "A" TRAIN SWITCH OUT OF CALIB. RECALIB. SWITCH
. CarFRESS08 START.
A230536 2 FT 001 3A 11/02/84 2-FT-001-5A.RECALIBRATE TRANSMITTER TFE TRANSMITTER WAS GJT OF CALIB. TE _ _.
TRANSMITTER WAS RECALIB.
A230537 2 FT 001 38 11/05/84 2-FT-001-38,RECALIBRATE TRANSMITTER TFE TRANSMITTER WAS GJT OF CALIB.THE TRANSMITTER WAS RECALIB.
A230538 2 FT 001 10A 11/02/84 2-FT-001-10A,RECALIBRATE TRANSMITTER TFE TRAN3MITTER WAS GJT OF CALIB. TE TRANSMITTER WAS RECALIB.
- - A230539 2 FT 001 108 11/05/84 2-FT-001-108,RECALIBRATE TRANSMITTER TFE TRANSMITTER WAS GJT OF CALIB. TE ,
TRANSMITTER WAS RECALIB. *
, A230540 2 FT 001 21A 11/02/84 2-FT-001-21A,RECALIBRATE TRANSMITTER THE TRAN3MITTER WAS GJT OF CALIB. THE i TRANSMITTER WAS RECALIB.~
A230541 2 FT 001 218 11/05/84 2-FT-001-21E,RECALIBRATE TRANSMITTER TFE TRANSMITTER WAS GJT OF CALIB. TE TRANSMITTER WAS RECALIB.
A230542 2 FT 001 28A 11/02/84 2-FT-001-28A,RECALIBRATE TRANSMITTER TFE TRANSMITTER WAS GJT OF CALIB. TE TRANSMITTER WAS OUT F CAL.J.
j A230544 2 FT 001 288 11/05/84 2-FT-001-288,RECALIBRATE TRANSMITTER THE TRAN3MITTER WAS GJT OF CALIB. TE
- TRANSMITTER WAS DUT T CALIB. >
! A233454 2 FT 003 155A 11/12/84 2-FT-003-155A DtTI TO ERRATIC FEASURErENTS DLRING THE TRANSMITTER WAS GJT OF TOLERANCE.
! CAV. VENTURI TEST, PMT-531811243 CALIB. OF THIS RECALIB. PER SI-97 4 ENTIRE LOOP IS REGJIRED INCLLX)IIC ALL y C0rF0ENTS(FT,FM,I TO I,ETC)
A282245 2 PDS 065 80C/D 11/07/84 2-PDS-065-80C/D. SWITCH C LED DOES NOT LIGHT WDEN THE DIOCE WAS DAMAGE 0. A NEW LIGHT BISTABLE TRIPS EMITTING DIODE WAS Il6TALLE0 A282246 2 FIC 046 57 11/13/84 2-FIC-046-57,0UTPUT IleICATOR IS NOT OPERATING TFE SERVO MOTOR WAS CEFECTIVE. MOTOR WAS PROPERLY REPLACED.
A28334B 2 PS 003 1384 11/08/84 2-PS-003-138A, SENSING LIFE FOR 2-PS-3-138A IS TFE ASSOCIATED FITTIDGS WERE FOUte LEAKING AT FITTING BELOW TE PS LOOSE.TFE FITTINGS WERE TIGHTEED ADE)
THE DRAIN VLV WAS CFECKED FOR PROPER
- l. OPERATION.
l A283633 1 PS 003 165A/B 11/02/84 1-PS-003-165A/B,IlNIBIT FUNCTION OF NOFE. LIFTED WIRES PER TACF
- 1-PS-3-165A/B BY LIFTING WIRE 4SF3 IN
- 1-L-11A,TB112,T8 A283635 1 PS 003 160A/B 11/02/841-PS-003-160A/B,IblilBIT FUNCTION OF NO FAILURE. LIFTED WIRE PER TACF 1-PS-3-160A/B BY LIFTING WIRE 1SF3 IN i 1-L-118.TB112,T8 l A285798 2 Lfl 003 156A 11/05/84 2-1.Ft-003-156A,I/P WILL NOT CALIBRATE OR REPEAT THE CONVERTER WAS DArmGED. TE CONVERTER i
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WAS REPLACED. I A286812 2 TCV 061 71 11/21/84 2-TCV-061-71 DOES NOT CONTROL TErp. PROPERLY ICE WAS COLLECTING ON VLV. ICE WAS
A286963 2 LT 003 173 11/06/84 2-LT-003-173,0UTPUT FLUCTUATING THE TRANSMITTER WAS DETERMINED TO BE
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, INSTRUENT'MAINTENAICE FENTM.Y SE2flARY -12 W -94 PN FIAINTENANCE' SUM)fARY Page 2 of 4
. CENF P9t.CorF U RMC SYS ADDRESS. DATE. . . . DESCRIPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . ..
FAULTY.THE TRANSt1ITTER WAS REPLACED A294763. 2 E 092 5001 11/15/84 2-XE-092-5: ^1, REPLACE S0tRCE RANGE DETECTOR INTERf1EDIATE RANGE DETECTCR INOPERABLE.
REDLACED 8 CALIB. DETECTOR 8 DRAERS _ _h A29664 2E 092 5002 11/15/84 2-XE-092-5002, REPLACE INTERFEDIATE RAICE INTERflEDIATE RANGE DETECTOR DETECTOR INOPERABLE. REPLACED & CALIB. DETECTOR &
DRAUER A29&70 2 FM 072 13A 11/13/84 2-FFI-072-13A.CIECK FOR PROPER OPERATI(N OF fl0DIFIER WAS OUT OF 04.IB.110DIFIER WAS FIODIFIER; APPE#iS TO HAVE ND GJTPUT. RECALIB.
A294773 2 191 092 50000 11/15/84 2-Xft-092-50C3D,2ERO ADJUST WILL NOT PEET CALIB. ZERO POT FAULTY.REpuEED POT RECALIB. ,
TOLERANCE CRMr2 BALL ATTACED. PER 94.3 $
A294957 2 LCV 062 118 11/14/84 2-LCV-062-110, INVESTIGATE AM RESOLVE PROBLEFIS SOLENDID FAULTY.REPUCED SOLENDID WITH ULV OPERATION A294962 2 LS 077 411B/D,011/01/84 2-LS-077-411B/D,0,D D,D D ,CECK CALIBRATION (F BISTABLES DUT OF CAL. RECALIB. BISTABLES BOTH SIDES OF DUAL BISTABLE PER INST. CAL. CARDS 24 records listed. .
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. Itt3TRifENT lt4INTENAICE 110NTILY SIMIARY C0r ,
W PLANT-MIINTENANCE
SUMMARY
Page 3 of 4 f5t2.... U RAC SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . . . . . . . . . .. . . . . . . . . . .
A285285 2 R1 068 396A 11/27/84 2-Fil-068-396A.CEO( LOOP CAL. PER IrlI-68 POER TRANSIS10RS 8 THE TRANSISTOR EAT
. SIE WERE FALLTY. TRANSISTORS 8 TE HEAT SIl4( UERE REPLACED _ _
A294858 2 FT 063 9'1C 11/28/84 2-FT-063-91C. REPAIR POER SIPPLY 8 TERE WAS A FAULTY CIRCUIT BOWID ON THE CALIB. TRANSrlITTER-Rift Pf9 A-A POER SUPPLY Z THE TRANSrtITTER WAS OUT OF CALIB. TE CIRCUIT BOARO IMS REPLACED 8 TE TRANSrlITTER WAS RECALI8.
, .2 records listed. ,
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- t l f I- Il6TRtfENT*MAINTEMAKE MONTILY SLft1ARY 12-06-84 PLANTMAikbNANCE"SUMMAnT Page 4 of 4 COnp F5t. Col 9 U RSC SYS ADDRESS. DATE. . . . DESCRIPTION. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION . . . .. . . . . . . . . . . . . . . . . . .
A293585 1 FE 063 75 11/15/841-FE-063-75, uIu FLOW ELEMENT IN PIPE CHASE NOT SQUARE R000 MODULE OUT OF CALIB.
. SHOWING FLOW WEN PERFORMING SI-128. THIS IS FOR RECALIC. MODULE. ,
SI-1298128. -
l A294205 2 FS 030 95 11/01/84 2-FS-030-95, ALARM COPES IN ON "LO FLOW" WEN ALL BLOCI(E0 PITOT- TUBE. IEPLACED TUBE.
l UPPER C019ARTMENT COOLERS ARE RlN4ING A298738 2 FM 070 170 11/11/84 2-FM-070-170,CALIB. Se ROOT 110DlA.E F0l#0 OUT W SQUARE ROOT MODULE OUT OF CALIB.
TOLERANCE LAiILE PERFORMING LR11220. RECALIB. f1000LE.
3 records listed. ,
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w Mechanical Maintenance Section
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November 198h Common -
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1.' In order to eliminate cutting each time'it became clogged, a spool piece was installed o'n the CDWE drain line.
- 3. Pressurizer safety valves were sent to Wylie Laboratories on November _1,1984. ' Steam testing was completed by November 22, and all . valves passed.
Unit 1
- 1. There were several steam leaks involving 1-PIPE-5,1-PIPE-6,1-FSV-5-94 and 1-FCV-1-98. All leaks were-fixed by November 5 by installing a new box on system 6 -and by reinjecting Furmanite into two other boxes. ,
- 2. Assisted Instrumentation in stopping a leak in instrument line 1-LT-68-320 to avoid shutting down the unit by repairing leaks and-installing insulation. The line was backfilled on November 30 and was shown'to be operable.
Unit 2
- 1. Set the head on the reactor on November 1, 1984.
- 2. Completed sleeving on CCS heat exchanger.
- 3. Completed sleeving on moisture separator reheaters.
- 4. Stud machining on the number four steam generator was completed by November 5.
- 5. Sludge lancing on the steam generators was completed by November 12.
- 6. Dog bone seals completed on all three condensers on November 5.
- 7. Cleaning and neolubing of the seal table thimble tubes were completed after questionable fittings were proven functional. ,
- 8. Ice weighing was completed.
- 9. The air compressor for the containment integrated leak rate testing-
.(CILRT) was repaired by replacing a gasket and the blower shaft.
Mechanical Maintenance Section (continued)
- 10. Problems filling for the sweep and' vent on November 23 due to a galled-up BIT bypass isolation valve (63-647). ,The 1-inch valve was replaced with a 3/4-inch valve.
- 11. Check valve 6-324 had bindibg inside. Removal of the operator did not solve the problem. Vendor modifications were completed, followed by a functional test which revealed no more binding.
- 12. 'The Gorman Rupp auxiliary diesel sump pump in the turbine building has a cracked block and was sent out on November 30 for repair or replacement.
- 13. During maintenance on the reactor coolant pumps, a' pin on the number four pump was found to be sliding out. The pin was removed for inspection, at which time it was discovered that the retaining clip was. missing. On pumps two, three, and four, the number two seal housing was removed and machined due to wear. The lower motor bearing on pump number four was found not to be centered in the housing.
The pumps were completed by November 30.
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.Mechanica1' Modification Section
-November 1984 ECN 2768 - RVLIS
~ All work'is completed..except the postmodification tests which will be
. done during startup.' ,
.. . SI-112, ECN 5773, Pressurizer Work, ECN 6196 All hangers are completed that are required for the single lift of the
- relief valves.
~ NUREG 0588 RELATED WORK ECN 6231 --Pipe Rerout'es All. work is completed except minor painting-touchup and insulation.
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= ECN 6200 - Main Steam Pressure' Switches
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The relocation was completed for unit 2. ,
ECN 5883 - Auxiliary Feedwater Pressure
- Switches The' auxiliary feedwater pressure switch relocation was completed for unit 2.
ECN 5457 - Solenoid Replacement ,
Solenoid replacement was completed for unit 2.
ECN 5895 - Solenoid Replacement
- Solenoid replacement was completed for unit 2.
ECN 5024 - Steam Generator Wet Layup
. All mechanical work and postmodification. tests were completed. Some insulation and paint work remains.
ECN 2780 - Postaccident Sampling All work except painting was1 completed. Postmodification tests are to be performed during startup.
ECN 5842 - Cavitating Venturi All work except painting was completed. The' final postmodification tests
~
will.be performed during startup.
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s Mechanical _ Modification Section (continued)
ECN 5939 - MFWPT Condenser Retubing MFWPT retubing was completed except for some minor insulation work.
ECN 5713 - Paul Monroe Snubber Monorail The Paul Monroe snubber monorail was completed.
ECN 5743 - Steam Generator Platforms and Ladders The steam generator access platforms were completed.
DCR 1729 - MSR Doghouse HVAC The top-mounted return fans were installed. Some wall-mounted dampers remain to be installed. Work will continue after the outage.
ECN 6243 - Penetration X87 The work was completed during this period.
ECN 6206 - CST B Painting CST B was completed, and the tank was returned to service.
ECN 5009 - ERCW to CCP 2B Crossover The supply / return piping to both the oil cooler and room cooler was changed out from carbon steel piping to stainless steel piping.
ECN 6256, 6257, 6262 - Turbine Building Side Performance Improvement Modifications The turbine building secondary performance improvement modifications were completed.
ECN 6263 - Feedwater Hangers These hangers were modified to address anchorage problems to the concrete.
DCR 1822, 1847 - Turbine Building Chemical Modification The turbine building chemical modification was completed.
ECN 5787 - Extraction Steam Line Supports Extraction steam line supports were installed to address vibration problems.
l Mechanical Modification Section (continued)
ECN 6001 - Fire Protection Isolation Valves
- Fire protection' isolation valves were installed along with related hangers.
ECN 6004 Stiffeners for various embedded plates were installed to address overloading problems.
ECN 5657 Isolation valves'for the MSR sightglasses were installed.
ECN 5889 Platforms for access in the valve room were installed.
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Page 1 of 6 APPENDIX A Sequoyah Nuclear Plant ODCK Changes
.Chanee 1 DESCRIPTION OF CHANGE The isotope list for monthly liquid dose calculations is expanded from 11 co 23 isotopes. Changes appear on pages 21, 22, and 23.
A';ALYSIS OR EVALUATION JUSTIFYING CHANGE The list was expanded when the monthly dose calculation was put on an 13:1 PC, replacing the previously used program on the HP 97 calculator.
Ihis lowers the need to change isotopes periodically to ensure the conservativeness of the dose. .
EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION This change will have no effect on calculated quarterly doses or setpcine determinations. It will raise the calculated monthly dose.
Change 2 DESCRIPTION OF CHANGE ,
The thyroid was added as a critical organ considered for the fish ingestion pathway. The change is reflected on pages 21 and 22.
ANALYSIS OR EVALUATION JUSTIFYING CHANGE The list of critical organs was expanded due to the expanded capability 4
of the IBM PC ODCM over the HP 97 ODCM program. This eliminates the need to periodically change the organs considered. ,
EVALUATION OF ACCURACY OF DOSE CALCULATION OR SETPOINT DETERMINATION 1 Ihis change will have no effect on calculated quarterly doses or setpoint determinations. It w'ill raise the calculated monthly dose.
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- APPENDIX A Page 2 of 6 SEQUOYAH NUCLEAR PLANT OITSITE DOSE CALCULATION MANUAL !,
EFFECTIVE PAGE LISTING REVISION.Il Page Revision TOC 1 through TOC 2 Revision 11 1 through 2 Revision 6 3 Revision 9 4 Original 5 Revision 3 6 Revision 4 7 Revision 8 8 through 9 Revision 5 10 Original 11 Revis' ion 5 12 throuth 13 Revision 9 14 Revision 7 15 Revision 9 15a Revision 9 16 Revision 9 16a Revision 8 Table 1.1 (2 pages) Revision 4 Tabic 1.2 (2 pages) Original Table 1.3 (8 pages) Revision 4 Table 1.4 Revision 9 Table 1.4A (removed from document) Revision 9 Table .- Revision 4 Tables 1.6 and 1.7 Revision 5 Table 1.8 Original Figures 3.1 and 1.2 Original Figure 1.3 Revision 3 17 Original 18 Revision 2 19 Revision 7.
20 Revision 6 21 Revision 11 22 Revision 11 23 Revision 11 24 through 25 Revision 10 26 through 29 Revision 8 Table 2.1 (3 pages) Revision 7 Table 2.2 Revision 5 Table 2.3 (3 pages) Revision le Tabic 2.4 a-c Revision 5 30 Revision 8 Table 3.1-1 (4 pages) Revision 4 Table 3.1-2 Revision 8 Table 3.1-3 Revision 4 Table 3.2-1 (3 pages) -
Revision 4 Figure 3.1-1 through 3.1-2 Revision 4 Figure 3.1-3 Revision 8 Figure 3.1-4 through 3.1-5 Revision 4 Figure 3.1-6 through 3.1-7 Revision 8
' '$h g,Y g G Y.
APPENDIX A Page 3 of 6 Sequoyah Nuclear Plant Offsite-Dose Calculation Manual Dates of Revisions Original ODCM- 1/29/80*
Revision 1 4/15/80**
Revision 2 1/7/80**
Revision 3 ./3/80, 2/10/81
- s. 4/8/81 and 6/4/81**
11/22/82 (10/22/81,
- Revision-4 11/28/81 and 4/29/82*
Revision 5 10/21/82**
Revision 6 1/20/83**
Revision 7 3/23/83**
Revision 8 12/16/83**
Revision 9. 3/7/84**
Revision 10 4/24/84**
Revision 11 8/21/84**
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f.1 V
- RARC Meeting date
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APPENDIX A Page 4 of 6
- b. During any calendar year to $ 3 mrem to the total body and to 110 mres to any organ.
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To ensure ccepliance, cumulative dose calculations will be performed at least once per month according to the following methodology.
2.3.2 Hoc.thly Analysis Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose. If the projected dose exceeds the above limits, the methodology in Section 2.3.3 will be implemented.
The 23 nuclides (listed below) contribute more than 95 percent of the dose to the total body and the most critical organs for each pathway. The critical organs considered for fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver. The critical organs for water ingestion are the GIT, bone, and thyroid. 11
. H-3 Fe-55 Sr-89 Tc-99m Cs-134 Na-24 Fe-59 Sr-90 Ag-110m Cs-136 P-32 Co-58 Zr-95 Sb-124 Cs-137 Cr-51 Co-60 Nb-95 I-131 Mn-54 Zn-65 Mo-99 I-133 A conservative calculation of the monthly dose will be done according to the followine, procedure. F 4. rs t , the monthly operating raport containing the release data will be obtained and the activities 11 released of each of the above 23 radionuclides will be noted. This information will then be used in the following calculations.
2.3.2.1 Water Ingestion The dose to an individual from ingestion of water is described by the following equation.
23 11 (DCF)g)
- Ig ), rem (2.11)
D):
i=1 B
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h21-]) Revision 11 L
APPENDIX A Page 5 of 6 whsr2:
D. = dose for the j' organ from eleven radionuclides, rem J '
J = the organ of interest (bone,GI tract, thyroid and total body).
11
.95 = conservative correction factor, considering only 23 radionuclides.
DCF g =criticalingestiondosecommitmentfactorforthej' organ of adult or child from the i radionuclide rem /pCi, see attached as Table 2.1.
ch radionuclide by the Ig = monthly activity ingested of tghe i critical age group for the j organ, pCi.
I.. is described by lj I.. =A 'V..3 (30) ,pci (2.12, tj i Fd (7.34 x 10 ")
where:
th radionuclide during the month, A. = activity released of i pCi.
V.. : maximum individual's water consumption rate corresponding 13 to the age group selected for the critical DCF,3 above (Muit.: 20uo mL/d, Child: 1400 a.L/d; Regulatory Guide 1.109) 30 = days per month F = average river flow at Chickamauga Dam for the month (cubic feet per second) d = fraction of river flow available for dilution (1/5) 7.34x10t o = conversion from cubic feet per second to milliliters per month.
Considering the conversion factor from rem to ares ( x 108 ), the dose equation then becomes:
23 Dj = 2.15 x 10 ~6 (V x DCF)q.x A g, mrem (2.13) 11 F
i=1 g
C' Oj.
- Revision 11
(-22-)
APPENDIX A Page 6 of 6~
2.3.2.2 Fish Inmestion The dose to an individual from the consumption of fish is d geribed by Equation 2.11. In this case the activity ingested of the i radionuclide (I t)) is described by 7,, =
A t B; N g3 , pCi (2.14)
LJ Fd (7.34x1010) where:
A.* = activity released of i' radionuclide during the month, pCi th B. = effective fish concentration factor for the i radienuclide 1
pCi/g, see attached as Table 2.2.
pCi/mL
= amount of fish eaten monthly by maximum individual M) g corresponding to age group selected for the critical DCF above (Adult: 1750s, Child: 575g; Regulatory GuiN 1.109).
F = average river flow at Chickamauga Dam for month (cubic feet per second) d = fraction of river flow available for dilution (1/5) 7.34x1010 = conversion from cubic feet per second to milliliters per month.
The dose equation then becomes 23
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Ai O i (M DCF)g), mrem (2. W D) = 7.17x10 11 i=1 Considering the conversion factor from rem to arem.
2.3.2.3 Recreation The total body dose to an individual via the shoreline recreation ..
pathway is described by the following equation. For this calculation, the total dose is estimated based on a calculation for Co-58, co-60, Cs-134, and Cs-137. These four nuclides are expected to contribute.
, over 95 percent of the recreation dose.
4 D= 1 ((RDCF)g - (g 67], mrem (2.16) 0.95 8760 1=1 F
4 jg
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(-23h - Revision l'I
TENNESSEE VALLEY = AUTHORITY e j Sequoyah Nuclear Plant j Post Office Box 2000 '
-Soddy Daisy, Tennessee 37379 Nuclear Regulatory Commission Office of Management Information and Program-Control '
Washington, DC 20555 Gentlemen:
SEQUOYAH NUCLEAR PLANT - MONTHLY OPERATING REPORT - NOVEMBER 1984 Enclosed .is the November 1984 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY P.' R. Wallace Plant Manager Enclosure cc (Enclosure):
Director, Region'II 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, CA 30339 Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. A. Rubio Electric Power Research Institute P.n. Box 10412 Palo Alto, CA 94304 (1 copy)
Mr. R. C. Goodspeed MNC 461 Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230 (1. copy) f(/ b J.E24 An Equal Opporiunity Employer