ML20149H795
| ML20149H795 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/31/1988 |
| From: | Dupree D, Shawn Smith TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8802220111 | |
| Download: ML20149H795 (49) | |
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TENNESSEE VALLEY AUTHORITY i
l OFFICE OF NUCLEAR POWER I
SEQUOYAH #UCLEAR PIANT 1
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NONTHLY OPERATING REPORT
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TO THE i
WUCLEAR REGULATORY CONNISSION l
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JANUARY 1988 i
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I UNIT 1 i
DOCKET NUMBER 50 327 LICENSE NUMBER DPR 77 l
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UNIT 2 I
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LICENSE NUMBER DPR 79 i
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Submitted by:
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9802220111 990 31
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TABLE OF CONTENTS 1
1 Page I.
Operational Summary l
l Performance Summary 1
Significant Operational Events 1
Fuel Performance and Spent Fuel Storage capabilities 2
PORVs and Safety Valves Summary 2
Special Reports 2-3 Licensee Events 3-8 l
Offsite Dose Calculation Manual Changes 9
II. Operating Statistics l
l A.
NRC Reports Unit One Statistics 10 12 Unit Two Statistics 13 15 l
B.
TVA Reports Nuclear Plant Operating Statistics 16 Unit Outage and Availability 17 18 Reactor Histogram 19 III. Maintenance Summary l
Electrical Maintenance 20 21 l
Instrument Maintenance 22-27
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Mechanical Maintenance 28 31 Modifications 32 44
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CPERATIONAL
SUMMARY
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PERFORMANCE
SUMMARY
January 1988 l
The following summary describes the significant operational activities for the month of January.
In support of this summary, a chronological lot of significant events is included in this report.
The units remained in an administrative shutdown the entire month due to design control review, configuration control updating, and resolution of significant employee concerns. Outage-related maintenance and modifications are being performed.
Unit I has been off line 892 days.
Unit 2 has been off line 893 days.
Preparations are underway for unit 2 alignment and mode 4 verification.
SIGNIFICANT OPERATIONAL E'/ENTS i
Unit 1 I
Date Time Event 01/01/88 0001E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration t
control updating, and resolution of significant employee concerns continues.
01/31/88 2a00E The reactor war in mode 5.
ine administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
Unit ?
l Date Time Event 01/01/88 0001E The reactor was in mode 5.
The administrative shutdown due to design control review, configuration control updatir.g. and resolution of significant employee concerns continues.
Preparations are underway for system alignment for mode 4 shakedown.
01/31/8A 2a00E The reactor was in node 5.
The administrative shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
Preparations are underway for system alignment for mode 4 shakedown.
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FUEL PERFORMANCE Unit 1 k
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I The core average fuel exposure accumulated during January was O MWD /MTU with i
the total accumulated core averste fuel exposure of 0 MWD /MTU.
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Unit 2
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i The core average fuel esposure accumulated during Janusry was 0 MWD /MTU with l
i the total accumulated core average fuel esposure of 8097.51 MWD /MTU.
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EfENT FUEL PIT STORAGE CAPABILITIES
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I The total storage capability in the spent fuel pit (SFP) is 1.386. However.
there are five cell locations which are incapable of storing spent fuel.
Four locations (A10. All. A24 A25) are unavailable due to a suction I
j strainer conflict, and one location (A16) is unavailable due to an t
instrumentation confilet. Presently, there is a total of 348 spent fuel t
bundles stored in the SFP.
J Thus, the remaining storage capacity is 1.033.
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NRC conducted a records audit January 13-15, 1988, on all special nuclear natorial (SNM) with particular attention directed to the nonfuel SNM l
l Management Program.
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Because of past records and procedural violations on the nonfuel SKM Program i
that were imposed by NRC in October 1986. special emphasis was directed to j
review TVA's corrective actions. Having implemented the new procedure (TI-101) and assigned a new responsible section (Reactor Engineering) on February 1. 1987. NRC was appeased with all corrective actions and the overall nonfuel SNM Management Program.
Therefore, all three violations l
were closed out, j
since initial criticality on unit 1 on July 5. 1980, this was the initial multi-day NRC records audit conducted on any form of SNM. The final j
evaluation resulted in no discrepancies in the overall SNM Management Program at Sequoyah Nuclear Plant.
t FORVs AND SAFETY VA1.VES
SUMMARY
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No PORVs or safety valves were challenged in January 1988.
I SPECIAL, RgPORTS The following special reports were submitted to WRC in January 1988, i
88-01 On January 4 1988. fire doors A-71 and A-72 (to 2A-A and 28-8 containment spray heat enchanger rooms, elevation 690, ausiliary l
building) esteeded the seven-day limit allowed by TS LCO 3.F.12.
l This was deemed necessary to facilitate structural modifications betrg performed on the heat exchangers. Doors A-71 and A-?2 were restored to operable status on January 22. 1988.
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SPECIAL REPORTS (continued) 87 22 This revision provides a new completion date for the corrective Rev. I action for a fire barrier.
87 23 This revision updates door C-37 lockset failure and provides an Rev. 2 anticipated completion date for corrective action.
LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in January 1988.
Description of Event LER 1 8707a on December 22, 1987, it was identified that the SQN emergency procedures may not sufficiently address the required operator actions following a postulated LOCA during mode 4 operation.
Since the SQN TS require the BIT to be operable in modes 1 through 3 only, GOI-3, "Plant Shutdown from Minimum Load to Cold Shutdown " instructs plant operators to deenergize the BIT isolation valves following entry into mode 4 in order to preclude the possibility of a spurious SI signal causing an overpressurization of the RCS, Isols'lon of ttv 8!T also results in the isolation of the high head SI '<Jtem flow path required by LCO 3.5.3.
However LCO 3.5.3 allows realignment of the ECCS during modo a.
Further investigation has shown that emergency procedure E-0, "Reactor Trip or Safety Injection " requires the plant operators to verify that at least one train of high head SI la providing flow through the BIT, but it does not provide specific instructions for reenergleing and opening the SIT isolatica valves in the event of a LOCA.
In addition. E-0 does not provide specific guidance for the realignment of the RNR system from the decay heat removal mode to the ECCS mode.
Guidance for realignment of the RHR system is provided in several operating instructions, including SOIs, Gols, and A0!s.
The appropriate SQN instructions will be revised to provide specific details to the plant operators to reenergize and open the BIT isolation valves and realign the RNR system to the ECCS mode of operation following a mode 4 or mede 5 LOCA.
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POscription of_ Event
__LER 1-87078 On December 21, 1987, it was determined that a chemical addition to unit 1 RCS on November ?$. 1987, caused a dilution of the RCS boron concentration and subsequent positive reactivity change.
Since both trains of CREVS were inoperable at the time of the chemical addition, action statement (b) to TS 3.7.7. which requires all operations involving a positive reactivity change to be suspended, was not complied with.
Further investigation identified other occasions when boron dilution or RCS cooldown have resulted in small positive reactivity changes that may not have compiled with action statement (b) to TS 3.7.7.
TVA is carrently investigating i
these events and will provide a supplement to this report.
1 The event was caused by an inadequate procedure for ensuring that RCS chemical additions, which were made during the period of time when both trains of CREVS were inoperable, did not result in positive reactivity changes.
As immediate corrective action, revised chealcal addition procedures are in place to ensure that RCS chemical additions will r.ot result in the dilution of the RCS i
boren concentration. In addition, a directive was issued to Operations personnel defining the specific plant evolutions 7. hat can and cannot be performed while the plant is in action statement (b) to TS 3.7.7.
Both trains of CREVS will be returned to operable status before unit 2 heatup (mode a).
1-87501 On December 31, 1987, the NSS at SQN was notified that an auxiliary operator (AO) had tested positive for a controlled substance.
The A0 was selected for a randem urinalysis simple on December 28, 1987.
The following day. the AO took sick leave and reported to the Epployee Assistance Program (EAP) Office. On 4
i December 30, 1987 EAP notified TVA Medical that the employee's medical clearance should be pulled. Medical called TVA Security explainirt that the individual's medical clearance was pulled.
Due to the loss of medical clearance. NSS pulled the employee's site security badge and suspended the AO's clearance. Upon confirmation by Medical that the employee had tested positive for a controlled substance, an Emergency Notification System phone call was made as required by 10 CFR 73.71.
The cause of the A0 testing positive for a controlled substance is being addressed by Medical /EAP under TVA's Fitness for Duty Program.
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Description of Even1 t,E R 1
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1-87502 On December 18, 1987, the review of a November 29, 1987 event by the Site Security Manager determined that the subject event was
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improperly classified as a 24-hour los event. The event met the i
r 1-hour phone call and 30-day report criteria of 10 CFR 73.71 l
Appendir G and, thus, an emergency notification system phone call l
was made at 1750 EST.
l The November 29, 1987 event was discovered by the WSS cifficer posted at the entrance to the ERCW pumping station. The officer l
observed two plant electricians with visitor badges without an
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escort.
The employees indicated that their escort had received a j
nessage to return to the plant. The escort told the two visiters i
to report to another individual working at the IRCW pumping
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station; however, the escort did not properly transfer the escort i
responsibility.
The visitors, determining it was close to the end i
of their shift. decided to return to the plant without locating the other escort.
The visitors left the ERCV pumping station and were f
attempting to return to the plant when stopped by the WSS officer j
at the ERCV purping, station. The officer ipenediately detalsed the visitors and called for additional NSS support.
The visitors were escorted out of the protected area. Security personnel conducted a search of the area for signs of suspicious activity or tamperint.
1 and none were found. NSS supervisors questioned both visitors, i
obtained statements. and instructed them on the proper j
visitor / escort procedures. This event was caused by personnel i
failure to follow procedure.
1-88001 On January ll,1988, all four D/Gs were declared inoperable tiecause I
the interval for TS SR 4.8.1.2 (chemical analysis of D/G fuel oil) was exceeded.
In addition, since the high pressure fire pumps use the D/Gs as an emergency power source, the plant fire suppression system was also declared inoperable, and a backup fire suppression system was established.
Because of an oversight during the recent conversion to a new corputer program used to sched11e $!s. 8!-116.
"Quarterly Chemistry Requirements on Diesel Generator Fuel 011."
was not performed within the time interval required by the TS.
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1 Imediately upon discovery of the event, a spocial 31-116 package was performed.
All D/Gs and fire suppression pumps were returned to operable status on January 12. 1988.
In addition, an tsuss>diate review of all sis was initiated to ensure that the mode j
requirementa in the scheduling program were consistent with the appilcability section. All sis cossoon to units 1 and 2 or I
applicable to unit 2 only have been reviewed. Three other i
deficiencies were found; however, none of these caused a TS SR to i
be esteeded. A sinitar review for unit 1 sis is currently being performed with an espected completion date of February 8,1944. To prevent recurrence of this event, a more in-depth assessment of the I
esisting surveillance scheduling program is being performed. A I
supplement report w!!! be issued identifying, specific corrective actions.
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Description of Event i
, LER 1-88002 On January 5, 1988, at approximately 1700 EST it was discovered i
that LCO 3.3.3.9 was not complied with as required by TSs. On January 4 1988, at approximately 1 3 0 EST Operations personnel declared 0-RM-90-134 and 0-RM-90-143 inoperable. However, Operations personnel did not comply with Action Statement 32 of the LCO for en interval of approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
An investigation of this event concluded that a sufficient description to determine the i
minimum channels of monitoring required to ensure compliance for the LCO did not exist.
This resulted in Operations personnel incorrectly interpreting the requirements of the LCO and, as a result, the action of the LCO was not entered. As instediate corrective action upon discovery of the noncompilance, Operations notified Chemistry to initiate the LCO action statement. To prevent recurrence, a TS interpretation is being issued to state that one channel for each ERCW effluent line discharge header is required to be operable during release throu6h these pathways.
A memorandum was sent to Operations v rsonnel to inform them of this e
interpretation. A TS change will be submitted to reflect that a minimum of one FM channel for each ERCW offluen'. discharge header is required. A review was performed of other effluent F.M LCOs, as well as other instrumentation LCOs. No similar situations were noted.
1-87063 This revision provides updated information in the area of Rev. I corrective action, i
1 87064 This revision provides additional information regarding completed Rev. I corrective actions.
1-87065 This revision provides updatec information in the corrective action Fev. 2 section of this report.
1-87072 This revision provides updated information in the area of Rev. I corrective action, i
1-87073 This revision provides updated corrective action for this condition.
Rev. I i
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E1.lcription of Event l
LER I
2-8'/010 This report described two CVIs that occurred on December 21, 1987.
i Because the two events were stallar, they were cowbtned in this i
report.
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On December 21, 1987, two CVI actuations occurred.
The first CVI I
occurred at approximately 0750 EST and was causes by a spurious j
high radiation spike ou containment RMs 2-RM 90-106 and/or 1
2-RM 90 112. State both RM chart recorders showed a high radiation spike at approminately the same time, neither high radiation alsrm 4
actuated; thus, it was not possible to determine which PM tenerated 5
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the CVI. At approsimately 0410 IST, the CVI was reset. The second CVI occurred at appresinately 0900 EST and was caused by a spurious 3
high radiation spite on RM 2 RM-90-112. The CVI was reset et j
spprestattely 0906 EST.
As a result of the recent trend 17 NT ettuations (sis within the interval from November 27 to Decratier 4. ', a r.pscial task force has
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beeh established to investigate tae ron* tause of the subject l
CY!s. Once a root cause is establichect
,ppropriate corrective l
actions will be determined and larl ee-Wd.
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ABBREVIATIONS 1.
4 1TS - Auxiliary Building Gas Trestment System i
2.
n ?.s
- Auxiliary Building Isolation 3.
AOI Abnormal Operating Instruction 1
5.
BAT Boric Acid Storage Tank 6.
BIT Boron Injection Tank 7.
CAQ:
Conditicq Adverse To Quality Report 8.
CCP Centrifugal Charging Pump 9.
CCW Component Cooling Water 10.
CRI Control Rooa Isolation 11.
CREV Control Room Emergency Ventilation System 12.
CSS Containment ! pray System 13.
CVI Containment lentilation Isolation 14.
D/G(s)- Diesel Genraator(s) 15.
DCR Design Chir.ge Request 16.
DNE Divisien of Nuclear Engineering 17.
ECCS Emergency Core Cooling System 18.
ECN Engineering Change Notice 19.
EGTS Emergency Gas Treatment System 20.
EMI Electromagnetic Interference 21 EQ Environnentally Qualified / Environmental Qualification 22.
ERCW Essential Raw Cooling Water 23.
ESF Engineered Safety Feature 24.
FCV Flow Control Valve 25.
FSAR Final Safety Analysis Report 26.
GOI General Operating Instruction 27.
IMI
- Instrument Maintenance Instruction 28.
LCO Limiting Condition for Operation 28.
LOCA Loss Of Coolant Accident 30.
MCR Main Control Room 31.
NSS Nuclear Safety Service 32.
NSSS - Nuclear Steam Supply System 33.
PORC Plant Operation Review Committee 34.
PRO Potential Reportable Occurrence 35.
RCS Reactor Coolant System 36.
RM Radiation Monitor (RAD Monitor / RAD MD" 38.
HWST Refueling Water Storage Tank 39.
SCR Significant Condition Report 40.
S/G(s)- Steam Generator (s) 41.
SI Surveillance Instruction /or Safety Injection 42.
SOI System Operating Instruction 43.
SQN Sequoyah Nuclear Plant 44.
SR Surveillance Requirement 45.
SSPS Solid State Protection System 46.
TACF Temporary Alteratinn Control Form 47.
TI Technical Instruction 48.
TS(s) - Technical Specificattor(s) 49.
WP Workplan 50.
WR Work Request s
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OFFSITE DOSE CALCULATION MANUAL CHANGES No chant,es were made to the Sequoyah Offsite Dose Calculation Manual (ODCM) in January 1988.
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET No. : 50-327 UNIT : ONE DATE : FEBRUARY 05,1988 COMPLETED BY : D.C.DUPREE TELEPHONE : (615)8'/O-6722 MONTH: JANUARY 1988 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (HWe Net)
DAY (MWe Net) 01 0
17 0
02 0
18 0
03 0
19 0
04 0
20 0
05 0
21 0
06 0
22 0
07 0
23 0
08 0
24 0
09 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
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l UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-327 UNIT NAME sequoyah one DATE February 5, 1988 COMPLETED BY D. c. Dupree REPORT !!ONTlf JANUARY 1988 TELEPliONE (615) 310-6544 c
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1 880101 F
744 F
4 Design Control, Configuration Updating, and Employee Concerns.
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Exhibit C-Instructions 4
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5: Scheduled A-Equipment Failure (Explain) 1-tf anual for Preparation of Data l
B-!!aintenance or Test 2-flanual Scras.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & Li, cense Examination Outage F-Administrative 5-Reduction 5
I G-Operational Error (Explain) 9-Other Exhibit I-Same Source l
II-Other (Explain)
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SEQUOYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : FEBRUARY 05,1988 COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 MONTH: JANUARY 1987 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net)
DAY (MWo Not) 01 0
17 0
02 0
18 0
03 0
19 0
04 0
20 0
05 0
21 0
06 0
22 0
07 0
23 0
08 0
24 0
09 0
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UNIT SIIUTDOVNS AND POWER REDUCTIONS DOCKET NO.
50-3?a UNIT NAME sequovah Two DATE Februarv 5, 1988 C0t1PLETED BY D.
- c. Dupice REPORT !!ONTl! JANtfARY 1988 TELEPIIONE (615) 810-6344 o
c Cause & Corrective cq oyg Licensee go, gg gg y3g Event gg oy Action to No.
Date e
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3o g
3gE Report i go eo Prevent Recurrence S~
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880101 F
744 F
4 Design Control, Configuration Updating, and Employee Concerns.
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4 Exhibit C-Instructions
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Forced Reason:
S: Scheduled A-Equipment Failure (Explain) 1-tfanual for Preparation of Data B-!!aintenance or Test 2-!!anual Scras.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & License Examination Outage F-Adernistrative 5-Reduction 5
C-Operational Error (Explain) 9-Other Exhibit I-Same Source II-Other (Explain)
9 e
L OPERATING STATISTICS (TVA REPORTS) j
TV A 7 3a2A (Ov+a n NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR PLANT Plant Persod Hours 74E Month JANUARY 1988 Item No.
Unit No.
UNIT ONE UNIT TWO PLANT 1
Averace Hourly Gross Load, kW 0
0 0
2 Mavir um Hour Net Generation, MWh 0
0 0
3 Core Thermal tinercy Gen. GWD (t)2 0
0 0
4 Steam Gen Thermal Energy Gen., GWD (t)2 0
0 0
l 6
Gross Electrical Gen., MWh 0
0 0
6 Station use. MWh 4.733 7,418 12,151 h
7 Net Electrical Gen., MWh
-4,733
-7,418
-12,151 E
8 Station Use. Percent N7A N/A N/A 9
Accum. Core Avg. E sposure. MWD / Ton!
0 0
~ 0 10 CTEG This Paontn.106 BTU 0
0 0
11 SGTEG This Month.106 BTU 0
0 0
1?
13 Hours Reactor Was CritecJl 0.0 0.0 0.0 14 Un61 Use, Hours Min.
0:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0
)
16 Turbing Avail. Factor, Percent 0.0 0.0 0.0 17 Generator Avail. Factor. Pergnt 0.0 0.0 0.0 18 Turbo:en Ava 1 ractor. Percent 0.0 0.0 0.0 g
19 Aeactor A sat Factor. Percent 0.0 0.0 0.0 0
20 Unit Avait ractor. Percent 0.0 0.0 0.0 21 Tu bine Startues 0
0 0
r 22 Aesctor Cole Startues _ _ _
0 0
0 2?
24 Gross Heat Rate. Btuw.h N/A N/A N/A f
25 Net Heat Rate,8tu kWh N/A N/A N/A
)
3 26 i
C
??
{
28 Throttle Pressure. esig N/A N/A N/A g _,g2 Throttie Temperature. r N/A N/A N/A
{
30 En haust Pressure, inh} Abs.
N/A N/A N/A g
31 Intake Water Temp., 'F N/A N/A N/A H
32 33 Phin Feed. vater M lb/hr N/A N/A N/A i
34 35 36 37 F ull Power Capacity, EFPO 404.86 363.65 768.51 38 Accum. Cycle Full Power Days, EFPO 0.0 210.8416 210.8416 j
39 Oil Fired for Generation, Gallons 2,838 3
40 Oil Hestino Value. Btu / Gal.
138,000 JL Muf Generation MWh 43 i
19 Man. Hour Net Gen.
Man. Day Net Gen-Load MWn Time Date MWh Date Factor. %
3 43 N/A N/A N/A N/A N/A N/A Remarke IFor BF NP this value is MWD /5TU and for SQNP and WBNP this value is MWO/f 4TU.
[
2(t) indicates Thermal Energy.
%a e
FEB 131988 A V('
Date Submitted Date Reviled s,.
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SUMMA.*Y OF MAINTENANCE ACTIVITIES
e 9
i MAINTENANCE
SUMMARY
(ELECTRICAL) l
)
..'. 21 CAL fiA1MTENANCE E0XihLY It?.MRY CCMP C2.. U IL'E SYS ADDREt!. DAlt.... DEICRIPTICH.......
............... CO RRE CTIVE ACTICH...............
F1155431 IM 268 012111/20/871-ICN-248 0121-A,CuMPRDO,122-A,122-A,12 HfDf0GG IGNITCR CURRICT tt'4IkC! WE7E 2 A,122-A,122 A,122 A,122-A,112-A,122-A, CUT OF $PECIFIED EMCC. EEPLACID 122-A,122-A,122 A,122 A,122 A,122-A,122-Nf 0f0GG IGNITCR 121 MD PERf 0fMID A,122-A,122 A,122-A,122-A,122-A,122-A,12 !!-305.1. CIRCUIf i 10 MEASURED 8.4 2 A,122-A,122 A,122-A,122-A,122-A 122-A, AMP 3 WR C115543.
i 122-A,122 A,122-A,122 A,122 A,122-A,122-l A,122 A,122 A,122,RIPAIR THE DETICTIVE HYD IGNITER CM CIRC 10A THD IMILE PERTCtMIKS $1305.1 (ITHER IGNITG 121 OR 122 It LAD PER THE CURRENT t[2ING1 TAKEN EY tuutTTE hhD IRU3 E12 W81 1 (C!! 201 CM /50 09/29/8710CIS 20101 /50 0,$PRINC WON'T AN INSPICTION CY THE RMUTACTURER ttCHAfGC ATTER Btt CLO!!!. HRDIS UP (W!!TINGICU$t) I2ICATED THE DCCRRICT WP11t?1. It! FOR ALT FOR TO ktD.140V CLD3!NG $PRING A31[RILIE! A4 TCP 3Huit0 W ID !$2 B CDMPARTMENT SB AUXILIMY SWITCH 43 NAD BEG Ih3TeLLED DURING PftVICu! EPAII.
1127725 2 LOP 070 0143 08/01/84 2 MVCP-070-0143-A,CsNTPCO,[XCtt3 LifCM MfX CONT DLti 110L VLV $W!iCH P.CR E78.
WHEN PLACDC THIS $ WITCH IN THE (PG PO!ITICS THC CN WILL NOT OPCW FULLY OILY A SMALL F2[ MENT $USPECT THIRMAL OVERLOAD! INVE! M0 ffPAIR E203 Sit 2 I;;20 230 MW /3710/20/87 2 ftIS 210 kN /3?,CnkPEDC.EEFUCE RAN !! 2?$.2 ON THE IItatER ltFOtt LRIMtt !! 271.2 DW 1 INSTALLAi!DN. IX3fALLED KG 8ttAt(R USIKG 31-275.2 W1 B20380 0204422 2 ICV 043 00h 08/28/87 2 rCV-043 00h,CuxPfDO,RIPLACE F0fiCM REFLACE MICto SWITCN CLEAktp PITit0 LIMIT $ WITCH FOR VW 2-FCV %3-00h CONTACT! AND FUNCTIONALLY CHECKED.
$209041 e itG 07716 /224 09/14/17 ( ittD 077-ts /224,0PEMER FAILID $1 s
273.2 CN 11 02233 h 1 GIMt 082 00010 04/24/871 GEKS 082 00918-9,CsNPRDO, cut!*
INE Best 3 PEED (100 RPM) POTENTIOPITCt TPCU!LitHC3T Cr !!S NO LOAD AT ALL WP3 Wat [tfATIC MD CN1D $PCCD Y PICKED UP EVG TFfDUGH $ PIED ! WITCH MD ALSO LOAD VARIATION WWEN SLICHILY ttMrtD. ICPLACCD THE PA1E $Ptt0 (900 RPM)) PDTENTICMCitt MD ADJU3 FED MD FALMCCD THE HLC M9 BALL EAD CtNtPNDR 1PEEDs. ADJUtit0 Bast $ PEED TO 900 RPM RAM,DIttCL LOMED MD UMLOADtD, VER1 TING Pit Sti POIWit WR B2235h 02391471 !ttC 0?2 0001010/20/971-(TIC Cl2 04018 C.CWPPDO,$ULACE PAIN THE St[MER CONktCTIR$ WCt! LUQ!t I
tC CCWilCL I?DtEl. THIS ttIArtt IN F0111 tty DUC TO letMAL 4!tRAi!ON Cr PLA(t (PPARMi[LY HA3 LCCit INf(PMAL kt AG. PCPLACt0 tMAt!I AND !!LNitNCD PHTS MD !! FOT MtING GCCD CONTACT (LECTf! CAL COMNCCTIO4. IM PO!! itti MD T!GHTCED ROIMilE I4 Lit AND Lytt 94
- 1239161, t24Tk57 1 l M i?0 CI 0!/14/tf 1 IV t*25) Of C.CoffDO,1:0V AC VITAL f ttfupC1 Mtitt le! OUT Of CtL!tt4itcN,
!$lttitt 1 TV LOW fitt ITT If tu4I13 Ott fitDUtHCY fCAD 112 M2 1
10 1 WttrLY.
i (Htrig)./CALIftAft0 TitNOCY M1tt Al
)
j 4
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20 l,
LCTE1 CAL fiAINTENMCE P. HTHLY SL.WkY CCMP M2... U IMC SYS ADCRE!3. DATE.... DE!CRIPTION.......
........ CO RE CTIVE ACTIDH..............
i de H2. WB24 N ?.
02W47 0 NIO 070 0051 12/22/87 04C18 0?)-M51-A.EtNP90a],0KAKIR ttEMER FAILED LONG DELAY TIME CRITERIA.
FAILED L DELAY TIME STEP ?.3.1 Il PO!!IKY 00E TO LOOSE MPTECTCE,
$1-258, AL30 FAILED (2) RETE!is T PfEVENTING CONTACT! TRDM PMING t
$1-258. REPLACE AnPTECICR UP./ ADS $fD MPTECTOR MD PERTUR.".E0
!I 258 FTR PR(FER OPERATICN.
F274208 2 I"1.' 048 ONA 01/15/tt 2 CCTA 048 0NA A CxWPaca),tREAIf 00E 10 h0EEMAL (FEAATICN, ThE IREAXEt3 APPEARS TO HAVE A IA0 TRIP COIL.
MECHANICAL CLD3ENG LEVER WAS OUI &
ADASTMD(T PEVENTDG THE FEAKER FICM TRIPPING PROPERLY. ADNSTED THE SPfIhG THAT KItt! TE Cl#3ING LIVER SACK.
EPLACED TE MC CHUTE A310 tty.
VERIFIED PRDPEE (FERATION F BREMER W i
C2 N 09.
l F27t'.08 2 RLY 0%
te22A 01/05/88 2-RLY 011 K422A, cup 2a,rNPf9a],WITH THE CENTER 3CEW IN THE CONTACT PAN WA3 PHASE 'T" $WITCNE! 2 H3-fl 644 8 B AWD LOQ$E PREVENTING TE RELAY FFOR 2-H3 43 484 8 EELAY K422 ENERCIII$ tut LATCHING. f!GMTEhED TE CENTER SCIEW DCCS Nui LAICH.
THE CtNTACT DAR THEN REMOWD AND ED3fELID TE ELAY. UERITIED PfCFD CPERATIDM F ELAY WE42?d508, l
02?i:102.TO V7 Ved 10/02/87 2 MVOP 047-0044 A,C NFP00,VLV WILL NOT I
ELECTRICALLY OPERATE ROTOR CONTACTC1$
WILL PICt17 Aho VOLTAGE !! CN LES$ FRCn itE COMPONENT TO WU.
r2?dtd4 2 GENI 092 000:$ 10/20/67 2 GEMB 462-M0294,EuMPE0a],tiX2 RELAY l
010 hai EERGIZE AS RE0'JIEED OURING i
PERFCRMMCE F $I-24. IWEli! GATE M0 REPAIR WHEN 0/t 234 WA3 STARIED FRUM A ELACIOUT FM3 OID NOT START 0296:tt 0 NTO 2M W 12/22/3? 04Af t 2H-CV-0,0'.l RING PERFCRMMCE OF CONECTICMS FEILCIN CELLS 18 AND 11 EAD i
$1 100.1 IN STEP d.2 CELLS 28 11 Cr 152 RILLIOMS A TO C, ild MLLICHn! A TO
[
VITAL letTEEY FAILIO.
O,134 ULLICX33 B TO C, H MLLIDAM B TO 0.
A TO 0, B TO C MD t TO O REO i
M GH. A TO C FAILED CRITERIA./CLEMID STEM TAR 1 BETWEG CELLS 18 MD 19 A2 i
APPLIED A FILM Dr F04X OVER TE STRW i
i (At. W4294N.
029G3481 (E4 082 0001A 10/24<8714EkB 082 0M1A A,C8dEO,0/G DGDE ADA$fE0 DCITER POTENTIOEftt! 18 2 1 A2 G34tR#02 It INDICATIXG MPf 0XIMTLEY FOR GCWINOR CE LIht-UP. MW 1/2 THTOTTLE WITH TFE ENCIXE !TCPPED. EXCITER TO ACHIEW PPOPER !!GNAL VtLIAGE. WI 29348 l
t i
1 l
21-
0 6
MAINTENANCE
SUMMARY
(INSTRUMENTATION) l I
i i
i l
INSTRUMENT MAINTENANCE MONTHLY REPORT FOR JANUARY 1988 COMMON j
1.
Initiated FCR-66a2 to replace the technical support center (TSC) l computer test point resistors associated with the auxiliary feedwater i
flow loops. The existing resistors will be replaced with larger value resistors to correct a transient loading problem that was causing the computer to read inaccurately.
2.
Completed corrective actions for CAQR SQP871697 concerning inadequate 7
response time testing of the containment spray system.
a 1
3.
Completed corrective actions for CAQR SQP870106 concerning reliability problems with magnetic flow transmitters in the chemical and volume i
]
control system.
W 4.
Completed corrective actions for CAQR SQP870767 concerning improper temporary alteration control forms on the essential raw cooling wnter i
system.
5.
Completed revision to SI-82, "Functional Test For The Radiation
(
Monitoring System," to clarify proper connection of test equipment i
i during functional testing of the radiation monitoring system. This was j
an NRC commitment item in accordance with CCTS NC0870350001, i
l UNIT 2 4
1.
Completed corrective actions of DQA Audit QSQ-A-86-0007-D01 needed to support entry into mode 4 This involved the verification that all i
CSSC instruments needed for mode 4 were identified and had a current calibration.
2.
Prepared WP 0097-01 and coordinated with Electrical Maintenance to change the settings on the time delay relays for 2-FCV-62-128 and
-144.
This work was authorized by DCN X000978 and needed to allow the j
automatic actuation of these valves to function properly.
3 3.
Prepared and performed STI-108 to measure the load sequencing delay time for containment spray pump 28-8.
This was needed to verify that the total channel response time for containment spray actuation is within the TS allowable limit.
Submitted response for closure of SAL 1068 concerning setpoint changes 4
on various ventilation, temperature, and flow instrumentation.
1 i
5.
Completed the evaluation and implementation of a calibration verification program for sensors in temperature loops required operable by TSs.
This was an NRC commitment item in accordance with I
CCTS NC0860329004.
i I
1; 22-
IRU 43I MIxf EECE.5;WTHLY ll&. arf Ct.P 92.
U ft.1C $Y1 AttEC!S. 09ft... DE3CRIPTICd.......
.......... C O RRE C TIVE AC TIDM...............
1221777 1 L:V 003 0164 09/29/871 LCV C03-41M,CvMPRDO,I/P P0tIIICHER A DETECTIYE METERING TIRT AC AIR RELAf DN WLUE 13 RE!PO@INC Iff Ai!CALLY TO A CAUSED TE E99ATIC OPER9fION/THE Alf CCHTAki IMPUT ECLAY WS EPAIED AMD THE MTERIG Td IE MD EQUIED GA!KEi! REPLACED. 31AftE I/P OUTPui WAS KRITIED THEN BETutKED 10 PROPER IFERATIDN. THE WLbt 11Rurt WA!
THEM YERITIED.
F22 $ 1 2 ti 063 HS110/14/87 2-LT 063 0051-E CnNP200.TR INDICATCR THE LEWL TRM!MITTER WS FCUND 10 ((
FERICDICALLY FAILS LOW DEFCCTIW. THIS MY M4W BEIN DUE 10 EQUIPflENT AGE OR NDRML WI.AR, TEM 3RITTER !! ENPOSED TO THE ELEPENT!.
TE TIM 3RITTER MS KfLACED WITH A NEW TRM3RITTER kNICH Mt EMIBRATED MD i
ETUEND TO SERYTCE uf $224841.
0225994 2 h 062 0093010/01/87 2 in-062 0093B,CMPACO,f?Dui1E2:00f THE RODITIER MS FOUPD OUT CT TOLEEMCC VEPITY VLV WILL FULLY Ct:3E HIGH TMIRIGHOUT THE ENTIRE RMGE. INI!
MY HAVE BEEN DUE TD IWflE EM. TE RODIf!ER WA3 ECEIBRATED MD VERITIED l
ALONG WITH TE YKVE MINTEMMCE WR D223194.
!?M12 2 TC'J C01 00011/20/87 2 P V 0Gi-0030 0,E41MDO, Alfeltt.I 6tCU@ THE VttVE PO!!TIOktf WAt DETERRIhED TO CCMit LLCt.
It CtFECTIkt. THIS Mi HAVE BEEN DUC 10 h0RML RECMNICE WEAE. THE PQ311!04f M! REM. ACED MD TE is!FIER MD UAltt CALI8tATED. VERIFIED AIR LIMAGE AIOudD l
THE P03!TIONER 10 IE DII.T NORRtl (ACEM PO RT. VERITICD PEPER WLUE SitCKI. WR B2h112 02M412 f f 041 cc92C 09/29/07 2 FI-063 0092C,Cwf;O, FEPLACE THE itM35!ifEE MD FAILED HICH QUT Cf itEMIffER WITH A 'EM CkE PWP TOLCtt.NCE THRCUCICUT ilE ENTIRE EMGE.
187 1006 003 THI! MY HAVE BEEX DL{ TO ECUIFMXT ACE OR NORML WEM. THE ftM3 HITTER HA$ A HIST 0tY /DF StiPCINT DRITT. A NEW FCX 20R0 TRM3RIttER $/N52173% WA3 TENCH CALItfATED. THE OLD TRAM 1MITTEE t/N ki15J51 MS EBO'.ED AND INITPALED THE REW TEMSRITTER. THE CETEfATIDM WA3 VERITIED AND THE TRAN3HTTER WA3 ttfi IN
!ERVICt WR I B234541 E:23c52tC.' M3 015810/21/87 2-LCV 403 01 M,COMtO.CEECL LCY If WAt FOUC THAT THE AIR RECULATCt WA!
f CCHiiDL C19tu11 TFM !#PUT CF THE IP TO $ET At 27.8 Pl! AFD SHXD MVC itCN l
)
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in!.:. 9i.': dithanCE n,HELY M.ARY CCr#
Td2.
U MC $Y! ADORE!!. CATE... DESCRIPTION.......
............ CORECTIVE AC TICN..........
THE LCV
$3+2 P$1C/iHE RECULATC'A WAS SET 10 SS P3I AND THE LOOP MD IK!TRMHf3 WEEE i
LEFT IN TOLERMCC E23607 2 "Dt 003 017210/23/8? 2-F03-C03-0112-A,EuXPF3sl, AIR It THE VtLUE T0!!IIMI WA! FDL'nD TO Hett A PL1.!ATING OUT Cf IECULAICR(LEMIE)
MfECTM AIR ECLAY M0 REGULAfot THIS MY HM BEEN DUE TO KCkMAL WEAR DE EQUIPEMT ACING /THE PO!!TICER AIR RELAY MD Rest 1ATOE WEE REPLACED MD CALIBRAID, CECIID FOR LEAKS MD fCURD NOME WR 6823 887 i: N t00 2 LI3 041 0115 !!/21/87 2-LIS cdi 0193,CwMFtt 3 -193 B/A (LO)
THE LO LEVEL $ WITCH M3 FIAIND OUT OF
!ETFDDT TUECTION !! DDPEFAftE -193 A/B TOLERANCE LOW. THIS MYA MLT ICEN OLE (MI) 1EiF0!hi M KE3 t 5 39" I iP6 $PEC
MIGH LEVEL 3 HITCH 2-LIS 041-0193A/t WA3 IN TOLEMMCC MD MD ADE3fMENT MM.
THE LO LEVEL ! WITCH 2*LIS-0410193R/A MS RECALIt#ATED MD LIETR IN TOLEEMCE.
TE 12ICAfDt M3 f(RJM INTILERMCE.
l WRIFIED ALAM $tTPCINT AT PROPEt LEttt.
MD I4ICAf0t itAttL WA! OPERATI>G PRIPERLY. THE LlIP WA3 RETUEMED 10 1EEVICE.
F M 107 2 1 W 003 015011/02/87 2 LCV 003-0154A,CnPfN.VLV WDLLD hOf IEN MVE POSITIMA WAS MIERMIME 1011 CLC1l: CCP/LETEl.Y W'4EN ATWP 2A-A M!
MfECTM. THIS MY HAVE KEN CVE TO EWING. REMIhED C7EN 1/4"-1/8".
EQUIPMENT AFE AND MRML EA4. THE POSITIMR WAS REPLACD WITH THE POSITIMI Cff M UMIT ONE VALVE 1 LCV-003-0154A. THE PC3ITIONER WAS CALIBfATED PER tillttILMCC IN3ffUCTICH
$1-73 MD VERIf!ED PROPER OPERATION.
C2%51:3 2 LCV C'3 0!N 11/02/87 2-LCV-C03-01M,CnXPPN,$/G NO.1 LEVEL THE UtiVE 3PRING TENSIDH MD STRCtt DCECA!ED ' 10/. ON NARfCW RAFSE VALVE WAS DUT Of MECHMICAL ADA!! MENT.
DDICATCt! MN VLV WA CLO3ED A$ FAR A3 THIS MY FAVE EtEN DOE 10 kCRML WEM If VOULD CD (*1/8"CFEN).
M D CTCLING. THE PACKDC MD Mtt $thi i
MRI P0h3IED THEN STROKED MVE.
l PERFORED CALI8tATION. ADW3fEDUAttT L1FT OTT !PRING TENSION TUR 13.3 P3!G.
)
STRCtED VAlt'E pet $URVEILLMCC j
INsitcCTION !! 73 WITH VAltT LIff Off AT l
3.3 P!IG INPuf FCM I/P. RETUINID VAlti LOCP TO !ERVICE MD titDKED VAltt.
-24
W,:, W..iuxiEFAtCE rQHTWLY PMARY CCf.P ti2...
U I' M !Y3 A00ft!!. CATE.,
CE!CilPTICN.
............... CO RRE CTIVC 6C TICH.....................
r247171 2 'T 044 03'411/12/87 2 PT 0(8 0N D.CuMPRDad10CTR50.W3,WH THE TRAN15ITTCA MS FCUM0 TO CE CUT OF ILE PEEFOUIMG PM 1943 048 FOUND TOLERANCE HIGH TWOUGH0di TM ENTIt[
IPM! MITT [I GUT 0F 70LCRMCC l.Y CHCCKING RAKE. THI!MY K DUC 70 ElRIIPMENT AGE.
it$T POINT. HIED TO CALItRATE.
THE iPM!RITTER MS RECALIl1ATED AND l
P0tf MINTDANCE I[$i[D.
j 024733d 2 tM ces 324 CVid/37 2 ifl-043-32%CsM60s],MPLACE TE THE HIGN ICA0ING 00f!NG CALICIATION OF i
MODIFIER WITH THE GIFIER REMOYD FE05 THE MCDITIEE MS P90MKY DLE TO TH!!
UNIT 1-E 22 DN WR 16247383 EDITIER BEING A NON-LINEAR PODUlt WHICH itND TO FLUCTUATC WITH Alf[RMAi!NG CURRENT POKE FLUCTUAi!DN!/TK 80)IFItt MS LETT At CALItaAfD MD THC LOCP KTURktD TO 3DVICI W 08N386. TMt Kr!CIDCY WILL K CORKCID WNCM PAlit i
DN CtKN AK KCCIVED. THE KW LIktAt MOD (I.C WILL K D$iALLD M WE 0214323 t27G32 2 TG' col om 08/23/87 24tV 041-0030 t,CrM'RDn],THE RIGL.tA10t 11 Mt FOUND THAT THE ELAY tilitICTION tDX CN 31st OF PCV 13 CCNTIWuGUILY PLUNGER MS STUCt. THIS MECMNICAL SLCVING CUT CF THE 4 TNT PART.
SINDING MY MYE (((N DUC TO THC PLANT ttING IN A QUTAGC CD41 TIM TUR SC LDC i
MD L0ct Of YALUC CYCLING. THE PLUMCG M! ExtRC!stD As MLYE STROKED.
RCCALICMf!ON PCI IN31MDT MAINi[MAMCI IN3ftuCTION IRI 1 MD LIff OPttAKE AMD IN SttVICE. MD GPENTION3 $1R0tI TE VALVE ff0M THC MMO SWITCH IN THE CONT 10L ROOM TO WRIFT OPERASILITY.
GW12 il c43 0129 J/01<87 2-LT 043 0121,CuMPits),WHEN EEilRxIKG THE TRAMSMIfitt M3 FOUND TO BE OUT or LCCP 101EPV!CE Cd SI 141 KVIATIIM CN TOL(RAMCC LOW THROUGH M0!i Of iME AMGE 2 LI-63-111 SD 121 WAS GREATER ThEM (
THIS MY HAUC SCD CLE TO AGING AND 4.23/ ALLCWARE CYtt!NG/THE TRANtnITTER WA$ CALIttAID MD RETWMED 10 stRVICE Ut 121W11.
G W 42#1 c!3 01200 01/C4/83 2 P3-063-012"C,CaORDs3,iHC LOCP IT MS O!!CC'ARCD THAT A GAA33 HCPPtt APPEAt! 10 Pati A DIttCT SH027. CM cKED FU!E HAD BLOWN. THIS MY MYC Ol(N Kt TEST POINI A917 iCAD 0.0000 YDC-THERE 10 $PIr! V01.TAGE. TE FU!C M3 ftPLAC AIIN'T E(EN M Si?AY MY'$.
WITH A SPARC ru!C FROM THE AUXILIARY INSTRUENT 2006 CA81 MET WE 829%i4.
r296737 2 ?C 001 M?212/11/f 7 2 PC-001-0072 E,CnVits),0W RT 8.18 CN THE LACK OF CUTPUT VCLTAGE 1805 fMI IMI-99 At 3CHECCLt0 CY DI N.100 PLACt0 MkUAL ! WITCH WA1 CAU3CD BY A KTEC TWITCH IN PJWL FNITICM WMD Cf GItt (LECTFOMGNEi!C PILAT/ Tit ICLAf M3 CHvit IN OUTPui A(PL.AttD AMD THE CCMittl.L(4 M! LitITID CP[M$tI IN MMCAL AWD FCTURN(D 10 l J
i
......... (CEI(CI M 8CIION.
IEEVICC THE !! SATI$fIED THE PO!T MINTEMNCE ftti at2H737 1292'*77 2." 070 0126 01/12/83 2 f14704123,CmMPRDO,FLD4 INDI".ATOR THE FLOW TRAh!MITTER 2-FT-070-0121 MA!
13 INDICATING FLCW WITH CCS flow FCLwD TD LE OUT OF TOLE 4ANCE HICW. THIS ISOLATED' Mf BC DUE TO THE [tUIPetNT AGE CI CYCLING TIME IN TE LW/ THC IPDICATCt MD RODITItt WEE FOU4 IN TOLERVCE.
lHE ffM3filiTER WA3 KCALIttAt[D MD ICfWND TO 3CIVICE.
129.N78 0 LI 002 023:D 01/11/23 0-t! 002-023;D,tsNFIDO,fME 0-LI-2-2300 THE INDICA 108 WAS FOUND 10 K DUT Of
!$ PCADD1; CNE FCOT LEtt IPM THC UNIT TOLUANCE NIGN ON TMC TOP CND Cf THE ONE DDICATCt.
RANGC iMIS MY MUC MD DUC 10 AGING MD CYCLDC/IE INDICATOR 0-t! H2 02300 Ms stCALINATED MD KiuWMED TO stiv!CC MD ttADS APPROXImitif TE $ ARC A3 INDICAfDR 6-LI 04242304 Wit 292478 6
(N:k) 2 U.3 30 0195 01/11/88 2-LI: H141%,CU41MC FILLD.C OPERAi!ON THC LtWL LO $'d!TCM 2 LI!441-01*tt WA!
OF [1PM110N TME CtYCOL LEli[L Ms TOUND (Bli Cf TOLUMCC NIEN. THI! MY WITKIA 1"' OF LCW Lfa LCL'IL A! L!tEL MS MVC DEIN DUt TO TE (GUIPMCMT AGE 04 I
IkCREASING. tWP PC&'D CYCtING Miff Of TM SWITCH. T M SWITCN MS ECCALIIIATED Pit $utVEILLANCE IM11tWCTIUM SI 1% Am EturyID TO 1ERVICE.
tnt % 2 II 043 013102 01/11/18 2 i!4414131832 Juh!O,2-i!-(3-131 & TH( I@ICATOR WAS TOUND OUT Cf TOL(IMCC 2 11 43 132 ftti (E WITHIN < 4 KitCE f LOW THREllGh0UT TE EN!1RC RAhSC. THl!
PCI !! 3.
CALIBFAfC f <I;C f!'$ KFOtt WAS PdA8LY DUE 10 ill MODIFIEf IFEY EXCICD '.FEIP CPMXIL CC LIMIT 3.
2 TH-004132 $CDC OUT Of ICICIANCC LCJ THEOUG)GT TE EXTItt EMGC/fME INDICATOR MD MODIf![t WEE BOTH CALIttAi[D IMTO K!!KD itLIRAKCC AC IME LOOP ICTLifMED TO $EfVICC Utli294%4 A PUTENTIALLY RCPCtf AttE OCCUtvtNCE 42881 M! $UMIfitD BY OPERAi!CN! ALCMG WITH A LIMITDG COWOITICN FCt CP[RATICM 3.1.2.5 [NTERED 1-7 it Af %31C MD EXIT 1 4 88 Af 150tC 02i?Ttt 2 G 10 010109/2d/87 2 Lf463 0109, COMP 7DO,1t?E91TTIE INE TRAN$R!lf!E M3 ftM3POlitD 10 THE Mirui WILL NOT CNMGE WITH (M.IISATED s' MOP WEtt THE CIRCUlf BOARD AN0 SifAIN Didit.
C4GC WttC REPLACO RETURNED TO LCOP WO l'CEITIED CN.Itf ATI3M POST MINICMM(t i
TC!T FUTORMCD Ne LCOP f(TLtxte.
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U n.3C SYS ADC#E!3. FATE... D E!CIIPTION.......................... C08 TCTIVE ACTICA.....................
i?.f.2? 1 :I' 047 %11F/E 10n8/871 PO!!-047 0491T/E A,CnHFk0s],ALEfl IM 8 THE PRC130E DIFTEEENTIAL Ia'DICAfDG WCM'T CLEAT INVESTICATE 8 EEFAIt.
SWITCH MAD DRIFTED OUT CF TCLERMCE.
THI: MY HNE BED Dl;[ TO EOUIPffENT AGING W CYCLDG DfIri. THE $ WITCH W43 IECA!.IttATED AND THE AhX:MCIAf 0R AL Att IE:ET AMD ETURMED TO !EEUICE WE B299427.
F218197 2 ft 045 1 P00210/2ut? 2 M 0481 P:'02-J,LDCP 11 CDCL LEC TEP.? THE REC 30ER WA3 TUU2 TO HAVE A LOD 3C FAILED LCW.
$1CNAL CONNECTBE/TPC RCttt0ER WA!
)
ElGED M0 D$PECTED. THE SICL%
CONNECTOR TICNi[ED Am THE EC30ER FEIMITALLED. TWC UtLTAGE AMD RECDf0ER FEN RE/dDG3 EE UERIFIED M0 RETURED 1
TO 3CRVICE W88298597,
!?157481 r: Cf2 (2;? '9/03/37173 062 02LT.,CaMPfDs), nIn ! WITCH It IME $W!iCH HA3 EEPLACED WITH A kEW 3
EECKEN. EtPLF.CC $VITCH MEEED TCt !!
! WITCH CALIStATED IM TE SMOP f.MD I
2cs.1 IMstALLED IN THE FIELD iME LOOP WA3 THEN ECTUEMED TO SERVICE.
- W 47 2 Li 043 elli 13/07/87 2 Li-0610119,Ca#Gu),WWEW RETLIPMDG LCC710 !E(VICC Cd $! 141 THE DEVIATICM i
EETVEEN CFAh4t$ 119 8121 WA3 GEATER I
i 1
IEMM 4.2N >EED TO VEtiff CALIBRATION.
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MAINTENANCE
SUMMARY
(MECHANICAL)
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MECHANICAL MAINTENANCE MONTHLY REPORT FOR JANUARY 1988 COMMON 1.
Completed work on "B" auxiliary boiler.
2.
Completed repairs on security building roof.
3.
Completed repairs on control building roof.
4.
Completed repairs on auxiliary building roof.
5.
Returned fire doors A-57. A-154, and A-159 to servare.
6.
Replaced valve 0-FCV-70-197 and -198.
7.
Completed repairs on "A" CCS heat exchanger.
UNIT 1 1.
Completed repairs on 1-FCV-70-90.
UNIT 2 1.
Replaced piping on ERCW 2A discharge header. MIC repair.
2.
Set RCp plugs.
3.
Restored airlock door interlocks.
4.
Set center missile shield.
5.
Completed repairs on 2-VLV-63-577.
6.
Replaced coils on AFW/CCW. 2-CLR-30-185.
7.
Completed repairs on 2-FCV-62-86.
8.
Completed repairs on 2-LCV-37-001.
9.
Completed repairs on 2-VLV-63-002.
100. Completed repairs on 2A CCP oil cooler heads.
11.
Completed reptics on 2-FSV-43-307.
OTHER 1.
Completed closure of various SALs.
2.
Continued closure of various CAQRs. CARS. DRs. etc.
28-
nECac v. MDifIXAE[ r.CMTELY !l.;r.".AEf GM 92.... U f tNC ;Y$ ADCit!! DATE..Ot!CRIPTICH.....
.......... CO Rtt C TIVE A C TI GN.................
A532721210V 030 0044 03/03/84 2-fCV 030-0044-A.RXPRM filtILD ACTUATCR REMOYt0 ACTUATOR, EttUlli ACTUATCt PCR CHANGC Gi[Att MI-11.10 AND REIX3tALLED ACTUATCR Of 4A512721)
A33(559 2 %V 0C 054510/21/85 2-VLV-063-0:45-A,CadPEDn],2 43-545 YLY EXCitDt0 LEM AAft PER SI 144.10 DUt FAILED $1144.10 PMi A LCM T[37. VALVE TO WORM DTIP.NAL3. IN3TALLD NEW YLY LtMING 2 Grn AT 2250 P3IA TECH SPEC DISC G $PRING MD CDdR LATPED VLU REGJJIRES
$[AT L103H12 TG 0?0 013v 01/23/87 2-FCV-07C-01M,tsNPIDa],VLY NEG!
PACUNG MS COMPItt3tD/ADCCD 2 RIN33 Il REPACIDG PACUNG. (WR 89103881) 011Mk12 RV edi 0122 04/24/84 2-FCV-041-0122, Cud 20s),$1pCit TIM [ hat 00Uttt0 1125573 2 V.V C47 05f20 01/21/88 2-YLV-047-05620 F,CsNPPDa],CRCI VLU LCMDC ThfDL'GH A3 TE!i Pit !! 144.23 i
0132t10 0 W 067 0*12 C8/24/87 0 PMP 047 0k!2,[evtDs2,PLP,P PA3ING IN$tALLt0 KW $NAff fLftVt, 0 IDGt AND NCD! AD/J371FG AND OR RIPLMC)
- PACUNG. ItWD ! POOL PIPDG CUT LI43 l
t IIIhtTELED PIPDG As btLCO LDIS.
PtiutNG 10 titVItt (WE B 132010) 1214783 ? ;W 062 C093 02/2d/87 2-fCV-042 00'l3,CaCmtu,aMFtDa],rtPAlt LEMING rdIM (214!st 2 VtV 070 0617 05/04/87 2 VLV 070-off7 A,ttW CNECK YAltt INittNALS Rulff, ICAfDG $Utf Atts D! TTY, INSTALL KUC TO DtitIAIME If 2 FCV 7c 87 INittML PIPDG HAS EUST AND CC#901!ON l
i Of 2 CV 70187 LEMDC C9JDG !! 158.1 NILD 17. ftMVD INitRNALS, LYPID L
itti DLE ltAT A2 D13C As ICAS30ftID MLtt.
EITUlkID TO $UVICES (Ist-8214161) 121%!78 2 W C3. CC02t2A C8/Ji/87 2 PM c!2 0032t2A-I,CMIDs),PUFP ttAL bA3 CA0/ttWD Ptif PIPDG 10 LEAUNG At $NAFT St*L. THIS WR stPLPCt! Punf, IN3fALLD EV PURP, NEW COLADG l
LO37 Wft214878.
SPICtt, M !CND Mi0t 10 PUM, RIPUCCD i
PIPING U3DG INRtc $EALMi, ETU2nED l
10 !! M Ct. (Wi-9214478) j L223215 2 t'V 074 432411/19/87 2 fCV-074-1824-8,CsMPfDs),MLtt HA!
ICVIlt (W4 8t223315) l LCICA (UILDLP AR0!AD $t[5 r224%12 r3 03) ct:1 C8/17/17 2 fCV-030-0C?4 8 tLU ACTUATCt APPEAE! TO ACTUATOR Ntt03 KMILDDC/EtUILI Et ti!Ct!KG GOING 10 iMt OPEN POf!!!CM ACTUATCR AND ftflstNED MLVC 10 stRVICE ACTUTCt AL10 APKM3 70 f t LC0lt (WE-6224%9) i (228kC6 2 M.'
082 4002t1A 49/1/87 2 Pr/ C82 000281A-8,Lut( QQ!L CIIC.PL2P $tAL M18PD/MMOLTD PUMP PIPDG TO l
211 MS EXCtt31VC 01L LtAt Af SWI PUM, INSTAltu EW MP, EW (CUPLDG l
3tti.
IPIDEI, ALIGND MTot TO PUMP, f*D MPLACD PIPDG USDC THECAD 3tALANT.
l Hitf 4D TO ttfVICt. (WR 8)T114478)
I (23:419 2 TCV 013 N:5 07/24/87 2-FCV-063-00:5 8,C8kPFDs),Veltt HA3 l
8CPCN ltlILD UP FVSfICJIfID I
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. alate /.M;E n;iiHLY str.nARf CCr?
nt2..
U FLtC tY3 ADCEE!$. DATE... DEfCIIPTION....
.............. COlit CTIVE Aci!ON............... '....y. '
0232393 2 f'? C03 011610/15/8? 2-Prf-003-0118.,CGPfDO,ROfAlt ETATING KDEMAL WEAR /DI!A31EMitED MD REP.CVD' C
A$iEB8LY IN 24 A AUX FEEDWATER Plfr RQiATING A!3EMBLY. t[PLACED ROTAfDr ELEMENT, tEALICNED COUPLINC t,ND F!! LED
((AfD*. WITH OIL, REh!![MBLEC MO
'fr(IN3ffi1EDPUMP. EETUPNED TO !ERVILT.
(iW-t2M394) t232133 1 F.'? t?%
0020 10/20/t7 1-PPP-074-0020- EnXPEDO,als it INI F'J# Ai AIN. THE DESIRED RUPOUT. REA!!EnttID
PunP MOTOR AND RETURNED TD titVICE.
1 (WR-8232535) s; P233223 0 P-C47 N210/07/87 0 PPP-of? 0kS2,EuwN,PLM FAf(D $1 DI! CHARGE PRE!!CEE WA3 LOW. PCTUAL 45.1 DISCXARGE PRE!!Utt LDU 84.2 P3!, PCCEPTABLE-90.3 Pt!,
4
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s f1LOWAFLE -87.4 PSI IfrELLIE OIQ Of '
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ADN3fMEXI. ADESTED IMPELLER CLLAIANCE
' s.fD.2N. THE ENTTRE Purr !! BEIs
^
. O JRUILT ON WR BU4424 M-423122;)
0234108 2 TCV C03 408? 11/03/87 2 fCV-003 0037 A,EilNM3,LOCPA.*ftatE ITEP< VI9s? LLWEICAfDC/.uPk!CATE0 V141
.f!ME EXCEEDED TAXI 5:.!5 RLLC'Mit $ft01( 1 TEM. OPLEATIch: $ttOt[D VALVE ED NO j
TINI NN !!-144.1 b'
- 7+
APPEARANCE Of Sitn 8IMDDG III Mr.rJMICM.
L 1
PRfit(A! IN tr.LL'E. M-823k108)
~
F N 484 0 !;P 04?
twl5 10/21/87 64 4110433.,fEPAIE Of REPLAEC,
COLFLING MA3 WDEN/IEPLACED CDUPLDC, l
f0.DG IENid MOTO 40 FIDUCDL
' CETHEfX FCTOR AND REDUCTION GEPR Ax0_.;
- IEPLACED GLIARD..PETutXED TO SEIVICt.
C M 8242484) 02kM23 2 TCJ C??
013101/04/h 2-FLV 070,0133-A,[e.PR9t!,'rPERfDW1,717I01 s
TO UNIT 2 EC3fARin INSPEtt Pt(Iht; ADA37 AMCI REPLACE Al REGUIIC.D 0251405 1 tEY 079 C00610/21/8/1-aQ-070-000$,s!' PLEASE Alf@E TO ~ ' E Pitted T;tE. Site!1 Catt0!ItN
' PERTCin IK!PECTION MD PLUl%1$ 7 tow CIACKING PEVIUU!!Y DOf!IFIED PAY LEP/IWC TetEt IR THE CCS HEAT EX0,mrt, ((!PONtI24.E FCI Tli raillE/ftt;&ED "A"
Tuf:E, Til!En MD FCV@ NO LEAL!.
REimiJ TO IIRVIt[. M-rdika!)
22N30 0 M Cl2 0$29 212 01/24/88 0 VLV Cl2 0529 2t?-C.FEPAIR CHECK V%VE "v3LVE WI UJH Csif/IEPMD M VALUE,
' <cLEMED THLTADED CONNECT r'.* a>D INSTALLID ATP UALVE. Etiur ) TO 4ERVICE L't 9?44230 F24 A32 2 PP C03 011t 01/24/83 2 P.9-C03-0118,0Ui!C90 PIN OIL FAULYY 4ILG-EEPLACE Outt0Alb OILER, IE!ERVCII tr.I, IETILL
'ADE$b #0R CdPRECT LEVEL, r!LLED DILEE WIT).' ttL TO CtttCCI LEVEL. IETURNED TO
!NVICE IWE424%320 E2 N ?S 2 TCV C42
- C93 12/W iti 2 rCV 942 0013,tD*?ECTED REPL PfttI 6 PAttW3A1 LDOLE fidel PREVIOut Etti Ox LEC, IW'.t!TIL4TE MD PEP AIR At NEltCl). Vf Lith'fLNED VALVE RETutNED VALLt TO O
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.1CC NX.'.AINTENMCE McHTHLY T2MRf CDs F42... U fuC $Yt ADC'#Et3. DATE.... DE!CRIPTICH.......................... CQ ttt C TIVE ACT I CN....
THE VLV It itING [XPD%D T3 A 2500
$(WICE. WE42?k175 PSIC PRC11 F2?d161 1 rit 070 000101/09/881-NEX-070 0028,CWPtH3,t[PAft fl2C REINSTALLED SOLT3 MD MADS. TCIGUCD LEM ON CCaFONENT C00 LING Mitt EAT COTH D03. IETURED TO S!WICE. (L't EXCHMCCI "i" (274141) 027492 2.t.9P 019 0053/412/07/8? 2-PPf 018 00$5/a4.IN!PECT AND REPAll il IEPOVED PUMP fl0511 ENCIht STM FOTP FCI 2B4 DIstL. INBCP.20 Pur CEKIATOR BUILDING ON W 08232323.
BEMINC UIStATIDM IN EXCt!! Of Il P,IL3 INSTALLED INTCIPAl.1 CF Pur INTO HOU3Ih6 l
YttTICet MD HCIIZ FCUND DutING CF PUMP DN 268-1 CNCINC RCTURNCD PUMP TO i
PitFCRMECE OF $!-7.3 NEED TO CD1Pi[TE 3(WICt. (181427d%2)
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WITH 214 DufACE I
(2642!k 2 FCV 074 0014 07/27/87 2-rCV 0?k-0014,CuMPtHLVALW titM LE MINC. REPACK VALVC.
0213143 2 A V 010 039312/17/8? 2-YLV 070-0M3-A, PLEA!C ttPAIR Of DI3A31sMittp VALWC CLEMED ALL PART!
t[ PLACE PeCKD1 DM VLV AT Af0VC ttA13t!KED VALW. ItPLACING $tWN RING 3 LOCATI0t RUP PE0'D.
Of PACKING BELON TE LMTEWN CING AND ttWM Ai4VE. KTWWED YALK 10 $tWICE.
(WR 81 2 45)
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MAINTENANCE
SUMMARY
(MODIFICATIONS) i 1
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1 SUhMARY OF VORK COMPLETED r
MODIFICATIONS - CURRENT STATUS JANUARY 1988 l
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e Major Capital Projects:
PN7101:
ECN 6388 - 500-kVA Swltchyard Current Transformer Heaters Workplan (WP) 12223 is in progress pending safe access to current transformers.
PN7102: ECN 5938 - Replace Feedwater Heaters 3 and a Preparation work is underway as time and manpower permits.
Installation of the monorail on unit 2 continues in preparation for the changeout of feedwater heaters 3 and 4.
Structural steel reinforcement continues on unit i heaters 3 and 4.
This work has been moved out into FY 1988.
PN7105: ECN 5009 - Essential Raw Coolina Water (ERCW) Pipina Chanaeout From Carbon Steel to Stainless Steel Some insulation activities remain incomplete and are being worked as resources permit.
No additional pipe replacement is scheduled in the near future.
PN7108:
ECN 6720 - Crane Consistency Proaram Unit 2 polar crane modification is complete.
Postmodification testing (PMT) by Electrical Maintenance is not complete. Unit 1 polar crane work started on July 6, 1987 and is approximately 98 percent complete.
Painting of blocks and limit switch weights remain. Auxillary Building crane WP 12596 is in the approval cycle.
Drawings have not been issued on the remaining cranes. WP 12596 is in nonwork status. Work is stopped pending resolution of budgetary problems..
PN7115: ECN 6719 - Volumetric Intrusion Detection System ECN 6719 is still on hold. Security is dissatisfied with system operation. Security and DNE have not concluded discussions on resolution.
Design is working on making the system functional.
Lighting is not finished. Workplan change for drainage is being written. Field Change Request (FCR) 6645 for DNE changes is approved. Work is stopped pending resolution of budgetary problems.
PN7122: DCR 1373 Secondary Side Steam Generator Preservation ECW 5657 - Installation of Moisture Separator Reheater (MSR)
Drain Valves Work is essentially complete on all the ECNs. Some since insulation installation activities are in progress as resources permit. b
Major Capital Projects (cont.):
ECN $712 - Evacuation Alarms - Auxiliary Buildint WP 12663 All fieldwork complete.
Workplan is in closure cycle.
ECN 5841 - Hot Shop Fire Protection / Evacuation Alarm -
WP 12664 All fieldwork for evacuation alarm complete. Awaiting Work Request (WR) B240406 to be worked to get fans restarted so we can do functional test of fire protection.
PN7123:
ECNs $938, 6305. 6571 - Replace Feedwater Heaters 1 and 2.
Units 1 and 2 and Eroded Pipe Modifications Group B is supporting PMT on heaters 1 and 2 on both units as requested.
Insulation work on unit 1 continues.
PN7130:
DCR 1156 - Pos; Accident Monitorint This work has slipped to allow work to continue on priority unit 2 restart efforts.
NRC commitment on NUREG 1.97 called for unit I completion by September 1987 (this has been moved to 1988) and unit 2 by U2C4 A request has been sent to the NRC to move the unit 2 completion date to U2C4.
PN7132: DCR 1748 - Seware Treatment Facility and Civil Urtrade New DCR for onsite sewage treatment facility upgrade. City of Soddy-Daisy will be responsible for interface work on site, lift station, and pipeline between Sequoyah Nuclear plant and Highway 27.
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PN7136:
ECN 6259 - MSR Tube Bundle Replaceme_nt Complete except for FMT. inservice leak test, and final cleanup.
FN7152:
ECN 6808 - External Conduit Seal [ng Both unit 1 and unit 2 workplans have been reported to Document Control as field complete.
ECN 6300 - Sensors and Detectors Complete.
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Major _ Capital Projects (cont.):
PN7161:
ECN $855 - Replacement of Doors A56 and A57 Installation of door A56 is complete. Security of A56 to be worked later. Work on door A57 and interlocks will begin later. Workplan 11654 is in work.
PN7181:
DCR 1898 - ECNs 6832 and 6596 - Dry Active Waste (DAW)
Building Electrical interface work is complete. Workplan closure held for Instrument Maintenance and Electrical Maintenance checks and update of SOIs by Operations.
PN7199:
Miscellaneous Activities Under $100.000 l
This is for various work orders prepared for work under
$100.000 total site cost. This wor),is done as m+npower resources are available that will not impact unit 2 restart effort.
Sitnificant Items:
The following major significant items are under Operation and Maintenance Expense (0&M) and will continue to be until restart of unit 2.
1.
Fuse Program Work ECN 5880 - Work complete for class IE unit 1 and 2 and non-IE l
fuses associated with unit 2 restart.
Remaining work is non-class IE unit 1 and non-class IE unit 2.
WP is being written for non-IE checklist for unit 1.
i ECN 685a - The workplan closure is complete, 2.
Cable Ampacity Program j
Unit 1 is in progress.
3.
Raychem Cable Splicing Work - Unit 2 Complete.
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Major Capital Projects (cont.):
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I ECN Sill - Provide Permanent Power to Manholes 42-46
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Electrical conduit and wiring installation for manholes 44-46 is complete according to WP 12262. Manholes 42 and 43 are being held for
.l information from DNE on power cable routing and terminations. FCR
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4572R1 was sent to DNE end was logged in, but it was not sent to the responsible engineer. Manholes 42-46 will be worked by FCR 4572RI.
i This item is not considered unit 2 startup by DNE and they will not l
authorize the engineer to do the necessary work to obtain pull cards or drawings for manholes 42-46.
FCR 4572R2 will be written to
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supersede 4572R1 for conduit and cable routing for manholes 42-46.
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ECN 5412 - ERCW Nuisance Alarms I
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WP 5412 Fieldwork complete.
Holding for Instrument Maintenance l
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TI-41-67.
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ECN 5:35 - Fire Doors i
I The installation of weather stripping continues as resources permit.
f ECN 5503 - Erscuation Alarms O&PS/ Fire Detection O&PS WP 12482 is in work.
WP 12664 - Material arrived approximately November 28, 1987. Work is I
in progress and is approximately 50 percent complete. Additional l
j natorial needs to be installed. A purchase request has been initi.ted.
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ECN 5552 - Condensate Demineralizer Modifications and High Crud Filter i'
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Upgrade to higher range instrumentation for condensate domineralizer j
system neutralization and nonreclainable waste pumps. A mode 2 l
restart item.
1 WP 5552 WP has been written and approved. Work is scheduled to start February 8. 1988.
ECN $599 - Conduit Suppotts for Fifth Vital Battery and Waste Disposal
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WP 12186 was closed and sent to Drawing Control Unit (DCU) on November 27, 1987. All fieldwork is complete.
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j Major Capital Projects (cont,j,:
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Other Items (cont.)*
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l ECN 5609 - Air Compressors Makeup Water Treatment Plant l
Installation and checkout is complete. Work is complete. WP 11987 is
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fleid complete. Obtaining all documentation for closure of workplan.
j ECN 5609 - Evacuation Alarm / Fire Detection Valve 26-290 i
WP 12387 is in work and is 90 percent complete. Workplan change is i
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needed to allow local testing of alarm horn, l
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ECN 5609 - Alteration to the Makeup Water Treatment Plant f
WP 12576 - Work is in process and approminately 90 percent complete, f
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j WP 12633 - Work is in process and approximately 50 percent complete.
j WP is being held for material on WP 12665 (Mechanical).
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VP 12731 - WP is approved and being held for material procured on purchase requests 74262A and 74321A.
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WP 12684 - WP in work, approximately 60 percent complete.
l WP 12665 - WP is being worked, and is 20 percent complete.
WP 12682 - WP is being worked, and is 20 percent complete.
j DCN 113 - WP 113 Workplan in work. WP 113 Workplan in work.
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DCN 66A - WP 0066A Modifications part is complete.
l ECN 5626 - Containment Ladders, Unit 1 A workplan is being written to incorporate this ECW. Modifications l
needs additional design information to complete.
DNE needs to issue i
all drawings listed on this ECN. Work has not begun because of this holdup.
STI - 105 - Complete.
ECN 5726 - CAQR SQP870478 - Reroute Sense Line Piping for Train i
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Separation to Panels 2-L-58 and 2-L-68 1
1 lieldwork is complete.
In-service leak check will be performed during heatup.
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1 Other Items (cont.):
ECN 575a - ERCW Nuisance Alarms VP $754 Fieldwork complete.
Holding for Instrument Maintenance TI-al-67.
ECN $8a1 - Hot Shop Fire Detec.tlon VP 12360 is 95 percent complete. Material needs to be ordered and installed for PNL 0-L-633.
4 ECN $935 - Correct Power Block Lighting Deficiencies Vp 12a37 has been approved and is in work. This is a nonrestart item. WP 12275 is being written.
Modifications needs DNE to provide light mounting detail for Raw Water Storage Tanks (RWSTs) and estimate design date after unit 2 restart. WP 5935-01 has been written to install security grills and gratings.
[CN 6005 - Replacement of AFV Air Ejector The workplan is complete except for the leak check to be done by SI-130.1 in mode 3.
ECN 6057 - Cable Tray Covers This activity is in progress for the unit 2 restart.
I ECN 6082 - Vent for Boric Acid Tank (BAT)
Work has started.
l ECN 6185 - Offsite Paging System Functional tests of the remote mobile units remain to be completed.
ECN 6196 - Pressurizer Hangers and Valves FMI is scheduled for unit I startup.
Remaining unit 2 work is scheduled for U2C3 refueling outage.
ECN 6205 - Replacement of Instrument Loop Fower Supply Fuses l
i Unit 2 and unit 0 work is complete escept for spares.
Fuses are not on order yet.
United Engineering has not notified materials group about fuse type (100 mil 11 ampere). Vorkplan 12447 has been turned i
into Document Control for partial completion.
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Major capital Projects (cont.):
Other Items (cont.):
ECN 6357 - Essential Raw Cooling Water (ERCV) Roof Access and Rails for Security Equipment WP 12238 is in work.
ECN 6380 - Replacement of Barton Pressure Transmitters Unit 2 fieldwort is complete, final closure awaiting instruction revision by Instrument Maintenance.
ECN 6388 Workplan 12223 - Craft support as needed for installation of hydrogen analyzers at 500-kV switchyard (50 percent work complete).
ECNs 6402 (Unit 1) and 6439 (Units 1 and 21 - Pressurizer Instrumentation Relocation Inservice tests will be performed when the system is brought up to temperature and pressure.
ECN 6429 - Component Cooling Heat Exchanger B Replacement DNE to procure piping, hanger, and PHE frame material. DNE to issue hanger drawings. Workplans are in work to fabricate and weld piping and fabricate and install new plate heat exchanger.
ECN 6437 - Replace FE-2-256 and 257 Complete.
ECN 6455 - Upgrade CV-3 Box Battery Packs WP 12295 has been issued. Modifications are complete for all CU-3 1
boxes.
Site Security still needs to perform some FMT before the workplan can be closed out.
ECNs 6491 and 6534 - Essential Raw Cooling Water (ERCW) Supports i
All restart work is complete. A workplan to remove previously i
j installed piping was approved and will be worked as resources permit.
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[CN 6543 - Install Public Safety Access Portals and Modify Entrance Road 1
Work is being held pending the release of drawings from DNE.
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Major Capital Projects (cont.):
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Other Items (cont.):
1 ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails for Security Equipment WP 12238 is in work.
I ECN 6380 - Replacement of Barton Pressure Transmitters i
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Unit 2 fleidwork is complete.
Final closure awaiting instructior:
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revision by Instrument Maintenance, j
ECN 6388 l
Workplan 12223 - Craft support as needed for installation of hydrogen
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l analyzers at 500-kV switchyard (50 percent work complete).
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t ECNs 6402 (Unit 1) and 6439 (Units 1 and 2) - Pressurizer Instrumentation Relocation
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Inservice tests will be performed when the system is brought up to i
ter.perature and pressure.
ECN 6429 - Component Cooling Heat Exchanger B Replacement DNE to procure piping, hanger, and PHE frame material.
DNE to issue hanger drawings. Workplans are in work to f abricate and weld piping and fabricate and install new plate heat exchanger.
i ECN 6437 - Replace FE-2-256 and 257 Complete.
ECW 6455 - Upgrade CU-3 Box Battery Pecks WP 12295 has been issued. Modifications are couplete for all CU-3 bones. Site Security still needs to perform suae PRT before the workplan can be closed out.
ECNs 6491 and 6534 - Essential Raw Cooling Water (ERCW) Supports l'
All restart work is complete. A workplan to remove previously j
installed piping was approved and will be worked as resources permit.
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j ECW 6543 - Install Public Safety Access Portals and Modify Entrance j
1 Road t
1 Work is being held pending the release of drawings from DNE.
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e Major Capital Projects (cont.):
Other Items (cont.):
ECN 6557 - Installation of CO2 Abort Switches Comp?ete.
ECN 6601 - Removal of Unit 1 Emergency Gas Treatmsnt System (EGTS)
Backdraf t Dampers PMT remains to be completed by the Mechanical Test Section. Fieldwork is cumplete.
ECN 6610 - Modify Air Return Fan Supports Unit I work is incomplete.
ECN 6631 - Modify Snubbers Documentation review is in progress for unit 2.
ECN 6689 - Relocation of Main Steam Power Operated Relief Valves (PORV)
All work is complete for unit 2.
Work on unit I has started.
ECN 6698 - Repull 120-Volt Cables Unit 2 is complete. Unit 1 is 90 percent complete and held by ECN 67a2.
ECN 6706 - 79.la Support Enhancement / Lost Calculations Repairs continue on unit I as resources allow.
This project has betn combined with the calculation regeneration project for unit I and work has started with one workplan being prepared and placed in the approval cycle.
Unit 2 work is complete and workplans are being closed.
ECN 6739 - Alternate Analysis Unit I work has started and 27 of 93 are complete. Work has not started on the maintenance items.
ECN 67a2 - Install Fuses in Radiation Monitor Power Supply Circuits The workplan is complete for unit 2.
Unit 1 is 50 percent complete.
Instrument Maintenance cannot support until 1988.
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Other Items (cont.):
ECN 6761 - East Valve Room (EVR) Blowout Panels Implementation of unit I work is progressing as resources are available.
Unit 2 work is complete.
ECN 678a - Documentation to Show Pipe Class Breaks Final closure is awaiting a revision to AI-19 deleting requirements to mark shift supervisor drawings.
ECN 6808 - Conduit External Sealing VP 12363 has been turned in to Document Control as field complete.
ECN 6815 - Installation Power Circuit Breaker Install 500-kV power circuit breaker and associated equipment for bay 1.
Retire 161-kV PCB and essociated equipment.
A total of eight workplans will be required.
Foundations and conduit are presently being installed by VP 1265a. VP 127a0 for lighting, drain pipe, and surface ground mat has completed the review cycle. VP 12739 for the structural steel installation has been written and approved.
Completion of VP 1265a will probably be delayed somewhat by late delivery of anchcr bolts and bad weather. An attempt is being made to make up for lost time. Vorkplan 6515-02 has been written and is 'n the review cycle. Vorkplan 6815-01 is now being written.
ECN 6860 - Control Room Bullet Resistivity - DCR 2268 - ECN 6860 VFs 12602, 12603, 1260s, and 12605 are in closure cycle.
ECN is complete except for miscellaneous touchup painting.
The lockset for door C-37 malfunctioned and a CAQR has been ititiated.
Expect l
modified design for lockset by February la. 1988.
Estimate two days work for completion.
ECN 6866 - Modification of Valve Room Doors Complete.
ECN 6871 - External Conduit Sealing DGB/CB/ERCV Complete.
l ECN 7000 - Addition of Support to Main Steam Dnsp Header Fieldwork is complete except for final inspections during heatup. __ _
Major Capital Projects (cont.):
Other Items (cont ?:
ECN 7078 - Install Hangers - Main Steam Piping Complete except for final inspections during heatup.
ECN 7190 - Replace Duct Detectors and Install Thermal Detectors WP 7190 Installation of uppar and lower compartment coolers is complete.
Installation of Auxiliary Building Gas Treatment Systen (ABGTS) train A and B coolers is complete.
Installation of containment purge coolers is complete.
Emergency Gas Treatment System i
(EGTS) train A and B sampling tubes is being reworked. Control Building emergency air cleanup for train A is complete. Train B work scheduled to start February 10, 1988.
ECN 7268 - Diesel Generator Remote Control Circuit Fuse Coordination Unit i VP 12653 is complete.
l ECN 7269 - Diesel Generator Remote Control Circuit Fuse Coordination Unit 2 VP 12653 is complete.
ECM 7291/7292_- DCR 2259 - WP 12715 - Unit 1 ERCW Strainers and Unit 2 ERCV Strainers l
Complete.
l ECN 729a - ERCV Check Valves for Turbine Building Compressors Complitte.
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ECN 7297 - Auxiliary Air Compressor ERCW Relief Valves Complete.
DCN X00006A - Remove Hydrogen Analyzers Tubing i
The workplan lacks PMT (SI-219).
l DCN 200018B - Install Needle Valve for Hydrogen Analyzers The workplan lacks PMT (SI-219).
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4 Major Capital orojects (cont. ):
Other Items (cont.):
DCN a9 - Computer Room Air Conditioner Awaitin6 instruction revision to close workplan.
DCN 70 - Hydrogen Analyzer Check Valves The workplan lacks FMT (SI-219).
DCN 80/82 - Flood Mode Spool Pieces Vork is complete.
DCN 85/86 - Replace Penetration Room Dampers Vork is complete.
DCN 89 - Crane Vall Penetration Additional penetrations were added by DNE and completed by Modifications.
DCN 95 - ERCV Cable Complete.
DCN 100 - Replace Valve 70-692 Complete.
DCN 116 - ERCV Cable Complete.
DCN 00068A__- DCR 2259 - WP 12700 -Reassign power supply breakers for boric acid evaporator "A" and control rod drive. Vork is complete, and the workplan is on hold for completion of work on ECN 5057. WP 12700 partial completion turned in to Document Control.
DCN X00091C - Complete.
Startup Activities List (SA;)
SAL Closure - Many man-hours were spent closinE these items.
Appendir A - Internal Conduit Scaling Complete.
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o Major Capital Projects (cont.):
Other Items (cont.):
Instrumentation Vertrication program for unit 2. there have been 953 discrepaneles issued to MODS to date with 476 not required for restart.
All discrepancies required for restart have been completedt 94 nonrestart discrepancies are open.
DCN aB - Complete.
DCN 7A - Cunplete.
DCN 9B - Complete.
DCN 14A - Complete.
DCN 204 - Complete.
DCN 23A - Complete.
DCN 28A - Complete.
DCN a5A - Complete.
DCN 46A - Complete.
DCN a8A - Complete.
ECN 7171 - Complete.
For unit 1 there have been 193 discrepancies issued to MODS to date with 30 not required for restart.
Of 163 required for restart. 93 remain open and are being worked.
Dry Active Waste Building ECN Sill - WP 12276 - Work is complete. WP closure is in process.
DCN X00059P, - WP 12713 - Work is complete. WP closed.
DCN X00061A - VP 12678 - Work is complete. WP closed.
DCN X000780 - WP 12725 - Vork is complete.
VP closed.
ECN 5712 - Evacuation Alarms Auxiliary Building WP 12663 - All fieldwork complete.
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Major Carital Projects (cont.):
Other I,tems (cont ):
ECN $841,- Hot Shop Fire Protection / Evacuation Alarm WP 12637 - All fieldwork for evacuation alarm is complete.
Modifications is awaiting Operations to get fans restarted to complete functional test on fire protection.
ECN 6388 - Install Hydrogen Analysers and Associated Equipeent for 500 tV PCB Current Transformers WP 12223 - Craft support as needed for installation of hydrogen analyzers at 500-kV switchyard. Work is 50 percent complete.
ECN 6596 - VP 12402 - Complete with the exception of five percent of paving to be completed spring 1988.
WP 12377 - Ccmplete.
VP12475 - Requires resolution of CAQR SQT871632 to begin closure cycle.
ECN 6832 - WP 12473 - Complete.
WP 124a9 - Complete. This was sent to Operations January 26, 1988 for closure.
WP 12477 - Requires Instrument Maintenance calibration and checkout of area radiation monitor and air compressor.
WP 12a78 - Complete.
WP 12612 - Cotplete.
Closure in process.
SOIs and $1s are being updated.
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a TENNECSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O.
Box 2000 Soddy-Daisy, Tennessee 37379 February 13, 1988 Nuclear Regulatory Connission Office of Managerent Inforeation and Progran Control Washington, DC 20555 Centlemeni SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT - JANUARY 1968 Enclosed is the January 1988 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY y/.
b 'n S'. J. 'S m i t h Plant Manager Enclosure cc (Enclosure):
Director, Region II Nuclear Regulatory Connission Office of Inspection and Inforcement Suite 3100 101 Marietta Street Atlanta, Georgia 303:3 (1 copy)
Director, Office of Inspection e'"jh 2-and Enforcerent l
Nuclear Regulatory Cor.nission Washington, DC 20555 (10 copies) i I
Mr. T. Marston Electric Power Research Institute P. O. Box 1041 Palo Alto, California 94304 (1 copy)
INPO Records Center I
Suite 1500 1100 Circle 75 Parkvay Atlanta, Georgia 30339 (1 copy) j Mr. K.
M. Jenison, Resident NRC Inspector i
OLPS-0. Sequovah Nuclear Plant i
A a E :. a t O c e :.< f on.tv Er ; toyer l
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