ML20237C538
| ML20237C538 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1987 |
| From: | Dupree D, Shawn Smith TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20237C477 | List: |
| References | |
| NUDOCS 8712210367 | |
| Download: ML20237C538 (53) | |
Text
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'-/ TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION
" NOVEMBER 1987" UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 v '
UNIT ?
DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted by:
S. J.< Smith, Plant Manager 9712210367 DR 8712151 ADOCM OMOO327 PDR, i A
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TABLE OF CONTENTS Page I. Operational Summary 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 4-7 Offsite Dose Calculation Manual Changes 8 l-II. Operating Statistics A. NRC Reports
. Unit One Statistics 9-11 -
Unit Two Statistics 12-14 '
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B. TVA Reports Nuclear Plant Operating Statistics 15 Reactor Histogram 16 Unit Outage and Availability 17-18 III. Maintenance Summary Electrical Maintenance 19-21 Instrument Maintenance 22-26 Mechanical Maintenance 27-28 Modifications 29-42 i IV. Offsite Dose Calculation Manual Change
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l OPERATIONAL
SUMMARY
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PERFORMANCE
SUMMARY
November 1987 n/
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The following summary describes the significant operational activities for I the month of November. ;In support of this summary, a chronological log of significant events is included in this report.
The units remained in an administrative shutdown the entire month due to ,
design control review, configuration control updating, and resolution of f significant employee concerns. Outage related maintenance and modifications are being performed. Unit 1 has been off-line 830 days. !
Unit 2 has been l off-line 831 days. Preparatations are underway for unit 2 alignment and mods 4 verification. !
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SIGNIFICANT OPERATIONAL EVENTS Unit 1
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Date Time Event 1 11/01/87 0001E The reactor was in mcde 5. The administrative i shutdown due to design control review, configuration control updating, and resolution of significant employee concerns continues.
[ 11/30/87 2400E The reactor was in mode 5. The administrative shutdown due to design control raview, configuration control updating, and resolution of significant employee concerns continues.
- Unit 2 1
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Date Time Event
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11/01/87 0001E The reactor was in mode 5. The administrative l t
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.
11/30/87 2400E The reactor was in mode S. The administrative shutdowra due to design control review, configuration control updating, and resolution of significant t employee concerns continues. Preparations are J underway for system alignment for mode 4 shakedown. !
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FUEL PERFORMANCE Unit 1
[' The core average fuel exposure accumulated during November was 0 MWD /MTU -
with the total accumulated core average fuel exposure of 0 MWD /MTU.
Unit 2 The core average fuel exposure accumulated during November was 0 MWD /MTU with the total accumulated core average fuel exposure of 8097.51 MWD /MTU. ,,
SPENT FUEL PIT STORAGE CAPABILITIES 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 ,
strainer conflict, and one location (A16) is unavailable due to an instrumentation conflict. Presently, there is a total of 348 spent fuel bundles stored in the SFP. Thus, the remaining storage capacity is 1,033.
PORVs AND SAFETY VALVES
SUMMARY
No PORVs or safety valves were challenged in November 1987.
SPECIAL REPORTS The following special reports were submitted to NRC in November 1987.
87-14 Fire doors C-36, C-37, and C-65 were not returned to functional status within the required seven-day limit allowed by TS LCO 3.7.12
- ending October 3, 1987. They were opened for ECN L6860 and WPs 12602 and 12604 to implement security improvements to comply with 10 CFR 73.55. These doors have.now been returned to operational status.
87-15 Fire door A-25 (to unit 1 turbine AFW pump room, auxiliary building, elevation 669) exceeded the seven-day limit allowed by TS LCO 3.7.12. The door was breached to facilitate the safe removal of asbestos insulation from the pump room to allow inspection of the piping in accordance with SMI-0-317-55, "Walkdown Of Alternate l
Analysis Piping And Supports." The door was opened on September 29, 1987, and returned to service on October 8, 1987.
87-16 Fire door A-71 (to 2A containment spray heat exchanger room, auxiliary building, elevation 690), opened September 30, 1987, exceeded the seven-day limit allowed by TS LCO 3.7.12.
Fire door A-72 (to 2B containment spray heat exchanger room, auxiliary building, elevation 690), opened October 11, 1987, exceeded the seven-day limit allowed by TS LCO 3.7.12.
p The doors were opened to allow temporary hoses (for service air / demineralized water connections) for wet layup of the shell side of the heat exchangers for chemistry maintenance, }
1 a j
87-17 On Novembsr 5, 1987, it was discovered (during a review of previously performed liquid effluent dose calculations), on two occasions TS LCO 3.11.1.3 total body projected dose limit was 7 exceeded. These releases were made without proceifsing through the (3 ) radwaste treatment system.
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TS LCO 3.11.1.3 requires that the liquid radwaste treatment system must be used to reduce the radioactive materials in liquid wastes before their discharge when the projected doses due to the liquid effluent to unrestricted areas would exceed 0.06 mrem per unit to ~
the total body or 0.2 mrem per unit to any organ in a 31-day period.
In June 1985, radioactive liquid releases were made with a projected dose of 0.14 mrem to the total body. In July 1985, radioactive liquid releases were made with a projected dose of '
j O.17 mrem to the total body. These releases were made from the condensate demineralized waste systems directly to the cooling tower blowdown line.
The cause of this problem was a deficient program in the past to ensure complete and accurate commitments in implementing documents. An SI review program has been implemented for technical adequacy and compliance with TS. Also, a filter system will be made available for releases before mode 4, unit 2.
87-18 Fire breached construction sleeve seals exceeded the seven-day limit required by TS LCO 3.7.12(a). These were opened to provide ventilation to dissipate welding fumes during the installation of bullet-resistant material per ECN L6860 and WP 12602. This maintenance was performed to improve security in compliance with
[T 10 CFR 73.55. The sleeves are located in the wall between the
( ) control building and unit 2 turbine building. All sleeves will be filled with concrete after it has been determined that they are no longer needed. '
87-19 The suspended ceiling in the Operations locker room, control building, elevation 732, was found damaged in three places, rendering the fire barrier nonfunctional. The ceiling provides 1-1/2 hours of rated protection. It was not repaired within the required time limit allowed by TS LCO 3.7.12, because materials could not be obtained. This repair is scheduled for completion in January 1988.
87-20 Fire door A-159 (personnel and equipment access room south of the refueling floor, auxiliary building, elevation 734) was breached October 27, 1987, and exceeded the seven-day limit allowed by TS LCO 3.7.12. A broken latch rendered the door nonfunctional, and the replacement parts could not be procured within the required time limit. The integrity of A-159 will be verified before unit 2 enters mode 4.
87-21 Fire barrier penetration door C-53 (to MCR, control building, elevatin 732) was nonfunctional greater than seven days as required by TS LCO 3.7.12. This was anticipated, since the initiation of q ECN L6860 to install MCR bullet-resistant doors. The door will be verified operable by December 19, 1987.
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. LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in November 1987. -
(.) Description of Event LER 1-87054 This report wa's submitted as a " voluntary report" to identify a potential problem with flood mode spool pieces and to keep NRC informed of ongoing activities at Sequoyah Nuclear Plant. ,,
A condition in which five ERCW flood mode spool pieces did not fit properly was discovered during an integrated design inspection. A CAQR was initiated to investigate the potential problem.
During the stage II flood preparation plan, these spool pieces are ~
required to be installed to replace CCS with ERCW as cooling water for spent fuel pool heat exchangers, reactor coolant pump thermal barriers, and sample system heat exchangers; and raw cooling-water with ERCW for the ice condenser refrigeration system. The root cause of the condition could not be specifically identified. The most probable cause is the gradual changes in internal piping stresses over the years, coupled with system modifications that have resulted in slight changes in the orientation of the piping.
Each spool piece was inspected and it was determined that all could be insta31ed with hanger adjustments, gasket adjustments, or alterations, if flooding conditions required installation. An O analysis is underway to assess the affects on the piping system.
/ It is not expected that any adverse affects would exist; however,
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the spool pieces are being modified to ensure proper fit. An inspection of all other spool pieces is underway. Long-term corrective action is still being evaluated. -
1-87067 On October 27, 1987, it was discovered that a portion of SOI-72.1,
" Waste Disposal System (Liquid)," was incorrectly performed. In order to ensure proper dilution of the monitor tank contents and comply with the limits imposed by TS 3.11.1.1, the SOI requires verification of a cooling tower blowdown flow rate of at least 15,000 gallons per minute (gpm). However, following a review of SOI-72.1, it could not be verified that the proper dilution flow rate was established. The event was caused by personnel failure to follow an approved procedure and the use of an inoperable flow transmitter to estimate the dilution flow rate. The flow transmitter was prohibited by the SOI because the diffuser pond was below the required minimum level of 679 feet. An alternate indicator is used if the primary indicator is inoperable. This also was not used for verification. Personnel involved in the violation have subsequently been counseled by management personnel about the importance of attention to detail and strict adherence to procedures.
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Description of Event LER i
1-87068 On October 27, 1987, during a review of SI-234.6,'" Technical
'\ Specification Fire Detectors, Units 1, 2, 0," it was discovered
- that one data sheet was missing. As a result, related fire alarm and annunciation equipment for zone 198 (125 volt battery board
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room II) exceeded its TS surveillance interval. The event was caused by personnel in the Electrical Maintenance Group not verifying that the SR was satisfied during its performance. Once .
it was determined that the subject data was not performed, a special performance package was issued and the fire alarms and !
annunciators were successfully tested. Personnel involved and )
l i responsible for approved work packages were counseled about the importance of ensuring that all work packages satisfy surveillance requirements. AI-4, " Preparation Review, Approval, and Use of j Site Procedures / Instructions," will be revised to provide ;
requirements for verification of correct and complete instructions.
1-87070 This report was submitted under 10 CFR 21 and as a " voluntary LER" to identify a defective voltage regulator on an emergency D/G.
On October 21, 1987, at 1100 EDT, it was discovered while troubleshooting a voltage regulator problem on D/G 2A-A, that a voltage-regulating diode was incorrectly installed. During the i
performance of SI-26.2A, " Loss Of Offsite Power With Safety Injection - D/G 2A-A Containment Isolation Test," the D/G came up to speed, but the circuit breaker that connects the D/G to the 6900 volt shutdown board closed with the terminal voltage at
[' approximately 5200 volts.
The immediate cause was that a diode was
( installed with the polarity reversed.
is still under investigation. The voltage The root cause of this event regulator with the reversed diode was installed on November 8, 1986, following
- troublehsooting for voltage swing problems. The post maintenance test did not detect the reversed diode at that time. The regulator with the reversed diode has been repaired and SI-26.2A has been performed with acceptable results. The voltage regulators for the remaining D/Gs, and a spare in stores, were inspected and all were found with correctly installed diodes.
1-87071 This LER was comprised of two separate conditions related to the i ERCW System. The conditions were reported as a " voluntary LER" to {
inform NRC of issues involving the ERCW system. {1 On October 5, 1987, it was concluded that electrical interlocks I (designed to prevent an ERCW strainer from automatically backwashing if a strainer in the same train is already backflushing) had been disabled and were not included in the most recent ERCW wiring diagram. Personnel failed to perform an adequate 10 CFR 50.59 safety evaluation or to request appropriate revisions to design documents before implementing a temporary alteration to disable the subject interlocks. ERCW strainer backwashing and backflushing operations are now being addressed by the implementation of manual procedures that are administratively controlled. Also on
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Description cf Event LER
,x-1-87071 October 5, 1987, a potential reportable occurrence'was written
( ) (cont)
\s / which concluded that the automatic features of the ERCW screen wash -
and strainer backwash systems had been disabled and subsequently l operated manually. Manual operation of the screen wash and strainer backwash systems was not reflected in the appropriate {
Operations procedures, nor was an adequate 10 CFR 50.59 safety evaluation performed to ensure that manual operation did not represent an unreviewed safety question. The event was caused by .
l the failure of Operations personnel to follow the applicable administrative procedure when changing the status of systems that are important to plant safety. Appropriate documentation has subsequently been issued to demonstrate the manual operation of these systems. TVA has evaluated these conditions, both )
individually and in combination, and determined that the ERCW system's ability to perform its designed safety function was not ,
compromised.
1-86015 This revised LER provided details concerning TVA's position with (Rev 3) respect to testing of the instantaneous trip function of molded case circuit breakers, and updates information originally supplied with respect to the status of corrective actions. Revision 0 was reported in the May 1986 report, revision 1 was reported in the June 1986 report, and revision 2 was reported in the September 1986 report.
1-87030 This revised LER provides additional information on completed
[} (Rev 1) corrective actions concerning a blown fuse in the emergency start
\,/ circuits, which resulted in spurious emergency diesel geenrator starts on two occasions. Revision 0 of this LER was reported in the July 1987 report. ~
1-87039 This revised LER provided a new reporting date of the analysis and (Rev 1) corrective actions for the ongoing investigation and the evaluation of the control room emergency ventilation problems. Revision 0 of this LER was reported in the August 1987 report.
1-87060 This revision LER provided additional details concerning an (Rev 2) inadvertent D/G start (caused by inadequate procedure) and the subsequent failure of a hydraulic actuator. Revision 0 of this LER was reported in the September 1987 report and revision 1 was reported in October 1987.
1-87065 This revised LER provides details concerning the ERCW screen wash (Rev 1) pumps being omitted from the ASME Section XI test program, resulting in potential degradation of ERCW flow to both units.
This revision clarifles the corrective action taken by TVA to ensure that pumps which are required to mitigate the consequences of an accident or achieve a safe shutdown of the plant are included in the ASME Section XI test program. Revision 0 of this LER was reported in the October 1987 report.
O V
ABBREVIATIONS n'
.[* l. ABI - Auxiliary Building Isolation
- 2. AFW -
- 3. AOI -
Abnormal Operating Condition
- 4. , BAT -
Boric Acid Storage Tank
- 5. ~ BIT - Boron Ihjection Tank
- 6. CAQR. - Condition Adverse To Quality Report.
- 7. CCS - Component Cooling System '
- 8. CRI - Control Room Isolation
- 9. CREV -
Control Room Emergency Ventilation System
- 10. CSS - Containment Spray System
- 11. CVI - Containment Ventilation Isolation
- 12. D/G(s)- Diesel Generator (s)
- 13. DCR - Design Change Request
- 14. DNE - Division of Nuclear Engineering '
- 16. ECN -
Engineering Change Notice
- 17. EGTS -
Emergency Gas Treatment System
- 18. EMI - Electromagnetic Interference
- 19. ERCW - Essential Raw Cooling Water
- 20. ESF - Engineered Safety Feature
- 21. FCV -
Flow Control Valve
- 22. FSAR - Final Safety Analysis Report
- 23. IMI - Instrument Maintenance Instruction
- 24. LCO -
Limiting Condition for Operation
) 27.
28.
PORC - Plant Operation Review Committee RCS - Reactor Coolant System 29, RHR - Residual Heat Removal
- 30. RM
- Radiation Monitor (RAD Monitor / RAD MON)
- 31. RWST - Refueling Water Storage Tank
- 32. SCR - Significant Condition Report
- 33. S/G(s)- Steam Generator (s)
- 34. SI - Surveillance Instruction /or Safety Injection
- 35. SOI -
System Operating Instruction
- 36. SQN - Sequoyah Nuclear Plant
- 37. SR -
Surveillance Requirement
- 38. SSPS - Solid State Protection System
- 39. TACF Temporary Alteration Control Form
- 40. TI -
Technical Instruction
- 41. TS(s) -
Technical Specification (s)
- 42. WP - Workplan
- 43. WR -
Work Request i
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0FFSITE DOSE CALCULATION MANUAL CHANGES O Revisions 16 and 17 to the ODCM were finalized July 6, 1987, and Decert.ber 4,1987, respe.ctively. A copy of each is found in Section IV of this report.
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e9 OPERATING STATISTICS (NRC REPORTS)
CPERATING. DATA REPCRT DOCKET NO. DO-327 DATE DECEMBER C4,1997 COMPLETED,DY D.C.DUPREE
(N/ TELEPHONE (615)B70-6722 ,
OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES:
- 2. REPORT PERIOD: NOVEMBER 1987
- 3. LICENSED THERMAL POWER (MWT): 3411.0 -
- 4. NAMEPLATE RATING (GROSS MWE): 1220.6
- 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS ' IN REPORTING PERIOD 720.00 8016.00 56257.00 f^% NUMBER OF HOURS REACTOR WAS CRITICAL O.00 0.00 24444.91
( ) REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
\s /. HOURS GENERATOR ON-LINE O.00 0.00 23781.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0 90 0.00 77060971.91
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 20976386.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) -4818.00 -43564.00 24858995.00
- 19. UNIT SERVICE FACTOR O.00 0.00 42.27
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 42.27
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 38.49
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 38.49
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 49.73
- 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
~
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
STARTUP IS UNDETERMINED AT THIS TIME PENDING DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SIGNIFICANT EMPLOYEE CONCERNS.
NOTE THAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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SEQUOYAH NUCLEAR PLANT
(S AVERAGE DAILY ~ POWER LEVEL
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DOCKET NO. : 50-327 UNIT : ONE DATE : DECEMBER 09,1987 -
COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 MONTH: NOVEMBER 1987 ,
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net) DAY (MWe Net)-
01 0 16 0 02 0 17 0 03 0 18 0 04 0 19 O 05 0 20 0
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OPERATING. DATA REPORT DOCKET NO.~00-328 "hTE DECEMDER 04,'1987 I- COMPLETED DY D.C.DUPRFF f TELEPHONE'(615)870-67DP ,
OPERATING STATUS 1.. UNIT NAME: SEGUDYAH NUCLEAR' PLANT, UNIT 2 NOTES:
- 2. - REPORT. PERIODi NOVEMBER' 1987
- 3. LICENSED . THERMALL POWER (MWT): 3411.0 --
4.1NAMEPLA'E R ATING (GROSS MWE): 1220.6
- 5. DESIGN ELECTRICAL. RATING (NET MWE): 1148.0
- 6. MAXIMUM . DEPENDABLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): .1148.0 8.- IF CH ANGES OCCUR ' IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS: ,
- 9. PCWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. : HOURS IN REPORTING PERIOD 720.00 8016.00 48217.00.
- ' <t. NUMBERLOF HOURS REACTOR WAS CRITICAL O.00 0.00 21984.54 0.00 0.00 0.00 k% ).HOURS REACTOR- GENERATOR RESERVE ON-LINE SHUTDOWN HOURS O.00 0.00 21494.22
.3 F4 UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
'16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22-
- 17. GROSS ELECTRICAL ENERGY' GEN. (MWH) 0.00 0.00 23536780.00-
- 18. NET ELECTRICAL. ENERGY GENERATED (MWH) ~3771.00 -54965.00 22512558.60
- 19. UNIT SERVICE FACTOR O.00 0.00 44.58
- 20. UNIT AVAILABILITY FACTOR O.00 0.00 44.58
- 21. UNIT CAPACITY' FACTOR (USING MDC NET) 0.00 0.00 40.67 '
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 40.67 1K3. UNIT FORCED OUTAGE RATE 100.00 100.00 50.38*j
~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:
PREPARATIONS ARE NOW UNDERWAY FOR SYSTEM ALIGNMENT. THE STARTUP
'OF UNIT-2 IS UNDETERMINED AT THIS TIME.
NOTE THAT THE THE YR.-TO-DATE AND CUINL ATIVE VALUES HAVE BEEN UPDATED.
- Corrected 3
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SEQUOYAH NUCLEAR PLANT
['N AVERAGE DAILY POWER LEVEL
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DOCKET NO. : 50-328 UNIT : TWO DATE : DECEMBER 09,1987 -
COMPLETED BY : D.C.DUPREE TELEPHONE : (615)870-6722 {
MONTH: NOVEMBER 1987 i
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe Net) DAY (MWe Net) 01 0 16 0 02 0 17 0 03 0 18 0 04 0 19 0 05 0 20 0
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TV A 482 A (Or@ *an NUCLEAR PLANT OPERATING STATISTICS SEQUOYAH NUCLEAR Plant
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Period Hours 720 Month NOVEMBER 1987 Item No. Unit No. UNIT ONE UNIT TWO PLANT 1 Averane Hourly Gross Load, kW 0 0 0 2 Maximum Hour Net Generation. MWh 0 0 0 3 Core Thermal Energy Gen, GWD (t)2 0 0 0 4 Steam Gen. Thermal Energy Gen., GWD (t)2 0 0 0 j 5 Gross Electrical Gen., MWh 0 0 0
% 6 Station Use, MWh 4,818 3,771 8,589 h 7 Net Electrical Gen., MWh -4,818 -3,771 -8,589
$ 8 Station Use, Percent N/A N/A N/A 9 Accum. Core Avg. Exposure, MWD / Ton 1 0 0 0 10 CTEG This Month,106 BTU 0 0 0 11 SGTEG This Month,106 BTU 0 0 0 12 13 Hours Reactor Was Critical 0.0 0.0 0.0 14 Unit Use, Hours Min. O:00 0:00 0:00 15 Capacity Factor, Percent 0.0 0.0 0.0 y 16 Turbine Avail. Factor, Percent 0.0 0.0 0.0 g 17 Gere ator Avail. Factor. Percent 0.0 0.0 0.0 0 18 Turbonen. Avail. Factor. Percent 0.0 0.0 0.0
$ 19 Reactor Avail. Factor. Percent 0.0 0.0 0.0 0 20 Unit Avail. Factor. Percent 0.0 0.0 0.0 21 Turbine Startuns 0.0 0.0 0.0 22 Reactor Cold Startuos 0.0 0.0 0.0 7's g 24 Gross Hes* Rate, Blu/kWh N/A N/A N/A j 25 Net Heat Rate, Btu /kWh N/A N/A N/A ,
y 26 W 27 g 28 Throttle Pressure, pseg N/A N/A N/A
& D Throttle Tempr rature. *F N/A N/A N/A d 30 Exhaust Presesre, inHg Abs. N/A N/A N/A E 31 Intake Water Temp., F N/A N/A N/A F 32 33 Main Feedwater, M lb/hr N/A N/A N/A y 34
[ 35 36 37 Full Power Capacity, EFPD 404.86 360.65 763.51 38 Accum. Cycle Full Power Days, EFPD 0.0 210.8416 210.8416 N 39 Oil Fired for Generation, Gallons 6,402 5 40 Oil Heatina Value. Btu / Gal. 138,000 41 Diese! Generation. MWh 97 47 Max. Hour Net Gen. Max. Day Net Gen. Load
~
~
MWh Time Date MWh l Date Factor, %
= 43 N/A N/A N/A N/A j N/A N/A Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
5 2(t) indicates Thermal Energy.
I mm Date Submitted DEC 151987 Date Revised h, _ rf , ,4/
/ +iant suberintencent
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SEQUOYAH ONE REACTOR HISTOGRAM
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SUMMARY
OF MAINTENANCE ACTIVITIES 0
_______________.__.____----__.____z _ _ - - - - _-_ - - - _ ---_ - - - - _ -
(-__ -
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MAINTENANCE sunnsgy (ELECTRICAL) l
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. .1 MAINTENANCE
SUMMARY
(INSTRUMENTATION) 1 i
)
i i
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-. % % s-..;2c.. ; ..>.;-c. u..L. .....o . ~ .
..- . CDMP MR2.... U FUNC SYS ADDRE!!. DATE. .. DESCRIPTION..... . . . CDD2ECTIVE ACTIDN. . . .. . ..
B125414 2 MVDP Od2 CW 03/26/87 2-MUDP-062-0090-A,EnXPRDw,ul0CFR50 t9x3, STPDKE TIME WAS TD0 SLL'W TD " ASS THE (10 VLV DPERATING SLDULY ITDE UZE !:2 SEC24D STRDKE REQUIREMENT. tDMhD E.~U
, SLOW TO PASS 10 SEC REQ DF SI idd.1 LIMIT SWITCH APPROXIMATELY 3 HANDWHEEL
( ACTUAL TIME 10.32 SEC TURHS FRDM FULL IPEN. WR B-125614.
T 2 FSV 001 0032 09/28/87 2-FSU-001-0032-A,En10CFR50.49n,nWRDn],Y LODSE OPERATOR PACKING NUT PDSSIBLY DUE ALUE WILL OPEN BUT WILL GT STAY DFEH TO VICRATION. TIGHTEED DPERATDR PACKING NUT RND RAN SI-idd.d FDR PRDPER DPERATIDN. WR B-223dd.
B239812 2 MVDP 063 0072 07/17/87 2-MUDP-043-0072-A,En10CFR50.49n3,nIn ADJUSTENT SCREW WAS LDOSE, PRODABLY DUE CLUTCH DN HANDWHEEL WCN'T ENGAGE TO VIBRATION, CAUSING TE DECLUTCH LEVER TO SLIP DUT OF TE PRDPER SETIING.
ADJUSTED HANDWHEEL DEC111TCH LEYER.
0239682 2 MYOP 074 0003 07/10/87 2-MUDP-074-0003-A,CN10CFR50.49n3,nIn STEM ACTUATED LIMIT SWITCH WAS DUT CF ,
ADJUST eTERLDCK LIMIT SWITCH FDR ADJUSTENT. ADJUSTED STEM ACTUATED LIAIT l 2-MVDP-dd3-72 SWITCH FDR PROPER CLOSURE. CHECKED UALUE l'
FDR PRIPER OPERATIDN.
B2434091 FSV 001 184 08/24/871-FSV-001-184-B,tn10CFR50.49n3,3.C. BLDW ACTUATDR ARM WAS DUT DF ADJUSTMENT. "
DOWN ISOL ULV. VLV WILL NOT DROP DUT ADJUSTED ACTUATOR ARM AND LIGHTS WORKED RED LIGHT WHEN STRDKED PROPERLY. ,
B276885 0 BLR 012 0050A 10/17/07 0-BLR-012-00508 ,B BDILER IS NOT GETTING NORMAL WEAR. REPLACED SHORTED SPARK ON AN IGNITIDH SPARK. INVESTIGATE AND IGNITER.
l REPAIR AS HECESSARY F277710 2 AHU 061 0024B 11/13/87 2-AHU-041-00248 ,NEED TO REPLACE DEFRDST HDRMAL WEAR. REPLACED CONTACTDR.
SWITCH DH 2kB
/
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l l
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- - ~ - ~ ~ ~ ~ ~ ---
~ - ~ ~ ~- -
mMEiL Jnihiwis,r. ~.sihe isJmr wh.57; ~ - - ~ - - -
COMP
. MR2.... U FUNC SYS ADDPE L Do fE, . . . DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . CDRRE CT"'!E ACTICN. . . . . . . . . . . . . . . . .
'l 82104441 MTRA 074 : 0C0 04/09/871-flTRA-074-0020-B,TDP DIL PDT HEDS REFEREFCE-l.RtB-202775. DIL LEAK WAS CASKET
~ CAUSED BY PREVIQUS INSTALLATI0H OF
/
G CDUERS ETIBIT CASKElt-REMDUED CDUERS -
MD REPLACD TDP CDUER MITH DNE FROM HDT . -
-] 1 ELECTRIC SHOP FABRICATD AND INSTALLED l GASKETS WIPD EXCESS DILFWDM MOTDR. i B2229451 GENB 082 091A 10/20/871-GENB-C82-C0018-A,EEMPRDn3,WHILE THE TIME DELAY RD.AY ACTUATED AT 5.60 .
PERFDRMING SI 102E/SA STEP d.2.5 TIME SECONDS MD SHOULD ACTUATE AT 5 SECONDS WAS 5.60 SHDULD HAYE E'EEN 5 SECDIOS + +- 1/2 SECDHD. ADJUSTED TIME DELAY RELAY '
1/2 SECOND TO 5.0 - 4.91 SECONDS. TESTD RELAY i REPEATEDLY nie PERFDRMED SI-102 E/SA WR B-2229d5.
B223604 2 BCTD 201 JL 10/19/87 2-BCTD-201-JL ,THE 480U BKR FOR 2B-9 ELDS ERE BROKEN DN TE POLE SHAFT.
FIE PUMP IS IMOPLAA8LE BECAUSE TE PERFDRED MI-10.5 DN BREAKER. REPLACD A CHARGING MOTW FAILS TO STDP WNEN THE POLE SHAFT MD FIBICTIONALLY TESTED
'SPIEDIC IS CHARGED MD FIRE CAME ET OREMER. PERFORflED PMT PER SI-275.2.
- AREND THE BREAKER WHEN IT MS DEED.
INUESTICATE AND KPAIR i
B223d57 2 FSV 001 0183 09/03/87 2-FSU-001-0183-A,Eu10CFR50.49m,NCZDNEu3, LIMIT SETCH ACTUATOR AIMI MS LODSC AND l BDTH RD MD GEEN LITES BURN cal 0RIT DPN NOT MMING CONTACT WITH LIMIT SMITCHES.
B229709 2 FSY 047 0338 '10/22/87 2-FSY-067-0338-B,tm10CFR50.4'Im3, DINTING TS-30-207 MS NOT EICED PRDPERLY FOR -
PERFRflANCE F SI-83 YALVE (FCV-67-338) PERFDIMIMCE F SI-83. SET HMDSWITCH IN j DID WOT CLDSE MEN EMER. CAS TREAT SYS P-AUTD: VALYE STAYED DPEN BECAUSE DF 1 RM CLR B-B HANDSETCH (2-HS-30-207) MS T3-30-207. CHMGED SETTING DN TS-30-207 PDSITIDN ED FDRfl START.TD P-AUTD. 5 FM STIFPED 5 FCU-d2-338 CLDSD. SET i TS-30-207 TD NORMAL 8 FM STMTED 5 YALUE IFEND. VERDID SDLENDID COIL AND~ -
M h
A,/1 GEND 082 0001E 10/19/871-GENB-082-00018-B, PERFORM LIMIT SWITCH IRIRKED PilIFERLY.
THE SPED SEITING W 02 EllG WAS SET AT TROUBLESHOOTING CECKS DM 1B-B D/G id (WIDE OPEN). ElRIED SPEED SETTING MOTRS MD CDUER ONN BUTH ACTUATURS MD <
CHECKD CLUTCHES AND INTEMAL GEMS.
ElRIUD FACE PLATE ON ENG 02 ACTUATOR MD AD,AlSTED FACE PLATE ON DOWEL PIM AND EINST8LLED FACE PLATE AFTER TE FIRST i RUN, RESET TE ACTUATOR TD 0. DIESEL RAN J
GuBD. i B233579 0 BATB 250 GW 10/20/87 0-BATB-250-DH-E,TlWEE 24 HOUR EDWALIZE SUSPECT DEBRIS OFF BATTERY PLATE HAD )
PERIDDS DID BRING TE PILDT CELL 53 DF SHORTD DNE OR Mille PAIRS OF PLATES VITAL BATTERY BANK II CAUSING EDUCED CELL VOLTAGE AND CAPACITY INSTALIID SINGLE CELL BATTERY 1 CHARGER DN CELL 53 Of VITAL BATTERY j BOARD II AND SET TD 2.3'l VOLTS. REMOVED .i CHARGER FRDM CELL 053 AND PERfDRED I SI-100. WR B-233581 INITIATED TD RESOLUE DN-2 0F SI-100.
- \
ri e
.. l4 sewann
__= ___ - ___ __-_ - .- -
t CDNP MR2. . . . U FUNC SYS A DDRESS. DATE. . . . DESCRIPTIDH . . . . . . . .... . . . . . . . . . . . . . CDRRECTIVE ACTIDH. . . . . . .. . .. . . . .
B234104 2 23 030 0014- 1 10/23/87 2-25-030-0014 1-A,[MioCFR50.490, LIMIT LIMIT SWITCH DAS DUT OF ADJUSTMENT. SEE SWITCH WILL HDT MAKE UP WHEN ULY IS WR-B-234144. ADJUSTED TCGGLE CAM AND FULLY DPEN HANDSWITCH IS ALSD DIFTICULY TIGHTEMED CDNTACT SinCK FDR 2-H3-3 i
(qV) . TD DPPERATE TAILED 31-146.18 SI-16d.4. 82M9. (DPEN LIMIT FAILED TO BREAK CLOSE0 -
RWP B7-2200-017 ANN LUGHT). ADJUSTED LIMIT SWITCH ACTUATOR ARM DH 2-ZS-30-14//1A. k"d B-2341% WAS WRITTEN FDR REWDRK. VALVE FAILID SI-16d.d.
B234107 2 ZS 030 6415 2 10/22/87 2-23-030-0015 2-B,[M10CFR50.49G,84 LIMIT SETCH WAS DUT OF ADJUSTMENT. .
ACCUM RDDM RX 714 A2 238 DEGREE tty ADJUSTD LIMIT SETCH TD DPERATE WHEN LIMIT SWITCH WILL HDT MAKE UP WHG FULLY UALVE FULLY DPEN. OPERATED UALUE AND AL j CLDSED FAILED SI idd.1 AND SI idd 4 LIGHTS WORKED PRTERLY.
B2345811 MTRA 074 {
002010/23/871-MTRA-074-0020-B,[N10CFR50.49n3, INSPECT A BREAK IN THE GASKET WAS EMITTING A i AND REPAIR / REPLACE THE GASKET TD THE SMALL JET OF HIL SMDKE AS WELL AS PUMP'S MDTDR CDVER ALLDWING DIL SEEPAGE. FABRICATED 5 INSTALLED A GASKET. -
B236707 0 TC 042 0105310/20/87 0-TC-062-01053 ,CKT 1653 CONTRDLLIR IS CONTRDLLER WAS BAD FOUND THE 10A FUSE l HDT CIVING AN DUTPUT TO THE HEAT TRACE. BLOWN. REPLACED CONTROLLER, WR B-236700 HD UDLTAGE DR CURRENT DUTPUTS HAS BEEN WRITTEN TD REPAIR DLD CDHTEDLLER. VERITIED YDLTACE.
B243283 2 FSV 030 0135 08/31/87 2-FSU-030-0135-A,[x10CFR50.49u3, REPLACE GRDUND INDICATION WHEN CIRCUIT 13 REED SWITCH. A GRDUND INDICATIDN EXISTS ENERGIZED DUE TO A CUT IN THE WHEN CIRCUIT IS ENERGIZED. WIRE-REN)YED CDVER FRDM YALVE AND LIFTED i WIRES. REPAIRED CUT IN WIRE WITH BAYCliEN SLEAYE. LAYED WIRE BACK DOWN AND REINSTALLED CDVER PER HIi 10.57 AND 21MsAI-7.M SLEAVE.
B2 0 CHR 311 012410/22/87 0-CHR-311-0124,5UCTION DIFFERENTIAL NDRMAL WEAR. REPLACED DIFFERENTIAL SWITCH IS HDT DPERATING PRDPERLY. PRESSURE SWITCH REINSTALLED AND ALICHED CHILLER.
B281204 0 LDCL 013 062910/22/87 0-LOCL-013-0629 , BATTERY 82 IN PANEL LIFE DF BATTERY HAD EXPIRED. REPLACED DLd29 FAILED DH SI234.7 REPLACE BAD BATERY 82. "
B297804 2 BDA 202 CP 10/20/87 2-BDA-202-CP-B,0N-DFF TDGGLE SWITCH BRDKEN TDGGLE SWITCH. REMDVED SWITCH BROKEN DFF AND CANNDT BE TURNED TF FRDM PANEL AND REPLACED. EMDVED 2 WIRES FRDM PRIMARY SIDE OF DLD SWITCH AND LAID THEM BACK DOWN DN PRIMARY SIDE DF HEW SWITCH. REMUDED 3 WIRES FRDM SECDHDARY SIDE OF DLD SWITCH AND LAID THEM BACK DDWH DH SECDHDARY SIDE.
B297870 2 FSU 043 028810/20/87 2-FSU-043-0288-A,[ul0CFR50.49M,NCZDNEu3, REED SWITCH WAS BAD. REMDUED TARGET RDCK WHEN IN CLOSE POSITIDH THE RED A10 GREEN YALUE CDVER 5 ADJUSTED THE REED SWITCH l LIGHT WERE DH FOR GREEN INDICATING LIGHT. STRDKED YALUE 4 TIMES. REPLACED REED SWITCH.
4
- i u&%,4
r
-INSTRUMENT MAINTENANCE MONTHLY REPORT FOR NOVEMBER 1987 I./
- I J COMMON 1.
Prepared and completed WP 7194-01 to change the setpoints of auxiliary air compressor pressure switches 0-PS-32-62. -62A, -82, -85, -88, and
-88A. This modification was necessary to support DNE accuracy
-calculations and was authorized by ECN 71948. .
2.
Prepared WPs 0093-01 (units 0, 1) and 0094-01 (unit 2) to change setpoints on various ventilation temperature and flow instrumentation as required to correct potential problems with safety limits as determined from DNE accuracy. calculations (reference DCN-X00093A and 94A). -WP 0094-01 is field complete.for the unit 2 instruments and WP 0093-01 is approximately 75 percent complete.
- 3. ' Coordinated with Operations and Project Management Staff to resolve reliability problems with the existing meteorological monitoring' system. Revised channel check and channel calibration procedures to
- allow the central emergency control center information system printer
[ located in the technical support center (TSC)] to be used as an alternate means for indicating meteorological date. Work is continuing to investigate signal cable deficiencies and additional indication ,
capabilities via the TSC computer.
- 4. Revised and performed calibration procedures for various CSSC instruments that were previously not included in a periodic calibration
} program. This is in accordance with the corrective action for DQA g/ Audit QSQ-A-86-007-D01. Work is continuing to verify that all CSSC instruments are properly addressed. j J
- 5. Prepared and performed Special Maintenance Instruction 0-90-2 to verify !
the calibration of rotameters in the radiation monitoring system. This completed the startup corrective action for DQA Audit QSS-A-86-0023-D09. Also prepared Preventive Maintenance Instruction 3 2522-90 to schedule future calibrations every 18 months.
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- 6. Continued work to identify and resolve discrepancies with the TI-41 scaling and setpoint document. This work is in accordance with CAR-85-08-13 and is currently scheduled for completion by June 1, 1988.
- 7. During a review / evaluation of PRO 1-87-396, it was discovered that SI-247.900, " Engineered Safety Features Response Time Verification,"
incorrectly calculated the response time for containment spray actuation. Previous test performances were reviewed and all data was acceptable. However, a recent modification to the containment spray pump load sequencing relay settings has caused the total channel response time to exceed the TS allowable value. PRO 2-87-106 was
-initiated, and Instrument Maintenance is coordinating with DNE, Site Licensing, and Electrical Maintenance to finalize a resolution.
- 8. During scheduled calibration testing, various compliance instruments
/" were found outside the required tolerances specified in TI-54 and TI-54.2. PR0s were initiated to document and evaluate each I out-of-tolerance condition. Additional reviews by the affected test organizations will determine if any past surveillance test results are invalid.
UNIT 2
.f'~St 1. Prepared'and completed WP 12623 to vent the dropping rssistor box for the. unit 2 turbine-driven auxiliary feedwater pump controls. This 1
i-l modification was authorized by DCN-X00044A and was needed to dissipate l heat buildup that had been causing component failures.
- 2. Completed all unit 2 instruction revisions and recalibrations required as a result of the revised Westinghouse setpoint methodology report. .
The revised setpoint analysis was necessary to reflect the actual accuracles of the measurement and test equipment available on site (reference NRC Violation 85-46-04).. With the completion of CAQR SQF870017 by DNE this issue will be restart complete for SAL 0859.
- 3. On November 27, 1987, a spurious high radiation spike occurred on radiation monitor 2-RM-90-106B. A CVI signal was initiated on train A.,
but not on train B. An investigation is underway to determine the root caule of the event and why only one train CVI signal was actuated. It is cuspected that the spike was caused by electrical noise and was not of sufficient duration to allow actuation of the additional relays required for a train B CVI signal.
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l , CDAP l MR2.... U FUNC SYS ADDRESS. DATE. . . DESCR.tPTIDH.. .. ... . . . .... ...... CDLxECTIVE ACTILH... .. . . .. . ..
i203553 0 FS OR I'6 09/22/87 0-FS-0#-204-A, CALIBRATE FLDW LDT F-47-204 AND APPLY TURQUE PUTTY TD
,,m FS-47-204 AFTER CEIBRATIDH -
Cf '2 FI 042 9JA 09/29/87 2-FI-062-93A ,EuMPRDu3,BDTH FLDW THE TRANSMITTER WAS FDUND TD BE DUT OF U/ .
INDICATORS 2-FI-62-938 AND 2-FI-62-82 TDLERANCE HIGH FROM THE MID THRDUGHT THE SHOULD READ apt EQUAL AC'9TS CALI:MrE G OD: TFE TiMMITTER 'aS P?CrFILLO
- LDDPS .
AND RECALIBRATES TO ACCEPTABLE IDLERANCES THEH LEFT IN SE2VICE.
0214364 2 TS 030 19610/23/87 2-TS-030-196-A.Ew10CFR50.49u3,UNISTRUT ORIGINATDR: K.HDFMANH-DNE E-1 CDRRECT MUT HDLDING UPPER LEFT CDRNER MDlNTING BEFDRE UNIT 2 STARTUP: UERIFIED THAT PLATE BDLT TD CHANNEL IS NDT IN RDPER UNISTRUT NUTS WERE PRDPERLY ALIGNED AKD UFRTICAL ALIGNMENT THAT HUTS ERE SMIC TICHT: VERIFIED BY QC. HD DEGRADATION FDUND.
B21Lt iR 2 TS 030 19710/23/87 2-TS-030-197-B,EN10CFTSL4953,ID TAG REQ 02IGINATDR: K.HDFMANN-DHE E-1:; ERIFIED MISSING 2-TS-30-197 THAT UNISTRUT NUTS WERE PRDPERLY ALIGED AND THAT NUTS WERE SNUC TIGHT. UERIFIED BY QC, ND DEGRADATIDH FDUND. #
D21 R49 0 FS 311 0010B 11/04/87 0-FS-311-00108,THIS FLOW SWITCH DDES FOUND DURING FIELD INSPECTIDd: REPLACED NDT HAVE A PROTECTIVE CDVER CDUER 5758 5888003427 B221949 0 FS 0# 209 09/22/87 0-FS-0R-209-B, CALIBRATE FLOW LDIP F-R-209 AND APPLY TDRQUE PUTTY TD FS-R-209 AFTER CALIBRATIDH 6:223689 2 LS 070 210B 09/28/87 2-LS-070-2100-A, CALIBRATE FDR ACCURACY CHECK QUT ENTIRE LDDP, IF HECESSARY 1:223@4 2 LS 070 210B 09/28/87 2-LS-070-2100-B, CALIBRATE FDR ACCURACY CECK DUT ENTIRE LDDP, IF HECESSARY B226202 0 TR 082 5034/3 09/29/87 0-TR-082-5036/3 , CALIBRATE AND ADJUST BRDKEN SWITCHS, MIPER FDR PRINT HEAD:;
HIGH TEMPERATURE SETPDIWTS DN EPLACED BROKEN SWITCHES, REED SWITCH, -
\O) 0-TR-82-5034/3 WIPER FDR PRINT HEAD AND CALIB. LEFT IH SERVICE 57565887015847, 5887016041, 5887015849, 5887015847, 5887015847.
023i266 0 FS 311 0033A 10/23/07 0-FS-311-00338 ,FLDW SWITCHES SUPPORT, SI-144.2SSTI-83, U-2 RESTART: .
0-FS-311-33A AND 0-FS-311-35A APEAR TD RECALIBRATES 3 PERFDRMED PMT BE CAUSING ERRATIC FAN DPERATIDR i B236267 0 FS 311 003410/23/87 0-FS-311-0034 , FLOW SWITCHES 0-FS-311-34 SUPPDRT QF SI-144 8 STI-83 FDR U-2, l AND 0-FS-311-35B APPEAR TD BE CAUSING RESTART:; RECALIBRATES 5 PERFORMED PMT ERRATIC FAN DPERATIDH D239929 2 SIS 082 5035B/3 09/29/87 2-$1S-082-5035B/3, TACK WILL HOT CAL 70 SI-170.3 BAD TACK: REPLACED TACHDMETER MEET SI-170.3 DH 2a-A DIESEL VERIFIED CAL PER -
SI-170.3.
8242R7 2 PS 082 5023/310/23/87 2-PS-082-5023/3 ,LDW ERG DIL PRESS HAS SI-102 BRDKEN BDDY WAS TICHTEN TD TIGHT l
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. COMP MR2... U FUNC SYS ADDRESS. DATE. . .. DE!CRIPTIDH.. . . . . . . . . .... .
CDRRECTIVE ACTIDH. . .. .. . ....
EXCESSIVE DIL LEAK. 5 CRACKED BODY DF SWITCH; REPLACED $
CALIBRATED SWITCH. LEFT IH SERVICE l f 57515837015455 i
I(V mJ2PS 082 5024/310/23/87 2-PS-082-5024/3 ,UIL LIHE TD PRESSURE BODY OF SWITCH WAS BRDKEN DUE TD BEING SWITCH IS LEAKING DIL. TIGHTEN TOD TICHT: REPLACED SWITCH 2-PS-82-5024/3 CALIERATED $ LEFT IM SERVICE.
B247351 1 PT 001 3073 10/23/87 1-PT-001-0073-D, EuMPR Du3, R EC ALIISTE THE TRANSMITTER WAS DUT OF TDLERANCE PRESSURE TRANSMITTER PER THE LATEST HIGH THRDUGHDUT MUST DF THE RANGE: THE UEVISIDH DF IMI-99,CC10.3B ,, !
TRAH$nITTER WAS RECALIBRATES WITHIH DESIRED TDLERANCE A PDST MAINTENANCE j TEST WAS PERFDRRED AND RETURNED LDDP TD SERUICE.
8248959 0 313 09/22/87 0-313 ,ENHPRDn3, TIGHTEN THE FLD(
THE SWITCH HAD DRIFTED LDW DUT OF ;
CDHDUIT AT THE INSTRunENT TOLERANCE: THE SETCH WAS CALIBRATED 0-FS-313-327(H) AMD AT IT'S RIGID' WITHIH DESIRED TOLERANCES AND LEFT IN' CDHDUIT SERVICE.
B2492341 PT 001 0072 10/23/87 1-PT-001-0072-E, ENHPR Du3, R EC ALIISTE PRESSURE TRANSMITTER PER THE LATEST REVISDH OF IKI99,CC 10.4B B274395 0 PDC 311 14 09/29/87 0-PDC-311-14, PRESSURE CDHIRDLLER IS FLUCTUATING EXCESSIVELY.
0274500 0 FM 027 0175 09/22/87 0-FM-027-0175, INSPECT AND REPAIR RECORDED. IT HAS FAILED DFFSCALE LDW B2766571 LIS 061 1958/B 10/19/871-LIS-061-1958/B ,ENHPRDn3, A CLDSUR OF INDICATDR GLASS BRDKEN & BINDING THE CLYCDL RETURH ULU. CAUSED THE GLYCDL PDIHTER. THE SWITCH CHARACTERISTICALLY EXPAHSIDH TANK TD DVERFLDW. HAS A SLOW RESPDHSE TINE 5 IF THE LEVEL <
CDMES UP DR DRDPS FAST THE SWITCH DDES -
[ HDT CD5E IN DE RESET.. A ZERD ADJUSinENT (g BRDUCHT THE INDICATDR IH. THE SWITCHES WERE FDUND TD BE IN TDLERANCE AND ANNUNCIATED IN THE CDHTRDL RDDM. -
B290024 2 TS 030 020109/26/87 2-TS"030-0201-A,En10CFR50.49n3,WHILE FDUND DH SI-193.2: REPAIRED / REPLACED PERFDRMING ST-193.2 WIRE WAS DAMAGED TERMINAL LUCS PER MSAI6 5 MSAI-7 WHILE REMDUING RAY-CHEM. WIRE HEEDS TD CDnPLETED SI-193.2 SECTIDH FDR BE REPAIRED. NEW LUG IS HEEDED DH 2-TS-30-186 5 201. CHARGES WERE WIRE. DOCUMENTED DH SI-193.2 5 IMI-134.
B290303 2 FIT 042 004910/23/87 2-FIT-062-0049 ,XnITTER WAS LOW 8 .1 GPM AND CDULD HDT BE ADJUSTED BECAUSE ZERD PDT WAS ADJUSTED DUT THE TDP.
B2903961 PT 003 132A 10/23/871-PT-003-132A-B, TRANSMITTER REQUIRED TD HD FAILURE:; CALIBRATED XHTRE PERFDRMED C\
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..a iau .uw . wu e s .snnu m.c.nxr u vz-a COMP M2. . . . U FUNC SYS ADDRESS . DATE. . . . DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . CO RRECTIVE ACTI0H. . . . . . . . .
BE CALIBRATED WITHIN 12 MONTHS Of Pfli' PERFIRMMCE (F RT 4990 (SI/00 TEST)
- W ' 2 FI ~ 047 12210/22/87 2-FI-Od?-122,EuMPRDG2-TI-67-122 SHDWS WHILE INVESTICATIHC THIS C0HDITICH IT j 3000 CPM. ERCW FLOW WITH HD FLOW EAS FOUND THAT TE FLOW TRANSMITTER -
PRESENT. 2-FT-047-0122 MAS DUT (T CALIBRATIDH AFFECTING THE INDICATOR READIHC.. THE a . TRANSMITTER WAS CALIBRATED WHICH CORRECTED THE INDICATOR READIHC.
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SUMMARY
(MECHANICAL) 1 0 '
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' MECHANICAL MAINTENANCE MONTHLY rep 0RT FOR NOVEMBER 1987
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COMMON L \- > 1. Completed repairs on auxiliary boilers.
- 2. Continued repairs on traveling water screens.
UNIT 2 ,
- 1. Completed repairs on CCS heat exchan6er "B".
2._ Completed repairs on elevation 690 penetration room coolers.
- 3. Completed repairs on auxiliary air compressor check. valves.
- 4. Completed repairs on 2-FCV-74-2 RHR valve.
- 5. Completed repairs on 2-LCV-3-164 auxiliary feedwater valve.
- 6. Completed repairs on 72-513 suction relief valve, CSS.
- 7. Continued repairs of ESF coolers. _
- 8. Completed WP 12676 on control room ventilation (A/C) dampers.
- 9. Completed repairs on B-train control room drive mechanism cooler duct.
- 10. Completed repairs.on 2-VLV-70-87/687 CCS.
OTHER
- 1. Continued clostre of various CARS, DRs, and CAQRs.
- 2. Continued Surveillance / Maintenance Instruction reviews and revisions.
- 3. Continued efforts to reduce WR backlog.
,_, 4. Continued support for equipment condition evaluation report.
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CCMP MR2. . . . U FUNC SYS ADDR E!S .; DATE. . . . DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . . . . . . . . . . . . . . .
B223314 2 FCV 074 001211/12/87 2-FCV-074-0012- A,UKUE HAS EDRON BUILDUP BORON BUILDUP-CLEAMED BORON OFF PACKING AROUND STEM CLAHD, REMOVED Dlb PACKING AND INSTELED
-p- NEW PACKING.
S' d 0 ULY 026 c96010/02/87 0-ULY-024-0940, EXCESSIVE LEMAGE, V- REPAIR AS NEEDD . RWP REG'D BAD UALUE-REPLACD DRIP CHECK VALVE.
B236054 0 DDR 410 C-54 09/08/87 0-DOR-410-C-54 ,FOR SUPPORT OF STI-83
~ RESTART U2 REPGIR DOOR SEAL TO STW AIR LEAKAGE.
B239764 2 ULY 062 035A 09/05/87 2-ULV-062-03054-A, LEAKING VALVE, RWP WDEN PACKING-REMOVED OLD PACKING, REQUIRED "'
CLEMED UALUE AND STUFFING BDX MD RPACKED UALUE.
B247418 2 ULY 042 ~0608 08/31/87 2-ULV-042-0608-5, PERFORM APPROPRIATE WDR PACKING-EMOUED EL OF THE OLD MAINTENANCE TO CORRECT THE REASON FOR PACKING, CLEANED URUE STEM MD STUFFING BORON BUILD W AREND STEM. - RWP BOX. REPACKED UEVE WITH NEW PACKING AND REGUIRD. ETIED TO SERVICE.
B2485951 ULU 026 1253 08/22/871-ULU-024-1253 ,EPLACE EXISTING FIRE MADE W 3/4" MIPPLES AND 1/2" NIPPLES, PROTECTION DRIP CECK URLVE WITH NEW INSTALLED K W U EUE.
DRIP C E CK UE E (1-24-1253)
B274035 2 ULY 047 0544D 11/04/07 2-ULU-067-05ddD-8,ELIEF ULY IS TRASH AND DIRT ON SEATS AND DISC, STEM RELEAVING ' 1 DRIP A SEC. WAS FIR 910 ENT- REMOED RELIEF URUE -
FROM LINE MD CARRIED TO SHOP, DISASSDBLED ELIEF URUE TO CLEAN, LAPPED URUE MD INSTELED NEW STEM AND GASKET Am REIMSTELD.
t B27 dido 1 PMP 003 0118 09/17/871-PMP-003-0118 ,[uMPRDu3,EXCESSIE PACKING WDR ET. PACKING WAS PEVIOUSLY PACKING LEAK 57 REPAIR AS NEEDED. ADJUSTD UNTIL TEE WAS 10 M0E ROOM FOR AD,AISTENT-REPLACED AND ADJUSTED PACKING. INSTELD NEW DILER BULB AND e
-O Bi 0 ULU 012 ADDD DIL.
0785A 11/10/87 0-ULV-012-0785A ,uIn VALUE IS LEMING DEFECTIVE UALUE- EPLACED URLUE THRU B29718d i ULY 024 128108/22/871-ULU-024-1281, REPLACE EXISTING FIRE MADE F 3/4" NIPPLES AND 1/2" NIPPLES, -
PROTECTION DRIP CHECK UALUES WITH NE!! INSTALLED NEW UALUE.
DRIP CECK UEVE.
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SUMMARY
l (MODIFICATIONS) 1 t
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SUMMARY
OF WORK COMPLETED MODIFICATIONS - CURRENT STATUS NOVEMBER 1987 I
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- i ! i. Maior Capital Projects:
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\j PN7101: ECN 6388 - 500-kVA Switchyard Current Transformer Heaters Workplan'(WP) 12223 is in progress pending safe access to current transformers.
'PN7102: ECN 5938 - Replace Feedwater Heaters 3 and 4 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 will be moved out into FY 1988. '
PN7105: ECN 5009 - Essential Raw Cooling Water (ERCW) Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of unit 1 isolation valves was completed. Some insulation activities remain incomplete and are being worked as resources permit.
PN7108: ECN 6720 - Crane Consistency Program -
Unit 2 polar crane modification is complete.
(T Postmodification testing (PMT) by Electrical Maintenance is
('~ ) not complete. Unit 1 polar crane work started on July 6, 1987 and is approximately 90 percent complete. Auxiliary Building crane WP 12596 is in the approval cycle. Drawings -
have not been issued on the remaining cranes.
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.
PN7122: 'DCR 1373 Secondary Side Steam Generator Preservation ECN 5657 - Installation of Moisture Separator Reheater (MSR)
Drain Valves Work is essentially complete on all the ECNs. Some minor insulation installation activities are in progress as resources permit.
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'(v ) Maior Capital Projects (cont.):
i PN7123: ECNs 5933, 6305, 6571 - Replace Feedwater Heaters 1 and 2, I
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Units 1 and 2 and Eroded Pipe i i
Modifications Group B is supporting PMI on heaters 1 and 2 on both units as requested. Insulation work on unit 1 continues. ,,
PN7130: DCR 1156 - Post Accident Monitoring This work has slipped to allow work to continue on priority unit 2 restart efforts. NRC commitment on NUREG 1.97 calls for unit 1 completion by September 1987 and unit 2 by U2C4.
A request has been sent to the NRC to move the unit 1 completion date to U2C4.
PN7132: DCR 2324 - Sewage Treatment Facility and Civil Upgrade This DCR has boen cancelled. TVA has opted to tie in with
, the Soddy Daisy sewer system.
PN7136: ECN 6259 - MSR Tube Bundle Replacement Complete except for PMI, inservice leak test, and final cleanup, t
( PN7152: ECN 6808 - External Conduit Sealing Unit 2 work is complete. Unit I workplan is in work. -
PN7159: Appendix R l
ECN 6300 - Additional Sprinklers and Draft Stops j
All fieldwork and testing are complete. Procedures revisions are in progress.
ECN 6300 - Sensors and Detectors All fieldwork and testing is complete.
PN7161: ECN 5855 - 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.
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j Major Capital Projects (cont.):
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PN7181: DCR 1898 - ECNs 6832 and 6596 - Dry Active Waste (DAW)
Building. ,
Electrical interface: DNE is to provide new design for ,j terminating the telephone cable - WP 12475RI. Operations is to upgrade WR B248540 for repair of 480-V power supply of DAW security lighting - WP 12476.
PN7199: Miscellaneous Activities Under $100.000 This is for various work orders prepared for work under
$100,000 total site cost. This work'is done as manpower resources are available that will not impact unit 2 restart effort.
Significant 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. Close out in process.
ECN 6854 - The workplan is complete. Close out'in process.
- 2. Main Steam Valve Vault (MSVV) Cable and Insulation Work l Complete.
- 3. Cable Ampacity Program Unit 2 is complete. Unit 1 is in progress.
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- 4. Raychem Cable Splicing Work - Unit 2 l
The 100 percent walkdown outside containment (requested by DNE) is in process. The walkdown is scheduled to be complete by December 8, 1987.
VLH Modifications 11/4/87
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r Major Capital Projects (cont.):
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Other Items (cont.):
ECN 5435 - Fire Doors The installation of weather stripping continues as resources permit. '
ECN 5111 - Provide Permanent Power to' Manholes 42-46 Electrical conduit and wiring installation for manholes 44-46 is complete according to WP 12262. Manholes 42 and 43 are being held for information from DNE on power cable routing and terminations. FCR 4572R1 was sent to DNE and was logged in, but it was not sent to the "
responsible engineer. Manholes 42-46 will be worked by this FCR 4572R1. This item is not considered unit 2 startup by DNE and they will not authorize the engineer to do the necessary work to obtain pull cards or drawings for manholes 42-46. FCR 4572R2 will be written to supersede 4572R1 for conduit and cable routing for manholes 42-44.
ECN 5503 - Fire Detection System O&PS Building Workplan 12482 is in' work.
- ECN 5599 - Conduit Supports for Fifth Vital Battery and Waste Disposal e Area N
Workplan 12186 was closed and sent to Drawing Control Unit (DCU) on November 27, 1987. All fieldwork is complete. <
ECN 5609 - Air Compressors Makeup Water Treatment Plcnt
)
Installation and checkout is complete. Work was completed. WP 11987 is field complete. Obtaining all documentation for closure of workplan. DNE is evaluating results of post maintenance test.
ECN 5609 - Evacuation Alarm Workplan'12387 is in work and is 90 percent complete. I ECN 5626 - Containment Ladders, Unit 1 A workplan is being written to incorporate this ECN. Modifications needs additional design information to complete. DNE needs to issue i all drawings listed on this ECN. Work has not begun because of this j holdup. )
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( Major Capital Projects (cont.): -
Other Items (cont.):
ECN 5713 - Various Platforms in Lower Containment The installation of-trollies on unit 1 is incomplete. ~
ECN 5726 - CAQR SQP870478 - Reroute Sense Line Piping for. Train separation to Panels 2-L-58 and 2-L-68 Fieldwork is complete. In-service leak check will be performed during heatup.
ECN 5841 - Hot Shop Fire Detection Workplan 12360 is 95 percent complete.
ECN 5935'- Correct Power Block Lighting Deficiencies Workplan 12437 has been approved and is in work. This is a nonrestart item. Workplan 12275 is being written. Modifications needs DNE.to provide light mounting detail for Raw Water Storage Tanks (RWSTs)'and estimate completion date after unit 2 restart. =
ECN 6005 - Replacement of AFW 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, j ECN 6082 - Vent for Boric Acid Tank (BAT)
Workplan is approved. Work will start as resources become available.
ECN 6147:- Airlock Packing Nut Final testing of the airlocks on unit 2 was completed. '
ECN 6185 - Offsite Paging System Functional tests of the remote mobile units remain to be completed.
ECN 6196 - Pressurizer Hangers and Valves i PMT is incomplete and scheduled for startup for unit 1. Remaining unit 2 work is scheduled for U2C3 refueling outage.
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-I Maior Capital Projects (cont.): ..
Other Items (cont.):
ECN 6205 - Replacement of Instrument Loop Power Supply Fuses Unit 2 work is complete. Unit 1 work and spares are incomplete. ~
ECN 6380 - Replacement of Barton Pressure Transmitters Fieldwork is complete. Final closure awaiting instruction revision by
- j. Instrument Maintenance.
ECN 6357 - Essential Raw Cooling Water (ERCW) Roof Access and Rails ~
for Security Equipment l
Workplan 12238 is being held for DNE. approval of FCR showing
. Installation details. No new date for release of approved FCRs or drawings by DNE has been established.
j 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 .
temperature and pressure. l ECN 6437 - Replace FE-2-256 and 257 1
Unit 2 work is complete. Unit 1 lacks electrical work and calibration. -
ECN 6455 - Upgrade CU-3 Box Battery Packs Workplan 12295 has been issued. Modifications are complete for 105 of 129 CU-3 boxes. Work is presently in progress.
ECNs 6491 and 6534 - Essential Raw Cooling Water (ERCW) Supports All restart work is complete. A workplan to remove previously
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installed piping was approved and will be worked as resources permit.
ECN 6543 - Install Public Safety Access Portals and Modify Enter.nce Road Work is being held pending the release of drawings from DNE. ;
ECN 6557 - Installation of CO2 Abort Switches.
Workplan 12607 is 40 percent complete.
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'[ Major Capital Projects (cont.):
Other Items (cont.):
~ECN 6601 - Removal' of Unit 1 Emergency Gas Treatment System (EGTS)
Backdraft Dampers PMT remains to be completed by the Mechanical Test Section. Fieldwork is complete.
ECN 6610 - Modify Air Return Fan Supports Unit I work is incomplete.
Documentation review is in progress for unit 2.
ECN 6689 - Relocation of Main Steam Power Operated Relief Valves (PORV)
Instruction revision is in process.
ECN 6698 - Repull 120-Volt Cables -
, Unit 2 is complete. Unit 1 is 90 percent complete and held by ECN _
[ 6742.
v ECN 6706 14 Support Enhancement Repairs continue on unit 1 as resources allow. Initial inspections for unit 1 lack approximately three supports for completion. Unit 1 i evaluations are continuing. Documentation review of unit 2 work is in progress. This project is being combined with the Calculation Regeneration Project for unit 1.
ECN 6715 - D/C Random Loads Both trains are complete. A technical specification change has been requested to close this workplan. The change has been approved by the NRC but has not yet been received by TVA.
, ECN 6717 - Stub Bus Fuses Work is complete.
ECN 6739 - Alternate Analysis Unit I work has been started.
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[ Maior Capital Projects (cont.): .
Other Items (cont.):
'ECN 6742 - 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.
ECN 6761 - East Valve Room (EVR) Blowout Panels Implementation of unit I work is progressing as resources are available. Work on a unit 2 EVR door was complete. However, a material change was requested by DNE and is in progress. '
ECN 6784 - Documentation to Show Pipe Class Breaks Workplan was approved.
ECN 6808 - Conduit External Sealing Workplan 12363 is in work.
ECN 6810 - Rework Category "C" Devices f Workplan closure is in process.
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ECN 6815 - Installation Power Circuit Breaker Install 500-kV power circuit breaker and associated equipment for bay-
- 1. Retire 161-kV PCB and associated equipment. A total of eight workplans will be required. Workplan 12654 is being worked. Workplan 12739 is being written. Workplan 12740 is in the approval cycle, j ECN 6866 - Modification of Valve Room Doors Fieldwork is complete. However, 'NE D requested a material change which is in progress.
ECN 6871 - External Conduit Sealing DGB/CB/ERCW Physical work is complete. Data sheet paperwork is being coordinated for closure by December 15, 1987.
ECN 7000 - Addition of Support to Main Steam Dump Header Fieldwork is complete except for final inspections during heatup.
ECN 7078 - Install Hangers - Main Steam Piping Complete except for final inspections during heatup.
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l -Maior Capital Proiects (cont.):
Other Items (cont.):
"DCN 80/8_2_ - Flood' Mode Spool Pieces l' A workplan was approved and work started. '
DCN 85/86 Replace Penetration Room Dampers i- The DCNs were_ received, and the workplans were written, approved, and
) placed in work.
l DCN 87 - AIW Silicon Rubber Cable Replacement '
A workplan is in process to remove the remaining AIW silicon rubber cables. The scheduled completion date is December 13, 1987.
1 DCN 89 - Crane Wall Penetration A DCN was received, and the workplan was written, approved, and placed in work.
l DCN 100 - Replace Valve 70-692 A DCN was received, and the workplan was written and placed in the j
Q spproval cycle. '
ECN 6429 - Component Cooling Heat Exchanger B Replacement .e A workplan is in the review cycle to modify two supports to resolve interference with the removal path. .DNE is to procure piping, hanger and plate heat exchanger (PHE) frame material. DNE is to issue hanger and frame drawings. A workplan is in the review cycle to fabricate and weld piping.
A DCN was received, and a workplan was written and placed in the approval. cycle.
Control Room Bullet Resistivity - DCR 2268 - ECN 6860 Workplans 12602, 12603, 12604, and 12605 are in work. Approval is needed from DNE for FCR 6271.
Startup Activities List (SAL)
SAL Closure - Many man-hours were spent closing these items.
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( Maior Capital Projects (cont.):
Other Items (cont.)
ECN 7089 - ERCW Check Valve Replacement Hanger work was completed. '
i ECN 7110 - Relocate Auxiliary Feedwater Controllers Work is complete.
ECN 7281 - Grout ERCW Hanger 4
Work is complete.
ECN 7294 - ERCW Check Valves for Turbine Building Compressors Fieldwork awaiting receipt of material.
ECN 7297 - Auxiliary Air Compressor ERCW Relief Valves Fieldwork is complete. -
ECN 7322 - Thermal Interferences a g An ECN was received, and the workplan was written and placed in the approval cycle.
r DCN X00006A - Remove Hydrogen Analyzers Tubing The workplan lacks PMTs (SI-219).
DCN 200018B - Install Needle Valve for Hydrogen Analyzers The workplan lacks PMTs (SI-219).
DCN 49 , Computer Room Air Conditioner The workplan is complete.
DCN 70 - Hydro 6en Analyzer Check Valves A DCN was received, and a workplan was written and placed in the approval cycle.
DCN,73 - Installation of Microbiological Induced Corrosion (MIC) Boots Work is complete.
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2 I Major Capital Projects (cont.):
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'Other Items (cont.):
Appendir A - Inter'nal Conduit Sealing Fieldwork is complete on WP 12272.
Instrumentation Verification Program
, There have been 953 discrepancies issued to MODS to date with 476 not required for restart. All discrepancies required for restart have been. completed, 231 nonrestart discrepancies are open.
t l DCN 4B - Fieldwork is complete.
DCN 7A - Fieldwork is complete.
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DCN 9A - Fieldwork is complete.
ECN 7297 - Auxiliary Air Compressor - ERCW Relief Valves The workplan is in the closure cycle. :
DCN 14A - Fieldwork is complete.
DCN 36A - Fieldwork is complete.
ECN 7171 - Fieldwork is complete. r Lost Hanger Calculations 1
ECNs 7276, 7282, 7283, 7284, 7290, 7293, 7295, 7296, 7298, 7299, 7300, 7302, 7303, 7304, 7305, 7307, 7308, 7312, 7313, 7320, 7321, and 25 WRs, There are 65 supports complete with 34 in work. Work is just starting on the 25 WRs.
Dry Active Waste Building l l l ECN 6832 - WP 12473 - Complete. l WP 12449 - Requires energization of charged HVAC system for closure. I WP 12477 - Requires Instrument Maintenance calibration and checkout of area radiation monitor and air compressor.
WP 12478 - Complete.
WP 12612 - Modification is to complete fire detection l system testing following vendor lateration of relay !
module. The relay module obtained could not accomplish DNE's intended function as originally installed.
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(%- ) Maior Capital Projects (Cont.):
1 Other Items (cont.):
ECN 6596 - WP 12402 - Complete with the exception of 5 percent of paving to be completed spring 1988. ,
WP 12377 - Complete. i ECN 7268 - Diesel Generator Remote Control Circuit Fuse Coordination Unit 1 WP 12653 is field complete and entering closure cycle.
Surveillance Operating Instructions (SOIs) are being ~
updated.
ECN 7269 - Diesel Generator Remote Control Circuit Fuse Coordination Unit 2 WP 12653 is field complete and entering closure cycle.
S0Is are being updated.
DCN 00068A - DCR 2259/WP 12700 - Reassign Power Supply Breakers For Boric Acid Evaporator "A" and Control Rod Drive
[ Work is complete. The workplan is on hold for completion
'N _j of work on ECN L5057.
ECNs 7291&7292 - DCR 2259/WP 12715 - Unit 1 ERCW Strainers and Unit 2 .
ERCW Strainers ECNs revised wiring and associated instrumentation to allow manual backwash and flushout of ERCW strainers.
Workplan is in work and approximately 75 percent complete.
WP 12715 - ECNs revised wiring and associated '
instrumentation to allow manual backwash and flushout of ,
ERCW strainers. I WP is in work and approximately 75 percent complete.
ECN 5712 - Evacuation Alarms Auxiliary Building WP 12663 - All fieldwork complete.
ECN 5503 - Evacuation Alarms O&PS l
l WP 12664 - Material arrived approximately November 28, 1987.
WP is in work and approximately 50 percent complete.
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4 Major Capital Projects (Cont.): ~
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Other Items (cont.):
ECN 5841 - Hot Shdp 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 7190 - Replace Duct Detectors and Install Thermal Detectors WP 7190-01 has been written and is in the approval cycle. '
ECN 6388 - WP 12223 - Craft support as needed for installation of hydrogen analyzers at 500-kV switchyard Work is 50 percent complete.
ECN 5111 - WP 12276 - Work is complete. WP closure is in process.
DCN X000598 - WP 12713 - Work is complete. WP closed.
DCN X00061A - WP 12678 - Work is complete. WP closed.
DCN X00078C - WP 12725 - Work is complete. WP closed.
\ DCR 2355 e
DCN X00107A - WP 107 WP preparation is in process.
DCN X00108A - WP 108 WP preparation is in process.
ECN 5048 - WP 5048 WP preparation is in process.
ECN 5412 - WP 5412 WP preparation is in process.
ECN 5754 - WP 5754 WP preparation is in process.
ECN 6162 - WP 6162 WP preparation is in process.
ECN 5609 - Construct An Additional Makeup Water Treatment Plant WP 12576 - Work is in process and approximately 40 percent complete.
WP 12633 - Work is in process and approximately 50 percent complete. WP is being held for material.
WP 12731 - WP is approved and being held for conduit / cable
, cards. This WP is scheduled to start December 4, 1987.
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( Maior Capital Projects (Cont.): .
Other Items (cont.):
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WP 12684 - WP has almost completed the approval cycle. ,.
Modifications is incorporation 6 comments for system engineer approval.
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