ML20205D494
| ML20205D494 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/31/1986 |
| From: | Dupree D, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8608180057 | |
| Download: ML20205D494 (59) | |
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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT HONTHLY OPERATING REPORT TO THE .._
NUCLEAR REGULATORY COMMISSION "MAY 1986"
. UNIT 1 -
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 l -
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,. UNIT 2 DOCKET NUMBER 50-328 _
LICENSE NUMBER DPR-79 l
Submitted by: .l .
P. R. Wallace, Plant Manager _
8608180057 860531 PDR ADOCK 05000327 R
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TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 June 11, 1986 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen SEQUOYAH NUCLEAR PLAYT - MONTHLY OPERATING REPORT - MAY 1986 Enclosed is the May 1986 Monthly Operating Report to NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY P. R. Wallace Plant Manager Enclosure cc (Enclosure):
Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement Suite 3100 101 Marietta Street Atlanta, Georgia 30323 (1 copy)
Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. A. Rubio Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 (1 copy)
INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 (1 copy)
Mr. K. M. Jenison, Resident NRC Inspector O&PS-2, Sequoyah Nuclear Plant g d/
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1983-TVA SOTH ANNIVERS ARY An Equal Opportunity Employer
-. _. _ _ l
4 TABLE OF CONTENTS I. Operational Summary Page Performance Summary 1 Significant Operational Events 1 Fuel Performance and Spent Fuel Storage Capabilities 2 PORVs and Safety Valves Summary 2 Licensee Events and Special Reports 2-5 Offsite Dose Calculation Manual Changes 5 .._
II. Operating Statistics A. NRC Reports Unit One Statistics 6-8 Unit Two Statistics 9-11 B. TVA Reports Nuclear P.' ant Operating Statistics 12 Unit Outage and Availability 13-14 Reactor Histograms 15 III. Maintenance Summary Electrical Maintenance 16-20 Instrument Maintenance 21-26 Mechanical Maintenance 27-31 Modifications 32-39 _
IV. Environmental Qualification (EQ) Summary 40-46 -
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OPERATIONAL
SUMMARY
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PERFORMANCE
SUMMARY
May 1986 The following summary describes the significant operational activities for the month of May. 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 significant employee concerns. Outage related maintenance and modifications are being performed. Unit I has been off-line 282 days.
Unit 2 has been off-line 283 days.
SIGNIFICANT OPERATIONAL EVENTS -
Unit 1 Date Time Event 05/01/86 0001C The reactor was in mode 5. The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
05/31/86 2400C The reactor was in mode 5. The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
Unit 2 Date Time Event 05/01/86 0001C The reactor was in mode 5. The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues. .
05/31/86 2400C The reactor was in mode 5. The administrative shutdown due to design control review, config-uration control updating and resolution of significant employee concerns continues.
FUEL PERFORMANCE Unit 1 The tore average fuel exposure accumulated during May was O MWD /MTU with the total accumulated core average fuel exposure of 0 MWD /MTU.
Unit 2 The core average fuel exposure accumulated during May 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 con-flict. 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 May 1986.
LICENSEE EVENT REPORT (S)
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in May 1986.
LER Description of Event
- 1-86010 A diesel start occurred when a fuse was inadvertently removed while verifying System Operating Instruction .
(SOI)-82.4 " Diesel Generator 2B-B". This event was I
caused by personnel failure to handle the fuse properly.
1-86012 During the review of Surveillance Instruction (SI)-166.1,
" Full Stroking of Category ' A' and 'B' Valves During Operation", on April 15, 1986, it was discovered that -
thirteen containment isolation valves (CIV) were tested in the wrong position. The procedure specified that stroke timing be done going to the open position instead of closed position. This deficiency has existed since the inception of this SI. This applies to both units.
Technical Specification (TS) 3.6.3 requires that CIV be operable with isolation times as specified by TS ,
Table 3.6-2. SI-166.1 was revised to specify the correct timing position for the valves in question.
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LICENSEE EVENT REPORT (S)
(continued)
LER Description of Event 1-86013 A special task force reviewing technical specifications surveillance requirements discovered that adequate testing ,
had not been performed on engineered safety features systems (ESF) as required by Limiting Condition for Operation 3.3.2. Certain manual features require testing every thirty-one days. This is a programmatic deficiency.
Sequoyah has a procedure to test the ESF functions.
It will be reviewed for adequacy and placed on schedule for monthly testing.
1-86014 On April 2,1986, it was determined that an incorrect --
duct area was being used to calculate auxiliary building gas treatment system (ABGTS) flow rates. Investigation revealed that the previous calculations using the correct duct area indicated flow rates were outside technical specifications (TS) criteria during various periods since June 11, 1980. This is failure to comply with TS 3.7.8 and 3.9.12. Procedures have been revised to indicate the correct duct area. ,
1-86015 Deficient testing methods were used on two separate events that resulted in a failure to properly functionally test the undervoltage and underfrequency trip attachments for the reactor coolant pumps and circuit breakers used for electrical overcurrent protection of the containment elec-trical penetrations. These events were identified April 7 and April 9,1986, respectively. This was due to inade-quate procedures. Test procedures are being revised to ensure proper techniques and testing. '
1-86016 Technical Specification Design Features 5.3.1 for fuel assemblies identifies a maximum total fuel rod weight of uranium, (1766 grams). On April 29, 1986, TVA was informed by Westinghouse that this weight was exceeded for rods in unit 1 and unit 2, cycle 3 reload assemblies and for unit 1,
- cycle 4, (132 fuel rods). This was due to technical advance-
, ments in production. This increase in weight has no bearing i
on the power limits, operation levels, or decay heat rate.
TVA is submitting a technical specification change concerning fuel weight.
(
I 1-86017 On April 19, 1986, it was discovered that Surveillance Require- _
ment (SR) 4.9.9 had not been fully implemented. The radiation monitor for the purge air system had not been tested as required to verify that a containment vent isolation (CVI) occurs on input of a high radiation test signal to the monitors.
l The inadequacy of the procedure was a result of misinterpretation i of the SR during the initial preparation of the procedure. The l test procedure is being revised to include the verification l that a CVI occurs on a high radiation test signal.
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LICENSEE EVENT REPORT (S)
LER Description of Event (continued) 1-85018 April 21, 1986, a special task force discovered that the surveillance instruction (SI) used to comply with action 'a' ~
of Limiting Condition for Operation 3.8.1.1 failed to verify indicated power availability as required. SI-7.1,
" Diesel Generator AC Electrical Power Source Operability Verification," did not include provisions to record available voltage on either the start buses or the 6900 kV shutdown boards. This instruction is used to ensure acceptable ac power sources are available when one diesel generator is out of service. SI-7.1 has been revised to include the requirement to record voltages to verify indicated power ._
availability.
1-86019 An auxiliary building isolation (ABI) occurred due to personnel error at 0706 CST on May 5,1986. A modification was being performed on 480 volt shutdown board 1Al-A. This required adding a fuse to each side of a fuse contact to the alternate breaker to prevent the contact from being fuse solely by the trip /close circuit. In the process of this modification, another contact was inadvertently rotated to a new position. After work was complete and the breaker was placed in position, it caused the alternate contact to move causing a loss of power causing an ABI. Procedures were instituted to ensure the correct positions of all contacts before modifications are performed.
1-86020 The technical review committee of Sequoyah discovered that a quarterly functional test for the steam generator blowdown system and condenser vacuum exhaust flow instru- -
mentation was not performed on Surveillance Instruction (SI)-244 (unit 1) and SI-244.2 (unit 2), " Periodic Functional Tests of Radioactive Effluent Monitoring Instruments". On May 1, 1986, it was discovered that the condenser exhaust was not being performed on unit 1. On May 5, 1986, it was discovered that SI-244.2 was not -
performed on the steam generator blowdown. These events were caused due to inadequate procedures. SI-244 and 244.2 were revised to functionally test these systems as required.
1-86021 A control room isolation occurred on May 2, 1986, due to a spike on "B" train chlorine detector. The cause of this event was undeterminable and is considered an isolated
- case. Before this event, maintenance was being performed on "A" when the spike occurred. An investigation showed no correlation between the trains. Attempts were made to recreate the exact conditions causing the spike, no alarm or spike occurred. This was an isolated case; no further action required.
O SPECIAL REPORT (S)
The following special reports were submitted to the NRC in May 1986.
Report # Description 86-04 The biological shield blocks have been removed, and the unit 2 '
building equipment hatch opened for fire protection modifications in the annulus. This condition has been identified as a breach of a fire barrier penetration and will remain nonfunctional for the duration of the outage.
86-05 On April 19, 1986, during the performance of Surveillance Instruction (SI)-237.1, " Powerhouse Carbon Dioxide Fire Protection System Test," a leak was discovered in the actuation system piping in the 24-ton carbon dioxide vault. The _
leak was significant. The main header isolation valve was closed making the system inoperable. The valves were corrected and the system was declared operable. However, the SI was initiated again and other leaks were found through the rubber disc valve seats on the main selector valves and through the pilot valves. The system was tagged again making it inoperable.
Technical specifications require a special report to be issued if the system is not repaired within 14 days. Parts are on order, thus the system will remain inoperable. The computer room and both unit 1 and 2 auxiliary instrument rooms are affected.
OFFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Sequoyah Dose Calculation Manual during the month.
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OPERATING STATISTICS (NRC REPORTS)
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. OPERATING DATA REPORT
. DOCKET NO, 50-327 DATE JUNE 6,1983 COMPLETED BY D.C.DUPREE TELEPHONE (615)S70-6544 OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES: -
- 2. REPORT PERIOD: MAY 1986
- 3. LICENSED THERMAL POWER (MWT): 3411.0 C. 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 C. 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 CUMULtTIVE
- 11. HOURS IN REPORTING PERIOD 744.00 3623.00 43104.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.00 0.00 24444.91
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 i 14. HOURS GENERATOR ON-LINE O.00 0.00 23871.13
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 77060971.91
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 25976386.00
- 10. NET ELECTRICAL ENERGY GENERATED (MWH) -3061.00 -17336.00 24925401.00
- 19. UNIT SERVICE FACTOR O.00 0.00 55.38
- 20. UNIT AVAILABILITY FACTOR 0.00 0.00 55.38
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 0.00 50.37
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 50.37'
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 27.29.
- 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:
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 DEEN UPDATED.
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SEOUDYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL .
DOCKET NO. : 50-327 UNIT : DNE DATE : JUNE 6.1986 COMPLETED BY : D. C. DUPREE -
TELEPHONE :(E15)B70-6544 I
i NONTH:NAY 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL
( DAY (NWe Net) DAY (NWe Net) .
01 0 17 0 02 0 18 0 03 0 19 0 04 0 20 0 ,
05 0 21 0 l 06 0 22 0 07 0 23 0 ,
OB 0 24 0 09 0 25 0 l
10 0 25 0 11 0 27 0 -
12 0 20 0 13 0 29 0 14 0 30 0 l
15 0 31 0 i
16 0 UNIT SHUTDOWNS AND POkIR REDUCTIONS DOCKET Wo. 50-327 UNIT NAME Sequoyah One DATE June 6, 1986 COMPLETED BY D. C. Dupree REPORT HONTH MAY 1986 TELEPHONE (615)870-6544 "u a ee c4 Y ee O Licensee E -F he CauSe & Corrective No. Date
~
o OO 5 55N Event UE 5E Action to I N5 E SUS Report #
- SO IO Prevent Recurrence N5 E 55 O o zmf n F 744 F 9 Design Control, Configuration Updating, 7 851220 and Employee Concerns.
3F: Forced 2 Reason: 3 Method: 4 Exhibit G-Instructions A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: Scheduled Entry Sheets for Licensee B-!!aintenance or Test 2-Manual Scraa.
C-Refueling 3-Automatic Scras. Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Operator Training & Li, cense Examination Outage F-Ailministrative S-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source H-Other (Explain) i
, OPERATING DATA REPORT DOCKET NO3 50-32]
DATE JUNE 6,1986 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6544 OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES: -
- 2. REPORT PERIOD: MAY 1986
- 3. LICENSED THERMAL POWER (MWT): 3411.0 C. NAMEPLATE RATING (GROSS MWE): 1220.6
- 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDADLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDADLE CAPACITY (NET MWE): 1148.0 C. IF CHANGES DCCUR 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 744.00 3623.00 35064.00
- 12. NUMDER OF HOURS REACTOR WAS CRITICAL 0.00 0.00 21984.54
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE 0.00 0.00 21494.42
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 69127977.22
- 17. CROSS ELECTRICAL ENERGY GEN. (MWH) 0.00 0.00 23536780.00 1C. NET ELECTRICAL ENERGY GENERATED (MWH) -4854.00 -23184.00 22608773.60
- 19. UNIT SERVICE FACTOR 0.00 0.00 61.30
- 22. UNIT AVAILADILITY FACTOR 0.00 0.00 61.30
- 21. UNIT CAPACITY FACTOR (USINO MDC NET) 0.00 0.00 56.17
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 0.00 56.17
- 23. UNIT FORCED OUTAGE RATE 100.00 100.00 28.77
- 24. SHUTDOWNG SCHEDULED OVER 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 PENDINO DESIGN CONTROL REVIEW, CONFIGURATION CONTROL UPDATING, AND RESOLUTION OF SION!FICANT EMPLOYEE CONCERNS.
NOTE THAT THE THE YR. -TO-DATE AND CUMULATIVE VALUES HAVE DEEN UPDATED.
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r SECUDYAH NUCLEAR PLANT AVERAGE DAILY POWER LEVEL DOCKET NO. : 50-328 UNIT : TWO DATE : JUNE 6.1986 COMPLETED BY : D. C. DUPREE
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TELEPHONE :(815)870-6549 NONTH:MAY 1986 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY CHWe 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 00 0 29 0 .
09 0 25 0 10 0 25 0 11 0 27 0 12 0 20 0 13 0 29 0 ly 0 30 0 15 0 31 0 1G 0 4
49 6
e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE June 6, 1986 COMPLETED BY D. C. Dupree REPORT MONTH MAY 1986 TEEPE'E (61315 m-6m
~ o a gg " oyg Licensee g-s, go, Cause & Corrective e o Event gg gy Action to No. Date 3g y3g y 3g g gge Report # gu gu Prevent Recurrence 5~ $$$
R 7 850821 F 744 F. 4 Design Control, Configuration Updating, and Employee Concerns.
3F: Forced 2 Reason: 3Hethod:
4 Exhibit C-Instructions A-Equipment Failure (Explain) 1-!!anual for Preparation of Data S: Scheduled Entry Sheets for Licensee B-Haintenance or Test 2-Manual Scram.
e-Refuelieg 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Cont. of Existing (NUREG-0161)
E-Cperator Training f License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other sExhibit I-Same Source II-Other (Explain) .
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OPERATING STATISTICS (TVA REPORTS)
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tva ne:A toew+en NUCLEAR PLANT OPERATING STATISTICS Sequoyah Nuclear Plant Period Hours 744 E 86 Month 19 Item .
No. Unit No. UNIT ONE UNIT 'lVO Pl. ANT 1 Averaae Hourly Gross Load. kW 0 0 0 2 Marimum Hour Net Generation, MWh 0 0 0 3 Core Thermal Enerav Gen. GWD (t12 0 0 0 4 Steam Gen. Thermal Energy Gen., GWD (t)2 0 0 0
,$ 5 Gross Electrical Gen., MWh 0 0 0 ti 6 5:ation Use. MWh 3,061 4,854 7.915 f 7 Net Electrical Gen.. MWh o 2. Station Use, Percent
- 3,061 N/A
-4,854 N/A
-7.915 N/A -
9 Accum. Core Avg. Exposure. MWD / Ton! 0 0 0 10 CTEG This Month,106 DTU 0 0 0 11 SGTrG This Month,106 0TU 0 0 0 12 13 Hours Heactor Was Critical 0.0 0.0 0.0 14 Unit Use Hours. Min. 0:00 0 00 0:00 1 15 Capacity Factor, Percent 0.0 0.0~ 0.0 y 16 Turbine Ava61. Factor. Percent 0.0 0.0 0.0
,, 17 GentIAlotAyalLiattadttignt 0.0 0.0 0.0 g fB Turbonen. Avail. Factor. Percent 0.0 0.0 0.0 j
g .1 , Heartor Avail. Fattor, Peregat 0.0 0.0 0.0
- u. 20 Un61 Avail. Factor. Percent 0.0 0.0 0.0 1 . Turbine Startuos 0 0 0 22 Heactor Cold StartWDs 0 0 0 21 g 74 Gross Heat Rate, ntu/kWh N/A N/A N/A
.25 Net hast Hate, Otu/kWh N/A N/A N/A M{ 26 5 27 28 Throttle Pressure, ps6g N/A N/A N/A
&g2 Throttle Temperature. *r N/A N/A N/A se rahaust Pressure, inHg Abs.
30 N/A N/A N/A H
f 31 1?
Intake Water Temp., 'T N/A N/A N/A ,
l Main i eedwater, M lb/br N/A N/A N/A
. 34 g 35 36
,1 I ull Power Capacity, f rPO 404.H6 3 6 ) . h 'a 7b8.51 3A __Accum. Cycle _ Full Power Days, IJ PD 0.0 210.8416 210.8416 Q l G61 rived for Generation, Galinns 2,640 2 2 011t.fedtlinYA!ue [119/ftai. 138,000
. (1. . DipttLGiritfation MWh 40
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Mas. Hour Nel Gen. Man. Day Net Gen. Load MWh Time Date MWh Date f actor. %
g 41 D[A lI[V lIIVD$b TIIV N/A 3 _flemar k s ! !# or lif NP this value is MWO/5 TU and for SONP and WilNP this value is MWU/M TU.
$ 2(t) Indicates Ihermal Inergy.
JUN.1319" C @ --A2 Date Submitted Date Hevised G.s\.. ~
Plant Superintendent
Yea 6%2c e b Na U*stT OUT AGE A*t3 CVARLAStLITY e
Se m ah Pescies Pmet wg one beaws Reaceae P%.ee %II vert stetNyem MAY 1966 cc-e aear p tg 3:20 3 **aM .
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MAINTENANCE SUNIARY (INSTRUMENTATION)
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INSTRUMENT MAINTENANCE MONTHLY REPORT FOR MAY 1986 COMMOR LER SQRO-50-327/86021 was submitted after an inadvertent control room isolation occurred. It was caused by a spike on the "B" train of the chlorine detector (CLAN-43-205B). .
Field verification of mounting on CSSC Foxboro transmitters to resolve an employee concern is 50% complete.
UNIT 1 PRO-1-86-11 was initiated for failure to perform channel calibration of the turbins trip P4 interlock. This was based on interpretation of Technical Specification SR 4.3.1.1.1.B.22.G and is applicable to both units. - - -
Workplan 12037 (ECNs 5196 & 2776 and FCR 4350) was completed which replaced the control board indicators on loops P-30-310 and -311. This applies to both units.
PRO-1-86-104 was written because no instruction existed to meet SR 4.3.3.9.C.5c for channel calibration of condensate demineralizer regenerant effluent continous composite sample flow monitor.
PRO-1-86-091 was initiated because the dynamic response of the RCS Tavg/AT instrumentation was not being verified during periodic calibration.
PRO-1-86-095 was submitted for failure to comply with technical specifi-cation surveillance frequency on SI-244 and SI-244.2.
A containment ventilation isolation occurred from a spurious high radiation signal on containment purge air exhaust rod monitor 1-RM-90-131. PRO-1-86-110 was submitted. ~
UNIT 2 The process computer rapid access device (RAD) was replaced with an expanded solid state version to allow more data storage after plant trips.
Workplan 10845R1 which performed a postmodification test on the square root module upgrade was completed.
PRO-2-86-031 was written because a quarterly check of blowdown through 2-F-15-44 was not performed as required by SR 4.3.3.9.D.1.b.
Two containment ventilation isolations occurred. One was caused by a personnel .
error while inhibiting the containment ventilation radiation monitor trip function (2-RM-90-106). The other was initiated by a spurious high radiation spike on the containment vent noble gas radiation monitor (2-RM-90-106B). PR0s 2-86-039 and 2-86-043, respectively, were submitted.
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6 9
W MAINTENANCE
SUMMARY
(MECIIANICAL)
O e.
-w--= a w v-- -
-- -r --- _. - - - -
MECHANICAL MAINTENANCE MONTHLY REPORT FOR MAY 1986 COMMON
- 1. During' Electrical Maintenance performance of an surveillance instruction ,
which proof tests the CO2 systems, a leaking valve was discovered.
Because of the possible personal safety hazard, the 24-ton CO2 system was tagged out and fire watch coverage provided while Mechanical Maintenance brought a service engineer in to help diagnose the problem. The problem was traced to a leaking leather seal. The vendor has since upgraded the valve design to replace the leak prone leather seals with Teflon seals.
A category "D" field change request and resulting engineering change notice replaced all of the master selector valve seals.
- 2. The main boom cylinder seals in the essential raw cooling water building crane were replaced.
- 3. The fuel oil pumps were replaced as a preventive measure on the emergency diesel engines leaving only one remaining to be replaced.
I
- 4. The remaining Appendix "R" fire door maintenance activities were completed; also a new maintenance instruction prepared to address non-functional fire door repairs was issued.
- 5. During a routine packing replacement task on two essential raw cooling water pumps, it was discovered that the shaft sleeve 0-rings were also
~
leaking. Replacement of these 0-rings has begun and preventive maintenance for 0-ring replacement is being evaluated.
- 6. A request for a personal services contract with Westinghouse to evaluate our maintenance instruction program was submitted.
- 7. Uncoupled and recoupled IBB and 2AA centrifugal charging pumps in
- support of a modifications workplan.
- 8. Started writing workplan to remove clutchtrippers on limitorque operators.
- 9. Craft and engineering personnel attended welding classes at the training -
center.
- 10. Four engineers successfully completed the four week engineer and manager training course at the training center.
- 11. Completed a scheduled preventive teardown / inspection of the "B" auxiliary I
control air compressor. .
i
MECHANICAL MAINTENANCE MONTHLY REPORT FOR MAY 1986 l
UNIT 1
- 1. Started collecting snubber nameplate data on unit 1 in response to i
an NRC concern on potentially under rated snubbers. Nameplate data is necessary to determine for which snubbers the concern is applicable.
- 2. As a result of increasing vibration levels on the IBB containment spray pump, an inspection of the pump alignment was made and found -
out of alignment. The pump was realigned.
- 3. Replaced seals in two unit 1 steam generator recirculation pumps.
e e
I
MECHANICAL MAINTENANCE MONTHLY REPORT FOR MAY 1986 UNIT 2
- 1. Completed collection of snubber nameplate data on unit 2. Submitted 4 potentially under rated snubber list to the one who is to determine which snubbers, if any, are under rated.
- 2. Disassembled 2A component cooling pump to replace the shaft sleeves due to wear from_the packing. Reassembly has begun.
- 3. Supported Combustion Engineering in completion of sludge lancing efforts on the unit 2 steam generators.
- 4. Removed, hydrolased, and reinstalled the four unit 2 feedwater flow elements.
- 5. The Nos. 2 and 3 reactor coolant pumps were uncoupled to allow electrical maintenance to repair the motor.
- 6. Realigned the unit 2 turbine driven auxiliary feedwater pump.
- 7. Adjusted packing in valve 2-VLV-068-546 in the resistance temperature device manifold.
- 8. Continued containment isolation valve repairs / tests. ~
'nECHANICAL HAINTENANCE MDNTHLY
SUMMARY
06-02-86 PACE 1
+
CORP BR.CDRP U FUNC SYS GDDRESS. DATE.... DESCRIPTION.......... .................. CORRECT!UE ACTION......... ... .........
B104983 1 VLV 062 03732 03/07/86 1-VLV-062-0393A-3, REPLACE THE RUCCER INSTALLED NEW DIAPHRAGR AND STUDS DIAPHRAM QN B.A. ULY 'A' FILTER DUTLET PRESS IND YLV L114021 2 ENG 082 0702A1 03/21/86 2-ENG-082-0002Al ,uMPRDu NEED TO INSTL NORMAL WEAR. PM. INSTLD NEW ENG DRIVEN NEW ENG DRIYEN FUEL DIL PAP FUEL DIL PMP 8114204 1 VLU 072 0303 03/13/861-ULU-072-0303-A,[uMPRDu],ULV BINDS WHEN WORN INTERNALS. DISASSEnBLED ULU LAPPED OPERATED GulNG IN THE CLOSED OR DPEN ULV SEAT & DISC. INSTALLED NEW PACKING P031TIDMS AND BDWHET CASKET PERFDRNED $1-186 AND RETURNED TO SERUICE ,
B119648 1 DISC 062 0192 03/19/86 1-DISC-062-0192 , REPLACE RUPTURE DISC NORMAL WEAR. INSILD NEW RUPTURE DISC
'A' BA EUAP B120862 1 DISC 062 0192 03/13/86 1-DISC-062-0192 , REPLACE RUPTURE DISC 30EFECTIVE DISC. INSTALLED NEW RUPTURE
'A' EUAP DIAPH BLEX AT 7 PSI RATED AT DISC 13.3 C122037 1 DISC 06? 0172 U3/13/86 1-DIIC-062-0172 , DIAPHRAGM BLUNH WORM DISC. INSTALLED NEW RUPTURE DISC B124282 2 Ol5C 062 0192 03/13/86 2-D15C-062-0192 , REPLACE RUP1URE DISC WDRN VUPTURE DISC. INSTALLED NEU RUPTURE 8124283 2 FCU 062 C196 03/19/86 2-TCV-062-0176 ,32 UAY AIR CONTROL ULV WDRN VLU. INSTALLED NEW ULY LEAKIH; DUT UENT AT ALL TIMES 8 records listed.
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4 6
G MAINTENANCE
SUMMARY
(MODIFICATIONS)
S I
i
SUMMARY
OF WORK COMPLETED MODIFICATIONS MAY 1986 NUREG 0588 ECN 6231 - Remove Interferences Work is in progress on the removal of one support and the addition of three supports.
ECN 6552 - 0588 Solenoids _
Functional testing has not been performed because of other work in progress on these valves.
ECN 6616 - Damper Fusible Link DNE is to issue drawings by June 20, 1986. Preliminary workplan preparation has begun.
ECN 6632 - Restrict Valve Room Flow Drains (Supersedes ECN 6609)
This work was completed.
APPENDIX R ECNs 5435 and 6343 - Fire Doors The replacement and repair of the doors and doorframes continue; five are incomplete.
i ECN 6235 - Recoute Various Cables Nine workplans are in work on conduit / cable reroute. Insulation is in progress at various locations.
l j
ECN 6311 - Operator Extension on PORY l
This work has been completed except for final cycling at startup.
ECN 6315 - Replace Fuses ,
Fuse installation is in work.
ECN 6319 - Fire Protection Piping Some minor hanger enhancements and paintwork are continuing.
P l
APPENDIX R (continued)
ECN 6642 - Annulus Fire Protection and Sealing Containment -
Penetrations Unit 2 fire protection work is complete except for final tie-in and hydro. Unit I work is in progress. Mechanical Modifications is waiting for DNE to issue drawings for the penetration work for unit 1. An electrical workplan is in writing.
OTHER ITEMS ECN 2783 - Installation of Fifth Diesel Six electrical-related workplans for the fifth diesel installation have been placed in the workplan closing cycle.
ECN 5009 - ERCW Piping Changeout From Carbon Steel to Stainless Steel The workplan for the replacement of isolation valves remains in the approval cycle. Some insulation activities remain incomplete. DNE is revising the USQD. Some additional hanger work may be required for the piping replaced on the upper compartment cooler lines inside containment.
ECNs 5034, 5713. 5743, and 606,4 - Various Platforms in Lower Containment The first trolley was modified by the vendor and found acceptable. -
The remaining trollies are being prepared for shipment to the vendor for modification.
ECN 5202 - Interface of Fifth' Diesel With Other Diesels l
Workplans for the interface of the fifth diesel with other diesels .
for trains I A-A and 1B-B are in the approval cycle.
ECN 5252 - Label Node Voltages in Manholes i
Work has been completed.
ECN 5596 - Extension of Pressurizer Condensate Drains _
Routing of the drains to the closed drainage system was completed on unit 2, thus completing this modification.
ECN 5620 - Add Instrumentation for Auxiliary Feedwater Pump i
Work is on hold.
ECN 5657 - Installation of MSR Drain Valves Reinsulation remains incomplete. Caps have been installed on the valve nipples.
OTHER ITEMS (continued)
ECNs 5703 - Reinforcement of Block Walls -
During the installation of the restraints, some mortar joints were broken. Efforts are underway to repair these joints before the restraints are installed.
ECN 5724 - CVCS/RHR Supports Three hangers and two notifications of indication remain incomplete.
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ECN 5795 - Field Services Building The fire detection system is in operation.
ECN 5914 - Improve Reliability of Steam Dump Functional testing remains on unit 1.
ECNs 5938, 6305, and 6571 - Replace Feedwater Heater and Eroded Pipe Insulation on unit 2 is complete. Mechanical Modifications is supporting postmodification testing (PMT) on both units. Insulation work on unit 1 has resumed. Building steel reinforcement for Nos. 3 and 4 feedwater heater replacement on unit 2 was completed.
Installation of the monorail was begun on unit 2.
ECN 6057 - Cable Tray Covers Approximately 240 out of 290 cable tray covers have been remanufactured or replaced.
ECN 6147.- Airlock Packing Nut Final testing of the airlocks on unit 2 remains incomplete. -
ECN 6185 - Offsite Paging System Cable pulling was completed. Functional testing will be completed the first week of June.
l ECN 6196 - Pressurizer Hangers and Valves PMT is incomplete and scheduled for startup.
ECN 6204 - Electrical Penetration Overcurrent Protection Fuse replacement and fuse block installation are complete.
Electrical Modifications is awaiting a procedure change to place the circuits in service.
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OTHER ITEMS (continued)
ECN 6259 - Moisture Separator Reheater Tube Bundle Replacement Insulation activities are continuing.
ECN 6380 - Installation of Replacement Flow Switches on Switches Preliminary workplan preparation has begun.
ECNs 6402 and 6439 - Pressurizer Isistrumentation Relocation
~~
All work is complete except seal welding fill tees. This will be completed after Instrument Maintenance completes fill and calibration.
ECN 6417 - Install Alternate Seal Water for Pumps, CDWE Electrical drawings remain to be issued.
ECNs 6491 and 6534 - ERCW Supports Work remains for one original support. Seven additional supports have been identified. DNE is issuing drawings.
ECN 6599 - Unit 2 Shield Building Anchor Problem All deficient anchors have been replaced. Variances are being approved to document the deviations.
ECN 6601 - Removal of EGTS Backdraft Dampers The damper was replaced. PMT remains to be completed.
ECN 6610 - Modify Air Return Fan Supports Work continues on the unit 2 fans.
ECN 6661 - Upgrade of ERCW Piping The workplan was prepared and placed in the approval cycle.
Dry Active Waste Building (DCR 1898) ,
Concrete foundation and floor slab work has been completed. Design drawings have been received, and the modification to the structural steel frame has begun. Steel erection is scheduled for June.
Equipment should be moved to the site and set in place by the first part of June, l
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OTHER ITEMS (continued)
Additional Office Buildings (DCR 2260)
The foundation and floor slabs and roof trusses have been completed. The outside stud walls and siding are 99-percent complete. The roofing is 98-percent complete, the inside stud walls are 90-percent complete, sheetrock and wiring are 25-percent complete, and plumbing is 25-percent complete.
Welding Project
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Support was provided to Welding Project personnel as requested.
Walkdown Field Verification Support SMI-0-317 Unistrut Clamps - Complete.
SMI-0-317 Concrete Edge Distance - Complete; DNE is evaluating the results.
SMI-0-317 79-14 Enhancement - 145 unit 2 supports have been inspected and are being evaluated. Approxi-mately 188 unit 1 supports have been inspected and are being evaluated. Work continues.
Alternate Analysis Walkdown Work was just beginning at the end of May.
Unit 2 J-Tube Replacement The workplin was written and approved, and work was started on this project. Combustion Engineering, Inc., began mobilization work on May 21 and opened the first steam generator on May 27. Work is progressing with minimal problems. .
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MODIFICATIONS ECN DCR WI SYS SEQUENCE DESCRIPTION UNIT ST L5034 D1147 X 068 9098 Steam generator inspec- 1 _
tion platforms (U1 only)
U2 EC 2757 L5252 D0704 S X 362 8631 Manhole cable tray desig- 1 nations, U2 ECN 2805 L5743 D0383 S X 320 9120 Provide permanent access 1 ladders platforms leading --
to top of each steam generator and the pres-surizer.
L5753 D1714 S X 055 12487 Change setpoints, logic, 2 modify plant components as per attached list worked up by SNP and EN DES.
L6289 F2994 S H 400 13223 Replace broken blowout 0 concrete plug of west valve room roof U2 and make all blowout concrete plugs of both W VLV RMS (Ul&U2) free from binding on edges.
L6454 F3613 S H 317 13468 Note addition to DWG. 2 series 47A050: Provide exemption to spacer requirement when total gap between end attach-ment & rear bracket is -
3/16" L6514 D0972 S X 030 13536 Add enviromentally quali- 1 fled conduit seals to 1-FSV-30-134 and 2-FSV-3-0-134 located inside containment. ,
L6524 D0972 S H 062 13573 To disconnect local control 2
- station wiring from hand-switches not qualified for inside containment post-LOCA enviroament.
O MODIFICATIONS ECN DCR WI SYS SEQUENCE DESCRIPTION UNIT ST L65327 D0972 S H 074 13574 Disconnect local 2 _
control station wiring from hand switches not qualified for inside containment post-LOCA environment.
L6551 D0972 S X 000 13597 Eevise setpoints for 2 safety-related instru-ments to allow for --
instrument inaccuracies due to harsh environ-ments resulting from a high energy line break.
L6554 D0972 S X 030 13599 Replace presently 0 installed transmitters 1&2 PDT-30-42&43 with qualified Foxboro trans-mitters.
- L6613 F4164 S H 400 13659 Add Note
- 5-Star grout 0 with 3/8 inch aggregate maybe used in lieu of concrete to repair at opening frame. This for is to replace for 607 which was lost.
REF: BWP 840702008.
L6632 D0972 S H 000 13713 (Predecessor-ECN L6561) 2 add a flow limiting orifice plate to the exposed floor drains.
L6640 D0972 S H 068 13728 Provide mounting 0 bracket details for 2-PT-68-334 & 340.
t Documentation change only. This ECN .
supersedes ECN 6592.
Not Req D0935 X 079 8999 Add load cell with 0 readout to monitor load while handling fuel assemblies.
FCN-TVAD-40504 1545 X 243 3384 Add oscillograph start 0 sensors; add diodes to sudden pressure relaying.
MODIFICATIONS ECN DCR WI SYS SEQUENCE DESCRIPTION UNIT ST ,
L5746 D0972 S X 070 12549 Replace CCS pumps motor 2 and CCS booster pump motor ref. NUREG 0588.
Ref. ECN 5370.
L6122 F2271 S X 070 13022 Per evaluation of 2 CEB rigorous analysis N2-70-19A and N2-70-18A _
spring supports on DWGS H10-616, H10-690.
L6371 F3343 S H 410 13312 Add two self- 0 lubricating bronze bushing and deletea steel washer. Replace with a bronze washer to top hinge A152.
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SUMMARY
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Date: 6/6/86 0041E Estimated Date of M 1etion SCR No. Description ECN Engineer Workplan No. U-1 U-2 Cauwnts EQP 8501 Disconnect 1- and 2-HS-62-61 6524 Peters 11901 C C U-2 QIR submitted.
- EQP 8502 Replace penetrations 23 and 6490 Peters 11801, 11802, C C Ca plete QIR submitted.
48 11810, 11811 l EQP 8503 Relocate RE-90, 273, -274 6500 Peters 11810, 11811 C N/A Caplete field verification sheets
! are in binder. No QIR needed.
EQP 8504 5plice methods not correct N/A Stockton 80 Nts C C Ca plete QIR submitted.
- , EQP 8505 Drawing N/A N/A N/A N/A N/A i $
- 8 EQP 8506 Seal containment isolation 6514 Kimsey 11880 C C a valve EQP 8507 Rewire MOV N/A Rutledge 11866, 11853 C C i EQP 8508 JB weepholes (press) 6523 Alas 11898 C C Ca plete QIR submitted.
EQP 8509RI Conduit seals 6529 Kimsey 11903, 11904 C C EQP 8509R2 Conduit seals 6615 N/A N/A N/A No field work remaining.
- EQP 8510 Disconnect local handswitches 6527 Peters 11901 C C EQP 8511 Submerged JB inside 6549 Peters 11901 C N/A containment EQP 8512R2 Rewire JB N/A Anburn 11855, 11856 C C A11 boxes rewired.
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b Date: 6/6/86 0041E Estimated Date of concletion SCR No. Description ECN Engineer Workplan No. t)-1 U-2 Conuents EQP 8513 Weep holes (moisture) 6547 Alas 11898 C C Conplete QIR submitted.
1 EQP 8513R2 Weep holes (moisture) 6565 Alas 11937 C C Conplete QIR submitted.
EQP 8514 Motor insulation 74-1, -2 6540 Branham 11906 N/A C Couplete QIR submitted.
EQP 8515 Replace 2-PDT-30-43 6554 Legg 11912 C C EQP 8516 Replace 2-LT-3-174 N/A Instrument N/A N/A C Maint.
EQP 8517 ABGTS humidity control 6578 Gonzalez N/A C EQP 8518 Submerged cables 6533 Various/6 Various 6/10 C Rework of tenninations is in progress, i
I EQP 8519 Tee drains N/A Electrical N/A C C Conplete QIR submitted.
! Maint.
EQP 8520 Expired cables 6553 Gonzalez 11902 C C EQP 8521 Delete TB and rework splices 6550 Stockton 11914, 11915 C C EQP 8521R1 Delete TB and rework splices 6651 EQP 8522 Rewire local panels N/A Stockton 11914, 11915 C C 1 EQP 8522R2 Rewire local panels N/A Instrument 12016 6/15 6/10 Maint.
Date: 6/6/96 0041E Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-1 W2 Cements EQP 8523 Missing bolts and washers N/A Stockton 11914, 11915 C C
- and misplaced brackets EQP 8524 Change setpoints 6551 Instrunent 11916 C C Maint.
EQP 8525 Reterminate hydrogen N/A Electrical N/A C C Canpleted by Electrical Maint, reconbiner (MR) Maint.
EQP 8526 Replace FSVs, W 1 1, W 2 11 6552 Mechanical 11897 C C i Mods.
8 EQP 8527 Coat TB, W13, W2 8 N/A Stockton 11914, 11915 C C (MR) l EQP 8528 Solder strain gauge Barton IMI Instrunent N/A C C QIR submitted 1/24.
transmitters Maint.
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EQP 8529 PDT-30-42, -43 6554 Legg 11912 C C
! EQP 8530 Gasket, Namco L/5 N/A Electrical N/A C C (MR) Maint.
EQP 8531 Delete MOV heaters 6544 Rutledge 11866, 11853 C C EQP 8532 Delete L/5 1 , 2-43-201, 6630 Alas N/A N/A No longer an issue.
4 -202, -207, and -208 EQP 8533 Delete dual voltage splice N/A Rutledge 11866, 11853 C C 1
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Date: 6/6/86 0041E Estimated Date of Completion i SCR No. Description ECN Engineer Workplan No. U-1 U-2 Copenents EQP 8534 Resplice valve positicr.cr N/A Maxwell Nt C C Conplete QIR submitted.
3-174 and -175 EQP 8535 Replace limit switches, 6556 Stockton 11927, U-2 C C U-1 10, U-2 12 11928, U-1 EQP 8536 Valve room submergence 6561 Mechanical 11939 C C Cap drains 6632 Mods. C C EQP 8536R1 Valve room submergence 6612 Electrical C C Mods, s~
Y EQP 8537 Rebuild or replace JB 3078 6579 Anburn N/A C EQP 8538 Replace capacitors N/A Maxwell 11977 N/A C FCD-31-475, -476 EQP 8539 Replace capacitors N/A Instrtsnent C C Maint.
l Eqa 8540 Replace pigtails to Target 6649 Maxwell 6/25 o/18 Holding for drawings.
Rock solenoid valves EQP 8541 Delete brakes 6582 Branham 11980 6/10 N/A 1-FCV-63-93, -94. 1-FCV-63-93 is conplete. 1-FCV-63-94 needs grease.
EQP 8542 Replace unqualified cables 6680 Hall 7/30 N/A Two cables will be replaced in accordance with a new issue.
Date: 6/6/86 0041E Estimated Date of Camletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Coments EQP 8543 Replace JB wire N/A Mburn 11855, 11856 C C EQP 8601 Replace I , 2-PT-1-2A, -27A; 6588 Elkins 12014 6/15 6/10 upgrade 2-PT-1-28 -27B EQP 8602 Reroute control cables for a " A A A """ a a a a" A a - a a a a a a a a a a a a a a n a a a a a a******* No longer an i ssue.
1 , 2-FCV-70-87, -89 EQP 8603 Replace portion of PP7118 6627 Kimsey N/A 6/6 Will splice in Additional Equipment Building and Elevation
, 759 Transfonner Room.
8 EQP 8604 Cable IPL3241A not qualifieu""aa A A A A"""a"aaaaaaaaaaaaaaaaaaaaaa"aa"aa No longer an issue.
EQP 8605 1 , 2-TS-74-43, -44, -45, 6589 Branham C C
~46 not qualified EQP 8606 Undervoltage concern on 6611 Rutledge 6/20 6/20 Delivery of solenoids expected j feedwater isolation valve 6677 4/15.
brakes EQP 8607 Delete TB for 1 , 2-PT-1-2A, 6626 Instrimnent 12014 6/15 6/10 Will work same time as EQP 8601.
-27A Maint.
- EQP 8608 Enable / disable MOV brakes 6621 Rutledge 6/30 6/30 i
6622 6665 6686
. e i r, Date: 6/6/06 0041E Estimated Date of Completion SCR No. Description ECN Engineer Workplan No. U-l U-2 cm ts
- EQP 8609 Replace cable IV79738 6618 C N/A EQP is reviewing ECN for technical correctness.
j EQP 8611 J8 has weephole in top N/A Anburn N/A C EQP 8612 Replace zone switches 6669 N/A 6/27 EQP 8614 Weepholes in JB 6652 C C l
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9 Date: 6/6/86 0041E Estimated Date of Concletion SCR No. Description ECN Engineer Workplan No. U-l U-2 Consnents N/A Move surge suppression 5773 Kimsey 11883 C C U-2 couplete. On U-1, 1-PCV-68-340 network for PORV in hold. Holding for maintenance to conplete.
EE8 8523 Penetration overcurrent 6606 Legg 6/15 6/8 During closure process, it was found that 6 circuits had not been addressed by ECNs. ECN 6606 addresses this. The ECN is at EQP for review. Drawings to be issued when ECN is approved.
I l g N/A Werk FCR to delete 1 , 5883 Hall C C Need SI-166.
I 2-PS-3-160A, -1608, -165A, and -1658 j' N/A Replace 1-FT-1-3A, -38, -10A, 6347 Instrument N/A C N/A Transmitters changed need response
-108, -21A, -21B, -28A, -288 Maint. test.
- NEB 8510 Relocate LT-68-320, 6439 Carrasquillo Various C C j PT-68-323, -320 Peters
! Remount 63-71,68-308 E4% Legg 11865 C C Replace LS-65-4, -5 6504 Legg 11865 N/A C MEB 8410R3 Replace LS-77-127 6525 Legg 11865 N/A C Delete brakes FCV-62-61 6521 Branham 11905 C C EEB 8517 Replace pressure transmitter 6488 Branham 11931 C C l PDT-65-80, -82, -90, and -97 il P
D 6 WIS PAGE INTENTIONALLY LEFT BLAng O
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OPERATING DATA REPORT
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DOCKET NO. 50-244 DATE Jmn 9.1986 COMPLETED BY EMbe' Andrew E. McNamara TELEPHONE 315-524-4446 Ext. 301 OPERATING STATUS
- 1. Unit Name: R.E. GINNA NUCLEAR POWER PLANT Notes The reactor power level
- 2. Reporting Period: May, 1986 was maintained at 100%
- 3. Licensed Thermal Power (MW:): 1520 for the majority of the 490 report period. One minor
- 4. Nameplate Rating (Gross MWe):
470 reduction for a slurt
- 5. Design Electrical Rating (Net MWe): period is detai1M on
- 6. Maximum Dependable Capacity (Gross MWe): 490
- 7. Maximum Dependable Capacity (Net MWe): 470 H. If Changes Occur in Capacity Ratings (Icess Number 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 744 3,623.00 144,743.00
- 11. Ilours in Reporting Period
- 12. Number of Ilours Reactor Was Critical 744 2,632.75 110,919.92
- 13. Reactor Reserve Shutdown llours 0 0 1.687.55*
744 2,603.50 108,628.13
- 14. Ilours Generator On Line 0 0 8.5*
- 15. Unit Reserve Shutdown llours
- 16. Gross Thermal Energy Generated (MWil) 1.129,992 3.757.008 151.479.633
- 17. Gross Electrical Energy Generated (MWil) 383,642 1,267,573_ 49,560,429
- 18. Net Electrical Energy Generated (MWil) 365,612 1,204,622 47,007,939
- 19. Unit Service Factor 100% 71.86% 75.05%
- 20. Unit Availability Factor 100% 71.86% 75.05%
- 21. Unit Capacity Factor (Using MDC Net) 104.56% 70.74% 70.67%
- 22. Unit Capacity Factor (Using DER Net) 104.56% 70.74% 70.67%
- 23. Unit Forced Outage Rate 0% 0% 7.17%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
- 25. If Shut Down At End Of Report. Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION -
- Cmm11ativo Total Comuncina January 1,1975 TW arv. *n o se 8606180075 860531 PDR ADOCK 05000244 I[I R PDR
AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO. 50-244 UNIT R.E. Ginna Nuclear Power Plant J DATE June 9, 1986 l COMPLETED BY nhP M"Flh A n d r e w E . M c N a m'a r a TELEPHONE 1 (315) 524-4446 Ext. 301 at Ginna MONTH Mav, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWu-Net)
- 1. 491 17. 492
- 2. 492 18. 493
- 3. 491 19. 492
- 4. 492 20. 492
- 5. 490 21. 492
- 6. 490 22. 493
- 7. 491 23. 493
- 8. 491 24. 492
- 9. 491 25. 492
- 10. 492 26. 492
- 11. 491 27. 492
- 12. 492 28. 492
- 13. 492 29. 490
- 14. 493 30. 489
- 15. 492 31. 489
- 16. 492 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
IM)CKET NO. 50-244 IINIT NAME R.E. GINNA NUCLEAR PO_WER PLANT -
UNIT SHUTDOWN AND POWER REDUCTIONS DATE June 9. 1986 COMPLETI-:D HY k3-5 7 M 74_%
Andrew E. McNamara REPORT MONTil IRY 1986 TELEPIIONE 315-524-4446 Ext. 301 m
~ e o'
a e
- mi Licensee g, c
- Cause & Corrective No. Date
{ jj 2 } .5*: u,I Event Report #
- .g yj gj ga A cti. , ,,
>- d6 d 2 e c g u prevent Recurrence o
i No outages or major power reductions "O report.
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4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative j G-Operational Enor (Explain) 5 w
nav. 4.c ase II-Other (Explain) Exhibit 1 - Same Source '
s NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO. 50-244 UNIT R.E. Ginna Nuclear Power Plant DATE June 9._1986 _
COMPLETED BY W Andrew 2AK E.h McNamara TELEPHONE 1 (315) 524-4446 EXT. 301 at Ginna MONTH May, 1986 The reactor power level was maintained at 100% for the majority of the report period, with one exception:
On 5/20 the power level was reduced to - 98% for a short period l to perform a Periodic Test on the Auxiliary Feedwater System. ;
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GINNA STATION MAINTENANCE REPORT
SUMMARY
i MAY, 1986 '
During the month of May, routine maintenance and inspections were completed. Major safety related work included:
. Install 1/2" SS Tubing in place of 3/8" SS Tubing on the A and B Boric Acid Equalizing lines.
. M-40 Monthly Snubber inspection.
. Excess Letdown System "T" Weld Repair.
. . V-110C - Replace Diaphram.
. R-10B Rad Sample Pump overhaul.
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_ , _ . . __ _ _ _ _ _ _ . , _ _ . . _ _ .._. . _ _ _ _ _ _ _ _ _ _ _ _ . . - _ _ . _ _ _ . _ _ _ _ _ . . _ _ . _ _ _ _ . _ . . . . _ _ ~ _ _ . . _ . _ _ . _ _ _
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' i en ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 +
..uco2U.T[e.2roo GINNA STATION June 9, 1986 Director, Office of Management Information and Program Analysis U.S. NUCLEAR REGULATORY COMMISSION Washington, DC 20555
Subject:
Monthly Report for May, 1986 Operating Status Information R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Sir:
Pursuant to our Technical Specification 6.9.1, attached herewith is the monthly operating status report for Ginna Station for the month of May, 1986.
Very truly yours, Mh Stanlet M. Spector Superintendent of Ginna Production SMS/eeg Attachments cc: Dr. Thomas E. Murley NRC (1) vd s1
+a , Y-butI o.
Docket Nos. 50-424, 50-425 License Nos. CPPR-108, CPPR-109 G9orgia Power Company W TN: Mr. J. H. Miller, Jr.
President P. O. Box 4545 Atlanta, GA 30302 Gentlemen: -
SUBJECT:
NOTICE OF DEVIATION (NRC INSPECTION REPORT NOS. 50-424/86-56 AND 50-425/86-25)
This refers to the Nuclear Regulatory Commission (NRC) inspection conducted by W. P. Kleinsorge on June 16-20, 1986. The inspection included a review of activities authorized for your Vogtle facility. At the conclusion of the inspection, the findings were discussed with those members of your staff identified in the enclosed inspection report.
Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observation of activities in progress.
The inspection revealed no violation of NRC requirements. However, certain activities having safety significance appeared to deviate from a commitment to the NRC. The deviation and elements to be included in your response are described in the enclosed Notice of Deviation.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
The responses directed by this letter and its enclosures are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
Should you have any questions concerning this letter, please contact us.
Sincerely, h$$${d;4 P r
Virgil L. Brownlee, Chief Reactor Projects Branch 3 Olvision of Reactor Projects
Enclosures:
(See page 2)
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JUL 2 9196 Georgia Power Company 2 *-
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Enclosures:
- 1. Notice of Deviation
- 2. NRC Inspection Report cc w/encis:
O'.' P. O'Reilly, Senior Vice President Nuclear Operations (f. E. Conway, Senior Vice President &
Project Director
((L 0. Foster, Vice President, Project Support J. D. Rice, Vice President, Project
- h. Engineering
. Pinson, Vice Prosident, Project onstruction
. T. Beckham, Vice President &
General Manager - Operations
$ . A. Thomas, Vice President, yd. Licensing S. Read, General Manager, Quality Assurance C . Hayes, Vogtle Quality Assurance Manager
. C. Ramsey, Manager -
Readiness Review (G. B. Bockhold, General Manager, fluclear Operations W. Gucwa, Manager, Nuclear Safety and Licensing d.H.Googe, Project
, Construction Manager vE. D. Groover, Quality Assurance Site Manager -
, / Construction W. A. Bailey, Project Licensing Jianager dr. F. Trowbridge, Esq. , Shaw, Pittman, Potts and Trowbridge gBf W. Churchill, Esq., Shaw, LI.Pittman,PottsandTrowbridge L. Blake, Jr. , Esq. , Shaw,
/Pittman, Potts and Trowbridge to. E. Joiner, Troutman, Sanders, Lockerman and Ashmore
- 60. G. Ledbetter, Commissioner, Department of Human Resources C H. Badger, Office of Planning and Budget LI Kirkland, III, Counsel, Of fice of the Consumer's Utility Council (cc w/encls cont'd see page 3) s
F Georgia Power Company 3 (cc w/encls cont'd) v0. C. Teper, Georgians Against Nuclear Energy M B. Margulies, Esq., Chairman, -
Atomic Safety and Licensing Board Panel Jr.O.H. Paris,AdministrativeJudge Atomic Safety and Licensing Board Panel JV A. Linenberger, Jr. , Administrative Judge Atomic Safety and Licensing Board P
/ anel P. Garde, Citizens Clinic, Director Government Accountability Project bec w/encls:
tJj. Reis, GS0 cW. M. Hill, IE J . Miller, NRR W. Brach, EDO
(,X Sinkule, RII (E. Christnot, RII gNRC Resident Inspector Document Control Desk State of Georgia RI4 k RII RI RI[ RII RI Kle shg Ib Bl k ARI t !dibson VLBrownlee Je ns y/O/86 05/p/86 f/86 U 186 96/t(/86 07 86 h
.. 4 ENCLOSURE 1 NOTICE OF DEVIATION Georgia Power Company Docket Nos. 50-424 and 50-425 Vogtle License Nos. CPPR-108 and CPPR-109 The following deviation was identified during a Nuclear Regulatory Commission (NRC) inspection conducted on June 16-20, 1986.
GPC lotter, dated July 22, 1985, indicated that FSAR Figure 9.4.1-2 (Sheets 1 and 3 of 3) would be revised such that Air Filter Unit 1-1531-N7-002-000 Static Pressure Sensor / Pitot Tube locations in the FSAR correspond to as-built configuration by September 13, 1985.
Contrary to the above, the revision indicated in Georgia Power Company letter dated July 22, 1985, has not been made.
Please provide in writing within 30 days of the date of this Notice a description of corrective actions regarding this deviation, actions taken to avoid further deviations, and the dates when these actions were or will be completed.
FOR THE NUCLEAR REGULATORY COMMISSION l.SL Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Dated at Atlanta, Georgia this ()3* day of July 1986