ML20154G310
| ML20154G310 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/1988 |
| From: | Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8805240317 | |
| Download: ML20154G310 (79) | |
Text
!
MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY APRIL 1988 "Safety and Quality are Paramount" 00CKET NUMBERS 50-259, 50-260, AND 50-296 LILENSE NUMBERS OPR-33, OPR-52, ANO DPR-68 Sub tted y:
- Y ohn G. Walker Plant Manager
$$R DC 0
59 R
TABLE OF CONTENTS PART I OPERATIONAL
SUMMARY
A.
Significant Operational Events Summary...........................
1 B.
Fuel Performance and Spent Fuel Storage Capabilities Summary..... 2 C.
MSRVs (Main Steam Relief Valve) Summary..........................
5 D.
Issuance of Special Reports Summary..............................
6 E.
Licensee Events Summary..........................................
8 F.
Offsite Dose Calculation Manual Changes.........................
12 G.
Ra d wa s t e S umma ry................................................ 13 1.
Total volume of solid waste shipped off site 2.
Nature of the waste (trash, resins, etc.)
s 3.
Gross curie activity 4.
Dates the material was shipped and the disposal facility to which the material was shipped.
5.
Estimated quantities of spent resin in storage.
6.
Estimated amount of spent resin that will be generated in the following month.
7.
Waste type and volume of radwaste containers that are onsite awaiting shipment.
FART II OPERATING STATISTICS t
A.
NRC Reports i
l 1.
Operating Data Report.......................................
17 2.
Average Daily Power Level...................................
20 3.
Unit Shutdowns and Power Reductions......................... 23 B.
TVA Reports 1.
Plant Operating Statistics..................................
26 2.
Unit Ou tage and Availability Data........................... 2 7 3.
Reactor Histogram (Reactor Power Percent)...................
30
{
t l
t i
,-,,e
,-----.._-,c.,
- -. -, - - - ~,., -. -,
o 3
1 l
TABLE OF CONTENTS (Continued)
Part III MAINTENANCE
SUMMARY
i A.
Electrical Maintenance...........................................
31 l
B.
Ins t rument Ma int enanc e........................................... 3 7 l
C.
Mechanical Maintenance...........................................
39 1
D.
Modifications.................................................... 44 l
E.
Un i t 1 Ma in t e nan c e............................................... 4 9 PART V OTHER REPORTS A.
Chemistry Summary 1.
P rima ry Co o lan t Chemis try.................................. 5 0 2.
Environmental Technical Specification Requirements.......... 53 3.
Ai rb o rna Re l e a s e s........................................... 5 4 4.
Liquid Releases............................................. 59 5.
Resin Usage Report..........................................
63 6.
Fuel Cladding Integrity Parmeters........................... 64 7.
Waste Treatment System Throughputs....................
65 B.
T e s t in g S u mma ry.................................................. 6 6 C.
Reactor Vessel Fatigue Usage Evaluation.......................... 68 D.
Change in Procedures.............................................
69 E.
Plant Ins t ru c t ion Re vis ions...................................... 6 9 F.
Change in Facility Design (ECNs).................................
70 G.
Change in Plant Organization.....................................
77 H.
Accidents........................................................
78
.n,
O e
d 0P33ATIO.. AL
~
~
SCMMARY I
a l
~ -,, -
,-,,e--.,,---._,..,.--,,,nn.
,,,m,,---
,, -,. -~,, -,.,,_.- ---.., -, - _.... - -.,,, - -,-.- - -- ---
Page 1 SIGNIFICANT OPERATIONAL EVENTS
SUMMARY
APRIL 1988 Unit 1 04/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 6 refueling and modifications continue.
04/30/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 6 refueling and modifications continue.
Unit 2 04/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 5 refueling and modifications continue.
04/30/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 5 refueling and modifications continues.
Unit 3 04/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Environmental qualification work and modifications continue.
04/30/88 2400 Unit remains on administrative hold to resolve various TVA sad NRC concerns.
Environmental qualification work and modifications continue.
Pags 2 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
APRIL 1988 Unit 1 Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date to be determined. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 1 modifications are environmental qualification of electrical equipment (10CFR50. 49 ), torus modification (NUREG 0661), containment instrumentation modifications (NUREG 0737), fire protection changes (Appendix R 10CFR50)
(all), MSIV leak rate reduction modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, (LER 82020),
valve leak rate testing modifications (Appendix J), HPCI improvements, modification of PCIS logic (LER 259 85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident sampling modifications (NUREG 0737), RPS voltage monitoring modifications H0 sample line modification (LER 81050), and EECW carbon to stainless 22 pipe change out.
There are 0 assemblies in the reactor vessel.
The spent fuel storage pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available capacity of the fue.' pool is 1355 locations.
Page 3 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
(CONT.)
APRIL 1988 Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined.
On September 3, 1985, the unit war placed on administrative hold to resolve TVA and NRC safety concerns. The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 2 modifications are CRD SDIV piping modification (IEB 80-17), environmental qualification of electrical equipment (10CFR50.49), torus structural modifications (NUREG 0661), contalnment instrumentation modification (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reductions modifications, modification of masonry walls (IEB 80-11), addition of feedwater nezzle temperature monitoring (%UREG 0619), evaluation of the vent drain and test connections, (tER 82020), valve leak rate testing modifications (Appendix J),
D/G speed sensor installation (LER 81004), HPCI and RCIC testable check valve change out, modification of PCT.S logic (LER 259 85009), HPCI improvements, various seismic progrcm review, and EECW carbon to stainless pipe change out.
There are 0 assemblies in the reactor vessel.
At month end there were 304 new assemblies, 764 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 a'ssemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 1481 locations.
All High Density Racks have been installed in the pool with the exception of two.
Page 4 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
(CONT.)
APRIL 1988 Unit 3 Unit 3 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be determined.
The sixth refueling outage involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-startup unit 3 modifications are environmental qualification of electrical equipment (10CFR50. 4 9 ), containment modifications (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reduction modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, (LER 82020), valve modifications ( Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14),
postaccident sampling modification (NOREG 0737), addition of redundant drywell control air supply, RPS voltage monitoring modification H 0 8 ample line 22 modification (LER 81050), replacement of jet pump holddown beam assemblies (IEB 80-07), EECW carbon to stainle:s pipe change out, and plant design upgrade to seismic qualification.
There are 0 assemblies in the reactor vessel. There are 764 assemblies to finish EOC-6, 248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent fuel storage pool.
The present available capacity of the fuel pool is 585 locations. All high density racks (HDR) have been installed in the pool with the exception of six.
Paga 5 MSRVs (MAIN STEAM RELIEF VALVE)
SUMMARY
APRIL 1988 No MSRVs were challenged during the month.
1
Page 6 ISSU ANCE OF SPECIAL REPORTS APRIL 1988 The following special reports are notices of violations issued for the month of April 1988.
87-29-01 During the Nuclear Regulatory Commission (NRC) inspection conducted on July 27-29, 1987, violations of NRC requirements were identified. The licensee did not maintain adequate written material control and accounting procedures to enable the licensee to account for special nuclear material in that at the time of the inspection. Technical Instruction 14 did not provido. Technical Instruction 14 was not followed in that during four (4) separate inventories of special nuclear material (SNM) stored in a wooden box on October 28, 1986, January 30, 1987 and twice on June 16, 1987 an accurate piece count and listing of serial numbers was not obtained.
At a result, a radioactive material shipment on June 16, 1987 was itaproperly documented as a shipment of five (5) Intermediate Range Monitors (IRMs) containing about one milligram of SNM each, as opposed to the actual count of six (6) IRMs contained in the shipment.
These violations have been categorized in the aggregate as a Severity Level IV problem (Supplement III).
87-29-02 10 CFR 70.51(c) requires that each licensee authorized to possess at any one time special nuclear material (SNM) in a quantity exceeding one effective kilogram of SNM shall establish, maintain, and follow written material control and accounting procedures which are sufficient to enable the licensee to account for the SNM in his possession under license.
Section 7.9 of Technical Instruction 14. Special Nuclear Material control, which was prepared by the licensee to satisfy the requirements of 10CFR 70.51(c), states that all established internal accountability records shall have prepared signature or initial lines, where required, to expedite and promoto proper documentation and identification of the responsible individuals. These records should readily yield information about SNM receipts, internal transfers of SNM, and any shipments of SNM.
Updates of these records should be completed within a reasonable time after the event necessitating the update.
Contrary to the above, the provision for the update of accountability records within a reasonable time was not met in that Fuel Assembly Transfer Forms for the Unit 3 Core Unload performed between January and February 1987 were not updated in a reasonable time with some being updated as late as four months after physical movement of the fuel.
This is a Severity Level IV Violation, (Supplement III) and is applicabic to Unit 3 only.
_ _. _... _ ~
Page 7 ISSUANCE O.F SPECIAL REPORTS (Continued)
APRIL 1988 88-06-01 On March 17, 1908, the following procedure violations were observed.
- Loose rivets were found on the refueling floor within the control zone and were mistakenly thought to have entered the reactor vessei during a lost-item recovery operation.
Accountability records did not identify what screws or parts were missing on the ultrasonic (UT) scannor used in the vessel.
- Several screws on the UT scanner were intentional!f loosened rather than correct a geometric deficiency.
Screws on the UT scanner were not attached with a lanyard or locking device.
The UT scanner was inserted and removed from the vessel several times to trouble shoot and repair scanner problems.
However, the missing screws and roll pin were never identified even after a lost item recovery occurrence, where this scanner was suspected of having lost the parts observed in the vessel cavity and inspection of the. scancer device was suppose to have been thoroughly performed.
No one verified or accounted for any of the missing screws or the roll pin.
This is a Severity Level IV Violation (Supplement I).
'I 4
page 8 LICENSEE EVENT REPORT (S)
A?RIL 1988 1
The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in April 1988.
Deveription of Event LER 1-86-024 Loss of Secondary containment caused by Design Rev. 02 Oversight On August 22, 1986, it was determined by TVA design engineers that various nonsafety-related piping systems penetrating the reactor building-turbine building wall are not seismically qualified. This condition, is not consistent with the design j
description in section 5.3 of the Final Safety Analysis Report (FSAR), which states that secon6ary f
containment penetrations are seismically constructed. As a conservative measure, plant management declared the secondary containment inoperable, and plans pending at the time to unload fuel from the unit 3 core were halt rJ.
A TVA design oversight permitted drawings to be insured which did not include any requirements to seismically qualify secondary containment penetrations, as described in the FSAR.
A fuel handling accident is the only event that could challenge secondary containment under the present plant conditions.
An analysis was performed which found doses resulting from such an event to be well within 10CFR100 guidelines. TVA will demonstrate that the plant is capable of maintaining a negativo 1/4-inch of water pressure in secondary containment following a design basis earthquake prior to unit 2 startup.
1-88-011 Engineered Safety Feature Actuation Due to personnel Error During Returning System to Service on March 4, 1988, at 1039 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.953395e-4 months <br />, with all three units defueled, three emergency equipment cooling water (EECW) pumps were inadvertently started due to pressure drop in the raw cooling water (RCW) system caused by the opening of the temperature control valve (TCV) at the reactor building closed cooling water (RBCCW) heat exchangers.
Low RCW prescure is a designed start signal for the EECW pumps.
The shift supervisor (SS) discovered that the RBCCW temperature at tha pumps was hot.
Description of Event pags 9 (Continued)
LER Upon this discovery the SS opened the TCV to the A RBCCW heat exchanger 20 percent more on unit 2.
This caused low RCW pressure on unit 3, and thereby completed the start logic for the EECW pumps. This was an unplanned actuation of an engineered safety feature.
The unit operator then started another RCW pump.
Two hours later tha tht-ee EECW pumps were returned to standby readiness and the additional RCW pump was shutdown to see if the event could be duplicated. The EECW pumps auto started again when the additional RCW pump was chutdown.
The unit 2 RBCCW system was removed from service due to finding several valves out of position. These valves were out of positica due to a previous SS waiving the restoration checklist in 2 workplan.
After removing R8CCW from service, valve checklists were per formed for RGW ' nd RBCCW system. The operators will be provided with a description of this event.
1-88-012 Battery Failure Concurr.ent With LOP /LOCA Prevents Automat}c Start Of Residual Heat Removal Pump During a review of the 250V de system a condition was discovered that could prevent the automatic initiatica of a residual heat removal (RHR) pump.
The failure of a battery supplying logic foe one division of RHR would prevent one of the two pumps from sta
- I"g.
The other RHR pump in the division that it.-
+ic power also receives a start signal from the opposite RHR division logic. The battery failure caus$c the start logic in the other division to sense diesel generator power is available for the RHR pump that lost division logic. This energizes the start relay for the RHR pump and causes the breaker to try and close onto a deanargized electrical board. When this occurs the pump breaker will trip. The pump must then be manually started from the electrical distribution board.
This condition was the result of a design error when the RHR logic was modified in 1977. The condition will be evaluated to determine the necessary corrective action. Changes in the TVA design process ensure that modifications receive a thorough review foe implementation of design requirements.
l l
Description of Event Piga 10' (Continued)
LER Padiation Monitor Spike Initiates control Room, 1-88-013 Emergency Ventilation On March 28, 1988, at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, with all three units defusled, both control room emergency ventilation (CREV) trains inadvertently started due to a high radiation signal from the control room air inlet radiation monitor (RM).
A high radiation signal is a designed start signal for the CREV trains.
In preparation for installing insulation plant craftsmen were vacuuming near the unit 3 control bay RM.
A high radiation signal was received from this RM which resulted in control room ventilation isolation and both CREV trains atarting. This is considered on unanticipated actuation of_an engineered safety feature (ESF).
The Assistant Shift Operations Supervisor verified.
by the review of the RM chart recorder, that a spike on RM 0-RM-90-2598 had caused the ESF actuation.
Twelve minutes later the unit operator reset the isolation and returned the CREV to standby readinass.
Instrument and controls personnel will investigate the possibility of a radio frequency tripping 0-RM-90-259B using a radio frequency generator and determine if the RM is adequately shielded. The Shift Operations Supervisor requested the modification carpenters place a protective plywood shell around 0-RE-90-259B to ensure that affected safety equipment is protected as Eccessary, when modifications are being performed.
1-88-014 Surveillance Testint Of Liquid Radioactive Waste DischarRe Isolation Valves Incotaplete Due To Inadequate Procedures As a result of the programmatic upgrade of the Browns Ferry surveillance instructions (SI) it was reported on March 29, 1988, that the SI which tests g
the automatic isolation logic of the liquid radioactive waste discharge isolation valves did not fully test all operational configurations and
,/ - :
that the flow switch on the tooling tower blowdown line was not identified as technical specifications (TS) required instrument and had not been calibrated on a regular schedule.
TS 4.8.A.3 requires annual testing of the automatic isolation valves.
Failure to test the logic and calibrate the flow switch was a violation of the TS surveillance requirement. No instances of inadvertent discharge due to logic f ailure have been identified.
All three units were d-fueled at the time of discovery.
e Description of Event Pago 11 (C:ntinued)
LER Administrative controls were established to ensure p
improper releases were not permitted until such time as the automatic isolation logic could be tested for each unit respectively.
sis have been prepared which fully test the pump interlock logic.
A calibration procedure will be prepared for the flow switch. The discovery of this deficiency is considered a good indication of the quality and capability of the upgraded program, therefore additional recurrence control actions are not considered necessary.
J e
r 1
Pago 12 OFFSITE DOSE CALCULATION MANUAL CHANCES l
l APRIL 1988 No changes were made to the Browns Ferry offsite dose calculation manual during the month.
1 I
i l-
Page 13 o
Radwaste Summar)
April 1988 Coauton The radwaste system performed as designed. Approximately 1.01E+06 gallons of waste liquid were discharged containing approximately 3.19E-02 curies of activity.
There were five spent resin shipments and two trash shipment during March.
All shipments were to Barnwell SC.
Paga 14 Solid Radioactive Waste (Continued)
April 1988 Summary Type Shipped to Packaged on Gross Curie Estimated of
'BarnweLL Site Awaiting Content by Generation for Waste During Month Shipment Type of Waste Next Month Compacted Drums 660 Cu.Ft.(2) 135 Cu.Ft.
3.33E-01 600 Cu.Ft.(2)
Boxes 558 Cu.Ft.(2) 465 Cu.Ft.
1.27E+00 800 Cu.Ft.
)
Uncompacted Drums O Cu.Ft.(2)
O Cu.Ft.
0.00E+00 0 Cu.Ft.(2)
Boxes 800 Cu.Ft.(2) 0 Cu.Ft.
1.46E-01 600 Cu.Ft.
Resins CWP5 820 Cu.Ft.(3) 675 Cu.Ft.(3) 3.86E+01 450 Cu.Ft.(3) l RWCU 0 Cu.Ft.
75 Cu.Ft.( '
35 Cu.Ft.(
O.00E+00 TOTALS 2989 Cu Ft.(
S00 CU.Ft.('
4.04E+01 2000 Cu.Ft.
Total volume of waste shipped during the month:
2989 Cu.Ft.
Total volume of waste shipped year-to-date:
8952 Cu.Ft.
Unused 1988 burial volume allocation at Barnwell:
73848 Cu.Ft.
(1)
Actual resin volume (2)
Container burial volume (3)
Estimated volume in separators (4)
Does not include resins
Page 15 Solid Radioactive Waste April 1988 Dewatered Spent Resin Shipments (
Volume of condensate / waste resin shipped:
23.37 Cu.M. (820 Cu.Ft.)
Total curies shipped:
38.6421 Volume of reactor cleanup resin shipped:
O Cu.M.
( 0 Cu.Ft.)
Total curies shipped:
0 Date Shipoed Disposal Facility Type o[ Resin 04/04/88 Barnwell, SC CWP5 04/08/88 Barnwell, SC CWP5 04/12/88 Barnwell, SC CWP5 04/18/88 Barnwell, SC CWP5 04/22/88 Barnwell, SC CWP5 Dry Active Waste Number of drums Shipped:
88 Volume:
18.7 Cu.M.
( 660 Cu Ft.)
Total curies shipped:
0.3326 Number of boxe5 Shipped:
14 Volume:
38.49 Cu.M.
(1358.4 Cu.Ft.)
Total curies shipped:
1.4178 Date shipped Discosal Facitity Tvos nf Package 04/20/88 Barnwell, SC Bo::e s 04/28/88 Barnwell, SC Boxes & Drums (1) All shipments were by Sole-Use Vehicle he um i g iu
LIGUID RADWA'~jTE Pags U>
MONTHLY OPERATING REPORT APRIL 1988 TOTAL RIVER RELEASE FLOW RATE (GPM)
CATA PLOTTED FOR THE PREVIOUS 12 MONTHS TOTAL RELEASE (CZ) 40.
2 FLOW AATE fGAW) 30.
HI 27.10 LOW 11.62 AVG 19.10
~
~
y psn cP AM (E?)
HI 0.05 10.
LOW 0.01 AVG 0.03 O FLIWRATE O
9 0
EAY JUN wUL AUG SEP OCT NOV OEC JAN FEB RAR APR THAOUGHPUT fG ALM)
FILTER THROUGHPUTS 3
WASTE GALLONS X 10 HI 0.20E+07 5
LOW 0.85E+06 AVG 0.13E+07 4
FLCCR CRAIN HI 0.99E+06 LOW 0.49E+0S 3
AVG 0.76E+06 gF i
.hs k
LAUNORY
[$1 x
s LOW 0.00E+00 2
HI 0.11E+05 R
l l twi !M.g,1 !M M !F r.e,,a Ml k
^"
i _
0 MAY JUN JUL AUG SEP OCT NOV OEC VAN FEB MAR APA COST OF OPERATION 57m ", in s, egenAT,,
THOUSANOS OF 00LLARS WASTE 10CL HI 0.64E+05 90.
LOW 0.19E+05 AVG 0.3BE+05 70 _
}
80.
{
[
FLOOR ORAIN 60 _
i y
HI 0.45E+05
~
N l LOW 0.21E+05 1
i (
I AVG 0.29E+05 50 _
j
,l l
LAUNORY t
t t
40.
j y
L 5 d 30.
': I HI 0.18E+03 l
j th%
b Q
- '3 LOW 0.00E+00 i
r 20 -
y,t//, '
Vui,;
AVG 0.43E+02 ll ap,; ];
~
MAY JUN JUL AUG SEP OCT NOV OEC VAN FEB MAR APR WASTE COLLECTCA SYSTEM LAUNORY SYSTEM FLOOR ORAIN SYSTEM STARTING 3-87 COSTS INCLUCE RESIN DISPOSAL
~.
t S
CPERATING STATISTICS 1
--- -,. -.- -,,,,, -. - - -. --,,-~- --- - - - - -., - - -
Page 17 OPERATING DATA REPORT DOCKET NO.
50-259 DATE _05-01-88 CO.lPLETED BY J.D. Crawford
\\
TELEPHOSE (205) 729-2507 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Unit One Noth
- 2. Reporting Period:. April 1988
- 3. Licenwd Thennal Power 15thti: 3293 1152
- 4. Nameplate Rating (Gron 5!Wel:
- 5. Design Electrical RatingINet SlWel:
1065
- 6. Stasimum Dependable Capacity (Gross 5!We):
1098.4 1065
- 7. Stasimum Dependable Capacity (Net SIWE):.
- 8. If Changes Occur in Capaciay Ratings (items Number 3 Through 7) Since Last Report. Gise Reasons:
N/A l
- 9. Power Lesel To which Restricted.lf Any l Net S!We):
N/A N/A
- 10. Reasons For Restrictions.lf Any:
This Slonth yr..to.Date Cumulative II. Hours In Reporting Period 719 2903 120.583
- 12. Number Of flours Reactor Was Critical 0
0 59,521.38
- 13. Resetor Resene Shutdown liours 0
0 6.997.44
- 14. flours Generator on.Line 0
0 58.267.26
- 15. Unit Rewne Shutdown llours 0
0 0
- 16. Gran Thermal Energy Generated (5thil, O
O 168.066.787 0
0 55.398.130 I 7. Grow Electrieal Energy Generated I.\\lWtt)
-4606
-9415 53.696.987 _
IS. Net Electrical Energy Generated ISIWil)
- 19. Unit Senice Factor 0
0 48.32
- 20. L* nit Asailability Fwtor 0
0 48.32
- 21. Unit Capacity Factor ll' sir.: \\lDC Net) 0 0
41,81,
- 22. Unit Capacity factor (U>ing DI:R Net) 0 0
41.81
- 23. Unit Forced Outage Rate 100 100 42.80
- 24. Shutdowm Scheduled Oser Nest 6 \\lonths IT.spe.Date,and Duration of Facht-
- 25. If shut Down At End of iteport Period. Estimated D.ite of Startup:
To be determined 2t,. Unin in Test Status (Prior to Commercial Operationi:
Forecast L hiesed INilI \\ L CulIICAl.1IY INill \\L ELLCTRICITY CO\\l\\lritCl\\L OPlit\\lloN l'3,III I i
l l
1
Psgo 18 OPERATING DATA REPORT DOCKET NO.
50-260 DATE os-01-98 CO.\\lPLETED BY M n tw o r TELEPHONE (205) 729-23b OPER ATING STATUS N"I"
- 1. Unit NJme:
Browns Ferry Unit Two
- 2. Reporting Period:
April 1988
- 3. Licensed Thermal Power 15thrt:
3293 1152
- 4. Nameplate Rating (Cross Sthet:
1065
- 5. Design Electrical Rating (Net SIWet:
1098.4
- 6. Alasimum Dependable CapacityIGross 5thet:
1065
- 7. Stasimum Dependable Capacity (Net SlWel:
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 71 Since Last Report.Give Reasons:
N/A (Net SlWel:
N/A
- 9. Power Lesel To hhich Restricted,if Any/A N
- 10. Reasons For Restrictions. lf Any:
This.\\lont h Yr. to.Date Cumulatise i1. Hours in Reporting Pened 719 2903 115.470
- 12. Number Of Hours Reactor has Critical 0
0 55,860.03
- 13. Resetor Resene Shutdown Hours 0
0 14.200.44
~
- 14. Hours Generatur On Line 0
0 54.336.36
- 15. Unit Rewne Shutdown !!ours 0
0 0
- 16. Cross Thermal Energy Generated (Nihill 0
0 153,245.167 17 Gron Electrical Energy Generated tSihHI O
0 50,ill,198 IS. Net Electrical Energy Generated 15th H)
-1924
-7666 49,176,167
- 19. Unit Senice Factor 0
0 47.00
- 20. Unit Asailability Factor 0
0 47.06
- 21. Unit Capantv Factor IUsing AIDC Net) 0 0
39.99
- 22. Unit Capacity Factor (Uning DI:R Net) 0 0
39.99
- 23. Unit Forced Outage Rate 100 100 42.10 24 Shutdowns Scheduled Oser Nest b Stunths IT.spe Date,and Duration of Eacht-
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: To be deterrained
- 26. Unis in Tot StatusiPrior to Commercial 0perationi:
Furecast Achiesed INITI \\ L CRITICAll TY INITI A L ELECTRICITY CO\\l\\lERCl \\ L OPI'I; A TION eh77)
Pags 19 OPERATING DATA REPORT DOCKET NO.
50-296 DATE._95-01-88 COSIPLETED BY J.D. Crwford TELEP110NE (205) 729-2507 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Unit Three N"I"'
- 2. Reporting Period:
April 1988 3293
- 3. Licensed Thermal Power (5tht):
- 4. Nameplate Rating (Gross 5thes:
1152
- 5. Design Electrical Rating tNet SlWe):
1065
- 6. Stasimum Dependable Capacity (Gross 51We): 1098.4 1065
- 7. Stasimum Dependable Capacity (Net SlWel:
S. If Changes Occer in Capacity Ratings litems Number 3 Through 7) Since Last Report. Give Reasons:
N/A N/A
- 9. Power Level To Which Restricted,if Any/A INet SlWei:
N
- 10. Reasons For Restrictions.lf Any.
This 51onth Yr..to.Date Cumulain e
- 11. Hours in Reporting Pened 719 2903 97.895
- 12. Number Of flours Reactor Was Critical 0
0 45.306.08
- 13. Resetor Resene Shutdown tiours 0
0 5.149.55
- 14. flours Generator On.Line 0
0 44,194.76
- 15. Unit Rewne Shut < lown llour, 0
0 0
- 16. Gran Thermal Energy Generated (5thill 0
0 131.868.267 17 Grow Electrical Energy Generated IMhHi 0
0 43.473.760 IS. Net Electrical Energy Generated 15thH)
-1763
-10.530
_ u.030.o b-
- 19. Unit Senice Factor 0
0 eW
- 20. Unit uailability Factur 0
0 43.14
- 21. Urut Capacity Factor (Using SIDC Net) 0 0
40.31
- 22. Unit Capacity Factor iUsing DER Net) 0 0
40,31 -
- 23. Umt Forced Outwe Rate 100 100 45.57
- 24. Shu Jowns Scheduled Oser Nest 6 Stonths iTypc. Date and Duratmn of Facht-
- 25. If Miut Down At End Of Report Period. Estimated Date of Startup:
To be determined 2 ts. Umts in Te t StatuuPrior to Cmnmercial Operatione Forecast Abies ed INITI \\ L CRITICA LiTY INITI \\L ELECTRICITY CO\\l\\lERCI \\L OPER \\IlON im77 )
AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.
50-259 UNIT One DATE 05-01-R8 COMPLETED BY J.D. Crawford TELEPHONE (205) 729-2507 MONTH April 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Nett tywg.Ne p i
6
-6 g7 2
-7
-5 IS 3
-7
-7 gg 4
-7 20
-7 g
-7
-7 6
-7
-8
?
-7
-5
- 3 3
-7
-7
$4 9
-2
-6
,3 10
-5
-7 3
Ii
-7
-6
,7 1
-7
-6 33 13
-7
-7
,9 l
14
-6
-6 30 1
-7 15 3
16
-6 INSTRUCTIONS On this format.!ist the average Jaily unit powcr level in Mwe. Net for exh da) ut the reportmg :n.inth. Compute to the nearest whole megawatt.
vuiis
d Page 21 l
4VERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 UNIT TWO DATE 05-01-88 COMPLETED BY J.D. Crawford TELEPHONE (2051729-2507 MONTH April 1988 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL tMWe Net) y w,.3,,,
1
-2
-2 37 2
-2 13
-2 3
-2 39 1
4
-2 20
-3 5
-2
- g 2
-2 4
6 7
-2 1
,3 3
-2 34 3
9
-3
-2 3
10
-3
-4
,.6 ll
-3
-5 12
-3
-2 13
-3
-3
,9 14
-3
-2 30 l$
-2 yg In
-6 INSTRUCTIONS On this format,hst the aserage daily unit pe>wer lesel m StWe Net for ea6h da) in the repi.rting m.inih.C impute io the nearest whole megawart.
(9 '*7 )
1
AVERAGE DAILY UNIT NWER LEVEL l
000ET No.
50-296 Unit Three DATE 05-01-88 CO WLETED BY J.D. Crawford TELEPHONE (205)729-250Z l
l MONTH April 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mde-Net)
(Mde-ket) 1
-2 17 2
-2 I8
-1 3
-2 19
-2 4
-2 20
-3 l
5
-2 21
-2 6
-2 22
-4 f
I i
7
-2 23
-2 l
8
-2 24
-3 I
9
-3 25
-2 10
-2 26
-2 II
-3 27
-2 12
-3 28
-2 13
-3 29
-3 14
-2 30
-2 15
-2 31 16
-2 INSTRUCTIONS On thIs formet, Iist the average del 1y unlt power leveI in MWe-Net for oech day ir the reporting month. Compute to the nearest whole megawatt.
(9/77)
Page 23
\\.
N n o 6 m w
C N a: %
e
=
0: 3 @
O e
i e N Z
e 6
N g
=
N c u s
t, i
-a e, _.m c v
. c oa 2-~
.= - } *-
e e c c e aw i!.-
- N v
eu 2
9-
.c a
wv 2.a--
.s c
w >.
g.2 oo
=
= 5, : 1,
)
a "u
<a g,5 r
u
>ga o
mu
- ;sc w.
f 4
5_
4., x
- .m x
~Moz u
w-y < y=
x e.-:-
=
a m
=~~C4
=
w
.,3 o
oe g
e u,.c 3
t wb w
a2
-=
C Q
-aw mn m
K i
gapo)
=25
.i M j _, 4 iuauodiuo) x
~2 -
~
a n
r P".]
2 i i 5 $.
5 8
w y-
{
c unains
,x e a-,-
g
=
=
z I
w v
u z
3 32 m
= -r 2.W; oE 9
g I
=
E a
~
~;
x E
i
=
.mt.sray u w a 3
z t
utiings 4
=
y in P'41)W
-3,
=.
1 i
=..
3, g-
.thitroy
=. -
v c.
2 s
-: y -
i i
l 1
9 : s-
-. ; x ;.: - 4 03H"ll) m
-g 4..
- "I ~L uos tring i3 p5
- i"
-a
=, 5" "c.= ;
= = -
=
=
32,52C t~
w, = y.:
v g.N $1
.)== E % E O d=O x"=-wa--J:
i CO CC l
\\
N, L
f O
+
s?
s O
Mi ws e
- i. 3 c
Y
- /.
"n
?
..m
Il' l
e 2%
t 7
e d 0 r 5 G
o 2 f
I
+
R w 9 l
8 a 2 i
8 r 7 N
0 C
e e (e 6
cl 1
)
v.
s
_ 5 l s i aml c
2 0
e D. 0 on
- m. ta c 'i u
o s
0 w 5 2
sr eDAR u
5 T 0 J (
e e
ee u 'l N
s I
v c
1 s
u rc e o O. EEYE t
c n
s o m. l c
t t
s i
u D O os c ssn. f o L
i n oo n
e e N MTBN s s s
I u
t c n
r e
A A
- a u e s
u p.
T N D E H CiR dC Ga l
e I
e E
s l R pSR ts K T TP
&a s oN sne I
E E t
1 i
O U P E u
s d
la P s) sa 1 ai C N L L wAu h
e c e.
l is c
i l
- n. n s l s
s
)
a e
en MI C
o I
s B I I I I
F va O
i C
t A 4
s aV rT tss i u no iimr d a A v SN
)
in H
. s i l
%lO i a 1
m C
n s a
U cjeEu aSl p s
)
e Sss s.
I E
e.
8 a l ni 1 l
t i
a J. uu oc l
s R
i n nnt i r,7,O I l l E
r a a ul r
-[3n ckbAO W
p O
A MI 24 4 i
P
)
l I
i I
N f
A N
O e
e SN M
c t
nnr W
T e
e o c v p
)
R M
O i : e s
I l
l R
=.
l P
e U
E sa H
R n
S sn i
, =EE c!6 ua l
N Esg I
U g
4
)n w
t j23e lp s s p
o.
ei.
ia s.
.l s
ui s
w l
it in 3j4 sul ss F
I s
a e e
(
g s.
s n e
us s l l
r iao cnce ne n
I l'
R a s.
a 9
e s sa la lp 3gE tns 1
k
>I s es s e u. n.
e.
t I
g 7
- i. 3]
me ns h
s.
ci a s.
i
. pa ci a sus a e us
- s. sui ie e pJ pl nn gcms w
c ug a ta
.MRROAOi
,i-F ea 1
8 l
l RAHCI iiGi w
[
8 8
se
/
1 a
i 0
l
/
4 l.
0 le J u cd
.s c.
3
.l
.k 1
5 W
)
0 n
7 1
3 I i
/
l
'l
+
e e
' ^
3!
'1 1
I
- i!
l 4
I g
Page 25 b
m o w e e n w
s x
3:
3 @
cs:
t1 N l
w W G
N' *
.e e u
9 e, 3.2 s
e e
-M e
u e
< c oa a---
1 o
e o c M u 1-g 1
e e
< ~
vv
- - x
=
A mv y
wa x
= =., _
e w
2.E oo 35:-
=
IwN>a
.r. 5
'. 3, 4 I
).
-2
" W 3
mu
..-v j
u i= Z a w s
-x
- 2,2 E _
gk M*z w
OZ
~ C
?
y a
ski 2C :1-
?
^
R 4
0 ec
..E. E k '
7 7
>n A
w
.e u<
o>
wH w
M M a
- :s C O w.ce aw mn VI I
T t
apo.)
- i.2 s, iuauodtuo
.'. e
=
)!_
-w l
m 7 3' s.=.
J 8
L r po) 244i3 a
w n
3 waisig 2e A=
z Z
K
~
u u
E 2
3=.
c
z t w= uL w
n e
x
.?
t m
w x
=
2 3
.mpray uwe 3
j Sujiinys to NytaW
=-
3
-s-
- ?*=
1 n
b*
me
- lk M P.iy g
- 3 4.a
=,
4
_O" 2
v 4
3
.J. =,.3.
- 0
/*
=
- 3
=,
o h
I d 1
-S
.m I
A.
s Ik k bb M
I) g c.E ;
- r: 212~2*
L
- s. =., V.=y,y3_
=
_. =_
2-,
h M
I A
a
- W w
w to x4=LO--J=
l Pt
[
N CO v
i 9
2 O
eo
~2 w
t O
7 V ~3
$o
-s i
1 N
=
N
[
/
4
== #
m i,
y 1
t i
I e
-.. =.... - -.... - -, - - -.,
tva ns: Acon s.sil NUCLEAR PLANT OPERATING STATISTICS Browns Ferry Nuclear Plant 19 Month April 19 88 Period Hours llem No.
Unit No.
UNIT 1 UNIT 2 UNIT 3 PLAST 1
Averane Hourly Gross Load. kW 0
0 0
0 2
Maximum Hour Net Generation. MWh 0
0 0
0 2
0 0
0 0
3 Core Thermal Enerav Gen. GWO (t1 4
Steam Gen. Thermal Energy Gen., GWD (t)2 j
5 Gross Electrical Gen.. MWh 0
0 0._
0
- s 6
Station Use MWh 4606 1924 1763 8293 7
Not Electrical Gen., MWh
-4606
-1924
-1763
-8293 fo 8
Station Use, Percent 0
0 0
0 9
Accum. Core Avg. Exposure, MWO/ Ton!
0 0
0 0
10 CTEG This Month.106 BTU 0
0 0
0 11 SGTEG This Month,10 BTU C
0 0
0 6
12 13 Hours Reactor Was Critical 0
0 0
0 14 Unit Use. Hours Min.
0 0
0 0
15 Capacity Factor, Percent 0
0 0
0 16 Turbine Avail Factor. Percent 0
0 0
0 y
17 Generator Avail. Factor. Percent 0
0 0
0 g
0 0
0 0
18 Turbqgepvail. Factor. Percent g
0 0
0 0
t 19 Reacje Avail. Factor Percent 0
20 Unit Avail. Factor. Percent 0
0 0
0 0
0 0
0 21 Turbine Startuos 22 Reactor Cold Startues 0
0 0
0 21 24 Gross Heat Rate, Btu /kWh 0
0 0
0 f
25 Net Heat Rate, Btu /kWh 0
0 0
0
}
2s W
27 g
28 Throttle Pressure, plig 0
0 V
U g
29 Throttle Temperature. 'F 0
0 o
o j
30 Exhaust Pressure, inHg Abs.
0 0
0 0
g 31 Intake Water Temp., *F 0
0 0
0 32 33 Main Feedwater, M lb/hr i
34
[
35 36
~
(4) 37 Ful! Power Capacity, E FPD (J)
(4) je) 38 Accum. Cycle Full Power Days, EFPO (4)
(4)
(4) 9 39 Oil Fired for Generation, Gallons 13360 40 Oil Heati a Value. Btu / Gal.
[39900 75.6 41 Dietal Generation. MWh i?
Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Data Factor. %
3 43 0
1 0
0 Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
j 2(t) indicates Thermal Energy, 3
3 Int omation f urnished by Reactor Analysis Group, Chattanooga
~
A 4 Administrative Hold A
//
a
/J il //
j j
/
- v Date Submitted Date Revised
/, e
/ Plant Superinteiwent
==
I s:
i
. i.
I i;-
l.
i a
l.1 i
,i i'
i v>U i l
l I -
l I
t J.
< - E j ;i -
(
I l
i
',t Pago 27
< i 1
i l
t; i
t r.'
0, % W l!
i i
I 1.
E, l
- =:
i L
i i
'~#
i l.i
!!!,t i
i I
ll l
!fl!
i f
<; ~,
1 i
i 4 i i
I!
e i 4 ',l
. i
, i
- l. i a
j,
I l
i g-,s s
1 d
-4 j,
I I I ll l
i O
7 Zt t l ' '
l l !
l i
i
<E-l i
$ c
- -xx i
I i ! -
!il
!'3
. > - ! l!
! cl i
i i i.
l1}i A--
j
! 'i 1,.I!!
I i l
ll>!
i,!
I!i
r-l i
l
,, i i j
i i
j i
I i,
l i
.i i,
i 1
- 5 4
~
i t 1
I i
t i,
ji,.
i l
i ( -i t
i i
1-lt l,i l
X = $ ~s
.i t,
i,
=-
4
- 2)i
)
l t
J 3
I
[
i, i
i
.e.
i I
' !:2 i
i l
i i
e 1
i _e i
i i
t 6
I g
g' I
I q
i i
w l
i I
{
l N
g
- 5 lj,l li
!,i l
li',!,,-!! 'l J
t, i
, i 4
J 1
t l 1 1.
_I '!
I
!4 k
i t a ll i ! t d
.T i"l
, i i
E j',;
. i !,.
1'
+
I
~
p!S.1 i
I a
j !',. t I, !
,! l.'
i i
I '
,c i
I '.
l'3 m3ll,
,I I 1 6
aC l
i I
i 3
E E-
.j !..,.1 l '..'..l.{.l.i!
..... -......'..i...:
'i b l!ll t
w m
k
,h
$l l l I f,!li l
l l.!
~
l*
i I
T. _._l..
.-__..) _ _, _ _ _.4 f
[IlkI
'l
('!I i
I
,.L..a s.s.!.s' i!!,
i s.'s.'
s i lt ll 1
't l
O4 4.@ i h
i 4.h
. I c a r.~. N 1 1 4
- 3. f.$.l o g'w!gi'II!!
l l
I lI ( q!g!
i !
j o
i r a.
i j
f l. p 4.cm l 9
- ie e.,N-I i l lJ f ! '
l
'I I i ll l ll l I3 )
,N - l 4 t l,
- { l i
.E,.o gg i 9' fj-liii.
, li!
,,,,l i I -,
,9 9 '
t i
! i 1 t
- e.: _ r
+
( v -J I
4
[
'-p : p 6
,fI ll'l ' 6 1
~
f '4
- l**l l
-* dm ti l
..k} 9 lf1 i * * ' - '
l{. t l l
. t )
4 i
a
$lN f!'!lllI i I{
IiI!I l
l l l ( ?_ ?.,'
2
!.,. 8,.8, ?.
b i
! [!"'C'
. ' f l
- i "*"* I
- ** JM
-f il1 j'l I l g
-f P
i,lI i li i
t j j j i
l
. i
- I i
i i
j
_$}
_..1
__,_...___..-.-,_I_
, _. _ _ J. _... _,i y
I!!!}iIl!IiII!lllIlIIil}IIi!j h,.f h' d
3 f,
..I t
2 5 SU
. dllli!.llI l
, _ -. 4.,I _l1 l.l..l.i _!.l.l.!.l.. l.l.' :
_l._ !.l,!.l,_,'
S s
s
= _
l 4
k x f m' l.a l.O.i _5 r.' W =* i A.Il A f a i ? l.*. h - ev a"" - '.* +
5
- j, 'e
.eJNe2 A t 4 ' *. 2 l - !, 9. '
,6 c 4 e a c. c a s 6
y
..m-
_4 l
h **
4
+
l i
i..,
l!.
i i.,
{
1 l',
j
_i :
il
%3E ! l i
ll-l! : !
'I i
Pags 28 i
l
_.z : )
i !-
1 i j
l
,;I l
j i i !
=
- I
- s I
l+
l{
. i l!
3 i
v.-
ll,i' i,i li i
1 s:s i
i w 23 i
.;i i
j!Ij:
- j
- *i S
I !!!
!!!i l'i lllI
- i 1
4 i,
lIl t
l.
I fl:
- l e:49d l'
I f
I e<
=
i
- <E-i,, i,
,iil i.
I,l
,i ili.i l
s a 2 x2 i
eww l -
l
>i i
i i
l 11 i'
i il!<!
I.
i 4
l l
r 4
ll l
1II
...:lI
! llil li
,3 e 2= c j-
,1i i
. i !
!!! Ii!
l'il
.i
- -fD
- ! t :
4 l1 054 i
t ii
- 5 5l l i lI 5
i !
i'!li l'
i 7
.e i i, I
. i
,i i
i i
e 1
t 4.
I I
l l a.
. +
i i
a i
i i i I
i,
i +
i g
I 1
I '
(
C4 il l
i l i f,i}
i i
1 w
i l l
j.l l
l
- i
,l
' i i
j. i :
.v
!ill,r!!
!!l!
i -
c 4
i s
.=v 1
i 1
!;:j i
i, :
'l f
Iil l
(.
s 7
I i, j i,
s x
c 1
i ;;!
4 l,
j,,
i l
i 2
- 1..
i a
I l
!'j I
!;:l'i i
l i
i I
i t
t i
o E Ek 1.l.l...!.! ! 1.[ 4.l ! '
i.i l. l.....i l....
!';!!i l!
13 w
2 m4
!llii!
- ili 3
.1.
5 i
.s.i _l.i i.s.i ll'
!l, bl l
1 d 2 U
3 i
,1 i j
,r L", l 1
l.)
j
!!!;ii llll
~~
t I i
.j p e.g g,
- i!:;
u
- 1. n_..
t
.m
~l$lfNO 4 l lr If I
>lI ! l i l!'
A!*.!
i I
l 6
,..,iw_
_I
.l~~~~
i,!lll1 l ' i, !
- b_ l I
ll ll lil
? l!
l l
- ++"*
i
{l
.'I i
6
!1 l l j i
l i i ll FR l
.L,. 9.'s @. 8 '
Il!
i
}
' I 1 e
/m.
el+ + m +
f I "* ** M N i l;' g
, l l
..e i e l I r #
! I f I li l l "*, [ j t
i
.....h.
h 9 ]j ltil l'I,. l i 'i l lllIN:i.l 2I.!,?'f;Oni-ll.l t !. t
,.I
+
i i
e
-.h.l__.r!.I._..., _ _ _
I..I. -.% f _f _ _ a..l _1_
.m.f l. ;!
i I._.,.l-i
.....y f
h
_3
_3 i
f# I
. !i l
I' I
l
.l.......! !.,. -.!.,_f -..I f
f
~
l g.
l l
. z
?
.i...i +. m.,, =,_v. s _:.o ~.._ - w._+.,g.. w~,J~ec.a. w -\\-
ix y
2 lg
!-l l l
- f c
.. 7 3
j hg l
)I
!fIfl I
'E I
a t r
a-n-L
,.s au
&- + - -A
>-A A
P-5"3
-eb-+-
im-"+-
4 6-
%. - ' ~
h-A'<
aA'-
L D--
e, G=
.x.
- VyE Page 29 gE:
1 e
_o-d b
UCd e:S i
~
- x-i
$ b kh
<h
~l,
% i. :c ad' I
- =<
s l=-
~i lh hb
- : tW:h 4
_i
,g t
i l
I.
i
, ('
i
- E
'I k'
' t; I
l l
S
{
v m
.2 i
V j
u s I
5
.I t a I
l J
5
~
j i
a i
n l
,$ g [i Ii i
h 14.b 8,,
l l
e sr g!
.I 1"3 e
.e
-.7..
s IIl l
l l
lll l l iI f
\\
jgpd l l IIlllll I_IllllllllIILb3_
j g)!M,941 !
11 ll FF E i
t,$. 5 dd,dll II Il l
I Lha r
4 f f.,%; l l
l l
.f
$N I\\
hl j
i h
h 8
t 3
w
- .a -.
, n 211911 l
l l
l l
l
~
~ :
I,
! JI.fdd.d I I
I i
l Iii l Jss 1.fqqll 3
l l
l m e
~
k.$l
)
3, _ E 5 y.
i -el q *g I 1
i i
c, 2
a i
i 1 1 l fl I
- i. N iii I
l li'-
t j !i 2 ;-
-+-
8
- e i!
k fi l
l l } fI
~ -
- ~
~ => s :- d-4 5 c g
- u g c f u g j e
- e et T1 ~1
~
1 F
1 1
REACTOR POWER PERCENT APRIL 1988 UNIT 1 Pencaut tM N
M n
M AOMINISTRATIVE HCLC g,
40 M
M ts 0
- * * * * * * * *@+@@%$@@0@@ff+fffffff+
UNIT 2 Pencaxi iM M
M 10 M
10MINIOTRATIVE SJLD 40 M
M 10 0
% * * * * * * * *@%% S@@@$4@@ff@ffffffff UNIT 3 Penczxt tM M
M 70 M
10 MINI 3TRATIVE HOLD 40 M
N 10 0
%
- i " * * * * *@%% % % %' @ @ @ @ @ f f f f f f f f f f f
S 6
i MAIXTIA.. CE
~
~~
S C~MMARY I
L I
i i
pago 31 ELECTRICAL TECHNICAL SECTION MONTHLY REPORT APRIL, 1988 Unit Common Major Routine Activities --
CIRCUIT BREAKER REBUILDS:
AI60V 480/250V Total Number of Breakers To Be Rebuilt 303 493 Total Number of Breakers Rebuilt 9
17 Completed This Month 0
0 Reviewed several surveillance instructions and maintenance procedures for the month of April, 1988.
power Service Shop crews are onsite for the replacement of Unit 2 main generator T10 stator bar. The generator is disassembled. General Electric personnel will be on site May 3, 1988.
HFA r21ay database is one-third complete.
Forty eight technical reviews were done in April 1018.
Secondary containment was established to permit fuel handling activities Five out of tolerance investigations and dispositions were completed for measuring and testing equipment returned from the central labs af ter calibration.
A database file has been set up to include forty (40) sump pump level switches.
ELECTRICAL EQUIPMENT LIST:
515 drawings were received in April, 1988.
203 drawings were reviewed in Apell, 1,38.
4.669 drawings are in backlog.
FUSE CONTROL PROGRAM:
Drawing review continues, unit 2 is 95% complete and unit 0 is 30% complete.
Fuse input sheets are being put into EQIS.
All 500 are expected to be entered by May 4, 1988.
Information and most materials needed for operations to replace fuses was given to them in early April, 1988.
The fuse engraving report, revision "C" fuse relabeling effort is complete for unit 2.
Unit 1 and unit 3 were held up due to lack of craft support.
However, unit 1 is 90% complete. Unit 3 has not been started.
EBASCO's first calculation for fuse evaluations given to DNE on April 29, 1988. The Electrical Technical Section is scheduled to review the information of the first calculation from DNE on May 6, 1988.
Failure Investigation 88-3, 88-4 and 88-7 were completed.
The unit 3 KMG cot has been made functional. QMDS has been divided and responsibilities determined between Electrical Technical I&C and Mechanical.
Page 32 2
Electrical Technical Section Monthly Report 35GT cables were meggered for damage in conduit duct.
No cables displayed any damage.
One cable was not tested and the Electrical Technical Section has contacted Design to determine if the test is still required.
No response has been received from Design.
Revisions for EMI-53 and EMI-58.3 have been completed.
Preventive maintenance for the replacement of coils or relays for CR120A relays have been completed for safety related relays.
A technical review has been done for SI-4.9.A.3.a (Unit 1 and 2) and ECI-0-000-RLY003.
DNE work to return charger SD-B to service is complete. Waiting for receipt of materials.
Repairs complete on D/G 3C Charger "A".
Charger is back in service.
Restart testing and corrective maintenance complete on charger SB sparo.
Discharge testing of D/G 3D battery for required surveil. lance and restart testlng was completed satisfactorily. The battery is at 91.6% capacity.
ECN E-2-P7010, Workplan 2149-88 was written and revised to install / test thermal overloads on various unit 2 breaker compartments.
34 unit 2 flow control valves are affected by this workplan.
DCN H00110A WP 2180-88.
This workplan was written to set the open and closed thrust valves on 2-FCV 73-81 and provide margins for setting limit switch #4 to prevent inadvertent backseating.
DCN WO144A, WP 2181-88 was written to set the open/ closed thrust valves on the following unit 2 valves:
23-FCV 71-34, 2-FCV 68-01, 03, 77, 19 and also provide margins for setting limit switen LS-4 to prevent inadvertent backseating.
WP 2231-84 was revised during April 1988 to add the steps necessary to install a new termination box on 2-FCV 74-66.
WP 2227-84 was revised during April 1988 to add the steps necessary to install new breakers and thermal overload elements on 2-FCV 74-60, 61 and to add steps necessary to install a new termination box on 2-FCV 74-5~.
Page 33 3
Electrical Technical Section Monthly Report 011 in main tank of unit station service transformer 2A was treated with the Purivac unit during April 1988 because of hydrogen generation determined from a gas-in-oil lab analysis.
The interruptor head of 5214 was opened and inspected for internal damage caused by the crane accident.
Head is now disassembled and waiting on parts.
Oil treatment continued during April 1988 on 500KV main transformers 2A and 28.
The oil was salvaged by circulating it throuyh the Purivac.
Unit 2 main 500KV transformer bank was returned to service on the week-end of April 9 1988.
A minor leak was repaired on 500KV main 25 at the end of April 1988.
A week-end outage was executed on main buss 1 (Buss 1. Section 1) so as to test the main buss potential transformers.
Minor maintenance was also performed on the junction box at the potential transformers. A burned potential transformer pressure relay caused an unwanted extension of the buss 1 outage. All work and testing was complete in April 1988.
Did same to buss 2 potential transformer.
All three 500KV shunt reactors were flushed and had oil purified by the Purivac unit during Apri. 188.
VALVE CROUP:
Field Work Completed:
Up 12 to 63 total.
Final Inspections:
Up 19 to 43 total.
NOVAT's Test Completet Up 10 to 23 total.
Processed approximately 15 drawing discrepancies in support of fleid work.
Processed ITC's on EMI 18, 18.1 and 105.
Closed CAQR BFP880308 written against 3-FCV-67-26 and provided documentation for closure on three additional CAQR's issued by the CEC group.
Shipped seven motors to the Power Service Shop for repair and restocking in Power Stores.
ELECTRICAL TECHNICAL SECTION Pago.34 MONTHLY REPORT i
APRIL 1988 i
1 I.
WORK TIME SCHEDULE i
Received /
Assinned Completed 9g33 l
Red Folders 4
3 12 Orange Folders 2
2 10 t
Yellow Folders 0
1 1
Blue Folders 4
6 4
l Purple Folders 1
0 3
t Active Engineering Assignments 6
1 20 Engineering Backlog 5
5 65 New Engineering Assignments 0
0 0
i Completed Engineering Assignments 0~
0 0
i II.
C000tlTMENT TRACKING i
Licensing Issues (NCO & SLT)
NCO O
2 18 SLT 2
1 4
l PORS Tracking Items (BFC) 0 0
3 CAQRs 1
4 8
i Average Age of CAQRs Five Months i
Employee Concerns 0
0 1
Safety issues List 0
0 0
III.
STAFFING LEVELS AND TRAIBING Personnel Apyroved Headeounts current Headeounts ASP 36 31 ATL 4
4 HTL 0
0 Contractors 5
4
{
i i
TOTAL 45 39 l
IV.
OVERTIME 13.6%
j V.
PROCEDURES l
i 16 procedures PORC approved 3
10 procedures sent to Word Processing VI.
226 Outstanding Status "H" hrs 0 OUTSTANDIkG STATUS "Q" MRs i
i t
i
A ELECTRICAL *S REQUIRED U-2 START-UP SURVEILLANCE
!NSTRUCTIONS STARTING SEPT 1,1987 70 60 Ih
.X*
50
- E I
40-g y/
30-1
=[fy o
10 M =7 I / 5 ' F-1; [
20-
- V x
I I
l SEPT OCT NbV DEC JHN FEB MHR HPH MAY JUN JUL
-*- B ESTIMATED
- - B DRAFTED
-"- BTEC REVD
-o-B INDP REVD
-^- B WALKDWN
-^- B APPROVED
-*- B SUBMITTED 3
ELECTRICAL'S REQUIRED U-2 START-UP MAINTENANCE INSTRUCTIONS 90 I
80 f*/
70 60 2
h
/-l&pv' c
20 gE I
~
o-
'g
'gIY/I 10 o I
0n SEPT OCT NOU DEC JflN FEB Mflfi
-flPfl MilY JUN JUL flUG TIME BEGINS SEPT 1,1987
-*- A ESTIMATED
-o-A DRAFTED
-"- A TEC. REVD.
- - A WALKDWN
+ A SUBMITTED
+ A APPROVED
-- g
_m V
a Page 37 I&C TECHNICAL APRIL 1988 1.
Work Item Schedule Received /
Completed Open Assigned Red Folders 1
1 1
Orange Folders 0
1 7
Yellow Folders 0
0 0
1 Blue Folders 0
0 3
Purple Folders 2
2 1
Total Assignments Active Engineering Assignments 7
14 28 Engineering Backlog 11 MRs (Status "H" and "Q")
70H 70 II.
Commitment Tracking Licensing Issues (NCO & SLT)
NCO 2
2 12 SLT 0
0 3
PORS Tracking Items (BFC) 0 0
2 CAQR (Onsite) 0 2
E CAQR (Off-site) 0 0
0 Average Age of CAQRs 4.5 months Employee Concerns 0
2 0
Safety Issues List 0
0 0
III.
Staffing Lo.iuls and Training Approved Headcounts Current Headcounts Personnel ASP 17 13 ATL 4
3 HTL 0
0 Contractors 4
TOTAL 21 20 IV.
Overtime 8.70%
V.
Procedures 40 procedures were sent to Word Processing
Page 38 I&C TECHNICAL APRIL 1988 VI.
Maintenance Improvement Plan Items ITEM l
Description l
% Complete l
l III.H.1 l
M&TE l
60%
IV.B.3 l
M&TE l
60%
IV.C.1 l
Maint. Instructions l
- 1) 100% 2) 90% 3) 33%
IV.C.2 l
Maint. Instructions l
0%
IV.C.3 l
Maint. Instructions l
34%
V.B.2 l
Spares Parts l
0%
V.B.3 l
Spares Parts l
0%
-VI.C.2 l
PM l
10%
VIII.B.10 l
Technical Issues l
52%
VIII.D.
l Employee Concerns l
33%
SUMMJLrty The major activities of the
'h involved. preparation of instructions to support the retest schedule and the War Rc. a SI schedule.
Scaling and Setpoint Documents to support these instructions are also being issued.
Page 39 MECHANICAL TECHNICAL SECTION HONTHLY REPORT COMMON UNIT ONLY (UNIT 0)
APRIL 1988 Common No major noncoutine activities.
1.
Closed the following commitments.
a.
INPO SOER 83-009 - Report on motor-operated valvo performance b.
INPO OER 88-2427 - Generator shaft jacking device failure c.
NCO 850171002 - HCV 71-32 and HCV 73-24 d.
BFC 861084001 - Inspection of springs of.all Atwood & Morrill MSIVs e.
SLT 850925011 - Revised pinion gear in Limitorque operator f.
SLT 861072002 - CST tunnel pipe hangers g.
R35 880404 334 - MS-CEB-008 - Miscellaneous structural steel supports h.
G-29(RO) - PS 3.M.3.1 Add. 4(R3) 1.
G-29(RO) - PS 3.M.3.1 Add. 5(RI)
J.
G-29(RO) - PS 1.M.1.2 Add. 3(RS) k.
G-29(RO) - PS 1.M.l.2 Add. 1(RS) 1.
G-29(RO) - DWG-PS 1.M.1.2-15 Sheet 6(R3) m.
G-29(RO) - DWP TB 103.103-2(RO) n.
G-29(RO) - DWP-SM-U-2(R6) o.
G-29(RO) - DWP-GT11-B-1(Rl) p.
G-66(R2) - Inspection and testing of maxiholt undercut anchors q.
NQAM,II,5.3A(RS) - Training and cortification program for QC inspectors r.
SRN-G-3 G-spec. for installing electrical conduit systems SRN-G-39 Cleaning during f abrication of fluid handling components s.
revision t.
SRN-G-4 Installing insulated cahics rated up to 15,000 volts u.
Tech Spec - Amendment 138, 134, and 109 v.
TS-228 - Tech. Spec. review
Page 40 MRCHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)
APRTL 1988 2.
The following instructions were approved, revised, or cancelled.
a.
0-SI-4.3.B.2 - Control Rod Drive Housing Support b.
0-SI-4.5.B.2A - Residual Heat Removal System Drywell Spray Header Air Test c.
0-SI-4.5.B.2B - Torus Nozzle Test d.
0-SI-4.C.H.1 - Visual Examination of Hydraulic and Mechanical Snubbers c.
0-SI-4.7.A.4.B - Crywell Pressure Suppression Chamber Vacuum Breaker Inspection f.
BF-3.10 - Cleanliness of Fluid Systems g.
MCI-0-001-VLV013 - Reactor Feedwater Pump Turbine Low-Prest.ure Control Valves FCV-1-129A, FCV-1-13 7A, and FCV-1-140A ; Di sasnembly, Tnspection, Rework, and Reassembly h.
MCI-0-003-PMP003 - Reactor Fecdwater Pump Auxiliary oil Pump; Disassembly Tnspection, Rework, and Reassembly i.
MCI-0-003-PMP005 - Reactor Feodwater Pump Main Oil Pump and Covernor; Disassembly, Inspection, Rework, and Rouscembly J.
MCI-0-018-PHP004 - Fuel Oil Transfer Pump for Standby Dicsel Generator; Disascembly, Inspection, Rework, and Reassembly k.
MCI-0-026-PHP001 - Motor Driven Fire Pump; Disassembly Inspection.
Rework, and Reassembly 1.
MCI-0-070-PMP001 - Reactor Building Closed Cooling Water Pump; Disassembly, Inspection, Rework, and Reassembly MCI-0-071-VLV002 - RCIC Turbine Covernor Valve FCV-11-10; Disassembly, m.
Inspection, Rework, and Reassembly MCI-0-071-VLV003 - Reactor Core Isolation Cooling (RCIC) Turbino Trip n.
Throttle Valve FCV-71-9; Disascembly, Inspection, Rework, and Reassembly MCI-0-075-PHP001 - Core Spray Pump, Bingham Centrifugal 12x16x14-1/2, o.
ono-Stage; Disausembly, Inspection, Rework, and Reassembly p.
MCI-0-0/5-VLV004 - Core Spray Testable Check Valves FCV-75 26 and FCV-75-54; Disassembly, Inspection, Rework, and Reuscombly
)
Page 41 MECHANICAL TECHNICAL SECTION MONTliLY REPORT COMMON UNIT ONLY (UNIT 0)
APRIL 1988 q.
MCI-0-082-CLR001 - Standby Diesel Enginc Water Coolers; Disassembly, Inspection, Rework, and Reassembly MCI-0-082-CLR002 - Standby Diesel Engine Lube Oil Cooler; Disassembly, e.
Inspection, Rework, and Reassembly s.
MCI-0-082-CLR003 - Standby Diesel Engine Aftercoolor: Disassembly.
Inspection, Rework, and Reassembly t.
MCI-0-082-ENG005 - Standby Diesel Engine Fuel Injector; Disassembly.
Inspection Rework, and Reassembly u.
MCI-0-082-ENG006 - Standby Diesel Engine Fuel Injector Test Stand Inspections mci-0-082-ENG007 - Standby Diesel Engine Crank Shaft; Disassembly.
v.
Inspection, Rework, and Reassembly w.
MCI-0-082-ENG009 - Standby Diesel Engine Cylindce Head and Valve Assembly; Disassembly, Inspection, Rework, and Reassembly MC'I-0-082-ENG012 - Standby Diesel Engine Camshaft Drivo Housing; x.
Disassembly, Inspection, Rework, and Reaccembly y.
MC1-0-082-ENG013 - Standby Diesel Engine Catshaft Gear Train; Disassembly Inspection, Rework, and Reassembly z.
MCI-0-082-ENG014 - Standby Diesel Engine Generator Removal and Installation MCI-0-082-ENG015 - Standby Diesel Engine Ring Gear and Coupling Disc; aa.
Disassembly, Inspectioth Rcwork, and Reassembly bb.
MCI-0-082-FLT001 - Standby Diesel Engine Lube Oil Strainer, Disassembly, Inspection, Rework, and Reassembly MCI-0-082-FLT002 - Standby Diesel Engine Lube Oil Filter; Disassembly, ec.
Inspection, Rework, and Reassembly dd.
MCI-0-082-FLT003 - Standby Diosol Engine Auxiliary Turbo Lubo 011 Filter; Disassembly, Inspection, Rework, and Reassembly MCI-0-082-FLT004 - Standby Diesel Engine Mounted Turbo Oil Filter; ee.
Disacnembly Inspection, Rcwork, and Reassembly ff.
MC1-0-082-FLT005 - Standby Diesol Engino Fuel Transfer Filters; Disassembly, Inspection, Rowork, and Reassembly e
e. -.. -
Pagg 42 MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)
APRIL 1988 gg.
MCI-3-082-FLT006 - Standby Diesel Engine Fuel Filters; Disassembly, Inspection, Rework, and Reassembly hh, MCI-0-082-FLT007 - Standby Diesel Engine Fuel Oil Filter; Disassembly.
Inspection, Rework, and Reassembly 11.
MCI-0-082-GOV 001 - Diesel Engine Governor, Woodward Model ECB-10 Removal and Installation jj.
MCI-0-082-GOV 002 - Standby Diesel Engine Governor Drive Assembly; Disassembly, Inspection, Rework, and Reassembly kk.
MCI-0-082-PHP003 - Standby Diesel Engine Water Pump; Disassembly, Inspection, Rework, and Reassembly 11.
MCI-0-082-PMP005 - Standby Diesel Engine Lube Oil Circulating Pump; Disassembly. Inspection, Rework, and Reassembly mm.
MCI-0-082-TCH001 - Standby Diesel Engine Turbo-Charger, Removal and Installation MCI-0-082-VLV002 - Standby Diesel Engine Thermostatic Valve; nn.
Disassembly, Inspection, Rowork, and Reassembly oo.
MMI Removal, Replacement, and Inspection of Permali Neutron Shielding at Sacrificial pp.
MMI Scheduled Maintenance Standby Diesel Cennrator qq.
MMI Inspection of Secondary Containment Rollof Panols MMI Ifigh-Pressure Coolant Injection (HPCI) System Maintenanco re.
ss.
MMI Jet Pump Beam and/or Pump Removal and Replacement tt.
MMI Liquid Penetrant Examination of Piping and Piping Components Which Were Exposed to Residue from Plant Firo - Unita 1 and 2 MMI-105 - Leak Testing of the Drywell Torus Delta P Air System uu.
vv.
MMI-109 - Isolation and Cleaning of the Raw Water Head Tanks ww.
MMI-147 - Surface Indication Removal - Units 1, 2, and 3 MMI-153 - Temporary Ventilation for the Electrical Equipment Rooms xx.
yy.
MMI-154 - Repairs using Belzona Molecular and Similar Metals
Page 43 MF.CMANICAL TECliNICAL SECTION MONTliLY REPORT COMMON UNIT ONLY (UNIT 0)
APRIL 1988 MMI-156 - Inspection and Maintenance of Stack Gas Sample Pumps zz.
aaa.
MMI-159 - Sampling Inspection Program for Verifying Correct Installation of Concrete Expansion Shell Anchors bbb.
MMI-170 - Fuel Pool Cooling (FPC) Pump Maintenance - Units 1, 2, and 3 cec. 11MI-187 - Installation and Removal of BWR-6 Control Rod Drives ddd. MMI-190 - Control Rod Uncoupling GE Tool 3.
The following CAQRs (Conditions Adverse to Quality Reporte) were closed, a.
BFQ 87-1160 - C-39 Flushing and Cleaning Celteria 4.
The Mechanical Technical Section devoted 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of training during the month of Apell.
i l
l l
l i
Page 44 MODIFICATIONS HONTHLY REPORT APRIL 1988 MAJOR WORK PERFORMED ECN NARRATIVE Appendix R P0808 Continued conduit and cable work on control power circuits (workplan 2048-87, 2091-87, and 2047-87).
P0879 Continued work on fire door upgrade (work plans 2068-87 and 2212-87).
P0883 Field completed changeout of fuses and fuse blocks (workplan 2111-87, 2112-87, and 2089-87).
P0885 Continued conduit and support work on RB fire detectors (workplans 2012-87, 2013-87, 2014-87, and 2015-87).
P0887 Started work on conduit reroute (workplan 2182-86).
P0889 Continued reroute of conduit for separation (workplano 2053-87, 2054-87, 2221-87, 2050-87, 2052-87, and 2044-87)
P0913 Field completed unit 1, 250V DC, trip circuit fuse protection modifications (workplans 1022-86 and 1023-86)
P0914 Continued craft work on fuse and fuse block replacement (workplans 3027-86 and 3028-86).
Field completed workplan 3026-86.
Environmental Qualification P3145 Continued electrical conduit scaling activities (workplans 2074-85, 2070-85, and 2078-85).
P3148 Started removal of interim SDBR HVAC piping and supports (workplan 2110-84).
P3205 Continued small piping and support work on H02 2 analyzer lines (workplans 2158-87, 2159-87, 2199-87, 2200-87, 2160-87, 2161-87, 21F".-87, 2201-87, 2202-87, and 2163-87).
Page 45 MAJOR WORK PERFORMED ECN NARRATIVE Environmental Qualification P7032 Continued cable replacement in steem tunnel (Continued)
(workplan 2069-88).
P7039 Started preliminary work on shutdown transformer 2A replacement (workplan 2076-88, 2077-88, and 2078-88).
Field completed workplans 2073-88 and 2075-88.
S31smic Issues B0005A Started replacement of EECW sectionalizing valves (workplan 0027-88).
B0019A Started field work on control room panel anchoring (workplan 1039-87).
B0033 Field completed SBGT support rework (workplan 3003-88).
P0289 Started work on EECW dresser coupling replacement (workplan 2137-88).
P0361 SMMI rework of torus attached piping and drain supports continued. Workplan 2158-84 was field completed.
P0370 Continued structural work on seismic qualification and designation of block walls (workplans 1030-87, 2092-87, 3024-87, and 3036-87).
P0859 Continued work on catwalks R9 and 13 (workplans 2066-87 and 2209-86, and 2143-87).
P0944 continued work on seismic qualification of U2, RB conduit (workplan 3040-87).
P0945 Restarted work on unit i seismic conduit qualification (workplan 1037-87).
P0946 Started craft work on seismic qualification of unit 3 RB conduit (workplan 3038-87).
P0998 Drywell catwalk upper elevation work reached 99% complete. (workplans 2146-87, 2147-87, and 2148-87).
Field completed workplan 2160-87).
P2036 Continued additional 79-14 support fixes to CRD return piping (workplan 1036-87).
F2042 Continued RilR support rework (workplan 1035-87).
l i
P2044 Completed craft work on unit 1 RB drain
$0N3N7$. pump 79-14 modifications (workplan E
Paga 46 MAJOR WORK PERFORMED ECN NARRATIVE Scismic Issues (Continued)
P2088 Continued field work on additional 79-14 fixes to fuel pool cooling system (workplan 2274-87).
P2090 Started additional 79-14 fixes on radwaste sump pump discharge system (workplan 2273-87).
P2154 Started field work on RHRSW and EECW trains B and D outage fixes (workplans 0028-88 and 0023-88).
P7018 Continued work on drywell HVAC seismic qualification (workplans 2282-87, 2281-87, 2280-87, 2279-87, and 2278-87).
P7029 Continued repair of lower drywell structural steel (workplan 2234-87).
P7083 continued craft work on common area tubing seismic qualification (workplans 0007-88,0008-88, 0009-88, and 0010-88).
P7085 Continued craft work on unit 2 tubing seismic qualification (workplans 2058-88, 2059-88 and 2060-88).
P7115 Started craaft work on unit common tubing seismic qualification (workplan 0025-88).
TMI Mods P0354 Continued electrical and sample line work on stack radiation monitor (workplans 2142-85, 2156-85, and 2086-85).
P5451 Started work on stack radiation monitor pressure and temperature compensation mod (workplan 0028-87).
Other M0075A Continued tube removal on unit 2 condenser--removed 39,000 of 54,000 tubes.
P0085 Continued reroute of conduit on drywell pressure and temperature upgrado (workplan 2192-87).
P0286 Continued work on yard security lighting (workplan 0022-86).
P0384 Continued tubing and electrical work on containment purge valvec (workplan 2049-86).
P0392 Continued SHMI rework of scram diccharge volume supports.
PO422 Continued work on RPS clacc 1E pentection (workplans 2144-84 and 2143-84)
P0547 Continued rep check valvos (lacement of rceirculation system workplan 2050-85).
Page 47 MAJOR WORK PERFORMED.
ECN NARRATIVE Other (Continued)
P0569 Continued support work on RPV vent line r
(workplans 2051-84 and 2204-84).
P0720 Continued work of jet pump instrumentation lines (workplan 2109-85).
P0956 Continued installation of duct and duct supports for new shutdown board room HVAC (workplans 2228-87, 2229-87, 2256-87, 2257-87, 2258-87, 2253-87, 2254-87, 2262-87, 2263-87, and 2249-87).
20968 Field completed last workplan to allow LLRT of FCV-84-8A, B, and C (workplan 2128-87).
P0984 continued work on upgrade of site microwave telemetry system (workplans 0036-87 and 0037-87).
P0990 Started work on unit 1 turbine building crane safety improvements (workplan 1031-87)..
P1001 RHR, RWCU, and Recirculation System support work continued (workplans 2283-87, 2284-87, 2285-87, 2286-87, 2009-88, and 2008-88).
Field completed wt kplan 2018-88.
PS269 Installation of supports for uninterruptable demineralized water connection for torus water level transmitters continued (workplans 2292-87, 2065-86, and 2293-87).
P5291 Continued reactor water icvel instrument sense line modificat ion (workplans 2153-87, 2154-87, and 2232-86).
P5480 Installation of vessel drain supports continued (workplan 2218-87).
P7002 Continued field work on hydrogen water chemistry modifications (workplans 2088-84, 2087-88, and 2092-88).
P7006 Started work on ATU inverter replacement (workplans 2066-88 and 2081-88).
P7037 Began craft work on installation of quick disconnect couplings on testabic check valves (workplans 2107-88, 2105-88, 2109-88, and 2110-88).
P7045 Continued valve and support modifications for ATWS/ARI (workplan 2115-88).
Page 48 MAJOR WORK PERFORMED ECN NARRATIVE Other-(Continued)
P7048 Started craft work on reactor water level instrumentation sense line modification (workplan 2003-88, 2085-88, and 2084-88).
l Drywell Fire Recovery B00061A Continued replacement of damaged system 70 conduit and cable (workplan 2112-88).
B00062A Started replacement of damaged system 68 conduit and cable (workplans 2135-88 and 2139-88).
M00067A Started replacement of damaged system 92 conduit and cable (workplan 2117-88).
P3163 continued drywell cable replacement (workplan 2237-87).
P3180 Continued electrical work associated with containment penetration replacement (work-plans 2036-87, 2105-87, 2022-87, and 2083-88).
Field completed workplan 2083-88.
,er.-
Unit 1 Maintentnce Monthly Report April 1988 Major Activities:
1)
Reassembled valves FCV-23-46 and 52 and performed EMI-18 on each.
2)
Installed LPCI M-G set 1EA and 1EN.
Lack cycling valve FCV-74-73 to complete testing.
3)
Replaced Turbine Building Exhaust Fan IB motor.
4)
Coupled IB and ID RHR pumps to motor.
5)
Installed new turbo-charger and realigned diesel engine and generator on IB D/G.
6)
Completed testing of : ables to SBGT Trains A, B, and C.
7)
Worked various MRs in support of EECW south header outage.
8)
Removed motor from 1A CRD pump and installed on IB CRD pump.
9)
Walked down SBGT, D/G, Off-gas, stack and all unit 1 buildings to verify deficiency tags.
- 10) Closed Green Folder NCO 860326179 (R35880412618).
- 11) Worked various U2 Restart MRs.
1097B
8 4
OTHER REPORTS i
I l
l
Page 50 CHEMISTRY
SUMMARY
APRIL 1988 Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month.
Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.
This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.
Unit 2 The conductivity of the reactor coolant remained within technical specification and fuel waterer.ty limits during the month.
Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.
This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.
Unit 3 The conductivity of the reactor coolant remained within technical l
specification and fuel warranty limits during the month.
Chloride l
l concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.
This calendar year, l
the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.
l l
Page 51 PRIHARY COOLANT CHEHISTRY APRIL 1988 Parameter Unit 1 Unit 2 Unit 3 1.
Gross Radioactivity a.
Crud (filter) (mci /ml)
High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A b.
Filtrate (mci /ml)
High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A I
2.
Hilipore Iron (Fe. ppb)
High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 3.
Tritium (mei/mt)
High 5.593E-5 5.619E-5 1.385C-4 Low 5.186E-5.
4.677E-5 1.195E-4 Average 5.392E-5 5.157E-5 1.33E-4 4.
Iodine-131 (mci /ml)
High
<2.89E-6
<1.24E-6
<1.49E-6 Low
<7.75E-7
<1.03E-6
<2.40E-7 Average
<1.49E-6
<1.14E-6
<6.30E-7 5.
Iodine-131: Iodine-133 Ratio g
High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A p
Pags 52 PRIMARY COOLANT CHEMISTRY (Continued)
APRIL 1988 Parameter Unit 1 Unit 2 Unit 3 6.
Chloride (pob)
High
<20
<20
<20 Low
, <10
<10
<10 Average
<20
<20
<20 0
7.
pH925 C High 6.4 6.2 6.2 Low 5.7 5.8 5.8 Average 6.0 6.0 6.0 0
8.
Conductivity (mmho/cm025 C)
High 0.23 0.79 0.30 Low 0.14 0.51 0.11 Average 0.18 0.61 0.20
i Page 53 CHEMISTRY SUKKARY (Continued)
APRIL 1988 Environmental Technical Specification Requirements The ambient upstream river temperatures (24-hr. avs max) averaged 64.5'F ranging from 67.8*F on April 24 to 61.3*F on April 01.
The downstream temperature varied from 67.9*F on April 24 to 60.9'F on April 01.
The greatest temperature change was 1.6*F on April 6.
The sewage lagoon (DSN 111) remained locked out for the entire month and there was no discharge.
The sedimentation pond (DSN 102) remained out of service for the entire month. Modification of the pond has been initiated to include a synthetic liner.
An unpermitted discharge of sodium nitrite from a leak in the unit 1 Control Bay chillers was identified on April 6.
The sodium nitrite was discharged to the Tennessee River via unit 1 and 2 office building drain (DSN 110).
A total of 25 pounds of sodium nitrite was added to the chillers from March 31 to April 4.
The plant did not experience any other compliance problems during the month.
Pags 54 AIRBORNE RELEASES (1)
APRIL 1988 SUMMATION OF ALL RELEASES UNIT THIS MONTH A.
FISSION AND ACTIVATION GASES 1.
TOTAL RELEASE CI
< 8.63E 01 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC
< 3.57E 01 3.
PERCENT OF TECH. SPEC. LIMIT (0.05 CI/SEC) 0.00E-01 B.
10 DINES 1.
TOTAL IODINE - 131 CI
< 2.39E-05 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC
< 9.90E-06 3.
PERCENT.10F TECH. SPEC. LIMIT (0.4 UCI/SEC) 0.00E-01 C.
PARTICULATES 1.
PARTICULATES WITH HALF-LIFES > OR = TO 8 DAYS CI
< 1.13E-04 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC
< 4.67E-05 3.
PERCENT OF TECH. SPEC. LIMIT (0.4 UCI/SEC) 0.00E-01 4.
GROSS ALPHA RADI0 ACTIVITY CI
< 6.14E-07 D.
TRITIUM 1.
TOTAL RELEASE CI 6.79E-02 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2.81E-02 3.
PERCENT OF TECHNICAL SPECIFICATION LIMIT 5.87E-02 4.
GROUND LEVEL RELEASE CI 6.77E-02 5.
ELEVATED RELEASE CI 1.95E-04 (1)
REPORTING PERIOD 20 DAYS
Page 55 AIRBORNE RELEASES (CONTINUED)
APRIL 1988 7
0 E_EVATED RELEASES A.
FISSION OASES UNIT THIS MONTH AR-8 C
<6 68E-KR-85 CI
< 2.8'/E 01 KR-87 CI
< 2.84E-01 l
KR-88 CI
< 2.53E-01
)
XE-133 CI
< 1.39E-01 XE-135M CI
< 1.30E-01 XE-135 CI
< 7.36E-02 XE-138 CI
< 7.02E-01 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 3.04E 01 B.
10 DINES I-131 CI
< 1.61E-06 I-133 CI
< 3.08E-05 I-135 CI
< 3.26E-02 TOTAL FOR PERIOD CI
< 3.26E-02
/
Page 56 AIRBORNE RELEASES (CONTINUED)
APRIL 1988 ELEVATED RELEACES C.
PARTICULATES UNIT THIS MONTH SR-89 CI
< 4.04E-07 SR-90 CI
< 1.33E-07 CS-134 CI
< 1.38E-06 CS-137 CI
< 3.28E-06 BA-140 CI
< 7.49E-06 LA-140 CI
< 6.45E-11 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 1.27E-05 D.
TRITIUM CI 1.95E-04
Page 57 AIRBORNE RELEASES (CONTINUED)
APRIL 1988 GROUND RELEASES A.
FISSION GASES UNIT THIS MONTH KR-85H CI
< 2.21E-01 KR-85 CI
< 5.12E 01 KR-87 CI
< 6.49E-01 KR-88 CI
< 5.99E-01 XE-133 CI
< 2.10E-01 XE-135N CI
< 8.58E-01 XE-135 CI
< 7.47E-02 XE-138 CI
< 2.14E 00 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 5.60E 01 B.
10 DINES I-131 CI
< 2.23E-05 I-133 CI
< 2.04E-04 1-135 CI
< 1.85E-01 TOTAL FOR PERIOD CI
< 1.85E-01
Page 58 AIRBORNE RELEASES (CONTINUED)
APRIL 1988 GROUND RELEASES C.
PARTICULATES UNIT THIS MONTH SR-89 CI
< 3.03E-06 SR-90 CI
< 1.10E-06 CS-134 CI
< 2.04E-05 CS-137 CI
< 2.22E-05 i
BA-140 CI
< 4.47E-05 LA-140 CI
< 8.81E-06 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 1.00E-04 D e[f TRITIUM CI 6.77E-02 l
l l
t 5
w
Pags 59-BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES APRIL 1988 RADI0 ACTIVE LIQUID EFFLUENTS 1.
GROSS RADI0 ACTIVITY UNITS a)
TOTAL RELEASE CURIES 3.19E-02 b)
AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.90E-09 c)
PERCENT OF APPLICABLE LIMIT ( 1E-7 UCI/ML )
1.90E 00 l
2.
TRITIUM l
I a)
TOTAL RELEASE CURIES 1.39E-01 i
b)
AVERAVE DILUTED CONCENTRATIUN RELEASED UCI/ML 8.24E-09 c)
PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) 2.75E-04
(
(1) l 3.
DISSOLVED NOBLE GASES l
(
l a)
TOTAL RELEASE CURIES
< 8.35E-04 b)
AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML
< 4.96E-11 c)
PERCENT OF APPLICABLE LIMIT (2E-04 UCI/HL)
< 2.48E-05 4.
OROSS ALPHA RADIDACTIVIT(
a)
TOTAL RELEASE CURIES 1.53E-05 b)
AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 8.94E-13 5.
VOLUME OF LIGUID WASTE TO DISCHARGE CANAL LITERS 3.92E 06 6.
VOLUME OF DILUTION WATER LITERS 1.6SE 10 (1)
INCLUDES XE-133, XE-135, AND OTHERS
Page 60 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES APRIL 1988 ISOTOPE 3 RELEASED UNITS CI CR-51
< 2.76E-03 MN-54
< 2.93E-04 CO-58
< 2.67E-04 FE-59
< 5.58E-04 CD-60 3.30E-03 ZN-65 1.24E-03 ND-95 2.37E-04 ZR-95 4.31E-04 MOTC-99M i 2.36E-04 I-131
( 3.61E-04 XE-133
< 6.48E-04 C3-l'd4 5.57E-03 XE-135
( 1,87E-04 CS-137 2.18E-02 BA-140
< 1.33E-03 LA-140
< 1.09E-04 CE-141
< 4.26E-04 SR-89 c 1.46E-04 SR-90
- 7.85E-05 FE-55 1.33E-03
Page 61 BROWHS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES APRIL 1988 OTHERS UNITS j
CI SB-125 2.35E-05
\\
\\
d a
f e
i e, s s
=
G e
(A a
BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES APRIL 198P
)
LAUNDRY DRAIN VOLUME RELEASED:
0.0 G ALL 0tlS FLOOR DRAIN VOLUME RELEASED:
856059,4 GALLONS WASTE SAMPLE TANK VOLUME RELEASEP:
17858V.2 GALLONS
}
DISTILLAIE TAilK VOLUME RELEASED:
0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLUME RELEASO:
0.0 UALLONS TOTAL VOLUME RELEASED TO THE RIVER:
1034643.6 GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR MONTH:
4.03E-09 UCI/ML A/D LONGEST RELEASE TIME FOR HONTH:
455 MIrlUTES SHORTEST RELEASE IIME FUR MONTH:
20 MINUTES TOTAL TIME OF RELEASF.S FOR MONTH:
11120 MINUTES AVERAGE TIME FOR BATCH RELEASES:
301 tlINU T E S NUMBER HF BATCHES RELEASED:
37 i4 UMBER OF ADMINISIRATIVE LIMIT VI1LATIONS:
0 NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS:
O P
4 Page 63 RESIN USACE REPORT APRIL 1988 RESIN CONSUMED (CU.FT.)
'l
% of Total ggg'h ))OWDEX ECODEX ECOSORB EPIFLOC Total Radweste l
Floor Drain Filter 34.1 0
80 0
5 33 118 Waste Domineralizer 0
0 0
0 0
0 0
Waste Filter 56.0 0
169 0'i, 21 4
194 Fuel Pool Domins 3.5 0
12 0
0 0
12 Reactor Water Cleanup s,
Unit 1 0
0 0
0 0
0 0
Unit 2 0.6 0
2 0
0 0
2.0 Unit 3 0
0 0
C 0
0 0
cond. Domins Unit 1 0
0 0
0 0
0 0
Unit 2 5.8 0
20 0
0 0
20 Unit 3 0
0 0
0 0
0 0
Totals 100 0
283
_0 26 37 346 4
i h
J s
f 4
Paga 64 FUEL CLADDING INTEGRITY PARAMETERS APRIL 1988 Unit 1 Reactor Water lodines (ucl/sec.)
Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharte of SJAE (uci/sec)
- Date Flow MW1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage r
Unit 2 Reactor Water Iodines (uci/sec.)
Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharte of SJAE (uci/sec)
}
Date Flow MWt X.e-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage i
Unit 3 Reactor Water Iodines (uct/sec.)
Date I-131 I-132 T-133 I-134 I-135 Unit in Outage Fission Gases at Discharte of SJAE (uci/sec) i Date Flow MWt Xe-138 Kr-87 Kr-6)
Kr-85m Xe-135 Xe-133 Unit in Outage i
i e
t
MASTE TREATHENT 'SYSTEN Tifl006tFUTS APRIL 1988 m.~
FLOOR FLOOR FLOOR DRAIN DRAIll DRAIN a 2.n+E GE: 8.5CE+i5 COLLECTOR FILTER
]
SAMPLE Gn: s.5sE+05 R
TANK I
TANK (a CtFT: 11a.00 j
Gn-e.56E+05 GPO: 0.ME+M j f 1 I LAUNDRY GAL: 0.00E+00 GPit 0.00E+00 DRAIN
,g;,,,,,,,,E CANAL TANK ePo: 3.45E+70
, 3,yg, GE: 1.03E+06 g,y,g ECYCLfIl WATER GPD: 5.82E+03 GAL 1.75E+05 1 I j
.. _ _ _ (I3
_m I
WASTE WASTE i
i WASTE
'I WASTE GPD: 5.95E+03 COLLECTOR r
SAMPLE O
~
i l
FILTER IDEMINERALIZER GE: 1.79E M5 TANK j
TANK i
1 l
I
't j
(1) CtFT: 194.00 y D) CtFT:
0.00
)
GR: 1.10E+06 y
I (1) CUR POWDEX 169.00.CtFT ESIN s FIKR MIXTLE 4.00 QFT ECOSm8: 21.00 CONDENSATE g
2.49E44 a nFT m e.a. Curt msis s FIstn uixTtsF: 33.00.CUFT ECOSUREt 5.00 GE: 7.UE+05 STORAGE 8
(3) SEAD KSIN j
TANK
Pago 66 TESTING
SUMMARY
APRIL 1988 Survelliance Testina Unit 0 A total of 137 surveillance tests were completed per 34 different test instructions.
Unit 1 A total of 111 surveillance tests were completed on unit 1 per 44 dif ferent test instructions.
Unit 2 A total of 167 surveillance tests were completed on unit 2 per 44 different test instructions.
Unit 3 A total of 90 surveillance tests were completed on unit 3 per 37 different test instructions.
I
,1 e
um m a im i
umi um u
_.....m-iW
r Pags 67 e
TESTING
SUMMARY
(Continued)
APRIL 1988 Channes. Test, and Em eriments Requirinz Authorization From the NRC Pursuant to 10 CFR 50.59(a)
There were two revisions for unit 1, 2, and 3 technical specifications, d
Channes. Tests, and Eperiments not Requiring Authorization from NRC Pursuant to 10 CFR 50.59(a)
There were no special tests completed for this month.
r
Pag 3 68 I
REACTOR VESSEL FATIGUE USAGE EVALUATION APRIL 1988 The cumulative usage factors for the reactor vessel are as follows:
Usame Factor Location Unit 1 Unit 2 Unit 3 l
Shell at water Line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360 e
t b
Pegs 69 CHANGE IN PROCEDURE APRIL 1988 There were 406 revisions to plant instructions during the month; 405 instructions were changed primarily for correction, and the remaining 1 revisions related to safe operation of the plant.
PLANT INSTRUCTION REVISIONS APRIL 1988 Category Instruction Reason fot* Request Change in SDSP 9.8 BFEP To upgrado the walkdown procedure to Response to Walkdown Program include a planning review by a LER. IE aad Constructability person with integrated plant Bulletin, NRC Surveys knowledge when physical work is Inspection required.
Per LER 259/88005 Report. OPQA l
t
(
- -., ~,
w,
Pags 70 CHANGE IN FACILITY DESIGN APRIL 1988 Package Number Description Safety Related ECW P0671 - High Pressure (WP&IR 2016-87) Modified sprinkler Fire Protection System connections and piping in Battery Room 2 and Common (U2)
Battery Board Room 2.
The ECN was not coapleted.
This workplan only covered a umall portion of the mechanical work.
ECN P1001 - Reactor (WP&IR 2018-88) - Reinspection of dimensions Recirculating System - Unit 2 and welds of miscellaneous steel ladders, U2, Reactor Building, elevation 584'-9.5". At 45, 135, 225, and 315.
All existing welds determined unacceptable were reworked using DWP SM-P-1.
The ECN was not completed.
ECN B0033A - Standby Gas (WP&IR 3003-88) - Performed fabrication.
Treatment System -
installation, and inspection of seismic Unit 3 restraints for Standby Gas Treatment Fan C.
The DCN was totally completed.
The operational and functional requirements of the system were not affected by the modification.
Therefore, the margin of safety was not reduced.
ECN L2079 -
(WP 2024-85) Cut out existing valves H02 2 Valves16-49A & B, 51A & B, and 61A & B.
Unit 2 Installed, new valves and reducers.
The ECN was not completed for unit 2.
A very small portion of the work was covered by WP 2024-85.
ECN P0957 - Reactor (WP&IR 2243-87) - Reinstalled the Bio-Shield Recirculating System -
bars which were removed to facilitate the Unit 2 installation of the shielding frame for the safo end replacement.
The ECN was not completed.
ECN L2053 - Cooling (WP 8227) - Provided a local hand switch for Towers - Common each tower lift pump to over-ride the 94.75' temperature trip and allow flushing the hot water away from the temperature probe to enable restarting the towers.
The ECN was totally completed.
Pagt 71 CHANGE IN FACILITY DESIGN (Continued)
APRIL 1988 Package Number Description Safety Related The modification did not adversely affect the operating of the cooling tower.
No Technical Specifications or Environmental Technical Specification requirements were affected.
ECN P0968 - CAD System (WP&IR 2139-87) - Installed block and test Unit 2 valves to allow forward flow LLRT testing of CAD System FSV Valves 84-8A, 8B, 8C, and 8D.
The ECN was completed as it only covered unit 2.
The CAD system is not affected by the additional valves during normal operation.
The tests are only conducted during refueling outages.
The manual block valves will be open and the test connections will be closed during CAD system operation.
Therefore, the margin of safety was not reduced.
ECN P0362 - Torus (bP 2060-86) - Modified MSRV struts Modification -
and clamps inside the unit 2 torus. A Unit 2 very small portion of the work covered by the ECN was completed.
ECN PS327 - Chilled Water (WP 0024-87) - The work plan was written for Circulating Pumps -
documentation only to as-construct drawings Common and remove TACF 0-85-028-031.
The drawings now reflect the modifications made on raised face flanged joints on the chilled water circulating pumps for the units 1 and 2 control bay. The ECN was only partially completed.
Physical work remaining to be implemented.
(WP&IR 2110-87) - Replaced the 30A fuceblocks Unit 2 with 15A fuseblocks on the AKV Unit Board 2C, Turbine Building, elevation 604'.
A small portion of the work covered by the ECN was completed.
Page 72 i
CHANGE IN FACILITY DESIGN (Continued)
APRIL 1988 Package Number Description Safety Related ECW P5366 - HPCI System -
(WP 2015-86) - (HPCI Support R23) - Removed Unit 2 six existing lugs and replaced with larger lugs.
Also added two lugs to achieve symmetry. Added gussets to two main baseplates.
The ECN was completed as it only covered unit 2.
The modifications should reduce the anticipated fatigue and transient daasse to the HPCI discharge piping and supports.
Based on this, the margin of safety was not reduced.
DCN P00069A - Diesel (WP&IR 1007-88) - Corrected Diesel Generators Generator System -
KVAR sharing problem by rolling conductors in Units 1 & 2 the electrical control cabinets.
The DCN was totally completed.
The modifications did not affect Technical Specifications or involve a USQ.
System function operability was not affected. The modification did not involve a change to the FSAR or Design Criteria which would alter i
general system requirements or operational limits or system.
ECN P00086A - RHR Service (WP&IR 0033-88) - Documentation only -
Water - Common Revised drawings to reflect changes in setpoints for RHRSW compartment sump pump switches. The switches are 0-LS 81A & B, 82A & B, 83A and B, and 84A & B.
The ECN was completed.
The sump pumps and level switches are not active or passive components required for reactor safe shutdown or maintaining reactor in safe shutdown conditions. The switches do not servo any cafety function and are not addressed in any Technical Specifications.
ECN P3219 - Control Bay (WP4IR 2259-87) - Removed air-conditioning HVAC - Unit 2 equipment in the Unit 2 Board Room D and the Unit 2 Vent Tower.
A very small portion of the work covered by the ECN was completed.
Pago 73 i
CHANGE IN FACILITY DESIGN (Continued) i APRIL 1988 l
Packame Number Description Safety Related ECN P0859 - CRD System -
(WP&IR 2086-87) - Installed supports for Unit 2 conduits over CRD structures, Unit 2. Reactor Building, elevation 565'.
A very small portion of the work covered by the ECN was completed.
(WP 2073-87) - Installed screwed connections Unit 2 for back washing Core Spray and RHR coolers.
The ECN was completed for unit 2.
Work is remaining to be implemented on units 1 and 3.
The ECN provided a means of removing silt from cooling supply and return lines.
The e
modification did not adversely affect the ability of the EECW system but improved reliability of the system.
Thus, the margin of safety was not reduced.
ECN P0827 - Reactor (WP&IR 1009-87) - Installed coordinating fuses Recirculacion 07: tam -
downstream of main circuit fuses in the Unit I negative polarity of the protective relay circuits (4KV Reactor Recire Pumps 1A and IB MG sets). The ECN was totally completed.
The addition of the fuses did not change the function ot operation of the system circuitry.
b?E calculations show that the fuses are propecly sized to not spuriously open for normal operation and startup loading transients as well as provide adequate coordination upon a fault.
Based upon this, the margin of safety was not reduced.
ECN P0883 - 4KV Bus Tie (WP&IR 2108-87) - Replaced 35A fuseblocks Boards - Units 2 & 3 with 15A fuseblocks, unit 3, Bus Tie Board, compartments 106, 103, 104, 105, 101; breakers 1632, 1642, 1732, 1742, and 1934 (WP&IR 2112-87) - Replaced /added 15A fuseblocks in 480V Shutdown Board 2A.
The ECN was not completed.
A small portion of the work covered by the ECN was implemented by these two WP& irs.
9
Page 74 CHANGE IN FACILITY DESIGN (Continued)
APRIL 1988 Package Number Description Safety Related ECN P2146 - Drywell - Torus (WP&IR 2287-87) - Removed one support on Purge Piping - Unit 2 the drywell torus purge piping system Unit
- 2. Reactor Building, elevation 621'3".
The ECN was completed.
Analysis were performed and determined that the support change did not adversely af fect the system's safety functions or safety analysis. The margin of safety as defined in 4
the basis for any Technical Specification was not reduced.
ECN P0126 - P3145 Reactor (WP 2235-87) - Replaced pressure transmitters Bldg. Ventilatlon and and terminated shield wire of cables 2R971 Reactor Feedwater Systems -
and 2R2339 on T.B. GG in JB101, panel 25-6A.
Unit 2 A small portion of the work covered by the ECNs was completed.
(WP& irs 2185-87, 2294-87) - Replaced internal Unit 2 position switches for Target Rock solenoid valves 2-FSV-84-8A, B, C, and D.
Insulation was repaired on cable going to position switch on 2-FSV-84-8A.
The ECN was not totally completed.
ECW P5523 - Radwaste/
(WP&IR 1029-07) - This modification added Radiation Monitoring -
two automatic isolation signals, downscale Common and inoperative, to radiation monitor R-90-130 to isolate liquid radwaste discharge valves FCV-77-58A and B.
The ECN was completed.
The modification fulfills an NRC commitment for Radiological Environmental Technical Specifications (TS-221, RI) implementation.
The release flow rate of radwasto discharge l
was increased which in turn improved radwasto system operations.
The margin of safety was not reduced.
ECN P0362 - Torus (W.P. 2037-87) - Added 13 ring supports to Modification - Unit 2 SRV lines next to jet deflectors in drywell basement.
A very small portion of the work covered by the ECN was completed by this workplan.
Pago 75 CHANGE IN FACILITY DESIGN (Continued)
APRIL.1988 Package Numbe_e Description Safety Related ECN P0653 -
(W.P. 2013-84) - Changed bumper springs, Main Steam -
inspected and repaired bushings on the Unit 2 MSRV tailpipe vacuum breaker valves. The major portion of the field work covered by the ECN was completed.
Paperwork remaining to be closed for one workplan which will complete the ECN for unit 2.
ECN P0533 -
(WP 2178-84) - Removed old and installed Torus Temperature new Sequential Events Recorder in panel Monitoring System 9-3 7, unit 2, auxiliary instrument room.
Unit 2 Only a portion of the work covered by the ECN was completc.1.
ECN P5319/P5380 -
(WP&IR 0040-87) - The workplan was written Reactor Protection for documentation only to as-construct System - Units 1 & 2 drawings and lift TACFs 1-85-029-99, 1-85-28-99; 2-85-52-99 and 2-f~-53-99.
The modifications covered replacing the #6 AWG with #2 AWG from the 100 amp circuit breaker to the CR bus, panels 9-15 and 9-17 in the auxiliary instrument room.
The ECNs woro co:npleted.
Pags 76 L
CHANGE IN FACILITY DESIGN (Continued)
APRIL 1988 Package Number Description Non Safety Related DCN B0007A -
(WP&lR 0022-87) - Replaced the existing (ION Security - Common Track Instruments Model 75) with new ION Track Instrument Model 85 at the west gatehouse. The DCN was totally completed.
ECN P1052 -
(WP&IR 1013-88) - Installed a microswitch in Door Interlock series with push buttons on doors 221 and and Alarm System 236 to prevent breach of containment. The Unit 1 & 2 workplan was written for documentation to lift TACF 1-86-19-260 and to as-construct drawings. The ECN was totally completed.
ECN P1053 -
(WP&lR 3013-88) - Installed a microswitch Door Interlock in series with push buttons on doors 244 and Alarm System -
and 249 to prevent breach of secondary Unit 3 containment.
The workplan was written for documentation to remove TACF 3-86-19-260 and to as-cc7struct drawings.
The ECN was totally completed.
l I
Page 77 b
CMANGES IN PLANT ORGANIZATION APRIL 1988 There was one change in plant staff for those positions designated as key supervisory positions Gary T. McChristian, Assistant Manager to Plant Manager.
i 4
Pego 78 ACCIDENTS APRIL 1988 There were three loss-of-time accidents during the month.
0 Browns Ferry Nuclear Plant Post Office Box 2000 Decatur Alabana 35602 thtf i 6 1988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention: Office of Management Information and Ptogram Control In the Matter of the
)
Docket Nos. 50-250 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTMLY OPERATING REPORT - APRIL 1988 Enclosed is the APRIL 1988 Monthly Operating Report to NRC for Browns Forry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESS.E VALLEY THORITY l
lbg V
J
. Walker I.
t Manager Enclosure cc: Mr. G. E. Gears Mr. G. G. Zech, Director Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 101 Marietta St., NW, Suite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector Region II Browns Ferry Nuclear Plant Attn:
Dr. J. Nelson Grace.
Route 12, Box 637 Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power Mr. Ted Marston, Director Operations Electric Power Research Institute Suite 1500 P. O. Box 10412 1100 Circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389
(' ]
h\\