ML20151Z380

Monthly Operating Repts for Jul 1988 for Browns Ferry Nuclear Plant

ML20151Z380
Person / Time
Site:	Browns Ferry
Issue date:	07/31/1988
From:	Campbell G, Crawford J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20151Z364	List: ML20151Z360 ML20151Z380 ML20151Z397 ML20151Z400 ML20151Z403 ML20151Z408 ML20151Z414 ML20151Z427 ML20151Z432 ML20151Z438 ML20151Z443 ML20151Z447 ML20151Z453 ML20151Z458 ML20151Z463 ML20151Z470 ML20151Z475 ML20151Z481 ML20151Z492 ML20151Z504 ML20151Z509 ML20151Z519 ML20151Z524
References
NUDOCS 8808290312
Download: ML20151Z380 (84)

Text

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364 880815 .8 1 1 MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY JULY 1988 "Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 r

Submitted by:

_~ b egge2;ggg gj@@$339 Guy G. Campbell III R PNV Plant Manager ,

. e TABLE OF CONTENTS PART I OPERATIONAL

SUMMARY

A. Significant Operational Events Summary........................... 1 B. Fuel Performance and Spent Fuel Storage Capabilities Summary..... 2 C. Main Steam Relief Valve (MSRVs) Actuation Summary................ 5 D. Issuance of Special Report s Sunnary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Licensee Event Reprets Summary................................... 7 E.

F. Offsite Dose Calculation Manual Changes......................... 11 G. Radwaste Summary................................................ 12

1. Total volume of solid waste shipped off site

2. Nature of the wasto (trash, resins, etc.)

3. Gross curie.setivity

4. Dates tho 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.

PART II OPERATING STATISTICS A. NRC Reports

1. Operating Data Report................................... ... 21 Average Daily Power Level................................... 24 2.

27

3. Unit Shutdowns and Power Reductions.........................

B. TVA Reportt

1. Plant Operating Statistics.................................. 30

2. Unit Outage and Availability Data........................... 31 Reactor Histogram (Reactor Power Percent)................... 34 3.

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a o TABLE OF CONTENTS (Continued)

Part III MAINTENANCE

SUMMARY

A. Electrical Maintenance........................................... 35 B. Instrument Maintenance........................................... 40 C. Mechanical Maintenance........................................... 42 D. Running Maintenance.............................................. 45 E. Modifications.................................................... 46 PART IV OTHER REPORTS A. Chemistry Summary

1. Primary Coolant Chemistry .................................. 47

2. Environmental Technical Specification Requirements.......... 50

3. A i rb o rne Re l e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52

4. Liquid Releases.......................................... 57

5. Resin Usage Report.......................................... 61

6. Fuel Cladding Integrity Parmeters . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2

7. Waste Treatment System Throughputs.......................... 63 B. Testing Summary.................................................. 64 C. Reactor Vessel Fatigue Usage Evaluation.......................... 66 D. Change in Procedures............................................. 67 E. Plant Instruction Revisions...................... 2 .............. 67 F. Change in Facility Design (ECNs)................................. 68 G. Change in Plant Organization..................................... 76 H. Accidents........................................................ 73 9

Addenda: Revisions to April 1988, June 1988 Revisions to correct unit 1 station uso meters that were read to the wrong multipliers from September 1986 through March 1988.

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0PERATIO.. AL SCMMARY I

Page 1 SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

JULY 1988 Unit 1 07/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 6 refueling and modifications continue.

07/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 6 refueling and modifications continue.

Unit 2 07/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continue.

07/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continues.

Unit 3 07/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Environmental qualification work and modifications continue.

07/31/88 2400 Unit remains on administrative hold to reco1ve various TVA and NRC concerns. Environmental qualification work and modifications continue. , ,

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Page 2 FUEL PERFORMANCE AND SPENT FUEL STORACE CAPABILITIES

SUMMARY

JULY 1988 Unit 1 Unit I 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 refuelius will involve e

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 o

presently contains 284 new assemblics, 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 fuel pool is 1355 locations.

Pags 3 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONT.)

JULY 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 was placed on administrative hold to resolve TVA and NRC safety conce rns . 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 podifications (NUREG 0661), containment instrumentation modification (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reductiono modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections, (LER 82020), valve leak rate testing modifications (Appendix J),

D/C speed sensor installation (LER 81004). HPCI and RCIC testable check valve change out, modification of PCIS logic (LER 259 85009), HPCI improvements, various seismic program 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 E00-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of 1

the spent fuel pool is 1481 locations. All High Density Racks havo been installed in the pool with tho exception of two.

Pags 4 FUEL PERFORMANCE AND SPENT FUEL STORACE CAPABILITIES

SUMMARY

(CONT.)

JULY 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 loadin6 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-startup unit 3 modifications are environmental qualification of electrical equipment (10CFR50.49), containment modifications (NUREC 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 (NUREC 0737), addition of redundant drywell control air supply, RPS voltage monitoring modification H O sample line 2

modification (LER 81050), replacement of jet pump holddown beam assemblies (IEB 80-07) EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.

There are 0 assemblics in the reactor vessel. There are 764 assemblics 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 $85 locations. All high density racks (HDR) have been installed in the pool with the exception of six.

a Page 5 MAIN STEAM RELIEF VALVE (HSRVs)

SUMMARY

JULY 1988 No !!SRVs were challenged during the month, r

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Pegs 6 ISSUANCE OF SPECIAL REPORTS JULY 1988 There were no violation notices issued for the month of July 1988.

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Page 7 LICENSEE EVENT REPORT (s)

July 1988 Descriptien of Event LER 1-88-016 Personnel Error Resulted in e Violation of Technical Specifications on March 20, 1988, at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, with all three Browns Ferry units defueled, a personnel error resulted in the requirements of Technical Specification (TS) Table 3.2.K note "Action D" not being met. On June 1, 1988, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, during the cognizant engineer review of Surveillance Instruction (SI) 4.8.B.1.a.1 "Airborne Ef fluent Release Rato" data package, two off-gas stack flow estimates were found to be outside the 4-hour TS requirement. On March 20,1988, the stack flow monitor was inoperable. With this instrument inoperable the stack flow rate estimstes are normally recorded every four hours as required by the plant's TSs. On March 20 and 21, 1988, stuck flow rates were recorded at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, and 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />. This gave an interval of six hours for two readings. This was attributed to personnel error by the assistant unit operators (AUOs) responsible for recording these readings. The AUOs became involved in other duties and neglected to take readings within four hours as required by the plant's TSs. The Operations Supervisor has counseled the individuals involved.

1-88-017 Unplanned Standby Cas Treatment Actuation Due to Personnel Error One June 4, 1988, at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br />, with all three units defueled, the C train of standby gas treatment (SBGT) actuated while the system was being returned to service following maintenance.

The train was immediately stopped and placed in standby readiness.

The engineer directing the maintenance had erroneously instructed the craft personnel to change the state of latching relay (labeled MCX) in the train's control circuit. The relay was manually put in the actuate (or operate) state by the craft personnel, as instructed, thereby allowing train actuation upon supply breaker closure. The engineer made an erroneous assumption concerning operaticn of this relay.

The shif t Operations Supervisor (SOS) was notified prior to t h event of a possible engineered safety feature (ESF') c.ctuation because the maintenance engineers were unsure of the relay #

state. The SOS directed the main control room hand switch for the SBGT train be placed in pull-to-lock believing that to be an absolute control over train actuation. The relay in question is located downstecam of the pull-to-lock contacts and was not affected by the action.

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l Pags 8 I Description of Ev^nt (Continued) 1-88-017 Maintenance engineers will receive information on these events.

(Continued) Operators will receive information on these events and pull-to-lock logic. The bleaker maintenance procedure and the SBGT system operating instruction will be revised to add more detail defining the states of the MCX relay. Additional information will also be provided in the operating instruction concerning the pull-to-lock logic.

1-88-018 Unplanned ESF Actuations Due to Circuit protector Trio Caused by Unstable Undervoltaxe Relay Failure l One June 5, 1988, at 1152 hours0.0133 days <br />0.32 hours <br />0.0019 weeks <br />4.38336e-4 months <br />, with all three units defueled, the 1A1 t'eactor protection system (RpS) circuit protector tripped deenergizing the unit 1 RpS bus 1A. This caused a half scram, partial primary containment isolations, secondary containment isolations, and actuation of the control room emergency ventilation system. The operators reset the circuit protectors and the isolations and returned the systems to standby readiness by 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.

At 1202 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.57361e-4 months <br />, the same circuit protector tripped again causing a repeat of the earlier event. The operators reset the circuit protector and the isolations and returned the systems to standby readiness by 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br />.

A troubleshooting investigation was initiated which determined that the undervoltage relay in the circuit protector was unstable when subjected to minor vibration. This relay failure caused the trip of the circuit protector which deenergized the RpS bus and led to the ESF actuations.

The relay was replaced and will be returned to the manufacturer for evaluation. ,

1-88-019 ESF Actuations Occurred Due to personnel Error On June 8, 1988, at 0623 hours0.00721 days <br />0.173 hours <br />0.00103 weeks <br />2.370515e-4 months <br />, with all three Browns Ferry units defueled, the following unanticipated ESF actuations occurred. These ESF actuations occurred when a jumper placed in the Al ventilation system isolation trip circuit fell off while plant personnel were replacing a fuse. personnel involved were aware that if the jumper fell off while the fuse was out of its holder en ESF actuation would occur. Standby gas treatment '

(SBGT) trains A and C and control room emergency ventilation (CREV) train A started. Also, a refuel zone isolation occurred in all three units. A reactor zone isolation occurred in unit 1 only; however, this is not part of the same isolation logic.

Page 9 Description of Ev nt (Continued) 1-88-019 The immediate corrective action was to quickly replace the fuse (continued) in its holder and reset each involved ESF. The ESF systems were reset at 0627 hours0.00726 days <br />0.174 hours <br />0.00104 weeks <br />2.385735e-4 months <br /> on the same day. At 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br />, the fuse was pulled twice in an attempt to recreate the event. Each time the fuse was pulled, all ESF lo6 1c involved' operated as designed. The fuse was replaced and the systems were returned to normal lineup for standby readiness, 1-88-020 ESF Actuation duo to Personnel Error and Procedural Inadequacy On June 23, 1988, at 0902 hours0.0104 days <br />0.251 hours <br />0.00149 weeks <br />3.43211e-4 months <br />, with all three Browns Ferry units defueld, the D diesel generator (DG) an ESF, inadvertently auto started due to personnel error and procedural inadequacy.

While removing a clearance on the D DC, the logic breaker was closed prior to returning power to the shutdown board. The D DG logic energized and sensed an undervoltage condition on the shutdown board. This resulted in the automatic start of the D DG, an ESF. This ESF actuation was esused by the personnel error of returning logic power to the DG before the shutdown board was energized. This personnel error is being attributed to a procedural inadequacy. The present equipment clearance procedure does not require that a sequence be specified for the retura to service of the components under clearance. The D DGs function was accomplished as designed and it was returned to standby readiness at 0916 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.48538e-4 months <br />.

The immediate corrective action was to open the D DG logic breaker and to stop the D DG locally. All operators will review the operations critique on this event. The personnel involved in the equipment return to service have been counseled. The procedural inadequacy will be corrected in the equipment

, clearance procedure.

3-88-003 DeslRn Deficiency in DG Breaker LoRic Prevents Three DGs from Connecting to Shutdown Boards During Loss of Power / Loss of Coolant Accident (LOP /LOCA) Test On June 5, 1988, during the performance of the LOP /LOCA test, i

breakers connecting diesel generators 3A, 3C, and 3D to their respective 4KV shutdown boards opened just after closing and would not automatically reclose because an open signal sealed in the logic. An operator monetarily doenergized the power to the breaker logic which reset the logic. When the logic was #

repowered, the breakers closed as required.

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Pags 10 pescription of Event (Continued) 3-88-001 The sequence of events, the time response characteristics of each DC and certain logic components, the closure circuit logic, and the trip circuit logic all contributed to the condition.

The breaker circuit is being evaluated and will be modified as ,

required to eliminate the possibility of the breaker not closing '

on a valid close signal.

This event occurred with all three units shut down and defueled.

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, . ... = . . - . . .. .. - ~. .. -- .. ,. . . ~ . .-

Yt P&gs 11 0FFSITE DOSE CALCULATION MANUAL CHANGES i

JULY 1988 No changes were made to the Browns Ferry offsite dose calculation manual during the month, i

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Pcgo 12 RADWASTE

SUMMARY

JULY 1987 The radwaste system performed as designed. Approximately 1.04E+06 gallons of waste liquid were discharged containing approximately 3.98E-02 curies of activity.

There were two spent resin shipments and two trash shipment during July.

All shipments were to Barnwell, South Carolina.

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Pags 13 Colid Radivoctive waste July 1388 Dewatered Spent Resin Shipments ('

Volume of condensate / waste resin shipped: 3,?1 Cu.M. (288 Cu.Ft.1 Total curies shipped: 3.444 Volume of reactor cleanup reain shipped: O Cu.M. ( 0 Cu.Ft.)

Total curies shipped: 0 Datr Shioned Disonsol Facility Type of Resin 07/18/88 Barnwell, SC CWP5 07/21/88 B a r r.we l l , SC CWP5 Dry Active Waste (II Number of drums shipped: 47 Volume: 3.95 Co.li. C 352.5 Co.Ft.)

Total curies shipped: 0.2473 Number of 'soxes shipped: 3 Volume: 8.15 Cu.M. ( 289.0 Cu Ft.)

Total curies shipped: 0.0573 Number of HIC's shipped: 1 Volume: 3.33 Cu.M. ( 120.3 Cu,Ft.)

Total curies shipped: 105.9237 Dato ShiDDed Disone,al Facility Type of Package *

[

07/13/88 Barnwell, SC Drume/ Boxes 07/20/88 Barnw+ll, SC HIC U

(1) All shipments were by Gole-Use Vehicle

Sulid Radioactive wasto (Continued) f July 1980 Sunina r y Type Shipped to Packaged on Gross Curie Estimoted of Bernwell Site Awaiting Content by Generation for Waste During Month Shipment Type of Weste Next Month Compacted Drums 352.5Cu.Ft.( ' 315 Cu.Ft. 2.4?E-01 600 Cu.Ft.(

Uoxes 03 Cu.Ft.I2) 2/9 Cu.Ft. 3,79E-02 000 Co.Ft.(

Uncompacted Drums O Cu.Ft.(2) O Co.Ft. 0.00E+00 0 Cu.F*,.(2) 2)

Boxes 196 Cu.Ft.(2) 302 Cu.Ft. 4.52E-03 800 Cu.Ft.  ;

HIC's 120.3Co.Ft.I I O Cu.Ft. 1.06E+02 0 Cu.Ft.I2' Resins CWP5 288 Cu.Ft.c$) 1569 Cu.Ft.g3) 3.44E+00 450 Cu.Ft.g$)

RWCU O Cu.Ft.( ' 225 Cu.Ft.(3' O.00E+00 35 Cu.Ft.( '

TOTALS 1103 Cu.Ft.I ) 896 Cu.Ft.( 1.10E+02 2,200 Cu.Ft.( '

Total volume of waste shipped during the month: 1,103 Cu.Ft.( '

Total vulume uf weste shipped year-to-date: 14,557 Cu.Ft.

Unused 1988 burial volume allocation at Barnwell: 63,243 Cu.Ft.

(1) Actual resin voluine (2) Cuntoiner burial volume (3) Estimated volume in separators (4) Does not include resins o

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Pags 15 LIGUID RADWASTE MONTHLY OPERATING REPORT JULY 1988 TOTAL RIVER RELEASE FLOW RATE (GPM) DATA PLOTTED FOR THE PREVIOUS 12 MONTHS TOTAL RELEASE (CI) 40 . 2 FLOW nAT, f dDM) 30

• HI 27.10 LOW 11.62 N, , AVG 19.82 20 . k '

1 TOTAL y ^s pf_ y g, Aar fcT1

,.# Y HI 0.05 10 . -c ' LOW 0.01 AVG 0.03 3 FLOWRATE O E 2 E "

Z " " ~ " " " N AUG SEP QCT NOV OEC JAN #EB EAR APR MAY VUN VUL O D RELEASE (CZ)

THADUGHPUT fr At 4)

FILTER THROUGHPUTS WASTE 0ALLONS X 10 S HI 0.17E+07 4 LOW 0.86E+0E AVG 0.11E+07 3 -

FLOOR ORAIN HI 0.98E+06 LOW 0.49E+06

AVG 0.76E+06 h  ! i . LAUNDRY j j jj fi r - .- l ,!  ! !j HI 0.13E+05

.: )[

jl! j! LOW 0.00E+00

} 'l'I "i j,,;;) ir# : eg j i l g  : ,

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f**i AVG 0.62E+04 M

-  !  :~-- ' ) -

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0

--- j F)h d b AUG SEP OCT NOV DEC VAN FEB MAR APR MAY VUN JUL dbh - -- -

,-- !h ----- --

C0ST OF OPERATION nornSe'7fni, iam .

THOUSANDS OF DCLLARS 100 WASTE HI 0.59E+05 90 - *"*"*

. . LOW 0.19E+05 80 .  : ,

l .{ AVG 0.37E+05 70 j  : m t.  :  : FLOOR OrIAIN 60 - i* i

• I - - I'  ! l H 0.42E+05

t LOW 0.21E+05

! _ .O I jj i ***** I I 50

!l AVG O.31E+05

:  ;  :  :: P -

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:l ':j $x);' j 40 .

30 j

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' l LAUNCRY HI 0.37E+03 r

'! s I ':I :  : 'I  !  ! T,<,4  !  : LOW 0.00E+00 20 < l l *

(***** y:  ; ': ';

AVG 0.64E+02

' ~ "

0

-- hk--- -

AUG SEP OCT *aOV DEC VAN FEB MAR APR MAY VUN JUL l

' WASTE COLLECTOR SYSTEM '

LAUNDRY SYSTEM t ,'

I......) Ft00R DRAIN SYSTEM STARTING 3-87 COSTS INCLUDE AESIN DISPOSAL l

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Pags 16 l REACTOR POWER - MWT UNITS 1, 2, AND 3 JUL Y 1988 MWT .

3s00 -

3000 -

I UNIT 1: OUTAGE 2000 -

UNIT 2: OUTAGE 1500 -

UNIT 3: C'1iAls 1000 -

500 -

o

• • %%***h**R@&O%S544#444444444444 Chen)stry Section DAYS .-

Cchn1 col Services koms Ferry httelear Plant REACTOR WATER CONDUCTIVITY UNITS 1, 2, AND 3 JUL Y 1988 UMH0/CH CONDUCTIVITY 1,75 -

UNIT i CCNDUCTIVITY 1.25 -

UNIT 2 g ............................................................

0.75 \s ~- - -

0.5 -

o.M A EXPECTED RANGE COLD SHUTOOWN o

• • • • • • Sh**#@@QJ##4@@@@@@4SS44@4&ACTION L EL I LIMIT Cheistry Section DAYS COLD SHUTDOWN .

Technical Services W:wns Ferry hticlear Plant REACTOR WATGR CHLORIDE UNITS 1, 2 AND 3 JUL Y 1988 PPB so............................................................... fM.0 RICE UNIT 1 g ,  !

CA CAICE 34 -

UNIT 2 20 -

W.. HIC E

'217.

to -

EXPECTED DANGE 0

' LL A CONDITIONS

• • • • • • • • • • @@&O@@#0@@SCSQY@$4$@ft monistry Sn cion DAYS Techn1 cal Services koms Ferry httclear Plant

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1 OPERATEG STATISTICS f

l i

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. - . , - . _ . - - . . _ - , _ _ _ . - - . . _ _ . . - _ - _ _ _ , . . . . . _ _ . - _ _ . _ . _ _ . - _ . , . . . _ ~ .-_ , ___ , , . - _ _ --

OPERATING DATA SEPORT Pags 21 DOCKEi NO. 50-259 DATE 0841-88 COMPLETED BY J. O. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS l Notes l

l. Unit None Browns Ferry Unit One l l

2. Reporting Period: July 1988 l l

3. Licensed Thermal Power (MWt): 3293 l l

4. Namoolate Rating (Gross MWe): 1152 l l S. Design Electrical Rating (Not MWe) 1065 l l

6. Maxinxsn Dependable Capacity (Gross MWe) 1098.4 l

7. Maximun, Dependable Capacity (Not MWe) 1065 l

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

N/A

9. Power Lovel To Which Restricted, if Any (Not MWe): N/A

10. Roasons for Restrictions, if Any: ,

N/A This Month Yr-to-Date Cumulative

11. Hours in Roporting Period 744 5111 172,791

12. Nur:bsr of Hours Raactor Was Critical 0 0 59.521.38

13. Reactor Reserve Shutdown Hours 0 0 6.997.44

14. Hours Generator On-Line 0 0 58,267.26

15. Unit Raserve Shutdown Hours 0 0 0

16. Gross Thermal Enorgy Generated (MWH) 0 0 168,066.787

17. Gross Electrical Energy Generated (MWH) 0 0 55,398.130

18. Not Electrical Enorgy Gonorated (MWH) -5132 -29019 53,652,454

19. Unit Service Factor 0 0 47,50

20. Unit Availability Fector 0 0 47.50

21. Unit Capacity Factor (Using MDC Net) 0 0 41.05

22. Unit Capacity Factor (Using DER Net) 0 0 41.05

23. Unit Fored Outage Rate 100 100 44.01

24. Shutdowns Scheduled Over Noxt 6 Months (Type, Date, and Duration of Each):

25. If Shut Down At End of Roport Period, Estimated Date of Startup To be determined

26. Units in Test Status (Prior to Ccreercial Operation): Forecast Achieved INITIAL CRITICAllTY INITIAL ELECTRICITY COMERCIAL OPERATION (9/77)

OPERATING DATA REPORT Pego 22 DOCKET NO. 50-760 DATE 08-01-88 COWLETED Bf J. O. Crewford TELEPHONE (205) 729-2507 OPERATING STATUS lNotet l

1. Unit Nanet Browns Ferry Unit Two l l

2. Reporting Period: July 1988 l l

3. Licensed Themel Powoc (MWt): 3293 l l 4 Nameplate RetIng (Gross MWe): 1152 l l

5. Design Electrical Rating (Not MWe) 1065 l l

6. Maximum Dependable Capacity (Gross MWe) 1098.4 l l

7. Maximum Dependable Capacity (Not MWe) 1065 l l

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Give Reasons:

N/A

9. Power Level To Which Restricted, if Any (Not MWe): N/A

50. Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumu stive ll. Hours in Reporting Period 744 Sill 117.678.00

12. Number of Ilours Reactor Was Critical 0 0 53.860.03 _ i

13. Reactor Reserve Shutdown Hours 0 0 14.200.44 ,

14. Hours Cenerator On-Line 0 0 54.338.36

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 153.24' 167

17. Cross Electrical Energy Conerated (MWH) 0 0 50.771.798

18. Net Electrical Energy Generated (MWH) -2419 -14.526 49.169.307

19. Unit Service Factor 0 0 46.20

20. Unit Availability Factor 0 0 46.20

21. Unit Capacity Factor (Using M)C Net) 0 0 39.23

22. Unit Capacity Factor (Using DER Net) 0 0 39.23

23. Unit Forced Outage Rate 100 100 43.43

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 To te dotemined

26. Units in Test Status (Prior to Comercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C0 mERCIAL OPERATION (9/77)

Page 23 OPERATING DATA REPORT 00CKEi NO. 50-296 DATE 08-01-88

-- COMPLETED BY J. D. Crawford TELEPHONE (205) 729 2507 OPERATING STATUS l Notes l

l. Unit Names Browns Ferry Unit Three l l

2. Reporting Period: July 1988 l l

3. LIconsed Thermal Power (MWt): 3293 l l 4 Naneplate Rating (Gross m): 1852 l l

5. Design Electrical Rating (Net % ) 1065 l l

6. Maximum Dependable Capacity (Gross MWe) 1098.4 l l

7. Maximum Dependable Capacity (Not MWe) 1065 l l

8. If Changes Occur in Capacity Ratings (it m s Number 3 Through 7) Since Last Report, Give Reasons:

N/A e

9. Power Lovel To hhich Restricted, if Any (Net MWe): N/A J 10. Reasons for Restrictions, if Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reparting Period 744 Siti sw l( LOO i2. Numter of Hours Reactor Was Critical 0 0 45, X 6.06

13. Reactor Reserve Shutdown Hours 0 0 5,149.55

14. Hours Generator On-Line 0 0 44,194.76

15. Unit Reserve Shutdown llours 0 0 0

16. Gross Thermal Energy Generated ('%H) 0 0 131,868,267 P. Gross Electric.I Energy Generated (WH) 0 0 43,47,t,250

18. Net Electrical Erw rgy Generated (KnH) -1833 -15,891 42,025,257

19. A lt Service Factor 0 _

0 44.15

20. Unit Availability Fector 0 0 44.15

21. Unit Capacity Factor (Using MOC Net) 0 0 39.41

22. Unl* Capacity Fx tor (Using DER Net) 0 0 39.41

23. Unit Fo ced Outage Rate 100 100 47.00

24. Shutdowns Scheduled Over Next 6 Monthe (Type, Date, and Duration of Each):

25. If Shut Down At End Of Report Period, Estimated Date of Startup To te determined

26. Units in Test Status (Prior to Ccrrercial Operation): Forecast Achloved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 1724n

Paga 24 AVERAGE DAILY UNIT POWER LEVRL DOCKET NO. 50-259 Unit One DATE 08-01-88___

COMPLETED BY J.D. Crawforf TELEPHONE (205)729-2107 MONTH JULY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net) (NWe-Net) 1 -7 17 -7 2 -7 18 -7 3 -6 19 -7 4 -7 20 -7 5 -7 21 -7 6 -7 22 -7 7 -6 23 -7 8 -7 24 -7 9 -7 25 ,

-7 10 -7 26 -7 11 -7 27 -7 ,

12 -7 28 -7 13 -6 29 -7 14 ~7 30 -7 e

15 -7 31 -8 9

16 -7 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 negawatt.

^

(9/77) 1724n

Pcgo 25 AVERACE DAILY UNIT POWER LEVEL

'\

DOCKET No. 50-260 Unit Two DATE 08-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH JULY 1988 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 -3 17 -3 2 -4 18 -3 3 -4 19 -3 4 -3 20 -3 5 -4 21 -3 6 -4 22 -3 7 -3 23 -3 8 -4 24 -3 9 -3 25 -3 10 -4 26 -3 11 -3 27 -3 12 -3 28 -3 __

13 -3 29 -3 14 -3 30 -3 15 -3 31 -4 e

16 -3 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 wholo megawatt.

(9/77)

L_

Pago 26 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Unit Three DATE 08-01-88 COMPLETED BY J D. Crawford TELEPHONE (205)729-2507 MONTH JULY 1988 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 -2 17 -3 2 -2 18 -3 3 -2 19 -3 4 -2 20 -2 5 -2 21 -3 6 -3 22 -3 7 -2 23 -3 8 -2 24 -2 9 -2 25 -2 10 -3 26 -3 11 -2 27 -3 12 -3 28 -2 13 -2 29 -3 14 -2 30 -3 15 -3 31 -3 a

16 -3 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.

(9/77) '

1724n

UNIF SHU1 DOWNS AND POWER REDUCTIONS DOCKETNO. 50-259 UNIT NAME One DATE U5-01-55 REPORT MON f H July CODEPLETED sY J.D. Crawford TELEf900NE (205) 729-2507

.l

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g j- E ~' Lkensce  :-e, K Cause a r.u ,ect,,e

%.. Date

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g jg5 Event s7 97 Action ..

$3 j i73 j Repews e eNO yb Prevens Reaurente d

315 07/01/88 F 744 F 4 Administrative hold to resolve various TVA and NRC concerns.

I 2

- 3 4 F: F wced Reaum: Method: Exlubie G. Insivuttiuos S Stheduled A-1:quipmen: Faduse t Explaini l -Manual y few Preparati.un. f Data c.

8-Maintenance or Test 2-Manual Saam-C-Refueling 3-Autimutet Strain.

Entry Sinects fin I.icensee $

D Regulatin) Rcssektiim Evens Rep.=: ILE RI File t NURI G-

44) lica IEmplaml m F4)penas.u Teainmg & t.atense I:sanniusum 01till w F-Admimstiaine 5

G 4)perati. mal Es n o I Emplas.i t l'8/77) IIUnlecs (Eaplaun t I stubs I .Same S..uscc e

UNIT SIIUIDOWNS AND POWER REDUCTIONS DOCKETNo. 50-260 UNIT N AME Two DATE 08-01-88 REPORT MONgII ,Tulv COMPLE1ED BY J.D. Crawf ord TELEPflONE (205) 729-2507 i

-  ? E h Date

-, 33 r j ~Ei Licensee ,E*,

h~3 Cause & C.wsettive i

3j [a 2 $ Evens g7 9 Atsi.m s..

fE 5 } if, Repins e tra O Presen Recurresse

]'

6 305 07/01/88 F 744 F 4 Administrative hold to resolve various TVA and NRC concerns.

I 2

- 3 4 F: F.wted Reasimi: Method:

S Stheduled A-Equrpmen: Failure (Explaml Ex!ubit G-Inumctiims 1-Manual l'. or Psepasate es .4 Data B4tamienance or Test 24tanual Sra n. Entry Sheets I.w tiensee y

C-Refueling ao 3-Ausonnatic krani. Evens Rep w (LI'RIFde tNURI.G-

• D-Regulaiew) Resisicts m 4-Oshes i Explami)

E Operaso Teammg & License Exanunaisim 01till N F-Adnumu rae r.e 5

Geperati. mal Eisen iExplaus t l/77) IIO:het iEsplaml i stubit I -Same Semesc

^

UNIT SIIUIDOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 UNIT MAME Thrce DATE 08-01-88 REPORT MON TH July COMPLETED itY LD- f'rmf o rd TELEPHONE (205) 729-2507

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e. 3 == 4 5 1 :- s yE4 lx.ensee =* ,, c4 rause A c. .ect e

%' - DJ'c h 3?  ! 2i2 Evens E? h Ati .,

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Rep.w e <N 0

]b r,c,c , Rec.,,e.te I'57 07/01/88 F 744 F 4 Administative hold to resolve

, various TVA and NRC concerns.

I 2 _I 4 F: F.wted Reas.m: Me:Iwat:

S 5theduled Exlubis G. Icseracsimes A-Eqwpmen: Failure (Explaint I-Manual f.w reepasasi.wi . f Data *o Balaintenanceof Test 2 Manual Scram.

C-Refueling J-Aus. music Strain.

Entry Sheets fue tiensee $*

Evcns Rep ws (LERIFile(NUREG-D-Regulas n> Restrictiene 4-Osleen iExplaml 0161I w EOperas n Teammg & IArnse Exananaimme

• F-AJmimstrasaw $

Goperasi. mal Lor = tEmpim.sl

(*8/77) Estubis I .Smsic Sansra II4hher (Emplan t -

6 e  %

w

Tvc rastmonposu NUCLEAR PLANT OPERATING STATISTICS Pags 30 Brovns Ferry Noelent Plant Period Hours 744 . Month in1v 19 L ltem No. Unit No. UNIT 1 UNIT 2 UNIT 3 Pl. ANT 1 Aversoe Hourl9 Gross Load. kW 0 0 0 0 2 Maximum Hour Not Generation. MWh 0 0 0 0 3 Core Thermal Eneroy Gen. GWO (t12 0 0 0 0 4 Steam Gen. Therrnal Energy Gen., GWO (t)2

$ Gross Electrical Gen., MWh 0 0 0 0 hl 6 Station Use, MWh 5132 2419 1833 9384 Net Electrical Gen., MWh -5132 -2419 -1833 o

f 8 7

Station Use, Percent 0 0 0

-9384 0

9 Accum Core Avg. Exposure, MWO/ Ton 3 0 0 0 0 to CTEG This Month.106 BTU 0 0 0 0 11 SGTEG This Month,106 BTU 0 0 0 0 12 m

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 y 16 Turbine Avail. Factor, Percent 0 0 0 0 d 17 Generator Avail. Factor. Percent 0 0 0 0 g 18 Turbooen. Avail. Factor. Percent 0 0 0 0 g 19 Remeter Avail. Factor. Percent 0 0 0 0 w _ 20 Una Avail. Factor. Percent 0 0 0 0 21 Turbine Startuos 0 0 0 0 22 Reactor Cold Startuos 0 0 0 0 93

> 24 Gross Heat Rate, Btu /kWh 0 0 0 0 fW 25 26 Net Heat Rate, Btu /kWh 0 0 0 0

= -

W 27 '

g 28 Throttle Pressure, psig 0 0 0 0

& 29 Throttle Temocrature. 'F 0 0 0 0 30 Exhaust Pressure, inHg Abs. 0 0 0 0 Q

g 31 intake Water Temo., *F 0 0 0 0

>= 32 33 Main Feedwater, M lb/hr 34

35 36 37 Full Power Capacity, EFPO (M (4) (4) (4) 38 Accum. Cycte Full Power Days, EFPO (4) (4) (4) j 39 OilYired for Generation, Gallons 8,280 3 40 Oil Heatino Value. Btu / Gal. I34.900 41 Oceaf Generation. MWh 42,O L*

Max. Hour Net Gen. Man. Day Net Gen. Load MWh Time Date MWh Date Factor, %

3 _ 43 0 0 0

$ R emark s IFor BFNP this value is MWD /5TU and for SONP and WBNP this value is MWD /MTU.

l 2(t) indicates Thermal Energy.

3 3 lytornation furnished by Reactor Analvmis Groun. Chattanooga 4 A ministrative Hold /!

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3 o m le T ..

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1 2 3 4 5 6 7 a 9 0 t 2 3 4 s 6 7 s 9 0 1 2 3 4 5 6 7 8 9 0 1 sa A e n u 1 i 1 1 1 i 1 1 i 1 2 2 2 2 2 2 2 2 2 2 3 3 t c D v e e o T U G D T O

i!22 !J il , *  ! .i] i ; i ' i' 1 iL

P a *-

REACTOR POWEP PERCENT JULY 1988 UNIT 1 PUEU IM -

M -

M -

70 4

M -

ACMINISTRATI'!E HOLC 40 -

M -

a0 -

10 -

0%

• S * * ** *

• s' + @ @Ss s* & C & s* f + + 0 Y @ f & s' & + +

UNIT 2 POGG 100 M -

M -

70 -

M -

ACMIN13T9ATIVE H.D 40 -

M -

a0 -

10 0 - - - - - --

S4 6 9 ** * * + sN @ @ s* @ @ O @ s* f f f 9 t* @ f f f S f f UNIT 3 PERCDU 100 M -

M -

70 -

M -

1 ADMINISTAATIVE HOLD M -

46 -

M -

M =

iO -

l 0

% 44 b * **

• 9 + s% @ @ s" @ @ si*s*@@@@@@@@@@f@s ,

4 MAIXTEXAXCE SC.1 MAR I

l ELECTRICAL TECHNICAL SECTION Page 35 MONTHLY REPORT JULY, 1988 Unit Comon Major Routine Activities- -

ELECTRICAL EQUIPMENT LIST: 345 drawings were received in July 1988. 4788 1 drawings are in backlog.

FUSE CONTROL PROGRAM: Operations has completed approximately 90 percent of the fuse changeouts on MRs.  !

Orawing reviews continue with unit one 50 percent complete, unit two 95 percent complete, unit three 50 percent complete and unit zero 35 percent complete.

TS0-E044: Since receiving the data sheet for the first calculation (480V SD Bds) no more data sheets have been received and to reply to our request for clarification on the items on the first calculations. The calculations were to be transmitted along with fuse data sheets in three Stages, first stage due May 5, 1988, second stage due June 27, 1988, and the third stage is due August 22, 1988. The delays will lead to the Electrical Technical Section possibly not being able to meet their responsibilities and the deadline date of November 2, 1988.

Completed the calibration of 28 normally energized DC HFA relays in order to close folder (INP0 SER 87-022).

Researched questions raised by QA in order to close green folder on the replacernent of HFA relay coils (NC0 840128003).

LIMITOROVED:

94 Valves Functional.

90 Valves Have Had Final Inspection .

i 60 Valves Have Been MOVATED.

47 Valves are work complete.

FUEL LOAD REQUIREMENTS:

71 Valves MOVATED.

76 Valves Are Work Complete Forecast fuel load completion for limitorque work is August 17, 1988.

C0 PP0 GRAM:

~

Completed the baseline evaluation of 19C9 QMOS items.

Began compilation of maintenance spare parts matrix. ,

Preparation to revise SDSP 7.7 is continuing.

Investigated the failure of the "B" service cnd control air compressor motor stator and as a result revised MMI-020 to implement an inspection and cleanliness step to prevent the build-up of oil and lint on this equipment.

A 90 percent review meeting participation on ECN-L1972, ECN-P7155, ECN-P?l58, ECN-P7159, ECN-P7160, DCN-WO745A, ECN-P5274, DCN-H0402A.

Page 36

)

2 1

Electrical Technical Section l Monthly Report UNIT COMMON:

Major Routine Activities -

Completed spare parts research f or control bay chillers l A and 18 and the emergency control bay chillers for units one and two. A parts request will be issued when the Vendor returns approximate prices.

ITC issued on EMI-63 (DC motor brush maintenance).

Tech review of hiI-T-02, Master refueling test instructions, EMI-73 and EMI-125.

Assisted Ope,ations on identification of primary and se ondary boundry for air handling units 3A and 38. Issued a drawing discrepancy concerning associated conduits ard junction boxes.

CIRCUIT P1EAKER REBUILOS 4160V 480/250V Total Nec.iber of Breakers To be Rebuilt 303 493 Total Number of Breakers Rebuilt 9 17 Completed This Month 0 0 Waiting on materials fcr breaker rebuilds Failure Investigation prepared on 4KV breaker for 2A RHR pump that failed during LOP /LOCA.

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Page 37 ELECTRICAL TECHNICAL SECTION MONTHLY REPORT JULY, 1988 I. WORK TIME SCHEuulE Received /

Assigned ComDieted ODen Red Folders 1 1 11 Orange Folders 2 1 12 ,

Yellow Folders 0 0 1 Blue Folders 0 1 7 Purple Folders 1 0 4 Active Engineering Assignments 0 0 21 Engineering Backlog 0 0 65 New Engineering Assignments 0 0 0 Completed Engineering Assignments 0 0 0 II. COMMliMENT TRACKING Licensing Issues (NC0 & SLT)

NC0 0 8 24 SLT 0 0 5 P0RS Tracking Items (BFC) 0 1 2 CAQRs 1 2 4 Average Age of CAQRs One Month Employee Concernr 0 0 1 Safety Issues List 0 0 0 III. STAFFING LEVELS AND TRAINING P,e rsonnel ApDroved Headcounts Current Headcounts ASP 36 31 ATL 4 4 -

HTL 0 0 Contractors 5 5 TOTAL 45 40 IV. OVERTIME 9.2%

Y. PROCdDURES 17 Procedures approved '

4 Procedures Sent to Word Processing VI. 39 Outstanding Status "H" MRs 42 Outstanding Status '0' MRs 96 Outstanding Status 'X" MRs

l ELECTRICAL'S REQUIRED U-2 START-UP SURVEILLANCE l

lNSTRUCTIONS STARTING SEPT 1,1987 70 . .

60 I '. f "- 5 50 ./TA fA -

40 y , rag- gy, ;;7Mgp =

20 f'L g ,__a WV fj p, -

1 0- A= -

7 7  !

SEPT OCT NOV DEC JAN FEB MAR APR MAY JUN JUL AUG

-*- B ESTIMATED - - B DRAFTED -"- B TEC REVD -o-B INDP REVD

-*- B WALKDWN -*- B APPROVED -*- B SUBMffTED

P m __ ___ _ _ __ __

u u - - --- -

ELECTRICAL'S REQUIRED U-2 START-UP MAINTENANCE INSTRUCTIONS 90 i , .

80 d' 70 4 60 a Me 50 '

^ " A

_o-=;V 4 7 P /

9 ._ WNV YE 20 /V g, ____. - V \// r o ,i s V rP -F SEPT OCT NOV GC JAN FEB MAR APR MAY JUN JUL AUG TIME BEGINS SEPT 1,1987

-*- A ESTiMATF_D -o- A DRAFTED -=- A TEC. REVD.

-o- A WALKDWN -'- A SUBMITTED -^- A APPROVED  ?

4 g

N

Pags 40 I&C TECHNICAL JULY 1988 I. Work Item Schedule Received / Completed Open Assigned Red Folders 1 1 1 Orange Folders 0 0 6 Yellow Folders 0 1 0 Blue Folders 2 3 1 Purple Folders 0 0 0 Total Assignments

. Active Engineering Assignments 1 13 27 Engineering Backlog 11 MRs (Status "H" and "Q") 60H 60 II. Commitment Tracking Licensing Issues (NCO & SLT)

NCO O O 11 SLT 0 0 1 P0RS Tracking Items (BFC) 0 0 2 CAQR (Onsite) 0 2 4 CAQR (Off-site) 0 0 0 Average Age of CAQRs 5 months Employee Concerns 0 0 0 Safety Issues List 0 0 0 III. Staffing Levels and Training Acoroved Headcounts Current Headcounts Persennel '

ASP 17 12 ATL 4 3 HTL 0 0 Contractors -

4 TOTAL 21 19 IV. Overtime 8.42% #

V. Procedures 43 procedures were sent to Word Processing

Pags 41  !

I&C TECHNICAL JULY 1988 VI. Maintenance Improvement Plan Items ITEM Description  % Complete III.H.1 M&TE 60%

IV.B.3 M&TE 60%

IV.C.1 Maint. Instructions 1) 100% 2) 90% 3) 33%

IV.C.2 Maint. Instructions 0%

IV.C.3 Maint. Instructions 34%

V.B.2 Spures Parts 0%

V.B.3 Sparts Parts 0%

VI.G.2 PM 70%

vIII.B.10 Technical Issues 52%

VIII.D. Employee Concerns 33%

SUMMARY

The major activities of the month involved preparation of instructions to support the retest schedule and the War Room SI schedule. Scaling ar.d Setpoint Documents to support these instructions are also being issued. +

l i

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Page 42 MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)

JULY 1988 Common No major noncoutine activities.

1. Closed the following commitments:

a. INPO SER 87-028

b. INPO OER 87-1963 (OE)

c. NCO 850236002

d. R35 880721 059

e. NCO 880132002

f. G-29(RO) PF-1013(R6) 5 NQAM,II,5.3(QN)(RO)

h. NQAM,II.2.3(R2)

1. G-29(RO) PF-1014 (R6)

j. G-29(RO) PS 3.M.3.1(R4)

k. G-29(RO) PF-1012(R12)

1. NQAM I,2.11(RO)

m. G-29(RO) PS 4.M.1.1 Add.12(R10)

n. G-29(RO) PF-1057(R3) o, G-29(RO) PS 4.M.1.2 Add.1(R1)

- p. G-29(RO) PS 4.M.2.2 Add.2(RO)

q. NQAM,III,2.2(QN)

NQAM,II,5.3A(QN) r r.

i

s. NQAM.II,5.3(QN)(RO) l

t. DPKN73R1(R1)

u. G-29(RO) DWP G.M.1.1-0(R4)

v. G-2(R6) Plain & reinforced concrete i

1 ,_ _

Page 43 MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)

JULY 1988

w. PMP0700 Part 1910

x. SRN-G-43-10(R9)

y. T304.13.07.1401(RO)

2. The following instructions were approved, revised, or cancelled.

a. MSI-0-000-PR0017

b. MCI-0-082-BL0001

c. MCI-0-082-CLR001

d. mci-0-082-CLR002

e. MCI-0-082-CMP 001

f. MCI-0-082-3NG002

g. MCI-0-082-ENG004

h. tipi-0-082-FCT008-01

i. MCI-0-082-COV001

j. MCI-0-082-SEP001

k. mci-0-082-CLOOO2

1. PMI-2.15 .

m. MllG-015

n. KMG-023

o. MMI-34

p. MMI-49

q. NMI-59D r

c. MMI-117

s. MMI-160

t. MMI-175

u. MMI-184

v. MMI-193

Page 44 MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)

JULY 1988

3. The following Conditions Adverse to Quality Reports (CAQRs) were closed,

s. BFA 880328808

b. SEQ 880161 - Generic review.

4. The Mechanical Technical Section devoted 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> to training during the month of June.

Pags 45 RUNNING MAINTENANCE JULY 1988 Data unavailable for the month of July 1988.

1 e

r

Pagn 46 MODIFICATIONS MONTHLY REPORT JULY 1988 MAJOR WORK PERFORMED ECN NARRATIVE Data unavailable for the month.

r l

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e r, I i i V .- ...J k 11P uRr,S ..

r

Page 47 CHEMISTRY

SUMMARY

JULY 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 specificatiot, and fuel warranty limits during the month. Chloride concentration and pH cf the reactor ecolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conotetivity and chloride havo not becu exceeded.

Unit 3 The conductivity of the reacter coolant remained within tect.nical specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant remained within technical '

specification and fuel warranty limits daring the month. This calendar year, the technical specification and fuel warranty limits for conductivity and chlorido have not been exceeded. .

Page 48 CHEMISTRY

SUMMARY

(Continued) 1 JULY 1988 ODCM Chanxes The ODCM was revised to reflect the Fall 1987 Land Use Census, the current program and to correct typographical errors. These ODCM changes were approved by PORC on July 12, 1988.

P P

G 1724n

Page 49 PRIMARY COOLANT CHEMISTRY JULY 1988 Parameter Unit 1 Unit 2 Unit 3

1. Gross Radioactivity

a. Crud (filter) (pci/ml)

High N/A N/A N/A '

Low N/A N/A N/A Average N/A N/A N/A

b. Filtrate (pci/ml)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A

2. Milipore 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 (pei/ml)

High 9.138-5 5.08E-5 1.22E-4 Low 4.47E-5 4.39E-5 1.18E-4 Averago 5.54E-5 4.76E-5 1.20E-4

4. Iodine-131 (pci/ml)

High <8.12E-6 <4.72E-6 <5.01E-7 Low <3.05E-7 <3.14E-7 <3.08E-7 <

Average <3.43E-6 <1.91E-6 <3.86E-7

5. Iodine r_131: Iodine-133 Ratio

!!igh N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 1

,--ee----- . - - - - - - - - - me-

- - , , -_,--,,,,,n,.-----n--

Page 50 PRIMARY COOLANT CHEMISTRY (Continued)

JULY 1988 Parameter Unit 1 Unit 2 Unit 3 ,

6. Chloride (ppb)

High <10 <10 <10 Low <10 <10 <10 Average <10 <10 <10

7. pH925 0C High 6.2 6.2 6.2 Low 5.8 5.9 5.9 Average 6.0 6.0 6.1

8. Conductivity (pmho/cm@25 00)

High 0.35 0.85 0.20 Low 0.087 0.67 0.098 Average 0.25 0.77 0.14 f

T I l

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4

-*----r- -,r.,

Page 51 Environmental Technical Specification Requirements The ambient upstream river temperature (24-hour average maximum) averaged 83.5 *F ranging from 80.4 *F on July 6 to 85.8 *F on July 31. The downstream temperature varied between 80.2 *F on July 6 to 85.9 'F on July 18. The maximum river temperature rise was 0.8 *F on July 18.

The sedimentation pond remained out of service for the entire month.

Preparation of an engineering design package for submittal to the Alabama Department of Environmental Management (ADEM) was initiated.

The sewage lagoon discharged from July 21 to July 27. The discharge was discontinued on July 27 because of excavation work being performed in the switetyard drainage ditch near the lagoon diucharge pipe.

The plant did not experience any compliance problems during the month.

r 1724n ,

Pags 52 AIRBORNE RELEASES (1)

JULY 1988 SlJNMATION OF All. RELEASES UNIT THIS HONTH A ., . FIfifiIGH AND ACTIt>A TION GASES

1. T O T Al. R Kl. E A S E. CI < 1.59E 02

2. At/ERADE RELEAfiE RATE FOR PERIOD UCI/SEC < 6.59E 01

3. PERCENT OF TECH. SPEC. l. IMI1 (0.1:i CI/SEC)  % 0 00E-01 B. IUDINGS

1. TO1 Al. 10 DINE - 131 CI < 6.47E- 04

2. At/ERADE RELEASE RATE FOR PERT 0D UCI/SEC < 2.60E-04

3. PERCEH1 0F TECH. SPEC. l.IMIT(2.19 UCI/SEC)  % 0.00E-01 <

C. PARTICULATES

1. PARTICUL ATES W1TH HALF-LIF ES > OR = 00 8 DAYS C.1 1 56E-04

2. AI)ERADE RElFASE RAIE FOR PERICD I!CI/SEC 6. 4!'E-05

3. PERCEH1 0F TECH. SPEC, LIMITi2.19 UC1/SEC)  % 2.95E-03 .

t

4. GROSS ALPflA Rt;DIOAC rit)ITY CI 4.4YE-06 D, TRITIUM

1. TOTAL. REl. EASE CI 1.13E-01 ,

2. At/ERAGE RELEAfiE RA TE FOR PERIOD tlCI/SEC 4.67E-02 r

3. PERCENT OF TECH. SPEC. L.IMI1 (2.19 IJCI/SEC)  % 2.13E 00

4. GROUND LEVEL RELEASE CI 1.13E-01

5. ELEVATED RELEA!:E CI < 4.63E-04

! (1) REPORTIHO PERIOD 2H DAYS i

'., --.-n - . , , . - - -

> Paga 53 9' AIRBORNE RELEASES (CONTINUED)

JULY 1988 El.L*.t>A TED REL. EASES A. F]SSIDH GAGES . UNIT THIS HONTH '

KR- 8SM CI .< 8 15E-02 KR-85 CI < 3.62E 01 KR CI < 2.08E-01 KR-88 CI < 3.63E-01 X E'- 133 CI < 2.07E-01 XE-135M CI < 3.25E-01 X E- - 13 5 CI < 8.39E-02 XE-138 CI < 4.15E-01 r 0THERS(SPECIFY)  ;

TOTAL FOR PERIult

- - - - - - - - - - - - - - - - CI < 3.79E 01 ,

l B.

10 DINES CI r 1 131 < 1.40E-06 I 133 CI < 4.79E-05 I-135 CI < 7.20E-02 TO TAL, FOR PERIUlt CI < 7.00E-02 9

Page 54 AIRBURNE RELEASES (CONTINtJED)

Jul.Y 1988

' El.E W)T EI) ItEl. EASES C. P ARTICltl. ATES UNIT THIS HONTH SR-SV CI < 2.64E-07

.SR-90 CI < 1.33E-07 CS -134 CI < 3.80E-06 CS'-137 CI < 1.52E-06 BA-140 CI < 8.94E-06 LA-140 CI < 1.65E OTHERS(SPECIFY)

TOTAL FOR PERIOD CI < 1.63E-05 h.

D. TRITItJM CI < 4,63E-04 s

1 4

e I

4

Pag @ 55 AIRBORNE REl. EASES (CONTINUED)

JULY 198C

. GROUND REl. EASES Ao' FISSION GASES UNIT THIS HONTH KR-05M CI < 2 97E-01 KR-85 CI < 1.17E 02 KR-87 CI < 4 84E-01 KR-88 CI < 1.02E 00 XE-133 CI < 7 57E-01 XE-135M CI < 4.90E-01 XE-135 CI < 1.57E-01 XE-138 CI < 1.55E 00 OTHERS(SPECIFY)

TOTAL. F OR PERIOD

--~~~~~---------

CI < 1 21E 02 B. IOl3XHES 3-13J CI < 6 46E-04 I-133 CI < 7.81E-03 I - 13tt CI < 2.29E 02 701'Al. FOR PCRIOD CI < 2.29E 02 4

~ . - . . _ .

Page 56

~

AIRBURNE RELEASES (CONTINUED)

JULY 1988 GROUND'REl. EASES

.C. PARTICULATES UNIT THIS MONTH J

SR-UY CI <.1.84E-04 SR-90 CI < 3.81E-05 CS-134 CI < 3.34E-04 CS-137 CI < 2.59E-04 BA-140 CI < 1 35E-03 LA-140 CI < 3.39E-04 OTHERS(SPECIFY)

CO 60 CI 1.56E-04 TurAL FOR PERIOD CI 1.s6E_04  ;

l D. TRITIUM CI 1.13E-01 l I

{ ,

d

! )

l l

I i

l l

l

Pags 57 BROWHS FERRY NitCLEAR Pl. ANT MONTHl.Y REPORT CALCULATIONS LIOLIID RELE ASES JULY 1988 RADIDACTIVE LIQUID EFFLUENTS 1, GROSS RAD 10 ACTIVITY UNITS a) TOTAL. RELEASE CURIES 3.98E-02 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/HL 3.00E-09 c) PERCENT OF APPLICABLE l.1 HIT ( 1E-7 UCI/HL )  % 3.00E 00

2. IRITIUM a) TOTAL REl. EASE CURIES 1.66E-01 b) AVERAGE Dil.UTED CONCEHrRATION RELEASED UCI/NL 1.25E-08 c1 PERCENT OF APPLICABLE LIMIT (3E-03 tlCI/HL)  % 4.17E-04 (1)

3. DISSOLVED HUDL.E GAGES a) 101 Al. REL.E ASE CURIES < 1.15E-03 I b) AVERAGE DIt.llfED CONCCHTRATION RELEASED UCI/HL < 8.64E-11 c) PEACENT OF APPLICABLE I.IHIT (2E-04 UCI/HL)  % < 4.320-0" i 4. GROSil Al.PHA RADIDACTIVITY a) TOTAL REl. EASE CURIES <2.95E-04 ,

b) AVERAGE DIt.UrED CONCEHrRATION HEl. EASED UCI/HL <2.22E-11

5. VOLUME OF LIOUID WASTE TO DISCHARGE CANAL LITERS 3.95E 06

6. VOLUME OF DILUTIDN WATER LITERS 1 33E 10 (1) INCLUDES XE-133: XE-233, AND OTHERS

Pegs 58 BROWHS FERRY N(ICL. EAR Pl. ANT t MONTHLY REPORT C/.l.CUL.ATIONS L10tlID RELEASES Jul.Y 1988 IG0f0 PES RELEASED tlHITS CI

- CR-51 < 3.18E-03 HN-Si 2.50E-05 CO-58 < 3 43E-04 FE-59 < 6.83E-04 C0-60 S.71E-03 ZN-65 8 91E-04 N8-95 < 3.13E-04 ZR-95 < 6.380-04 NOIC-99H < 2.73E-04 I-133 < 4.22F-04 XE-133 < 9.17E-04 I CS-334 6.56E-03 XE-135 < 2.01E-04 ,

CS-137 2.65E-02 BA-140 < 1.59E-03 LA-140 < 1.90E-04 ,

CE-141 < 4./8E-04 SR-89 < 8.33E-05 ,

SR-90 < 3.37E-05 I

, I 1

h t

Pega 59 1

BROWNS FERRY NUCLEAR PLANT '

H0HTHLY REPORT CALCULATIONS LIutJID RELEASES JULY 1988 j l

OTHERS UNITS -

CI .

FE-55 < 9.60E-04 SB 125 1.90E-04 l'

Pagt 60 BROWNS FERRY NtlCLEAR PLANT HONTHLY REPORT r.ALCULATIONS LIUtlID RELEA'1ES JULY 1988 L AUHl.1RY DRAIN VOL.tJNE RELCASEDi 0.0 0ALLONS FLOOR DRAIN VOLUME REl. EASED! 975614.9 GALLONS WAHTE SANPt.E RANK 90LtlME REl. EASED 67841.7 GALLONS DISTIl. LATE TANK VOLUME REl.EASEDt 00 0ALLONS LOCA TION O THER THAN RADWAS TE VOL.tlNE RELEASED: 0.0 GALLONS T01Al. VOL.llHE RELEASED TO THE RIVER! 1043456 6 GALLONS HIGHEST HATCH ACTIVITY RELEASED FOR N0HTH: 8.39E-09 UCI/NL A/D LONGEST RELEASE TIME FOR HONTH1 310 MINUTES SHORTEST RELEASE TIME FOR MONTH: 143 MINUTES T O'.' A L TIME OF REL. EASES FOR MONTH! 8773 HINUTES AVERADE TIME FOR BATCH RELEASES! 244 HINUTES NUMBER OF NATCHES RELEASEDI 36 NUMBER OF ADMINIS/RATIVC LIMIT VInt.ATIONS: 0 NUMBER OF TFCHNICAL. SPECIFICATION VIOLATIONS! 0

Pags 61 l

RESIN USAGE REPORT ,

1 JULY 1988 RESIN CONSUMED (CU.FT.)

% of Total Bead POWTEX ECODRX ECOSORB EPIFLOC Total l

)

Radweste .

I Floor Drain Filter 45.8 0 87 0 0 150 237 Waste Demineralizer 24.1 125 0 0 0 0 125 Waste Filter 25.1 0 72 0- 0 58 130 Fuel Pool Demins 2.3 0 12 0 0 0 12 Reactor Water Cleanup Unit 1 0.4 0 2 0 0 0 2 0 0 0 0 0 0 Unit 2 0 0.4 0  ? O O O 2 Unit 3 Cond. Demins 0 0 0 0 0 Unit 1 0 0 1.9 0 10 0 0 0 10 Unit 2 0 0 0 0 0 0 Unit 3 0 100 125 185 0 0 208 518 Totals 1

(

l l

1124n t.

c Pags 62 FUEL CLADDING INTPGRITY PARAMETERS JULY 1988 Unit 1 Reactor Water Iodines {uci/sec.)

Date I-131 I-132 T-133 I-134 T-135_

Unit in Outage Fission Gases at Discharge of SJAE (uci/sec)

Date Flow MWt Xe-138 Kr-87 Er-88 Kr-85m Xe-135 Xe-103 Unit in Outage Unit __2 Reactor Water Iodines (uci/sec.)

Data I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Cases at Discharge of SJAE (uci/sec)

Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85m Ke-13.5, Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (uci/sec.)

Date I-131 I-132_ I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uci/sec)

Date Flow MWt Ke-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 1

Unit in Outage r

. - - - =+

e. - c -. n_ - , -,_..n. ,

y

WASTE TREATHENT SYSTEM THROUGHPUTS -

JULY 1988 FLOOR FLOOR FLOOR R 3.15E __@

DRAIN DRAIN DRAIN ,pg. 3,1,g, GAe 9.7 a+05 COLLECTOR FILTER SAMPLE GAU 9.76E+05 TANK TANK I (a AFT: 237.00 e' 9.76E+05 GPD: 0.00E+00 if I f LAUNDRY GAC 0.00E+00 R 0.00E+00 DRAIN 3

,,g ,,,,g ,3 CANAL _

, ,,3ggy, TANK R 3.37E+04 Gau B.0 x +c5

• 1 0*+08 ECYCLED WATER R 1.22E+04 GAU 3.79E+05 iL

'f UI f WASTE WASTE WASTE WASTE R 2.19E+EJ COLLECTOR

• SAMPLE FILTER DEMINERALIZER 8C 8 7Edd TANK TANK (1) CIFT: 130.00 (3) CUFT: 125.00 y

gab 1.18E+06 (1) Curt Poucet 72.00 .Curi EsIN s FIBER NMU4E: 58.00 .0FT U:DSWB: 0.00

2. M CONDENSATE (a QFT POCOC 87.00 ,CIFT ESIN E FIBER MIXTUE: 150.00 .C1FT ECOS0Rit 0.00 '

7. STORAGE D) BEAD ESIN TANK L

, i Pago 64 TESTING

SUMMARY

JULY 1988 Surveillance Testing Unit 0 A total of 149 surveillance tests were completed per 41 different test -

instructions.

Unit 1 A total of 79 surveillance tests were completed on unit 1 per 27 different test instructions.

Unit 2 A toEa1 of 86 survelliance tests were completed on unit 2 per 38 different test instructions.

Unit 3 A total of 78 survelliance tests were completed on unit 3 per 29 different test instructions.

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i Pags 65  !

TESTING

SUMMARY

(Continued)

JULY 1988 l

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Chantes. Test, and Experiments Requirina Authorization From the NRC Pursuant to 10 CFR 50,59(a)

I There were no revisions for unit 1, 2. and 3 technical specifications.

Changes. Tests, and Experiments not Requiring Authorizat ion f rom NRC Pursuant to 10 CFR 50.59(a)

There were no special tests completed for this month.

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REACTOR VESSEL FATIGUE USAGE EVALUATION i

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. JULY 1988 i i i

The cumulacive usage factore for the reactor vessel are as follows:

Usaxe Factor Location Unit 1 Unit 2 Unit 3 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 I

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Pags 67 CHANGE IN PROCEDURE JULY 1988 There were 467 revisions to plant instructions during the month; 466 instructions were changed primarily for correction, and one revision related to safe operaticn of the plant.

PLANT INSTRUCTION REVISIONS JULY 1988 Category Instruction Reason for Request Change in 0-SI-4.7.B.6 Standby Implement response to NRC Inspection Response to Gas Treatment System - Report 88-05 by adding ASTM D LER, IE Iodino Removal 3803-79 test conditions to Bulletin, NRC Efficiency procedure.

Inspection Report, OPQA

Pag 3 68 CHANGE IN FACILITY DESIGN JULY 1988 Package Number Description Safety Related ECN P0684 (WP 2114-84) Fabricated and replaced hinge Primary Containment arm, hinge pin, and bushings for the Unit 2 drywell/ torus vacuum breaker valves.

Installed lower and upper limit switches.

Fabricated and installed pull boxes, solenoid valves, air lines, and stainless steel flex conduit; spliced electrical cables and added new air operated valves HCV-64-28A through 28M. The ECN has now been completed for units 2 and 3. Work is remaining on unit 1.

The normal operation, function, and qualifications o the r

torus vacuum breaker valves were not adversely affected by the modifications. Therefore, the margin of safety was not reduced.

ECNs P0361, P2095 (WP 2059-84) Modified hangers for core spray, Core Spray System loop II piping. A very small portion of the Unit 2 work covered by the ECNs was completed.

ECN P0511 (WP 2032-84) Replaced the reactor building Emergency Lighting emergency lighting transformer and relocated Unit 2 the transformer from elevation 608.3' to elevation 593'. The ECN was completed for unit 2.

The transformer was replaced due to discontinuance of the older model. The new transformer has the same capability and performs the same function as the old transformer. No Tec. Spec. addresses emergency lighting. The change did not affect to margin of safety for any Tech.

Spec.

ECN P0289 (WP 2137-88) Removed dresser couplings on EECW System 18-inch pump "D" discharge line in 3B/3D common tunnel and replaced with pipe. Only a portion of the work covered by the ECN was completed.

Pags 69 CHANGE IN FACILITY DESISN (Continued)

JULY 1988 Package Number _ Description Safety Related ECN P0289 (WP 2164-88) Removed six each dresser RHR Service Water couplings from the RHR5W lines in 2B/2D Unit 2 tunnel and replaced with pipe.

ECN P0289 (WP 2163-88) Romoved six each dresser RHR Service Water couplings from the RHRSW lines in 2A/2C Unit 2 tunnel and replaced with pipe. The ECN was not ecmpleted.

ECN P0289 (WP 2093-87) Installed bolt anchors in Hain Steam Tunnel steam tunnel, elevation 565. The ECW Unit 2 was not completed.

ECN P0289 (WP 3016-88) Removed two each RHRSW dresse.

RHRSW System couplings and installed weld neck flangv8 Unit 3 blind flanges, and vent valve assemblies. 3A and 3C RHRSW tunnels. The ECN was not completed.

ECN P0289 (WP 3031-88) Removed two each 16-inch RHRSW RHRSW System dresser couplings and installed weld neck tinit 3 flanges, blind flanges, and vent valve assemblies, 3B/3D RHRSW tunnels.

DCN B00031 (WP 2080-88, Unit 2) Fabricated and installed '

HVAC System flexible connections on existing ductwork for C and D 250V shutdown battery room exhaust, Units 2 and 3 inlet, and discharge sides of exhaust fan 2A and the discharge side of 2B, (bP 3002-88, Unit 3) Fabricated and installed flexible connectors between existing ductwork and main control room air handling units 3A and 3B. The DCN was completed for units 2 and 3.

1. l The flexible connections did not adversely affect the function of the plant HVAC system and improved its reliability. The modification ensures that the HVAC system'a safety functions will be performed and no other safety related systems were affected.

' Therefore, the marsin of safety was not ,

reduced.

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1 CHANGE IN FACILITY DESIGN (Continued)

JULY 1988 Package Number Description ,

Safety Related ECN P7039 (WP 2076-88) Removed existing transformer 4KV/480 Shutdown Transformers TS2A. The new transformer, TS2A, was Unit 2 installed by workplan 2077-88.

(WP 2155-88) Performed functional test on TS2A transformer. All work covered by the ECN has not been completed.

DCN H0587A (WP 2249-88) Replaces cables 2RP133-02, CRD/RPS Systems 2RP357-GJ. and 2RP358-G2 in conduit Unit 2 2RP507-02 End spliced back to original cables in junction boxes, JB 1220 and JB 2563. The DCN was totally completed as it only covered unit 2.

The replacement of the damaged section of the cables with new cables of equal or better qualifications and specifications did not reduce the margin of safety.

ECN P0623 (WP 2103-88) The work plan was written for Various Systems docamentation only. Drawings were Unit 2 as-constructed for work that was previously implemented and drawings were omitted from the work plans. The ECN has been completed -

for unit 2 only.

The ECN replaced GE multipoint recorders which were no longer manuf actured for various systems. However, the replacement recorders are as good or better than the orginals.

Based on this, the margin of safety was not reduced.

DCN P00096A (WP 3063-88) Replaced transformer TS3B with #

480V Shutdown Board the one in use as TS2A. (TS2A is being Unit 3 replaced by ECN P7039.) The DCN was totally completed as it only covered unit 3.

The modification will maintain and/or decrease the probability of malfunction of transformer TS3B, 480V shutdown board 3B and its loads. The modification did not change l or alter the function or operation of any safety related systems. l

Pags 71 CRANGE IN FACILITY DESIGN (Continued)

JULY 1988 Packaxe Number Description Safety Related ECN P5269 (WP 2292-88) Installed new 1-inch condensate Dem. Water domineralized water line supports, Unit 2 unit 2 reactor building, elevation S19' to 577'9".

(WP 2293-87) This work plan only covered the removal of 4-inch DW line and supports from the reactor building into condensate tunnel.

Also, installed blank flange on 4-inch line and sealed penetration. The ECN was not completed.

ECN PS251 (WP 2261-87) Replaced RCIC cables 2ES1278-I RCIC/HPCI Systems and 2ES1279-I with WVA-1 type cable and the Unit 2 associated flexible conduit. All the field work was completed on unit 2 only.

The replacement cables meet the necessary design requirements without limiting the operability or testability of either system.

Therefore, the margin of safety was not reduced.

DCN B00013 B & C (WP 2271-87) Rensved 11 thermowells in the RBCCW/ Reactor Recire. System RBCCW system and replaced with a new design. '

Unit 2 (Outside of drywell, unit 2 reactor building.)

(WP 2010-88) Removed 10 thermowells in the RBCCW system and 4 temperature element inserts in the reactor recirculation system and replaced with new design. The DCN was completed as it only covered unit 2.

The replacement thermowells are of better quality (per new design detail and #

calculation) than the original installation.

The modification did not change the system's

! function. Therefore, the margin of safety was not reduced.

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Pags 72 CHANGE IN FACILITY DESIGN (Continued)

JULY 1988 Package Number Description Safety Related ,

ECW P3205 (WP 2200-87) Installed 10 supports for the Containment Inerting System H3 0, sampling system, unit 2 reactor Unit 2 building, elevation 519'0". The ECN was not completed.

ECN P0859 (WP 2207-87) Installed pipe supports per RWSPD ECN P0859, unit 2 drywell. A very small Unit 2 portion of the work covered by the ECN was completed.

DCNs P00091B, P00092B, P00093B (WP 1056-88) Replaced 1-FI-23-36, 42, 48 RHRSW System and 54 with new indicators w'th range of Units 1, 2, and 3 0-6000 spm.

(WP 2333-88) Replaced 2-FI-23-36, 42, 48, and 54 with new indicators with range of 0-6000 gpm.

(WP 3070-88) Replaced 3-FI-23-36, 42, 48, and 54 with new indicators with range of 0-6000 gpm. All field work covered by the DCNs was completed on all three units.

The modification was required to enable the RHRSW system to meet the requirements of Tech. Spec. Section 4.5.C.1.b. .

DCNs B00040A, B00041A (WP 1003-88) Provided additional ventilation Standby Diesel Generators for the diesel generator control cabinets.

Units 1, 2, and 3 units 1 and 2.

(WP 3007-88) Provided additional ventilation for the diesel generator control cabinets in unit 3. The DCNs were fully implemented.

The modification added louvers and deflectors #

to the diesel generator electrical control cabinets. It improved performance by reducing the ambient temperature inside the cabinet without impacting the function of this or any other system. Based on this, the margin of safety was not reduced.

Pags 73 CHANGE IN FACILITY DESIGN (Continued)

JULY 1988 ,

Package Number Description Safety Related ECW P0289 (WP 1015-88) Removed two dresser couplings RHRSW System from the RHRSW lines and installed weld neck Unit 1 flanges with blinds, plus vent valve assemblies (IA and 1C RHRSW tunnels). Only a portion of the work covered by the ECN was completed.

ECN P5322 (WP 0051-88) The workplan was writtea for HVAC System documentation only to as-constructed drawings Common to show actual plant configuration for work that was implemented by TACF 0-84-92-31. The ECN was completed.

The change documented the modification of the connecting rods that attach dampers to the actuators (FCO-31-151 and FCO-31-152) pertaining to 12" X 8" vertical ducts. Both the connecting rods were threaded so lock nuts could be placed on each side of the damper control swivels. The locknuts prevent <

the rods connecting the dampers to the actuators from detaching. The modification did not alter the function of the actuators or the dampers. Therefore, the margin of safety was not reduced. .

ECN P3205 (WP 2158-87) Replace the H, sample Containment Inerting System lines from panel 25-341 to the drywell and Unit 2 to rus . A very small portion of the work covered by the ECN was completed.

ECN P0859 (WP 2142-87) Inspected, modified, and CRD System documented CRDH piping supports between I Unit 2 asimuths of 68* and 112' at various elevations below floor elevation 584'-11" #

inside the drywell. The ECN was only partially completed.

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Pcg2 74 CHANCE 'IN FACILITY DESIGN (Continued)

JULY 1988 Package Number Description Safety Related ECM p5291 (WPs 2232-86, 2153-87, 2154-87) Removed.

Reactor Feedwater System modified, and installed RPV sensing line Unit 2 pipe supports inside the drywell to penetrations X-28A, X-288, X-29A, and X-298.

The ECN was fully implemented as it only covered unit 2.

Repairs were made to ensure seismic qualification of the instrument lines.

Drawings were updated to show the as-constructed configuration of the plant.

Tech. Specs. were not affected. Therefore, the margin of safety was not reduced.

Pcge 75 CHANGE IN FACILITY DESIGN (Continued)

JULY 1988 Package Number Description Non-Safety Related ECW P5050 (WP 0022-84) Replaced the yard lighting photo security Yard Lighting cell with time delay photo cell (480V yard Common distribution cabinet). The ECN was completed.

ECW P0748 (WP 0083-84) Constructed exterior wood Training Services Modules decking for the Training Service modules. The Common ECN was not completed by this workp.an.

ECN P0634 (WPs 1041-88, 2273-88) Drilled '.wo holes in Process Computer System Operator's front console for communication Units 1 and 2 wiring. A very small portion of the work covered by the ECN was completed.

DCNs WO106A, WO107A, WO108A (WPs 1023-88, 2201-88, 3023-88) Installed Auxiliary Boiler System blind flanges and fabricated spare pool Units 1, 2, and 3 for deaeration steam lines. The DCNs were completed.

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Pegs 76 CHANCES IN PLANT ORGANIZATION JULY 1988 There was one change in plant staff for those positions designated as key supsrvisory positions. Charles E. Kent. Jr., Supervisor of Site Radiological

- Control. Radiological Protection.

P:g2 77 ACCIDENTS JULY 1988 There were two loss-of-time accidents during the month.

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