ML20151D329

Monthly Operating Repts for June 1988 for Browns Ferry Units 1,2 & 3

ML20151D329
Person / Time
Site:	Browns Ferry
Issue date:	06/30/1988
From:	Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20151D324	List: ML20151D322 ML20151D329 ML20151D333 ML20151D336
References
NUDOCS 8807250065
Download: ML20151D329 (93)

Text

F, R.9.0 880714

.8.0.2 o-MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY JUNE 1988 "Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Su imitted by ohn G. Walker Plant Manager kOOCk$$000339 PDC

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'A 4.

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..........................................

7 F.

Offsite Dose Calculation Manual Changes.........................

11 G.

R a d wa s t e S umma ry................................................ 12 1.

Total volume of solid waste shipped off site 2.

Nature of the waste (trash, resins. etc.)

3.

Grose curie activity 4.

Dates the material was shipped and the disposal facility to which the material was shipped.

5.

Estimated quantitles 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.......................................

19 2.

Average Daily Power Level...................................

22 3.

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

25 B.

TVA Reports 1.

Plant Operating Statistics..................................

28 2.

Unit Outage and Availability Data...........................

29 3.

Reactor Histogram (Reactor Power Percent)...................

32

. zy s

TABLE OF CONTENTS (Continued)

Part'III MAINTENANCE

SUMMARY

A.

Electrical Maintenanc3......................................... 33 B.

I n s t rume n t Ma in t e n an c e........................................... 3 8 C.

Mechanical Maintenance...........................................

40 D.

Running Maintenance............................................

. 44 E.

Modifiestions....................................................

45 PART IV OTHER REPORTS A.

Chemistry Summary 1.

Primary Coolant Chemistry.......................,......... 51 2.

Environmental Technical Specification Requirements.......... 54 3.

Ai rbo rne Re le a s e s..........,............................... 5 5 4.

Liquid Heleases............................................. 60 5.

Resin Usage Report....................................

..... 44 6.

Fuel Cladding Integrity Parmeters....................

......,65 7.

Waste Treatment System Throughputs..........................

66 B.

Testing Summary.................................................. 67 C.

Reactor Vessel Fatigue Usage Evaluation..........................

69 D.

Change in Procedures.............................................

70 E.

Plant Ins t ruc t ion Revis ions..................................... 70 F.

Change in Facility Design (ECNs).................................

71 G.

Change in Plant Organization..................................... 85 H.

Accidents........................................................ 86 Addenda Revisions to April and May 1988 i

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t Pags 1 SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

JUNE 1988 Unit 1 06/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 6 refueling and modifications continue.

06/30/88 2400 Unit remains on administrative hold to resolve various TVA and ERC concerns. Cycle 6 refueling and modifications continue.

Unit 2 06/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

Cycle 5 refueling and modifications continue.

06/30/88 2400 6.'.lc remains on administrative hold to resolve various TVA and NRC concerns.

Cycle 5 refueling and modifications continues.

Unit 3 06/C1/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

Environmental qualification work and nodifications continue.

06/30/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

Environmental qualification work and modifications continue.

Pcgs 2 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

JUNE 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 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 nodifications (NUREG 0737), RPS voltage monitoring modifications H0 sample line modification (LER 81050), and EECW carbon to stainless 27 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 f:tel pool is 1355 locations.

7--

Pago 3 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONT.)

JUNE 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 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), containment instrumer.tation modification (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reductions 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/G 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 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies 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.

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Paga 4,

FUEL PERFORMANCE AND' SPENT FUEL STORAGE CAPABILITIES

SUMMARY

'(CONT.)

\\:

JUNE 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 (10CFRSO 49), 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 (R"REG 0737), addition of redundant drywell control air supply, RPS voltage monitoring modification H 0 sample line 22 modification (LER 81050), replacement of jet pump holddown beam assemblies (IEB 80-07), EECW carbon to stainless pipe change out, and plant design i

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 f

the fuel pool is 585 locations.

All high density racks (HDR) have been installed in the pool with the exception of six.

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r Pega 5 4

MSRVs (MAIN STEAM RELIEF VAi,VE)

SUMMARY

JUNE 1988 No MSRVs were challenged during the month.

l

5 Page 6' Ae ISSUANCE OF SPECIAL REPORTS JUNE 1988 The following special report is notice of violation issued for the month of June 1988.

88-10-04 Administrative proceduce FMP 0602.01 was found to be inadequate in'that it lacked any requirement or guidance on the use of tentative or draft information in preparation of licensee's submittal of draft information-for NRC review on March 23, 1988. The licensee's calculations used to evaluate the effects of a pustulated fuel drop accident did not receive full independent verification nor approval for issuance until two days after issuance of the submittal.

This is a Severity Level IV Violation (Supplement I) and is applicable to all three units.

s pags 7 LICENSE EVENT REPORT (s)

June 1988 Description of Event s

LER E

1-88-015 Failure to Monitor Of f-Gas Stack Effluents Due To procedural Inadequacy and personnel Error on May 8, 1988, at 1856 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.06208e-4 months <br />, with all three units dafueled, chemistry laboratory personnel discovered that the power was off to the off-gas stack lighting which provided power to the radioactive gaseous stack effluent temporary monitoring system.

The power was lost from 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> to 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br /> on May 8, 1988, due to the performance of Special Tast 88-17, Diesel Generator B Emergency Load Acceptance Test. The normal off-gas stack radiation monitors had been declared inoperable prior to this event sud temporary continuous monitoring had been established under surveillance Instruction (SI) 4.8.B.1.a.2, effluent releace rate by manual sampling - unit O.

This procedure did not comply with the requirement for temporary alterations to.have a system status change documented in the shift operations supervisor's office while the temporary condition is established.

During the loss of power at the stack the 4-hour sample flow check, required by the plant's technical specifications was missed.. The failure to perform the sample flow check has been attributed to personnel error. This combination of the procedural deficiencies of SI 4.8.B.1.a.2 and the personnel error caused the unmonitored flow of radioactive gaseous stack effluents for S hours and 21 minutes.

The immediate corrective action was to restore power to the off-gas stack lighting. This action restored ths continuous monitoring of the effluent releases th ough the stack. Also, compensatory sampling and sample flow checks were resumed at 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br />.

SI 4.8.B.1.a.2 will be revised to correct deficiencies. The chemical laboratory technician involved in the failure to perform the sample flor check was counselled, i

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Pzgs 8 '

Description of Event (Continued) 2-88-001 Unolanned Diesel Generator Start Due To Insulating Boot Falling Off Logic Relay Contact Arm On May 10, 1988, at 1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br />, with all three units defueled, the 3A diesel generator started due to an inadvertent start signal.

The start signal was generated during a logic functional test of the unit 2 core spray system when a rubber insulating boot fell off of a relay contact arm.

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The test was stopped while the cause of the diesel start was being investigated.

The operators verified the start signal was not valid, shutdown the diesel at 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br /> and resumed the test.

l Boots are lightweight flextble electrical insulating material and fit loosely over the contact arms and are allowed random movenent during relay cycling. This movement allowed the boot to work its way off the contact arm.

Experlments were conducted with identical relays l

and boot materit The testing included dif ferent l

boot length and placement on the contact arm and calibration of the relay. The only test condition which allowed the boot to fall off was gross misplacement of the boot at the very top of the contact arm.

This is the first ideatified probler, with these boots during the three years they have been used at Crowns Ferry Nuclear Plant (BFN). Approximately 1500 cf these boots have been used. BFN considers the performance of these boots acceptable and will continue to use them unless a better method is obtained. The maintenance organization is considering other methods of possible improvements.

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<z Pags 9 Description'of Event i

(Continued) s 1

'2-88-002' Trio of Reactor Protection System Bus'2B Ftpfgr.

Breaker Initiates Enmineered Safety Features On May.26, 1988, at 1253 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.767665e-4 months <br />", and again on May 27, IS88, at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, with all three units defueled, the breaker feeding che. unit 2. reactor protection system (RPS) bus '4B tripped doenergizins the bus. This initiated standby gas treatment, control room emergency ve*,tilction and a half l

scram on unit 2.

The un'.t. 2 reactor zone ventilation. isolated, t'ao refueling zone ventilation isolated and isolation signal wr' diven to the unit 2 outboard isolation valves on tna reactor water cleanup, residual heat removal, primary containment ventilation, and traversing incore probe.

Following the first event the breaker was reset and all systems returned to

~

normal.

Following the second event the breaker was replaced with a molded case evitch as part of a previously approved modification. This replacement could be made sin:o circuit protection is proviced by two circuit pr.otectors installed et.rlier as part of the same modification.

A failure evaluation of the breaker and its associated circuitry could not determine the cause of the trips.

2-88-003 R[g) Found in Lower Containment Screv Header Due to Lg.akins Isolation Valves This report is being submitted as informat' only LER.

On January 15, 1988, at 110G hours, water was observed flowing from the lower containment spray header in the unit 2 drywell. At the time the water was discovered the residual heat removal (RHR) system was aligned for a hydrostatic pressure test. When the hesder was drained it was noted that some of the water appeared to have been in the header for quite some time.

It was this apparent long-term presence of water in the containment spray header that prompted the investigations and inspections that revealed two spray nozzles with 20 percent of their sparger holes clogged with rust particles and loose rust in the unit 2 lower containment spray header.

On May 27, 1988, it was determined that the rust in the header had the potential of degrading the containment spray function of the RHR system on unit 2.

Lasking isolation valves and extended outage is the cause of rust in the header, i

Page 10 Description of Event (Continued)

The immediate corrective action was to stop the performance of the hydrostatic pressure test, deorossurize the system, and drain the lower containment spray header. Visual inspections were performed on the units 1, 2, and 3 containment spray headers.

These inspections have identified a 170 degree circumference of the unit 2 lower containment spray header as the only problem area.

The nozzles on the unit 2 lower containment spray header have been removeo and cleaned. The unit 2 lower containment spray header is to be cleaned and isolation valves are to be adjusted or repaired as required to stop leakage into the header. The unit 2 lower containment spray header piping wall thickness is to be measured to ensure adequate pipe integrity.

--___._~.._,.__.____._.._.___m_.

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Pago 11-I i

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ON MANUAL CHANGES JUNE 1988 No changes were inade to the Browns Ferry offsite dose calculation manual

-during the month.

Q Psgs 11 w

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RADWASTE

SUMMARY

JUNE 1988 The radwaste system performed as desi ned.

Approximately 9.48E+05 gallons 5

of waste liquid were discharged containing approximately 2.73E-02 curies of.

activity.

There were two spent resin shipments and four trash shipment during Juno.

All shipments were to Barnwell. SC.

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Pcgo 13

-Solid Radioactive Waste June 1988 Dewatered Spent Resin Shipments '

Volume of condensate / waste resin shipped:

8.21 Cu.M. (288 Cu.Ft.)

Total curies shipped:

s.950 Volume of reactor cleanup resin shipped:

O Cu.M. ( 0 Cu.Ft.)

Total curies shipped:

0 Date Shipped Disposal Facility Tvoe of Resin 06/10/88 Barnwell, SC CWPS 05/14/88 Barnwell, SC CWPS Dry Active Waste Number of drums shipped:

159 Volume:

33.65 Cu.M. (1192.5 Cu.rt )

Total curies shipped:

1.S880 Number of boxes shipped:

15 Volume:

40.81 Cu.M.

(1446.4 Cu.Ft.)

Total curies shipped:

8.2150 Date ShiDDed Disposal Facility Tvoe of Dackace 05/01/88 Barnwell, SC Drums OS/08/88 Barnwell, SC Boxes 06/1S/88 Barnwell, SC D ums 05/03/88 Barnwell. SC 3cael i

I (1) All shipments were by Sole-use Vehicle

Pcge 14, Solid. Radioactive Waste (Continued)

June 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 Montn Compacted Drums 114 7.5Cu.F t. (2 )

225 Cu.Ft.

5.28E-01 600 Cu.Ft.)

I' Boxes 744 Cu.Ft.( '

O Cu.Ft.

7.63E+00 300 Cu.rt.

Uncompacted Drums 45 Cu.Ft.(2)

O Cu.Ft.

1.16E+00 0 Cu.Ft.(*)

Boxes 702.4Cu.Ft.(2) 298 Cu.Ft.

5.85E-01 800 Cu.Ft.C

Resins CWP5 288 Cu.Ft.(1) 840 Cu.Ft.(3) 9.50E-01 450 Cu.Ft.

• 1 RWCU 0 Cu.Ft.C' 115 Cu.Ft.(3) 0.00E+00 35 Cu.Ft.I I TOTALS 2980 Cu.Ft.(

523 Cu.Ft.(4' 1.09E+01 2,200 ru.rt.

Total volume of waste shipped during the month:

2,980 Cu.Ft.

Total volume of waste shipped year-to-date:

13,454 Cu.Ft.

Unused 1988 burial volume atlocation at Barnw?ll:

69.346 Cu.Ft.

(*)

Actual resin volume

'2)

Container burial volume (2)

Estimated volume in separators (4)

Does not include resins l

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ACCIDENTS JUNE 1988 There were no loss-of-time accidents during the month.

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Page 85 1

CHANGES IN PLANT ORGANIZATION JUNE 1988 There was'one change in plant staff for those positions designated.as key supervisory positions, John D.- Glover, Jr., Head, Group, Operations.

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CHANGE IN FACILITY DESIGN (Continued).

June 1988 Description Packaze Number Non-Safety Related (WP 2002-88) Replaced 1" pipe and 1" valve ECN P0032 -

in the drain line from the steam packing

' Off-Gas, System -

exhauster holdup line drain to the off-gas Unit 2 condensate drain sump with a.4" pipe and a 4" valve. The ECN was completed for unit 2.

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Pags 83 CHANCE IN FACILITY DESIGN (Continued)

June 1988

. Package Number Description Non-Safety Related ECN P0905 -

(WP 0012-87) Partial installation of 4" sanitary drain line for the new power stores Permanent Power Stores Facility facility.

Major portion of work covered by the ECN remaining to be impicmented.

Common (WP 009-87) The workplan was written for ECN P0617 -

documentation only to as-construct drawing Barge Docking for the barge docking facilities and the Facility - Common related haul road construction. The physical work had been previously implemented on other workplans. The ECN was completed, ECN P0851 -

(WP 0039-87) Installed evacuation alarm interfaces from the Training Center back to Communications the main plant communication room. A very Common small portion of the work covered by the ECN was completed.

ECN P0061 -

(WP 2158-88) The workplan was written for doturcentation only to as-construct drawings CCW System which were omitted when physical work was Units 1, 2, 3 previously performed on all 3 units. The ECN is totally complete on all 3 units.

ECN PC009 -

(WP 0046-85) The workplan was written for documentation only to as-construct drawings Security -

that were omitted from workplans when Co0 mon physical work was performed on the Plant Access Control Station.

No physical wack was performed by WP 0046-85.

The ECN is not totally completed.

ECN PS256 -

(WP 2130-85) This workplan covered only a Communications -

portion of the work covered by ECN PS256.

New terminal blocks were installed, terminal Common of a new telephone entrance cable in the telephone equipment hut, rerouted various cables and conduits within the hut.

~'

Pags 82 b

CHANGE IN FACILITY DESIGN _ (Continued)

June 1988 Description Package Number Safety Related (WP 2091-85) Replaced radiation recorders FJN P0710 -

2-RR-90-249, ~250, - 251, and -256 with Raciation Monitoring Tigraph 100 recorders. The ECN was System - Unit 2 corcpleted for unit 2 only. The work has not been implemented on units 1 and 3.

The The old recorders were obsolete.

manufacturer no longer supplied spare The replacement recorders utilize parts.

the same electrical power supply and are of equal or better quality. Therefore, the margin of safety was not reduced.

(WP 1216-85) The workplan was written for ECN P5138 -

documentation only to revise drawings and Radiation Monitoring close TACF 1-84-068-90.

The TACF had changed tha power feed for 1-RE-90-251 from panel 9-9 breaker 208 to panel 9-9 breaker 235. The motors in the monitors have been The ECN was changed from 1/3 hp to 1 hp.

completed as it only covered unit 1.

All the existing Safety Ang. lysis remained No new accidents or malfunctions the same.

This modification does not are foreseen.

affect Tech. Specs.

(WP 8539, 8540) Installed emergency lishtins ECH PO479 -

units with an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery power supply.

Emergency Lighting Installed brackets for the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery Units 1, 2, 3 powered emergency lights and installed battery packs in brackets.

The ECN has been completed for all 3 units.

The mounting of the new equipment was seismically qualified. The modification provides additional lighting for safe shutdown of the plant during or after an The change does not affect Tech.

emergency.

Specs.

0682C

p Pago_81 CHANGE _IN_ FACILITY DESIGN _ (Continued)

June 1988 Description Package Number I

Safety Related (WP 2035-85) Installed transmitters ECN P0126 -

PT-3-22AA, BB, C; PT-3-74A & B; PT-68-95 and Various System

-96.

Only a portion of P0126 was Unit 2 completed. The ECN covers many systems and transmitters.

(WP 2100-86) Remove electrical penetration ECN P3180 -

Electrical Penetrations EE.

Unit 2 (WP 2101-86) Installed new electrical penetration EB.

A small portion of the work covered by ECN P3180 was completed.

(WP 2069-86) Installed PT-23-4, Rosemount ECN P0381 -

transmitter.

The ECN was not completed.

1 RHR Service Water System - Unit 2 ECNs P0792, P0795 -

(WP 2120-86) Performed hydro test on modifications performed by ECN P0792 and RHR/Coro Spray Varicus workplans being performed P01905.

i Unit 2 by these ECNs.

Only documentation remaining to complete the ECNc.

(WP 2088-85) Install new stack radiation ECU P0354 -

monitoring equipment in stack monitoring Radiation Monitoring building and terminated all vendor internal System - Unit 2 The ECN was not completed.

cables.

(WP 0052-86) Inspected tnd as-constructed ECNs PS331, PS388, anchortage detail of the battery racks for PS389 - Battery MXs 1 thru 3, unit 1; MXs 1 thru 4 for unit Hacks - Units 1,2,3 2; MKs 8 thru 10 for unit 3.

The ECNs were completed.

The modifications will ensure that the as-constructed battery racks remain seismically qualified and meet the required design conditions. The modification did not affect the function or operation of any equipment.

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

Pags 80 j

CHANGE IN FACILITY DESIGN _ (Continued)

June 1988 Description gackage Number Safety Related These modifications ensure that the various safety-related conduits are seismically supported and conform to the requirements of the Technical Specifications for Class I structures. The modifications did not affect any system's operation and provided added assurance that the systems will operate as required to maintain an adequate margin of safety.

Based on this the margin of safety was not reduced.

ECN-P0360 -

(WP 2027-86) Installed new ring girder stiffner plates inside and outside the Torus Modifications-unit 2 torus. A very small portion of the Unit 2 ECN was accomplished in this workplan.

ECN P5413 --

(WP 0041-86) The workplan was written for documentation only to as-consttv.ct drawings Reactor Protection and lift TACP.

Protective covers were System - Unit 2 installed by TAC 2-S6-015-99 or, the RPS A r

& B se*c utop switches, the RFS A & B MG set voltage sdjustment control, and RPS A & B bus transfer switches. The tempotary modification perfermed by the TACF is now a permanent modification.

The ECP: wa9 totally cor.rplated as it only covered unit 2.

The operation and the design function of the RPS and 250 volt DC power supply and distribution system is not changed or altered. The margin of safety as defined in the basis of the Technical Specifications is not changed.

ECN.P0957 -

(WP 2201-86) Performed 1HS1 treatment on butt welds, unit 2 drywell, elevations 589' Reactor Recirculation 594' (N2 nozzles, safe-ends, and a portion l

System - Unit 2 of the associated recirculation system l

piping)..A small portion of the work

(

covered by the ECN was completed by WP l-2201-86.

l l

l

T' i

Page 79 CHANGE IN FACILITY DESIGN _ (Continued)

June 1983 Description Package Number Safety Related (WP 3019-88) Performed necessary seal ECN P7096 -

modifications to secondary containment

. Secondary Containment pipe penetrations on the unit 3 reactor The ECN was Unit 2 building roof, elevation 717'.

completed.

The new seals are qualified to limit in-leakage and ensure secondary containment Based will remain operable following a DBE.

on this, the margin of safety was not reduced.

(WP 2291-88) Changed the setpoints of the DCN M00074A -

Iow vacuum scram switches to.8 inch HG The DCN Condencate & Dem.

vacuum for PS-2-1A, 1B, 5A, and 8A.

Water System was completed.

Unit 2 Lowering the setpoints allows the plant to operate as described in the Tech. Specs.

8 The scram switches will be re.aoved at a 1 ster outage as Technical Specifications, have been_ changed to reflect that we do not require the low condenser vacuum ceram.

(WP 2168-86) Removed conduit, cable, and ECN L2079 -

junction boxes associated with flow solenoid Containment Inerting valves FSV-76-41A, -41B, 37A & B. -3?A & B.

System - Unit 2

-42A & B, -40A & B, 44A & B, -43A & B, and A very small portion of the work

-39A & B.

covered by the ECN was completed.

(WP 1017-86) Fabricated and installed scismic ECN P0862 -

conduit supports in the unit 1 and 2 control bay, elevation 606.

The ECN was completed.

Various Class 1E Conduits Units 1 & 2

Page 78 CHANGE IN "**ILITY DESIGN (Continued)

June 1988

' Package Number Sascription Safety Related ECN P7080 -

(WP 2113-88) Installed a mechanical stop Control Rod Drive to the 3-ton capacity control rod drive jib crane to precludo swinging a load Jib Crane-into or over panel 25-57.

Tha ECN was Unit 2 totally completed.

The operation and function of the jib crane are unaffected. The mechanical stop was seismically designed and analyzed to ensure that it will not collapse should a celsmic event occur. The margin of safety was not reduced.

ECN P2154 -

(WP 0015-88) Installation and removal of RHRSW supports for "A" pump room at the RHRSW Supports intake pumping station. Only a portion Common of the work covered by the ECN was completed.

ECN.P7106 -

(WP 2184-88) Performed necessary seal becondary Containment modific-ations to see?.tdary containment pipe penetrations on the Unit 2 reactor Unit 2

'aulidang roof, elevation 717' -

0".

The ECN was totally completed.

The acv seals are qualif ted to limit in-leakago and ensure secondary containment will remain operable following a DBE.

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

ECN P7107 -

(WP 2185-88) Performed nocessary seal Secondary containment modifications to secondary containment pipe penetrations on the unit 2 reactor Unit 2 building south wall, elevation 593'.

The ECN was completed.

The new seals are qualified to ilmit in-leakage and ensure secondary containment will remain operable following a DBE.

Based on this, the margin of safety was not

reduced, bi s

w t

Paga 77' CHANGE IN FACILITY DESIGN _ (Continued)

June 1988 Package Number Description Safety Related ECN PS170 -

(WP 3039-88) The workplan was written for documentation only to as-construct drawings RPIS Probe Storage Racks - Unit 3 and remove TACF 3-85-005-303.

The drawings were revised to show the rod positioning indicating system storage rack on elevation 565 in the unit 3 reactor building. The ECN was completed as it only covered unit 3.

The RPIS storage rack has no safety related function.

It is used only to hold spare RPlS probes.

However, the storage rack meets seismic class Il requirements, therefore, the margin of safety was not reduced.

(WPs 0008-88, 0010-88)

Installed capillary EC3 P1083 -

tubing supports in the reactor building and Various Systems tne control bay. Only a portion of the work Common covered by the ECN was completed. Various tubing supports and tube routing remaining to be implemented.

(WP 2060-88) Installed and modiflad capillary tubing supports in U2 drywell, steam tunnel.

(WP 2059-P6) Installed capillary tubing supports in the off-gas stack, tip room, and in the reactor building.

ECN P7136 -

(WP 2182-88) Hodified RHR loop logic systems for RHR pumps 2C and 2D automatic RHR System initiation involving use of existing Unit 2 undervoltage auxiliary relays spare contacts. The ECN was totally completed as it only covered unit 2.

The modification returns the RHR system logic to the intended configuration as described in the FSAR. The modification corrected a deficiency without affecting the intended logic for the RHR system.

Therefore, the margin of safety was not reduced.

Page 76 CHANGE IN FACILITY DESIGN _ (Continued)

June 1988 Description

' Package Number Safety Related The function-of-the system was not changed.

The valves were installed for maintenance reasons and personnel safety.

The mcrgin of safety was not reduced.

(WPs 3021-88, 6161) Set relay /moter (device ECN L9061'-

64) to 3.0MA.

Installed indicating lights Fire Protection bus ground detection circuits fire System - Unit 3 protection junction box 5662.

ECN L9061 was completed for unit 3 only.

ECN L9061 covered major modifications and additions to the fire protection equipment.

The major portion of the work was completed during fire restoration. These minor modifications just completed the ECN on unit 3.

(WP 2054-84) Cut out and removed old valve ECN P0652 -

2-FCV-71-40 and replaced with new Atwood Morrill valve. The ECN was not completed.

RCiC Systera Unit 2 The electrical portion of the ECN was not completed.

(WP 3004-88) Removed concrete block wall ECN P0370 -

in the Technical Support Center.

A very Masonry Walls small portion of the work covered by the ECH Tech. Support Center was completed.

(WP 2115-88) Modified the CRD control air ECN P/045 -

and valves to natisfy the requirements of CRD - Control Air The modifications provide a 10 CFR 50.62.

Unit 2 redundant method of isolating and venting the scram air header and hence, and Alternate Hod Insertion (AR1). The ECN was not completed.

Supports are still being installed.

r; I

Pags 75 a

CHANGE IN FACILITY 'JESICN (Continued)

June 1988 Package Number Description Safety Related ECN P5475 -

(WP 2203-87) Replaced foxboro flow Containment Isolation transmitters FT-64-37 and FT-64-38 with System - Unit 2 appropriate substitute. The replacement transmitters were purchased from the Air Monitor Corporation. The ECN was not fully implemented by this workplan.

ECN P0392 -

(WP 2239-87) Modified existing CRD CRD System cages.

A very small portion of the Unit 2 ECN was completed.

ECN P2054 -

(WP 1034-87) Installed new RBCCW pipe RBCCW System supports, R0089A and R0863, in the unit 1 Unit 'l Reactor Building, elevation 593'.

The SCN was completed as it only covered unit 1.

The modification provided assurance that the system meets the original design requirements for seismic qualification.

Changes made to the system assure conformance to the analyses required by NRC Bulletins 79-02 and ?9-14 ECN P5542 -

(WP 1027-87) Fabricated and installed motor Control Bay HVAC raounting besekets for FCO-31-81 and System - Units 1 & 2 FCO-31-42.

The ECN was totsily completed.

The modification ansured proper damper operation and provided necessary documentation to qualify the motor operations as class lE equipment.

The HVAC seismic design was not affected by the modification.

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

ECN P0646 -

(WP 3006-88) The workplan was written for Diesel Starting documentation only to au-construct drawings Air System to show existing configuration of valves Unit 3 already installed which satisfies the requirements of ECN P0646. The ECN was completro for unit 3.

Units 1 and 2 were previou.y completed, therefore, no work is remainint; for ECN P0646.

Pags 74 CHANGE IN FACILITY DESIGN _ (Continued)

June 1988 Description Package _ No.nber_

Safety Related (WP 2061-88) Replaced damaged position switch ECN P3204 -

to valve 2-FSV-84-8B.

This completed the Containment Atmospheric remaining work for ECN P3204.

Dilution System - Unit 2 The ECN raplaced the internal position switches for the Target Rock solenoid valves 2-FSV-84-8A, B, C, D.

The new switches are environmentally qualified for their environment. The new switches are also class 1 qualified. The function and operation of the switches was not changed, the margin of safety was not reduced.

(WP 2009-88) Modified RHR system ECN P1001 -

pipe anchor at penotration X13B.

A very RHR System small portion of the work covered by the ECN Unit 2 was completed.

(WP 0027-87) Documentation change only as-ECN P5444 -

constructed drawings to conply with existing Buildings and Structures cenditions and provided neans to upgrade coating systems.

The ECN was completed.

Common The_use of approved coating systems will ensuite that no plant feature is adversely Therefore, no margin of safety is affected.

reduced.

(WP 2213-87) Installed, removed, modified R-31, ECN P0361 -

DWTP branch line supports, R-29. R-30 R-32, R-34 R-35, R-36, and R-37.

The work-DWTP Branch Line Supports plan consisted of the inspections, Unit 2 performing of modifications and the documentation of work performed on the The ECN was not completed.

supports.

(WP 2214-87) Performed the same modifications but covered supports R-38 thru R-47.

The ECN was not completed.

Page 73

• l CHANGE IN FACILITY DESIGN (Continued) f June 1988 Package Number Description Safety Related (WP 2122-87) Modified drywell supports on the RBCCW system in the unit 2 drywell, elevation 549'-0" to 584'-0".

(WP 2272-87) Performed misc. steel weld inspections and cepairs on RBCCW system, unit 2, reactor building.

ECN P3205 -

(WP 2201-87) Installed 8 supports for Containment Inerting the H 02 2 sample system in the unit System - Unit 2 2 reactor building, elevation 565'-0" between R8-R10 and S-T column lines.

The ECN was not completed.

(WP 2202-87) Installed 8 supports in the reactor building, elevation 519'-0" between R and Ril column line.

ECN P0913 -

(WP 1023-86) lieplaced/added fuseblocks 480V Shutdown in the 480V shutde.wn board 18.

Only

. Board - Unit 1 a small portion of the work covered by the ECN was completed.

ECN P5434

('iP ?l86-87) Perfctmed modifications Suppression Chamber to suppression chamber narrow range Narrow: Range Water water level inctrumentation (piping Level Instrument Lnd rotameter mounting only) for LT-Systems 64 and 73 -

64-54.

Only a portion of the ECN was Unit L completed.

(WP 2187-87) Performed the same modifications for LT-64-66.

(WP 2189-87) Installed pipe supports, torus; Bays 7 and 8 on system 64 and 73.

(WP 2190-87) Installed pipe supports for system 64, unit 2 reactor building, Bay 11, elevation 524'- 0".

Page 72 CHANGE IN FACILITY DESIGN (Continued)

June 1988 Package Nuiaber Description Safety Related L

The FCN has been fully implemented as l

previous work had already been completed.

The ELN only covered unit 2.

HVAC supports which were determined to be inadequate were modified.

The supports were upgraded to a condition which ensures the HVAC will perform its intended function.

Because the ECN documented the as-constructed condition of the duct supports and repaired the deficient items, the margin of_saf.ety was not reduced.

ECN P0956 -

(WP 2155-87) Fabricated and installed HVAC System duct work for HVAC equipment in the Unit 2 SDBR 2D, elevation 593; Control Bay, unit 2.

Only a portion of the ECN was completed.

(WP 2258-87) Removal and reinstallation of SDBR 2C KVAC intruder barriers, unit 2 re&ctor building, elevation 621'.

DCN P0068A -

(WP 2248-88) changed the serias trip Unit Preferred device on breakers 7D of 480V shutdown 120V AC - Unit 2 board 7A from GE type EC-2A, characteristic 1B3 to GE type EC-2A characteristi: 1A3.

The DCN was completed.

The modification reduced tha. possibility of a spurious trip of the circuit breaker in the 480V shutdown board 2A and provided the increased time needed by the AC drive motor of the unit preferred AC MG set to obtain its operating speed and normal running current.

The margin of safety was not reduced.

ECN P0959 -

(WP 2121-87) Installed block test and RBCCW System vent valves to allow local leak rate Unit 2 testing of FCV-70-47 and 70-506.

Only a portion of the work covered by the ECN was completed.

~

Pags-71' CHANCE IN FACILITY DESIGN June 1988 Package Number Description Safety Related ECN P3205 -

(WP 2199-87) Installed 8 supports for Containment Inerting the H 02 2 sampling system, top of System - Unit 2 unit 2 torus.

A very small portion of the work covered by the ECN was completed.

ECN P0361 -

(WP 2176-87) Reinspected existing welds Misc. Steel Support and existing mise. steel (pipe Framing -- Unit 2 supports and anchors) in the unit 2 reactor building, elevations 565' and 541'.

Minor modifications were performed on and as-needed-basis. A very small portion of ECN P0361 was completed.

ECN P0922 -

(WP 0013-87) Replaced the carrier 500KV. Transmission relaying terminals on the Davidson Line.- Common 500KV line with cross-blocking relays. The relays were replaced in conjunction with the construction of 'the Maury, Tennessec 500KV substation.

The Browns Ferry-Davidson 500KV transmission line was looped into the Maury substetion. The ECN was completed.

The modification improved the reliability of the line because the new bus arrangement will prevent false operation and improved equipment fault protection.

Therefore, the margin of 9afety was not reduced.

ECN P5480 -

(WP 2217-87) Cut-out reactor drain pipe Reactor Drains, Vents and removed reactor drain valves10-503 and Misc. Piping -

and 10-504.

Replaced line with elbow Unit 2 and capped. The ECN was not completed.

Support modifications and testing remaining to be implemented.

ECN P7018 -

(WP 2280-87) Repaired, replaced, and HVAC System -

removed HVAC duct supports, unit 2 Unit 2 drywell, elevation 616'.

(WP 2279-87) -

performed same modifications for HVAC duct supports, elevation 604'.

- Page 70 r.'.

CHANGE IN PROCEDURE JUNE 1988

'There were 440 revisions to plant instructions during the month; 440 instructions were changed primarily for correction, and no revisions related to esafe operation of.the plant.

PLANT INSTRUCTION REVISIONS JUNE 1988 Category Instruction

Reason for Request

There were no revisions for the month.

8 v,.,

v-m e-

r.

Page 69-PEACTOR VESSFL FATIGUE USAGE EVALUATION JUNE 1988 The cumulative usage factors for the reactor vessel are as follows:

Usame Factor _

Location Unit 1 Unit 2 linit 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 er

-->-en

~

-.--s m

.-,-,y,

Page 68 4

A TESTING

SUMMARY

(Continued)

JUNE 1988 1

1 Changes. Test, and Experinents Requirint Authorization From the NRC Pursuant to 10 CFR 50.59(a)

There was one revi9 ion for unit 1, 2, and 3 technical specifications.

Channes. Tests, and Experiments not Requiring Authorization from NRC Pursuant to 10 CFR 50.59(a)

There were no special

&a*6*

_4teted for this month, f

Page 67 9

TESTING

SUMMARY

JUNE 1988 i

Surveillance Testing Unit 0 A total of 146 surveillance tests were completed per 41 different test instructions.

Unit 1 A total of 92 surveillance tests were completed on unit 1 per 41 different

. test instructions.

Unit 2 A total of 99 surveillance tests were completed on unit 2 per 46 different test instructions.

Unit 3 A total of 81 surveillante tests were completed on unit 3 per 27 different test instructions.

i

---r

-. -~-

. - ~

WASTE TREATHENT SYSTEN TIS 006tPUTS JUNE 1988 FLOOR FLOOR FLOOR DRAIN DRAIN DRAIN 3,gy,

~

GE: 7.85E+E COLLECTOR FILTER SAMPLE GAe 7.59E+05 TANK TANK (2) Q F T: 210.00 GAe 7.85E+05 l

GFD: 8.59E+02 I f 1 I LAUNDRY GAL: 2.58E+04 GPD: 0.00E+00 DRAIN 0

,,t

,,,,g,3 CANAL GPD: 3.61E+04 GAL: 9.48E+05 ECYCLED MAYER GPD: 1.14E+04 GAL: 3.41E+05 1 L I fl fI f WASTE WASTE WASTE WASTE GPD: 6.31E+03 COLLECTOR O

SAMPLE O

GAe 1.89 EMS FILTER DEMINERALIZER TANK TANK (1) QFT: 138.00 D) CUFT: 125.00 GM; 1./.5E+06 (1) CUFT PONDOt 125.00.0FT RESIN G FIBER HIXTLIF; 0.00.CUFT ECOSOREt 13.00 (2) CUFT POWDCC 140.00.CUFT HESIE G FIBER MIXTURE: 70.00. 0FT ECOS0 Alt 0.00 I fGPD: 3.06E+04 GAL: 9.19E+05 STORAGE D) BEAD ESIN TANK

Page 65 FUEL CLADDING INTEGRITY PARAMETERS

-JUNE 1988 Unit 1 Reactor Water Iodines (uci/sec.)

Date I-131 1-132 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 Xe-135 Xe-133 Unit in Outage Unit 2 Reactor Water Iodines (uci/sec.)

Date 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-08 Kr-85m Ke-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (uci/sec.)

Date I-131 I-132 1-133 I-134 I-135 Unit in Outcge Fission Cases at Discharge of SJAE (uci/sec)

Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-8:m Xe-135 Xe-133 Unit in Outage l

w-w,

Page 64 RESIN USAGE REPORT JUNE 19C')

RESIN CONSUMED (CU.FT.)

% of Total Bead-POWDEX ECODEX ECOSORB EPIFLOC Total,,

Radwaste Floor Drain Filter-41.9 0

140 0

0 70 210 Waste Decineralizer 24.9 125 0

0 0'

O 125 Waste Filter 27.6 0

125 0

13 0

-138

' Fuel Pool Demins 3.2 0

16 0

0 0

16 Reactor Water Cleanup Unit 1 0.4 0

2 0

0 0

2 Unit 2 0

0 0

0 0

0 0

Unit 3 0

0 0

0 0

0 0

Cond. Domins Unit 1 0

0 0

0 0

0 0

Unit 2 2.0 0

10 0

0 0

10 Unit 3 0

0 0

0 0

0 0

Totals 500.0 125 293 0

13 70 501

Pags 63

' BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES JUNE 1988 LAUNDRY-DRAIN VOLUME RELEASED:

0.0 GALLONS FLOOR DRAIN VOLUME RELEASED:

758918.8 GALLONS WASTE SAMPLE.fANK UGLUME RELEASED:

189291.0 GALLONS DISTILLATELTANK VOLUME RELEASED:

0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLUME REL EASED:

0.0 GALLONS L

TOTAL _ VOLUME RELEASED TO THE RIVER:

948209.7 GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR MONTH:

6.71E-09 UCI/ML A/D LONGEST RELEASE TIME FOR MONTH:

360 MINUTES SHORTEST RELEASE TIME FOR MONTH:

178 MINUTES TOTAL TIME OF RELEASES-FOR MONTH:

8189 MINUTES AVERAGE TIME FOR BATCH RELEASES:

256 MINUTES IJ NUMBER OF BATCHES RELEASED:

32 l

NUMBER OF ADMINISTRATIVE LIMIT VIOLATIONS:

0 NUMBER ~0F TECHNICAL SPECIFICATION VIOLATIONS:

0 t

i

(

l l

l l

l.

i a---a--a._--

--s.L_- -. - - - - --. =

i P2g-, 62 BROWNS FERRY NUCLEAR PLANT MONrilLY REPORT CALCULATIONS LIQUID RELEASES JUNE 1988 OTHERS UNITS CI FE-55

< 8.72E-04 SB-125 1.00E-04 9

s.

Pige

\\

BROWNS' FERRY NUCLEAR PLANT

-MONTHLY REPORT CALCULATIONS

. LIQUID RLLEASES JUNE 1988

' ISOTOPES RELEASED UNITS CI CR-51 2 56E-05 NN'-54 8 02E-05 CO-58

< 3.28E-04 FE-59

< 7.14E-04 CO-60 9.02E-03 ZN-65

-6.31E-04 NB-95

< 2.97E-04 ZR-95

< 5.13E-04 MOTC-99H

< 2 04E-04 I-131

< 3.03E-04 XE-133

< 7.14E-04 CS-134 3.4?E-03 X E-- 13 5

< 1.74E-J4 CS-137 1.40E-)

BA-140

< 1.20E-03 i

LA-140

< 1.21E-04 CE-141

< 3.60E-04 SR-89

< 7.!'C-05 SR-90'

< 4.88u 35 1

)

l l

L

.~.

-Page 60 i

up BROWNS FERRY NUCLEAR PLANT

.MONrilLY REPORT CALCULATIONS

LIQUID RELEASES.

. JUNE 1988 RADI0 ACTIVE LIQUID EFFLUENTS

-1.

GROSS RADI0 ACTIVITY UNITS a). -TOTAL. RELEASE-CURIES 2.73E-02 b )'

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 2.20E-09 c)

PERCENT OF APPLICABLE LIMIT (-1E-7 UCI/ML )

2.20E 00 I2.

. TRITIUM 4

-a ). 10TAL RELEASE CURIES 1.49E-01 b)

AVERAGE DIt.UTF:D CONCENTRATION RELEASED UCI/ML 1.20E-08 c)

PERCENT OF APPLICABLE LINIT (3E-03 UCI/ML) 4 00E-04 (1) u 3.

DISSOLVE 0 N08t.E GASES a)

TOTAL RELEASE CURIES

< 8.88E-04 b)-

AVERAGE DILUTED CONCENTRATION, RELEASED UCI/ML

< 7.16E-11 c)

PERCENT OF APPLICABLE LIMIT (2E-04 UC1/ML)

< 3.38E-05 4.

GROSS ALPHA RADICACTIV[TY a)

TOTAL RELEASE CURIES

<1.20E-04 b)

AVERAGE DflurED CONCENTRATION RELEASED UCI/HL

<9.64E-12 5.

VJLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 3.59E 06 6.

VOLUME OF D1LttTION WATER LITERS 1.24E 10

-(1)

INCLUDES XE-133, XE-135, AND OTHi!RS

.. ~ -

,.g.

.l.., ':

e c.

Pogo 59-l,

-AIRBORNE RELEASES ~(CONTINUED)

JUNE 1980 IGROUND RELEASES

[_______________.'

,' C.

PARTICULATES UNIT THIS MONTH SR-89~

C I'

< 4.32E-05 SR-90 CI

< 9.45E-06

' CS-134.

-CI'

.<'7.75E-05

~CS-137 CI 3.54E-05 BA-140 CI

< 3.04E-04 6

' LA-140 CI

< 8.42E-05 10THERS(SPECIFY) t'

)

CO -60 CI.

'1.01E-03 i

TOTAL. FOR PERCOD CI 1.04E-03

' D, TRITIUM CI 5.33E-02 0

1 b

f l

1 f

-.,-a

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

-.-.~,,..n.-

g

('

' - ge, 14-Pago 58-

-I AIRBORNE RELEASES (CONTINUED)-

a-JUNE

~

1988 0ROUND RELEASES A.

FISSION GASES UNIT

.THIS MONTH' KR-85M-CI

< 9 43E-02 KR-85 CI

<'O.66E 01 KR CI

< 3.69E-01

'KR-88 CI

< 5.09E-01 XE-133 CI

< 4.63E-01 i

.XE-135M CI

< 6.69E-01 XE-135 CI

< 1.59E-01

'XE-138 CI

< 1.39E-00 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI

< 9.03E 01

. B., -

10 DINES I-131 CI

< 8.55E-05 I-133 CI

< 6.76E-04 I-135 CI

< 5.98E-01 TOTAL FOR PERIOD CI

< 5.98E-01

~

c' Pago 57-l AIRBORNE RELEASES (CONTINUED)

JUNE 1988 ELEVATED RELEAGES C.

PARTICULATES UNIT THIS MONTH SR-89 CI

< 2.67E-07 SR-90 CI

< 1.35E-07 CS-134 CI

< 2.63E-06 CS-137 CI

< 4.28E-06 BA-140 CI

< 6.41E-06 LA-140 CI

< 1.47E-06 OTHERS(SPECIFY)

CD-60 CI 3.13E-05 TOTAL FOR PEkt0D CI 3.13E-05 D.

TRITIUM CI

< 3.00E-03 4

Pag; 56 AIRJORNE RELEASES (CONTINUED)

JUNE 1988 ELEt>ATES RELEASES A.

FISSION GASES UNIT THIS MONTH KR-85H CI

< 1.08E-01 KR-85 CI

< 3.64E 01 KR-87 CI

< 3.23E-01 KR-88 CI

< 4.76E-01 XE-133 CI

< 3.80E-01 XE-135M CI

< 1.39E-01 XE-135 CI t 1.57E-01 XE-138 CI

< 9.89E-01 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI

< 3.90E 01 B.,

10 DINES I-131 CI 2.23E-06 I-133 CI

< 1.09E-05 I-135 CI

< 1.03E-01 TOTAL FOR PERIOD CI

< 1.03E-01

Re n.'

?. d; Pago 55*

. AIRBORNE RELEASES (1)

JUNE 1988

(, SUMMATION OF ALL RELEASES UNIT THIS MONTH-A.: ::FIS3ICF e,4D ACTIVATION. GASES.

1.

TOTAL RELEASE CI

< 1.29E 02

. 8 :.

2.

AVERAGE RELEASE RATE FUR PERIOD UCI/SEC

< 4.28E'01 3.

.P.ERCENT OF TECH. SPEC. LIMIT (0.15 CI/SEC) 0.00E -P.'

IODINES F

II. / TOTAL IODINC -'131-CI

< 8.77E-05 2.

' AVERAGE RELEASE RATE FOR PERIOD UCI/SEC

< 2.90E-05 3.

. PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 0.00E-01 C.

lPARTICULATES 1.

'PARTICULATES WITH HALF-LIFES > OR = TO 8 DAYS CI 1 07E-03' 2.

AVERAGE' RELEASE ~ RATE FOR PERIOD UCI/SEC 3.54E-04 3.

1 PERCENT.0F' TECH. SPEC. LIMIT (2.1,9 UCI/SEC) 1.62E-02 i4. - GROSS ALPHA RADIOACT[VITY CI 7.67E-07

D.

' TRITIUM 1.

TOTAL RELEASE CI 5 33E-02 2.-

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1 76E-02 3.

' PERCENT OF TECH. SPEC.. LIMIT (2.19 UCI/SEC)

B.04E-01 4.-

GROUND LEVEi. RELEASE CI 5.33E-02 5.

ELEVATED RELEASE CI

< 3.80E-03

' ( 1 )'.

REPURTING PERIOD 35 OAYS 4

I m-

___.,.,,v.

-m..-,,

y,

y

Pags 54 CHEMISTRY

SUMMARY

(Continued)

JUNE 1988 Environmental Technical Specification Requirements The ambient upstream river temperature (24-HR AVG MAX.) varied between 80.4*F ranging from 76'.2*F on June 12 to 35.5*F on June 27.

The downstream temperature varied between 76.l*F on June 12 to 84.9'F on June 27.

The maximum river temperature rise was 0.5'F on June 1, 6, and 13.

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

The sewage lagoon remained closed through the month.

A leak of sodium nitrite from unit 1 and 2 and unit 3 control bay chillers was identified on June 30.

Chemistry personnel initiated chemical treatment of the chillers on June 30 by adding 5 pounds of reagent grade sodium nitrite to each system. A leak was suspected when high concentrations of nitrite were obtained in samples from both units 1 and 2 office building drain (DSN 110) and unit 3 control building drain (DSN 107). The leak from the unit 1 and 2 control bay chiller resulted'in an unpermitted discharge of sodium nitrite to the Tennessee River via DSN 110 and the leak from unit 3 control bay chiller resulted in an unpermitted discharge of sodium nitrite to the Tennessee River via DSN 107.

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

r; 3

1 Pag 3'53'

~

+.

PRIMARY. COOLANT CHEMISTRY (Continued)

June 1988' Parameter-Unit 1 Unit'2 Unit 3 16.

Chlo'ide-(oob)-

High

<10

' 10

<10 Low

<10

<10

<10 Average

<10

<10-

<10 7.-

pH9250C High 6.3 6.2 6.4 Low 5.9 5.7 5.8 Average 6.0~

o.O 6.1 8.-

Conductivity (mmho/cm02500)

High 0.82 0.93 0.12 Low 0.20 0.57 0.080 Average 0.43 0.76 0.097 k

t

d Para 52

'(_

PRIMARY COOLANT CHEMISTRY JUNE 1988 Parameter Unit 1 Unit 2 Unit _3, 1.

Gross Radioactivity a.

Ctud (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 (mei/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, g High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A i

3.

Tritium (mei/ml)

High 4.84E-5 1.23E-4 1.33E-4 Low 3.64E-5 3.738-5 4.27E-S Average 4.43E-S 5.74E-S 1.13E-4 4

Iodine *i31 (mei/ml)

High

<4.02E-6

<6.51E-6

<4.56E-7 Low

<S.31E-7

<1.10E-6

<2.76E-7 Average

<1.44E-6

<2.72E-6

<3.28E-7 S.

Iodine-131: Iodine-133 Ratio High N/A N/A N/A Low N/A N/A N/A Average N,4 N/A N/A F

Pags 51-CHEMISTRY

SUMMARY

JUNR 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 c.onductivity and chloride have not been exceeded.

UDit 2 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 3 The conductivity of the reactor coolant remained within technlett specification and fuel warranty limits during the month.

Chlorido 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.

L

D 4

4 0THER REPORTS e

l l

l 1

--w

--n

,y.,.,_-.,,,,_,r.,n,

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

MAJOR WORK PERFORMED EGE NARRATIVE Page 50 Drywell Firo Rectvery B00061A Ccntinusd rsplecem:nt of damIged system 70

.(C:ntinued) ccnduit tnd cable (workplen 2112-88).

B00G52A Continued replacement of damaged system 68 conduit and cable (workplans 2135-88 and 2139-88).

B00063A Continued replacement of damaged system 1 conduit and cable (workplan 2162-88).

M00079A Started replacement of damaged cables associated with systems 1, 3, 56, 57, 64, and 77 (workplans 2200-88, 2227-88, and 2225-88).

P3163 Continued dryvell cable replacement (workplan 2237-87, 2006-86, 2007-86, 2216-87, and 2238-87).

P3180 Continued electrical work associated with containment penetration replacement (workplans 2105-87, 2022-87, 2135-87, 2136-87, and 2137-87). Field completed workplans 2100-86 end 2101-86.

TT' NARRATIVE MAJOR WORK PERFORMED ~

ECH PagS 49 Oth;r (C:ntinu;d)

P0977 Stcrtcd work cn upgrcda of unit 2 oTf-line effluent radiation monitor (wsrkplcn3 2128-88).

P0978 Started work on upgrade of unit 3 off-line.

effluent radiation monitor (workplan 3010-88).

P0984 Continued work on upgrade of site microwave telemetry system (workplans 0036-87 and 0037-87).

P0990 Continued 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, and 2008-88). Workplan 2009-88 was field completed.

P5485 Continued work on SRM and IRM signal cable changeout (workplan 2095-88 and 2096-88).

P5534 Started work on SRM/IRM connector replacement (workplan 2144-88).

P7002 Continued field work on hydrogen water chemistry modifications (workplans 2090-88, 2087-88, and 2092-88).

P7006 Completed craft work on ATU inverter replacement (workplans 2066-88, 2097-88, and 2081-88).

P7037 Continued craft work on installation of quick disconnect couplings on testable check valves (workplans 2107-88, 2105-88, 2109-88, and 2110-88).

P7089 Started work on reactor vessel level and pressure circuitry changes per ATWS rule (workplans 2202-88 and 2203-88).

P7142 Started work on ampacity cable replacement (workplan 2262-88).

Ll791 Started electrical work on SJAE steam supply modification (workplans 2104-85 and 2102-88).

Drywell Fire Recovery B00060A Started work on system 80 cable replacement (workplan 2176-88).

^

MAJOR _WORlLPIRFORMED EE.

NARRATIVE Ptgs 48

=RWCU syatem Icprsvements P3429 Str.rted RWCU pump cccing codifications (wsrkpitna 2093-88, 2094-88, tnd 2170-88).

P7026 Started RWCU pump internal modifications (workplans 2188-88, 2187-88, 2188-88, and 2189-88).

P7030 Continued work on RWCU valve replacement (workplans 2150-88 and 2153-88).

P7082 Started RWCU pump instrumentation work (workplans 2239-88, 2240-88, 2231-88, 2234-88, 2232-88, 2235-88, 2233-88, 2236-88).

Other B0039 Started and completed craft work associated with LS-78-1A, B, and C replacement (workplan 3005-88).

B00047A Started work on 2-PS-24-133A upgrade.

M0075A Installed 30,000 condenser tubes (workplan 2165-88).

P0085 Continued reroute of conduit on drywell pressure and temperature upgrade (workplan 2192-87).

P0384 Continued tubing and electrical work on containment purge valves (workplan 2049-86).

P0533 Continued work on torus temperature monitoring system (workplans 2184-84, 2175-84, and 2185-84).

P0547 Continued replacement of recirculation system check valves (workplan 2050-85).

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 2229-87, 2256-87, 2248-87, 2252-87, 2255-87, 2250-87, 2257-87, 2100-88, 2253-87, 2267-87, 2254-87, 2262-87, and 2263-87). Field completed workplan 2155-87.

P0976 Started work on upgrade of unit 1 off-line effluent radiation monitor (workplans 1011-88).

MAJOR WORK PERFORMED E.GH NARRATIVE Pags 47' SIismic I sues (C:ntinued)-

P0370 Continued structutcl work en seismic qualification and designation of block walls (workplans 1038-87 and 3036-87).

P0392 Continued SMMI rework of scram discharge volume supports.

WO429A Started modification of unit 1 SBGT reactor zone auction duct support (workplan 0052-88).

P0625 Continued vent and drain support work (workplan 2007-88).

P0859 Started dryvell grating modffications (workplan 2289-87).

P2044 Continued craft work on unit 1 RB drain and sump pump 79-14 modifications (workplan 1033-87).

P2154 Completed craft work on RHRSW and EECW trains B and D outage fixes (workpl.,s 0028-88 and CO23-88). Field completed workplans 0015-88 and 0017-88.

P7029 Continued repair of lower dryvell structural steel (workplan 2234-87).

P7048 Continued modification of reactor water level instrumentation sense lines (workplans 2004-88 and 2005-88).

P7083 Field completed 2 of 4 workplans for common area tubing seismic qualification (workplans 0008-88 and 0010-88).

P7085 Field completed 2 of 3 workplans for unit 2 tubing seismic qualification (workplans 2059-88 and 2060-88).

P7115 Continued craft 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, 2086-85, 2089-85, and 2270-87).

P5451 Continued work on stack radiation monitor pressure and temperature compensation (workplans 0028-87 and 0031-87).

sy.

4

-r-t v

v-

_ ---+-

~

MAJOR WORK PERFORMED EH MARRATIVE Psgs 46 sntinutd c:all. piping cnd support work on Knvir:nmental Qu211ficcti:n P3205 s

'2 2 cn 1yzer linco (vsrkplens 2162-87, (C ntinu:d)

.0

.163-87, and 2183-87).

P7000 Started replacement of 2-LS-064-141A and B (workplan 2065-88).

P70:2 Continued RWCU heat exchanger room and steam tunnel cable replacement (workplan 2069-88).

P7036 Continued craft work on steam tunnel cable replacement (workplan 2122-88).

P7039 Continued replacement of shutdown transformer TS2A (workplans 2076-88 and 2077-88).

P7047 Started Raychem splice replacement (workplans 2166-87 and 2167-87).

Saismic Issues B0005A Contfaued replacement of EECW sectionalizing valves (workplan 0012-88).

B0012 Continued work on drywell steel stiffner plates (workplan 2178-88).

WO204A Completed craft work on unit 1 control room panel anchoring (workplans 1022-88, 1035-88, and 1042-88).

WO205A Completed craft work on on unit 2 control room panel anchoring (workplans 2191-88 and 2237-88).

WO206A Completed craft work on unit 3 control room panel anchoring (workplans 3022-88, 3036-88, and 3054-88).

WO269A Started modification of unit 3 SBGT reactor zone suction duct support (workplan 0052-dC,.

P0289 Continued 79-14 and work on RHRSW dresser coupling replacement (workplans 2121-88, 3031-88, 2163-88, 2164-88, 3016-88, 1005-88, 1032-88, 1015-88, 1016-88, 1043-88, 1009-88, 1010-88, 3038-88, 1036-88, 2269-88, 2224-88, 1047-88, 2281-88, 3058-88, and 3055-88.

P0361 SMMI rework of torus attached piping and drain supports continued. Field completed workplans 2158-84, 2176-87, and-2213-87.

Paga 45' MODIFICATIONS MONTHLY REPORT JUNE 1988 MAJOR WORK PERFORMED ECH NARRATIVE Appendix R P0753 Continued conduit and cable work on HPCI/ ADS separation (workplans 2084-85 and 2005-85).

P0819 Continued work on emergency lighting upgrade (workplans 1019-87 and 2013-87).

P0879 Continued work on fire door upgrade (workplan 2068-87).

P0885 Continued conduit and support work on RB fire detectors (workplans 2012-87, 2013-87, 2014-87, and 2015-87).

P0886 Started work on Appendix R penetration seals (workplans 2196-88, 2204-88, 2205-88, and 2206-88).

P0887 Started work on conduit fire wrap (workplan 2182-86).

P0889 Continued reroute of conduit for separation (workplans 2053-87, 2054-87, 2221-87, 2050-87, 2052-87, and 2049-87).

P0953 Continued evacuation. alarm panel power feed replacement (workplan 0051-86).

P7067 Started work on RB sprinkler system upgrade (workplans 2250-88 and 2251-88).

Environmental Qualification P3145 Continued electrical conduit sealing activities (workplans 2070-85 and 2078-85).

P3153 Continued modification and replacement of MSIV terminal strips (workplan 2025-86).

P3170 Started terminal block termination modifications (workplans 2244-87 and 2245-87).

P3173 Started replacement of 2-FSV-76-17, 18, and 19 (workplcn 2077-86).

RUNN]NG MA]NTENANCE-REponifon rue uonTu of JUNE SUPV. JonN C}oWELL l.

WORK ITEM COMPLETE RECEIVECVASSIGNED COMPLETED OPEN RED 0

0 0

OWCE O

O O

YELLOW 0

0 0

BLUE O

O O

PURPLE O

O O

ll. COMMITMENT TRACKING UCENSING ISSUES (NCO & SLT)

KD 1

3 2

SLT 0

0 0

PORS TRACKING ITEMS (BFC) 0 0

0 CKBS 0

13 8

AVENGEN3EOFCAORS 9 " 'ONTHS EMPLOYEECONCERNS 0

0 SAFETYISSUES UST 0

0 0

111. STAFFING LEVELS PERSOtNEL CURRENT HEADCOUNT ASP 69*

ATL 276 HTL 67 APPRENTICES 25 TOTAL 457

'7 ENG. AND ASSOC.ON LOAN FROM MTS, ETS, AND I&C TS I

V. PROCEDURE

S 0

PROCEDURESWERE PORC APPROVED 0

PROCEDURES SENTTOWORD PROCESS'NG V.

MBS 112 OUTSTANDING STATUS"H" MRS 70 OUTSTANDING STATUS"O"MRS 687 COMPLETED MRS THIS MONTH VI. MAJOR ROUTINE ACTIVITIES ANNUAL CHILLER INSPECTION MECH. & ELEC.

LAYUP SUPPORT-MECH. & ELEC.

MAINTAIN STD LAB-I&C PM'S ON VARIOUS SYSTEMS FOR ALL DISCIPUNES Vll.MMOR NONROUTINE ACTIVmES TRAVEUNG SCREEN REPAIR MECH.

INTAKE BUTTERFLY VALVE REPAIR MECH.

PROVIDED CRANE OPERATOR SUPPORT FOR REFUEL FLOOR-ELEC.

MAINTENANCE ON REFUEL BRIDGE ELEC.

HFARELAYCAUBRATION ELEC.

SUPPORT 2 BFN RTP l&C SUPPORT St WALKDOWN I&C

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

JUNE 1988 3.

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

a..

BFQ 880139 4.

The Mechanical Technical Section devoted _250 hours to training during the month of June.