ML20151G002
| ML20151G002 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/31/1988 |
| From: | Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8804190140 | |
| Download: ML20151G002 (84) | |
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'6 MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY MARCH 1988 "Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS OPR-33, CPR-52, AND DPR-68 Sub ..tted by:
[/hn G. Walker Plant Manager ., :1
<\ { l 1 0 1 59 '!
R DCD
TABLE OF CONTENTS PART I OPERATIONAL
SUMMARY
1 A. Significant Operational Events Summary........................... 1 S. Fuel Performance and Spent Fuel Storage Capabilities Summary. . . . . 2 C. MSRVs (Main Steam Relief Valve) Summary.......................... 5
! D. Issuanc e o f S pe ci al Repo r t s S umma ry . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . 6 E. Licensee Events Summary.......................................... 9 T. O f fsit e Dose Calculation Manual Changes . . . . . . . . . . . . . . . . . . . . . . . . . 12 G. Radvaste Summary............................................... 3 13
- 1. Total volume of solid vaste shipped off site
- 2. Nature of the vaste (trash, resins, etc.)
- 3. Gross curie activity
- 4. Dates the material was shipped and the disposal facility to which the material was shipped.
- 5. Estimated quantities of spent resin in storage.
6! Estimated amount of spent resin ti t vill be generated in the following month.
- 7. Waste type and volume of radvaste containers that are onsite avaiting shipment.
PART II OPERATING STATISTICS A. NRC Reports
- 1. Operating Data Report....................................... 17
- 2. Average Daily Power Leve1................................... 20
- 3. Unit Shutdowns and Power Reductions......................... 23 B. TVA Reports
- 1. Plant Operating Statistics.................................. 26
- 2. Unit Outage and Availability Data........................... 27
- 3. Reactor Histogram (Reactor Power Percent)................... 30
TABLE OF CONTENTS (Continued) ,
Part III MAINTENANCE SUtMARY I A. Electrical Maintenance........................................... 31 B. Instrument Maintenance........................................... 35
) C. Mechanical Maintenance........................................... 37 D. Modifications.................................................... 40 H
PART V OTHER REPORTS 5
A. Chemistry Summary
- 1. Primary Coolant Chemistry .................................. 44
- 2. Environmental Technical Specification Requirements.......... 47
- 3. Airborne Releases........................................... 48
- 4. Liquid Releases............................................. 53
- 5. Resin Usage Report.......................................... 57
- 6. Fuel Cladding Integrity Parmeters........................... 58 r
- 7. Waste Treatment System Throughputs.......................... 59 B. Testing Summary.................................................. 60 C. Reactor Vessel Fatigue Usage Evaluation.......................... 62
. D. Change in Procedures............................................. 63 ,
l E. Plant Instruction Revisions...................................... 63 F. Change in Facility Design (ECNs)................................. 65 ,
G. Change in Plant Organization..................................... 75 ;
t H. Accidents........................................................ 76 i l
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CPERATIONAL SEMMARY 3
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Pag 3 1 SIGNIFICANT OPERATIONAL EVENTS SUPEARY MARCH 1988 Unit 1 03/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycla 6 refueling and modifications continue.
03/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRG concerns. Cycle 6 refueling and modifications continue.
Unit 2 03/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle $ refueling and modifications continue.
03/31/88 2400 Unit remains on administrative hold to resolve various i TVA and NRC concerns. Cycle 5 refueling and l modifications continues.
1 Unit 3 03/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Environmental qualification work and modifications continue.
03/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns. Environmental qualification work and modifications continue.
Page 2 TUEL PERTORMANCE AND SPENT WEL STORAGE CAPABILITIES
SUMMARY
MARCH 1988 Unit 1 Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC 1
concerns. The unit also began its sixth refueling on June 1, 1985, with a l
scheduled restart date to be determined. The sixth refueling vill involve loading 8x8R (retrofit) fuel essemblies into the core. The prior-to-startup unit 1 modifications are environmental qualification of electrical equipment (10CTR50.49), torus modification (NUREG 0661), containment instrumentation modifications (NURIG 0737), fire protection changes (Appendix R 10CFR50)
(all), MSIV leak rate reduction modifications, modification of masonry valls (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 22sample line modification (LER 81050), and EECW carbon to stainless 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 fuel pool is 1355 locations.
pico 3 IVEL PERTORMANCE AND SPENT IVEL STORAGE CAPABILITIES
SUMMARY
(CONT.)
MARCH 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 (10CTR50.49), torus structural modifications (NUREG 0661), containment instrumentation modification (NUREG 0737;, fire protection changes (Appendix R 10CT150), MSIV leak rate reductions modifications, modification of masonry walls (IEB 80-11), addition of feedvater 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), KPCI 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 E0C-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.
Ptg3 4 WEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
(CONI.)
MARCH 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) aesemblies into the core and ATWS modifications. The prior-to-startup unit 3 modifications are environmental qualification of electrical equipment (10CT150.49), containment modifications (NUREG 0737), fire protection changes I (Appendix R 10CFR50), MSIV lesk rate reduction modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, (LER 82020), valve modifications (Appendix J), HFCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14),
postaccident sampling modification (NUREG 0737), addition of redundant drywell control air supply, RPS voltage monitoring modification H 22 0 8 ample line 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.
f There are 0 assemblies in the reactor vessel. There are 764 assemblies to finish EOC-6, 248 EOC-5, 280 E0C-4, 124 E0C-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the fuel pool is 585 locations. All high density racks (HDR) have been installed in the pool with the exception of six.
Page 5 MSRVs (MAIN STEAM RELIEF VALVE)
SUMMARY
MARCH 1988 No MSRVs were challenged during the month.
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LilUANCE OF SPECIAL REPORTS Pago 6 MARCH 1988 ,
The following special reports are notices of violations issued for the month of March 1988.
88-04-03 The design basis for Class I buried piping, at penetrations into secondary containment and at entry points into the intake structure as described in Appendix C, Section C.2.1 of the FSAR was not correctly translated into specifications and drawings.
This design basis specified that the analyses of the piping must be primarily concerned with differential movement at supports near entry points into structures. Hanger M-30, which provides the only trial restraint for RHRSW and EECW piping at the intake structure, was underdesigned and could not withstand the required thrust loading based on a recent analysis by the licensee. The analysis concluded that the hanger would bend and deflect out of position during a seismic event. This condition could allow a nearby flexible coupling to part potentially resulting in a loss of the RHRSW and EECW systems.
This is a level IV violation, (Supplement I) and As applicable to all three unitt.
88-04-02 Standard Practice (SP) 8.3, Plant Modifications, Section 11.2, Work Control was not adhered to for Workplan WP0017-86, Cable Pull al.1 Camera Support for Permanent Power Installation, in that Section XI of Form BF-62 for WP0017-86 was not signed by anyone even though the modification involved taking security equipment ott of service. Work commenced per the workplan in July 1987 and security camera was taken out of service in December 1987. The camera va: returned to service on February 19, 1988, following the inspector's inquiry of the camera's operability status on February 15, 1988.
SP 12.24, Conduit of Operations was inadequate in that it does not fully adhere to the requirements stated in Part III, Section 4.1 of the NQAM, paragraph 6.1.1 SP 12.24 allows the l use of uncontrolled "scratch pads" in the preparation of QA records. Section 5.4.2 of SP 12.24 encouraged operators to use "scratch pads" to maintain records of out-of-service equipment and return to service for subsequent entry into the operating logs. These scratch pads may be destroyed after use. No control measures over the nonpermanent scratch pads vere contained in SP 12.24
! This is a Severity Level V Violation, (Supplement I) and is applicable to all three units.
ISSUANCE OF SPECIAL EET0"TS (Continued) Page 7
- MARCH 1983 88-02-04 Browns Ferry Instruction BF MAI-23, Support & Installation of Piping Systems in Category I Structures, contains the following requirements: Paragraph 1.2.3 requires that piping and support installations shall be in compliance with the instruction and appropriate plant piping and support design output documents.
Paragraph 2.6 requires that relocated supports be fabricated within the allovable tolerances of Section 2.7 Paragraph 2.7.3 requires chat angles be maintained to a tolerance of 2 i
degrees, re.ragraph 5.1 requires that a final hanger inspection shall be documented by using MAI-23, Attachment A, "Hanger and Restraint Inspection Data Sheet".
Contrary to the above, activities affecting quality were not being accomplished in accordance with documented procedures and drawings in that an NRC field inspection of two QA accepted pipe supports revealed one support with deviations from the documented requirements. As a result, the support may not be able to perform its intended function as required by the design.
37-38-01 Nuclear Engineering Procedure 1.2, Rev. 1, "Training",
indicates that the Individual Training Record (ITR) is the comprehensive record of the training qualifications of the employee which ensures that the employee has been trained on the procedures and processes that govern the employeo's work.
NEP 1.2 also indicates the ITR shall be maintained up-to-date to reflect the training required versus the training received for each DNE employes. It further indicates that branch / project / division level staff shall develop and maintain a training matrix usin2 NEP 1.2, Attachment 1, "Training Matrix", as a basis for training by adding additional requirements as appropriate.
Contrary to the above, as of October 1987, DNE training and documentation failed to meet the requirements of NEP-1.2.
This in a Severity Level IV Violation
ISSUANCE 07_SPECIAL REPORTS (Continued) Pag 3 8 .
FJRCH 1983 ,
87-38-02 10 CTR Part 50, Appendix B, Cricerion XVIII, as implemented by TVA's QA Topical Report, TVA-TR75-1A, Rev. 9, Paragraph 17.1.18. "Audits" requires follovup on corrective action taken on audit deficiencies.
10 CTR Part 50, Appendix B, Criterion XVI, as implemented by TVA's QA Topical Report TVA-TR75-1A, Rev. 9, Paragraph 17.1.16, "Corrective Action", requires deficiencies to be promptly identified and corrected.
NQAM, Part 1, Section 2.18, Rev. O, "Audits", as changed by a Quality Notice dated January 16, 1987, indicates that responsibile management shall take necessary action to correct the deficiencies revealed by the audit. It further indicates that audits should provide an objective evaluation of compliance with established requirements and verify implementation of recommended corrective action.
Contrary to the above,10 audits from 1985 to January 1987; identified training deficiencies which, at the time of the inspection, had not been corrected.
This is a severity Level IV violation.
87-38-03 10 CPR Part 50, Appendix B, Criterion V, as implemented by TVA's QA Topical Report, TVA-5475-1A, Rev. 9, Paragraph 17.1.5, "Instructions, Procedures, Drawings", requires activities affecting quality be accomplished in accordance with instructions, procedures, or drawings.
NEP 1.3, Rev. O, "Records Control", as changed by DNE Interim
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Order-Supplement to NEP 1.3 (B05 27 0130 500) dated January 30, 1987, and NQAM, Part I, section 2.17 Rev. 0, "QA Racords", as changed by a Quality Notice dated December 1, 1986, both require pen and ink corrections to QA documents be made by drawing one line through the incorrect information, the correct information entered and the entry initialed and dated.
Contrary to the above, corrections were made to numerous documents in a manner not in conformance with the one line, initial, and date method.
This is a Severity Level V Violation.
LICINSEE EVENT REPORT (S) 9 MARCH 1988 The following licenses event reports (LERs) were reported to the Nuclear Regulatory Commission in March 1988.
Descriotion of Event LH 1-88-006 Unclanned Entineered Safety Feature Actuations Due to Personr.el Error Caused By Procedural Inadecuacies and Human Factors Concerns On February 20, 1988, at 0735 hours0.00851 days <br />0.204 hours <br />0.00122 weeks <br />2.796675e-4 months <br />, with all three units defueled, the unit 2 reactor protection system (RPS) bus 2A vas momentarily deenergized causing a half, scram, partial primary containment isolations, secondary containment isolations, and actuation of the control room emergency ventilation system. The temporary loss of power occurred during RPS modifications when an electrician inadvertently opened a set of auxiliary contacts while working inside the cabinet. The operator reset the isolation logic and returned the systems to standby readiness by 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />.
J The workplan controlling the modifications in question did not require actions which would have prevented these actuations and did not warn the craft personnel of the potential for deenergizing the 2A RPS bus. The workplan vill be revised to bypass this set of auxiliary contacts and to add a caution stating the need for extreme caution while working inside this cabinet. When similar modifications are performed on the other power supplies to the unit 2 RPS buses those workplans vill be similarly revised. The craft personnel involved vere counselled on the necessity of extreme caution when working around energi:ed equipment. A description of this event will be reviewed by current operations and modifications personnel.
, 1-88-009 Unolanned Standby Gas Treatment Train Actuations Due To Inadvertent Relav Operations On February 2,1988, with all three units defueled, the C train of standby gas treatment (SBGT) was being returned to service following extensive maintenance to the train's supply breaker. At 1902 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.23711e-4 months <br />, with no automatic initiation signals
paga 10 Descriotion of Event (Continued)
LEE prvjent, the supply breaker was manually closed and the train spurioi"'y actuated. The breaker was manually opened, .as main control room hand switch j was placed in stop (spring return to auto) and the 1 isolation logic vas reset. The breaker was i manually cycled again at 1917 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.294185e-4 months <br /> causing a l second spurious actuation. The breaker was j manually closed a third time, at 1943 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.393115e-4 months <br />, again
. actuating the train. The train was secured this time by placing the main control room hand switch in stop. The first two starts were unplanned actuations of an engineered safety feature.
The control logic was inspected and found to be in the proper configuration and operating properly.
The suspected cause of the actuations was a irtching relay (labeled hCX) in the trein's control i *s tic. The MCX relay was inadversently latched in the actuation state during the referenced maintenance activities . Functional testing could only be performed following maintenance when the breaker was replaced and closed. No failures or circuitry problems were identified. The electrical maintenance procedures vill be revised to verify the state of this relay prior to closing the supply breaker following maintenance on the breaker.
Since a definitive cause was not verified the investigation is continuing. If any significant findings are discovered they vill be provided in a l revised LIR.
I 1-88-010 Inadeaunte Procedures Cause Two Cases of Missed Sameles That Were Recuired To Comeensate For Inocerable Effluent Radiation Monitors.
On January 22, 1988 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, and on January 29, 1988, at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, with all all three units defuelad two similar events involving missed compensatory sampling for inoperable ef fluent radiation monitors occurred. The cause of both events was inadequate procedures.
Pcg3 11 Descrietion of Event (Continued)
LIA The first event occurred when compensatory sampling of the raw cooling water (RCW) discharge from a reactor pu11 ding closed cooling water heat (Tchanger was stopped. The heat exchanger was removel from service but the RCW flow was not isolat.ed.
The second event was declaring this off-gas post treatment monitors operable without cov ieting all surveillance requirements. Compensatory sampling was stopped.
The immediate corrective action for both events was the resumption of compensatory sampling.
The corrective action for both events is the revision of applicable procedures.
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' .Paga 12.. s OFFSITE DOSE CALCULATION MANUAL CHANGES MARCH 1988 No changes were made to the, Browns Ferry offsite dose calculation manual during the m,. nth.
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Page 13 Radwaste Summary March 1988 Common The radwaste system performed as designed. Approximately 1.21E+06 gallons of waste liquid were discharged containing approximately 1.29E-02 curies of activity.
There were seven spent resin shipments and two trash shipment during March.
All shipa n ts were to Barnwell, SC.
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Paga 14 Solid Radioactive Waste (Continued)
March 1988 .
Summary Type Shipped to Packaged on Gross Curie Estimated of Barnwell Site Awaiting Content by Generation for Waste During Month Shipment Type of Waste Next Month Compacted Drums O Cu.Ft.( ' 435 Cu.Ft. 0.00E+00 600 Cu.Ft.(2)
Boxes 1023 Cu.Ft.
' 279 Cu.Ft. 1.42E+00 600 Cu Ft.
2)
Uncompacted Drums O Cu.Ft.( 0 Cu.Ft. 0.00E+00 0 Cu.Ft.
Boxes 809 Cu.Ft.
' 302 Cu.Ft. 0.51E+00 400 Cu.Ft.( '
"5 CWP5 679 Cu.Ft.(1) 1209 Cu.Ft.(3) 3.18E+01 450 Cu.Ft.(1)
RWCU 206 Cu Ft.( 0 CU.Ft.C3) 4.03E+01 35 Cu.Ft.( '
TOTALS 2899 Cu.Ft.( ' 1016 Cu.Ft.(4' 7.41E+01 1600 Cu.Ft.
4' Total volume of waste shipped during the month: 2899 Cu.Ft.
Total volume of waste shipped year-to-date: 5963 Cu.Ft.
Unused 1988 burial volume allocation at Barnwell: 76837 Cu.Ft.
(1) Actual resin volume (2) Container burial volume (3) Estimated volume in separators (4) Does not include resins l
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Solid Radioactive Waste
- March 1988 Dewatered Spent Resin Shipments (
Volume of condensate / waste resin shipped: 19.90 Cu.M. (679 Cu.Ft.)
Total curies shipped: 31.8459 Volume of reactor cleanup resin shipped: 5.79 Cu.M. (206 Cu.Ft.)
Total curies shipped: 40.2889 Date Shipoed Disposal Facility Tvoe af Resin 03/01/88 BarnwelL, SC CWP5 03/04/88 BarnweLL, SC CWP5 03/08/88 BarnweLL, SC RWCU 03/15/88 Barnwell, SC CWP5 03/21/88 Barnwell, SC RWCU 03/29/88 BarnwelL, SC CWP5 03/29/88 BarnwelL, SC CWP5 Dry Active Waste (l' Number of drums shipped: 0 Volume: O Cu.M. ( 0 Cu.Ft.)
Total curies shipped: 0 Number of boxes shipped: 19 Volume: 51.9 Cu.M. (1831.6 Cu.Ft.)
Total curies shipped: 1.9269 Date Shicoed, Discosal Facility Tvoe gf Packaoe 03/09/88 BarnweLL, SC Boxes 03/23/88 BarnwelL,.SC Boxes (1) AlL shipments were by Sole-Use Vehicle
LIQUID RADWADTE gy, w .
MONTHLY OPERATING REPORT 1088 MARCH FLOW RATE (GPM) CATA PLOTTE R HE P E 12 HONTHS TOTAL RELEASE (CI) 40 - 2 AATE(GPM) 30 -
HI 27.10 LOW 11.62 3 AVG 18.71 20 1 TOTAL
- j RELEASE (CT)
HI 0.05 10 - LOW 0.01 AVG 0.03 o FLOWRATE APR MAY N VUL AUG SEP OCT NOV OEC UAN FEB MAR THASUGNPUT (G At 91 FILTER THROUGHPUTS ,,,,,
GALLONS X 10 0 HI 0.25E+07 5 - LOW 0.86E+0S AVG.0.14E+07 4 - FLOOR CRAIN HI 0.11E+07 LOW 0.49E+0S 3 -
AVG 0.78E+0S LAUNDRY 2 -
h) HI 0.iiE+05 i
NS .
LOW 0.00E+00 g . AVG 0.62E+04 0
APR MAY JUN VUL AUG SEP OCT NOV OEC JAN FEB MAR
-- - ~i6+1u "'s " -
g.. 0 F "'CPMA T I M --- -
THOUS. OF DOLLARS WASTE 10 1 HI 0.64E+05
_ LOW 0.19E+05 90 ,
AVG 0.36E+05 80 -
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FLOOR ORAIN 70 - ,
HI 0.56E+05 60 '
LOW 0.2iE+05 AVG 0.32E+05 40 . ..
LAUNORY 0.18E+03 HI I
0- N -
LOW 0.00E+00 20 .
AVG 0.43E+02 l APR MAY VUN JUL AUG SEP OCT NOV OEC JAN FEB MAR l
WASTE COLLECTOR SYSTEM LAUNORY SYSTEM I
FLOOR ORAIN SYSTEM STARTING 3-87 COSTS INCLUDE AESIN DISPOSAL
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OPERATIXG STATISTICS t
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O Page 17 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 0441-88 COPPLETED BY L D. Crawford TELEPHONE (2M 729-2507 OPERATING STATUS l Notes l
- l. Unit Nano: Browns Ferry Unit One l l
- 2. Reporting Perlod: Merch 1988 l l
- 3. Licensed Thermal Po w (MWt): 3293 l l 4 Nanoplate Rating (Gross %): 1852 l l
- 5. Design Electrical Rating (Not % ) 1065 l l
- 6. Maximus Dependable Capacity (Gross % ) 1098.4 l l
- 7. Maxirman Dependable Capacity (Not %) 1065 l l
- 8. If Changes Occur in Capacity Ratings (ltems Nun 6er 3 Through 7) Since Last Report, Give Reasons:
N/A
- 9. Power Level To Which Restricted, if Any (Not %): N/A 10.' Beesons For Restrictions, if Any: N/A This Mcmth Yr-to4 ate Cunulative
- 11. Hours in Reporting Period 744 2184 119,864
- 12. Nurter of Hours Reactor 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 Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0 168,066,787 17 Gross Electrical Erwgy Generatea (MWH) 0 0 55,398,130
- 18. Not Electrical Ermrgy Generated (MWH) -1978 4809 53,701,593
- 19. Unit Service Factor 0 _
0 48.61
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ev. Unft'Ava~ lie 6iiity Factor '
0 '
O 48.61
- 21. Unit Capacity Factor (Using M)C Net) 0 0 42.07
- 22. Unit Capacity Factor (Using DER Net) 0 0 42.07
- 23. Unit For:ed Outage Rate 100 100 42.39
- 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 deter ined
- 26. Units in Test Status (Prior to Ccreercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY CD9ERCI AL OPERAT10N (9/77)
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0 Page 18 OPERATING OATA REPORT
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DOCKET No. 50-260 DATE 04-01-88 COPFLETED BY J. D. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS l Notes l
- l. Unit Name: Brows Ferry Unit Tw l l
- 2. Reporting Period March 1988 l l
- 3. Licensed Thermal Po we (Mit): 3293 l l
- 4. Nanoplate Rating (Gross Mde): 1852 l l
- 5. Design Electrical Rating (Not Mie) 1065
- 6. Mexirnum Dependable Capacity (Gross Mde) 1096.4
- 7. Maximan Dependable Capacity (Not Mde) 1065 l l
- 8. If Changes occur in Capacity Ratings (items Nueer 3 Through 7) Since Last Report, Give Reasons:
N/A
- 9. Powe Level To Which Restricted, If Any (Not MWeis N/A
- 10. Reesms For Restrictions, if Any N/A This Month Yr-to-Cate Cumulative a
ll. Hours in Reporting Period 744 2184 if4.75l
- 12. Nurrber of Hours Reactor Was Critical 0 0 55,060.03
- 13. Reactor Reserve Shutdown Hours 0 0 14.200.44
- 14. Hours Generator On-Line 0 0 54,338.36
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated ( M ) 0 0 153.245.167
- 17. Gross Electrical Energy Genera +ed ( M ) 0 0 50,771,798
- 18. Not Electrical Energy Generated (MdH) -l,783 -5,742 49.178.091
- 19. Unit Service Factor 0 0 47.35
- 20. Unit Availability Factor 0 0 47.35
........____.2.lt.Urd t.Capeci ty Factor (Using M)C )det) 0 0 40.24
- 22. Unit Capacity Factor (Using DER Net) 0 0 40.24
- 23. Unit Forced Outage Rate 100 100 _ 41.65
- 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 be determined
- 26. Units in Test Status (Prior to Carmercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMERCI AL OPERAT10N (9/77)
Page 19
, OPERATING OATA REPORT DOCKET No. 50-296 DATE 'M DT-88 ' -
ColfLETED BY J. D. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS l Notes l
- 1. Unit Name 8cowns Ferry Unit Three l l
- 2. Reporting Period Merch 1988 l l
- 3. Licensed Thermal Powe (mit): 3293 l l 4 Nmeplate Rating (Gross % ): 1152 l l
- 5. Design Electrical Rating (Not % ) 1065
- 6. Maximun Dependable Capacity (Gross %) 1098.4
- 7. Maximue Dependable capacity (Not % ) 1065 l l
- 8. If Changes Occur in Capacity Ratings (Items Nunber 3 Through 7) Since Last Report, Give Reasons:
N/A 9 Powe Level To Which Rastricted, if Any (Not %): W/A
- 10. Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumulative a
- 11. Hours in Reporting Period 744 2184 97.176
- 12. Nurber of Hours Reactor Was Critical 0 0 45.306.08
- 13. Reector Reserve Shutdown Hours 0 0 5.149.55
- 14. Hours Generator On-Line 0 0 44,194.76
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated ( M ) 0 0 131.868.267
- 17. Gross Electrical Energy Generated ( M ) O __ . . 0 43.473.760
- 18. Not Electrical Energy Generated (M) -1.539 -8.767 42.032.381
- 19. Unit Service Factor 0 0 45.48
- 20. Unit Availability Factor 0 0 45.48
.._....___ _21._ Urtit. Capacity Factor (Using 10C , Net) 0 0 40.61
- 22. Unit Capacity Factor (Using DER Net) 0 0 40.61
- 23. Unit Forced Outage Rate 100 100 45.07
- 24. Shutdowns Scheduled Over Next 6 Mmths (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Cermercial Operation): Forecast Achioved INITIAL CRITICALITY INITIAL ELECTRICITY COP 9ERCI AL OPERATION (9/77)
Pags 20 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. J 0-259 Unit One DATE 04-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-25_0,1 MONTH MARCH 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net.) (MWe-Net) 1 -3 17 -4 2 -2 18 -3 3 -2 19 -4 4 -2 20 -3 5 i -2 21 -3 6 -2 22 -3 7 -2 23 -4 8 -2 ,, 24 -3 9 -2 25 -2 10 -2 26 -2 11 -2 27 -2 12 -2 28 -2 13 -2 29 -3 14 -4 30 -3 15 -4 31 -4 16 -4 4
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)
}
. Page 21
, AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 Unit Two DATE 04-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH MARCH 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 -3 17 -2 2 -3 18 -2 3 -3 19 -2 4 -3 20 -2 5 t -3 21 -2 6 -3 22 -2 7 -2 23 -2 8 -2 24 -2 9 -2 25 -2 10 -2 26 -2 11 -2 27 -2 12 -2 28 -3 13 -2 29 -2 14 -2 , 30 -2 15 -2 31 -2 16 -2 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)
s t Page 22 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Unit Three DATE 04-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)129-2507 MONTH MARCH 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Wet) (MWe-Net) 1 -2 17 -2 2 -2 18 -2 3 -2 19 -2 4 -2 20 -2 5 -2 21 -2 6 -2 22 -2 7 -2 23 -2 8 -2 24 -2 9 -2 25 -2 10 -2 26 -2 11 -2 27 -2 12 -2 28 -2 13 -2 29 -2 14 -2 30 -2 15 -2 31 -2 16 -2 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)
1 e e I
i DOCKET NO. 50-259 IINIISillllDOWNS AND POWER MEDUCTIONS UNIT NAME One t DATE 04-Ol-RR COf.lPLETED By J. D. Crawford REPORT hlONill March
, TELErilONE (205) 729-J507
. "E - -
No. Date
,, 5E 3 . Yk Iiccusce [-r, f4 Cause & Correceive g-5g 5 25& Event gg ci 3 Action su
$$ 5 3;Zg Repose a mO !' Psevens Recurrence a 4 _ u O
315 03/01/88 F 744 E 4 Administrative hold to resolve '
various TVA and NRC concerns.
~
I 2 3 4
- F: Forced Reason: hiciliod:
- S. S(hedulcil Exhibit C-Insisuctions A E.auipment Failure (Explain) I klanual for Psepasation of Data 11-Maintenance or Tess 2 hl.mual Scram. Enisy Sheets for 1.icensee C-Refuciang 3-Automatic Scram. @
Evens Reguns (1 ER) File INilRLG. j D-Regulatosy Restriction 4 Othes (Explain) 0161)
. E Opesator 1:4 ming & l.icense Exammainm F-Administ rative 5 O
G-Og< rational l's sus I F mplas.i) thlabit I - Same Somce 19/7J) 11 Gihes (I aplain)
i .
I t,3 Nil SilU1 DOWNS AND POWER REDUC 110NS DOCKET NO. 50-260
, UNIT NAME WO DATE 04-01-RR COMPLETED sy J. D. Crawford REPORT AIONHI March TELEPilONE (205) 729-2507
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c 305 03/01/88 F 744 F 4' '
Administrative hold to resolve various TVA and NRC concerns.
4 I 2 3 4 F fortcJ Reason:
S Sibcduled kicthod: likinbis G - Insituctions A E.guipinen: I ailuse (Explain) I klannat 11 Alaintenaswc or Test fo Picpaution of Data m 2 klanual Scram. Enisy SI.cces fus I isensee C-Refucting 3-Autonutic Sira n.
($
D Regulatoiy Rcs sittion Eveni I(cposi (I ER ) l'ile (NilRI G. - (D
-4 Ollect (limplain) 0161) h>
, E Opcsator Tsaisiingi i sccuse Exaannution
- F-Adininiuutive 5 G Operaliosul I eror (l'aplar.a) ps/M) II Other (l~ uplain) liliabit 1 - Same Somce
I l -
DOCKET NO. 50-2 %
hNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Three
! DATE 04-01-88 COMPLETED BY n rwurnrd
. 1-REPORT MON 111 March (205) 729-2507 TELEPilONE
. %= . -
c
, .5 g 'h jY5 Liccosce E-r. g4 Cause & Corrective N. . . Date g Eg s 2g& Event
[? g Aoion to 8- :
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- s*! u 6
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157 03-01-88 F 744 F 4 Administrative hold to resolve various TVA and talc concerns.
~
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I 2 3 4 e I~ l'orced Itcasor3: klethod:
S St heduled Exhibit G -Instrudious A-E.gurpment Failure (Explain) 1 -Manual for Preparation of Data B-Maintenance oi Test y 2 M.inual Scram. Entry Sheets for Licensee ce C-Refochog 3 Automatic Scram.
D Regulatory Restriction Eveni Repon (LER) File (NtlRLG- $
4-Other (Explain) 0161)
E-Operati.: Training & License Exanun.iimn g vi F-Ad minist rative 5 G-Operational frror (I xpl.n.il Estabit I- Same Source (9/ N ) II Oiher (E xplam)
O TV A 7182 A (ONP4 811 NUCLEAR PLANT OPERATING STATISTICS Page 26 Browns Ferry Nuclear Plant Period Hours 744 Month March 19 L ltem No. Unit No. I' nit 1 Un i e. 2 fini* 3 Olan*
1 Avef ace Houriv Gross Load, kW 0 0 0 0 2 Maximum Hour Net Generation. MWh 0 0 0 0 3 Core Thermal Energy Gen, GWD (t)2 0 0 0 0 4 Steam Gen. Thermal Energy Gen.. GWD (t)2 j 5 Gross Electrical Gen., MWh 0 0 0 0 7 6 Station Use. MWh 1978 1783 1539 5300 h 7 Net Electrical Gen., MWh -1978 -1783 -1539 -5300
$ 8 Station Use. Percent 0 0 0 0 9 Accum. Core Avg. Exoosure. MWD /Toni 0 0 0 0 10 CTEG This Month.100 BTU O O O O 11 SGTEG This Month.1068TU 1?
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 j 16 Turbine Avani. Facto., Percent 0 0 0 0
[ 17 Generator Avail. Factor. percent 0 0 0 0 0 18 Turbooen, Avail. F3Clor. Percen. 0 0 0 0
$' 19 meactor Avad. F3ctor. Percent 0 0 0 0
- 20 Unit Ayahl Factor. Percent 0 0 0 0 21 r u,bme Startuos 0 0 0 0 22 Reactor Cold Startuns 0 0 0 0
??
> 24 Gross Heat RJte, Blu,kWh 0 0 0 0
[ 25 Net Heat Rate. Blu/kWh 0 0 0 0 1 26 3 27 g 28 Throttle Pressure. os.g 0 0 0 0 I 29 Throttle Temocrature. 'F 0 0 0 0
{ 30 Ex haust Pressure, InHg Abs. 0 0 0 0 E 31 Intake Water Temo.. *F 0 0 0 0 0 32 33 Main Feedwater. M tbihr j 34
$ 35 36 37 Full Power Caoacity. EFPD (4) (4) (4) 38 Accom. Cycle Full Power Days. EFPO (4) (4) (4) j 39 Oil Fired for Generation. Gallons 5,920 2 40 Od Weatino Value. Btu / Gal 139,900 11 Desel Generation. VWh 79.8 19 Man. Hour Net Gen. i Max. Day Net Gen. Load MWh Time Date l MWh I Date Factor *4 3 43 0 i O l 0 _
$ Remarks: A For 8FNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.
j 2(t) indicates Tnermat Energy.
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MAINTEXANCE
SUMMARY
4
- _ , , , . ,, .-.,-.n,.,_,,__,___,-, . . - - , ,_n,,,,. - - , - _ _ , , - - , - - , , -- , - - - - _ -
ELECTRICAL TECHNICAL SECTION MONTHLY REPORT 9*
MARCH 1988 Unit Common Major Routine Activities--
ELECTRICAL EQUIPMENT LIST: 371 drawings were received in February 1988.
4,356 drawings are in backlog.
Fuse Control Program: EMI 92 is being revised. Drawing review continues and the fuse input sheets will begin to be put into EQIS in the latter part of April, 1988. Information and material needed for operations to replace fuses should be ready by the first part of April,1988. The fuse engraving report, revision "C", fuse relabeling effort is ready to begin.
RPS reliability study is complete.
Unit two main generator work continues. It has been determined that the T-70 stator bar must be replaced. Working with General Electric to make arrangements.
Prepared and reviewed procedure revisions to support restart testing.
Performed SI, MR and PM item reviews to support fuel reconstitution.
CIRCUIT BREAKER REBUILDS: 4160V 480/250V Total number of breakers to be rebuilt 303 483 Total number of breakers rebuilt 9 17 Completed this moonth 0 1 A major revision was made to EMI-18, calibration of pump level switches. This will allow calibration and/or inspection of twenty-two (22) level switches.
Thirteen investigations and dispositions were completed for measuring and testing equipment returned from the Central Lab out of aolerance.
Replaced filter capacitors to support restart testing on shutdown board battery chargers C, D, 3EB and spare.
Restart testing complete on shutdown board chargers C and D. Charger 3EB spare test deficiencies resolved by CAQR.
Diesel Generator 3C battery charger A out of service. Parts are on order.
Twelve (12) cells with loose posts removed form D/G "D" and replaced with new 3DCV-9 batteries.
Submitted revisions to ECI-0-254-BAT 001, 2SI-4.9.A.2.c(B).
l i
Elsetrien1 TEchnicci Section #9' Monthly Report Shutdown board charger B temporarily returned to service until parts can be fabricated.
Technical reviews were performed on S0 procedures during March.
Standby gas treatment heater inspection Surveillance Instructions were performed. ANSI NS10-1975 standards were met..
Grounded cable was replaced on SBGT Train A.
Unit one TIP shear valve E was repaired after a RADCON technician damaged it during survey, a
0-rings were changed out on relays for RHRSW pumps C1 and D3.
Major maintenance continues on 500KV air circuit breaker no. 5214.
The 25 ton (TV 91171) Grove crane being used to place the mufflers on 5214 tipped over on. March 30, 1988 and dropped the boom on top of the current transformer column of "B" phase of the breaker. The breaker head was tipped over a few degrees and was also rotated several degrees about the vertical axis. Two large pieces of porcelain were cracked at the head. Investigation continues'to determine internal damage. The crane was uprighted the following ;
day with an outage on Bus 1, section 1 for safety.
500 KV main transformer bank no. 2 was removed from service March 3,1988 due to oil leaks at cover bolts. Leak repairs were made during March, 1988. '
011 in main transformers 2A and 2B were found to be below standard due to age. Treatment with purivac continues into April, 1988 in hopes of saving the oil. Failure to save the oil vill result in it being replaced. The outage will continue into April, 1988.
LIMITOROUE VALVE GROUP:
MR review and close-outs were worked during March, 1988 with the following results:
Electrical and mechanical MRs on valve work were at a total of approximately 239. Mrs in XP status being processed for history are complete, (78 total).
Drawing discrepancies were processed on 15 FCVs in the field with no problems l at present.
An ITC was processed on EMI-18 for CSSC butterfly valves to allow setting by
- degrees.
l l
Page 33 Electrical Technical Section Monthly Report An ITC was processed on EMI-18.1 for minimum training radius prob!ces found in the field.
Two Electrical Technical personnel attended two weeks of training. One week e on limicorque valves and one week on MOVATS.
2-FCV 74-74 and 74-75: Revised W.P. 2231-84 (ECN P3117) to install new molded case circuit breakers and new thermal overloads. Added third phase overload kit on both valves. Added steps to correct minimum cable training radius problem on 2-FCV 74-75.
2-FCV 75-23 and 25: Revised W.P. 2195-84 (ECN P3118) to install new molded case circuit breakers and thermal overloads. Added a third phase overload kit on both valves.
2-FCV 75-51 and 53: Revised W.P. 2094-85 (ECN P3118) to ir. stall new molded case circuit b.eakers and thermal overloads. Added a third phase overload kit on both valves. Added steps to correct minimum cable training radius problem on 2-FCV 75-51, to reroute and replace conduit.
Orange Folder 88-0008 was closed during the month of April,1988.
Total CSSU limitorque rebuilds stand at eight (8) valves. Tctal fieldwork complete is at twelve (12). Field inspections stand at 17 and signature analysis is eleven (11) total.
One Electrical Technical engineer assigned to the valve group attended a one day workshop at the Chattanooga office. All TVA nuclear sites were represented. This will occur once per quarter so that information pertaining to Motor Operated Valves can be exchanged.
ELECTRICAL TECHNICAL SECTION MONTHLY REPORT -
MARCH 1988 paga 34 4
I. WORK TIME SCHEDULE Received /
Assigned Comele t'ed Qpan Red Folders 0 1 11 Orange Folders 4 4 10 Yellow Folders 1 0 2 Blue Folders 10 9 6 Purple Folders 4 2 2 Active Engineering Assignments 6 2 20 Engineering Backlog 5 5 65 New Engineering Assignments 0 0 0 Completed Engineering Assignments 0 0 0 II. COMMITMENT TRACKING Licensing Issues (NCO & SLT)
NCO 2 1 20 SLT 0 0 3 PORS Tracking It. i (BFC) 0 0 3 CAQRs 7 8 9 Average Age of CAQRs Two months and twenty five days Employee Concerns 0 0 1 Safety Issues List 0 0 0 III. STAFFING LEVELS AND TRAINING f
EersonJgl Aceroved Headcounts Current Headcounts ASP 36 31 :
ATL 4 4 l
HTL 0 0 Contractors _1 _.a TOTAL 45 39 IV. OVERTIME 8.07.
V. PROCEDURES I 14 procedures PORC approved 9 procedures sent to Wor;d Processing VI. 269 Outstanding Status "H" MRs 31 OUTSTANDING STATUS "Q" MRs i
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Pago 35 I&C TECHNICAL MARCH 1988 I. Work Item Schedule Received / Completed Open Assigned Red Folders 0 0 1 Orange Folders 1 2 8 Yellow Folders 0 0 0 Blue Folders 4 3 3 Purple Folders 6 3 4 Total Assignments
. Active Engineering Assignments 13 25 35 Engineering Backlog 13 MRs (Status "H" and "Q") 76H 76 II. Commitment Tracking Licersing Issues (NCO & SLT)
NCO O 4 12 SLT 0 4 3
' PORS Tracking Items (BFC) 0 1 2 CAQR (Onsite) 0 3 10 CAQR (Off-site) 2 .2 0 Average Age of CAQRs 8.4 months Employee Concerns 0 0 2 Safety Issues List 0 0 0 III. Staffing Levels and Training
- Aceroved Headcounts Current Headcounts Personnel ASP 17 13 ATL 4 5 HTL 0 0 Contractors - 4 TOTAL 21 22
, IV. Overti:se 6.75%
V. Procedures 54 procedures were sent to Word Processing
Pago 36 I&C TECHNICAL MARCH 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 Spares Parts 0%
V.B.3 Spares 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 and Setpoint Documents to support i these instructions are also being issued. t i
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Mechanicci Technical Section Monthly Report Paga 37 Common Unit only (Unit 0)
March 1988 Common No major nonroutine activities.
- 1. Closed the following commitments:
- b. NCO 85077010 - Core Spray Over-Pressurization Event
- c. NCO 870058001 - Install Proper Worm Gear in Valve 2-FCV-73-2
- d. NCO 870249001 - MSRVs Exceeding TS Tolerance on Setpoints
- e. R35 880218 678 - Approval of Master Specification MS-NEB-010
- f. R35 880222 725 - Approval of Master Specification MS-CEB-013
- g. R35 880222 741 - Management & Personnel Allegation (MP) ECP-87-BF-CS7
- h. R35 880222 742 - Approval of Master Specification MS-CEB-010
- 1. R35 880224 799 - Approval of Master Specification MS-MEB-004
- j. 235 880316 604 - Approval of Master Specification MS-CEB-007
- k. EEB-001 (RO) - Engineering Requirements Specification
- 1. G-29(RO) - PS 3.M.3.1 Add.5 (RS)
- m. G-29(RO) - DWP-SM1.1.3(21)
- o. G-29(RO) - PF1079(R1)
- p. G-29(RO) - TB103.103-1(R2)
! r. G-29(RO) - PS 3.M.3.1 Add.4 (R3)
- s. G-29(RO) - Material Handling & Processing Specification
- t. G-29(RO) - Material Fabrication & Handling Requirements
- u. N-VT-1(R10) - Preservice & Inservice Visual Exam l v. N-VT-4(RJ) - System Pressure Test - Visual Exam l
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y- Mechanicci Technical Section Mtnthly Report -
Paq3 38 Commen Unit only (Unit 0)
March 1988 .
- v. NQAM,I,2.16(QN) - Quality Notice - Corrective Action ,
- x. NQAM,II,2(QN)(RO) - Quality Notice - General Maintenance Activities
- y. NQAM,II,5.1(RS) - Nuclear Power Plant Components
- z. NQAM,II,6.3(R1) - Non-Destructive Examination aa. SRN-G-38 Installing Insulated Cables Rated Up To 15,000 Volts bb. SRN-G-38-23(RS) - Revision for Installing Irsulated Cables Rated Up To 15,000 Volta ec. SRN-G-38-24(RS) - Revision for Installing Insulated Cables Rated Up To 15,000 Volts
- 2. The following instructions were approved, revised, or cancelled.
- a. MSI-0-000-PRO-017 - General Torquing Guide
- b. MCI-0-001-VLV-011 - Reactor Feedvater Pump Turbine High-Pressure Stop 3 Valve FCV-1-127, FCV-1-135, and FCV-1-143; Disassembly, Inspection,
. Rework, and Reassembly
- c. MCI-0-002-PMP002 - Condensate Booster Pump - Ingersoll Rand; Disassembly, Inspection, Rework, and Reassembly
- d. MCI-0-003-PMP001 - Reactor Feedvater Pump - Pacific 16X HVCN; Disassembly, Inspection, Revork, and Reassembly
- e. MCI-0-023-PMP001 - RER Service Water Pump Room Undervatering Pump; Disassembly, Inspection, Rework, and Reassembly
- f. MCI-0-082-ENG-010 - Standby Diesel Engine Rocker Arm and Valve Bridge; ;
Disassembly, Inspection, Rework, and Reassembly
- g. MCI-0-085-VLV-007 - Cooling Water Riser Check Valve; Disassembly, Inspection, Rework, and Reassembly i h. BT-2.22 - Mechanical Maintenance Instruction Writers Guide i
- 1. MMG-032 - Emergency Showers and Eye Baths '
- j. MMG-039 - Application of Xypex Water Proofing to Existing Non-CSSC Concrete Structuras
- k. MMI Hydraulic Shock and Sway Arrestor - Bergen-Paterson and Grinnell, Unit Removal; Disassembly, Reassembly, and Replacement
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Mechaaicc1 Technical-Section Monthly Rsport Paga 39 Common Unit only (Unit 0)
March 1988
- 1. MMI Residual Heat Removal (RHR) Heat Exchanger Maintenance i
- n. MMI-117 - Overhead Traveling Bridge Cranes, Inspection Testing and Preventive Maintenance
- o. MMI-141 - Lubrication of Equipment
- p. MMI-154 - Repairs Using Belzona Molecular Metals and Similar Products
- q. MMI-163 - Surface Preparation for Non-Destructive Examination
- r. MMI-169 - Chemical Cleaning of Chilled Water System for Units 1 and 2 Reactor Building Control Bay
- s. MMI-174 - Replacement of Compression Fittings
- t. MMI-178 - Maintenance of V-Belt Drives
- u. MMI-184 - Procedure for Replacing RSW/AFFF Piping i
- v. MMI-186 - Installing Blanks to Allow Maintenance on Valves 23-34, 40, 46, and 52 (all units)
- 3. The following CAQRs (Conditions Adverse to Quality Reports) were closed.
- a. BFP 87-0890 - RHR "1C' Heat Exchanger
- b. Generic Review (SEQ) 87-1560 - Throughwa11 Laak in Valve Body of Seal Water Tiller Bypass
- 4. The Mechanical Technical Section devoted 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> to training during the month of March. ,
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Ptga 40 MODIFICATIONS MONTMLY REPORT MARCH 1988 MAJOR WORK PERFORMED ECN NARRATIVE Appendix R P0808 Continued conduit and cable work on control power circuits (workplan 2048-87 and 2047-87).
P0879 Continued work on fire door upgrade (work plans 2068-87 and 2212-87).
P0883 Continued changeout of fuses and fuse blocks (workplan 2111-87).
P0885 Continued conduit and support work on RB fire detectors (workplans 2012-87, 2013-87, 2014-87, and 2015-87).
P0887 Started work on conduit reroute (workplan
, 2182-86).
P0889 Continued reroute of conduit for separation (workplan 2053-87 and 2054-87).
P0914 Started craft work on fuse and fuse block replacement (workplans 3027-86 and 3028-86).
Environmental Qualification P3145 Continued electrical conduit sealing activities (workplans 2074-85, 2075-85, and 2078-85).
P3163 Continued drywell cable replacement (workplan 2237-87).
P3180 Continued electrical work associated with containment penetration replacement (work-plans 2036-87, 2105-87, 2022-87, and 2083-88).
Field completed workplans 2101-86, 2102-86, 2103-86, and 2104-86).
P3205 Continued small piping and support work on H02 2 analyzer lines (workplans 2158-87, 2159-87, 2199-87, 2200-87, 2160-87, 2161-87, 2162-87, 2201-87, 2202-87, and 2163-87).
MAJOR WORK PERFORMED ECW NARRATIVE Environmental Qualification P7032 Started cable replacement in steam tunnel (Continued) (workplan 2069-88).
P7039 Completed craf t work on shutdown transformer 2B replacement (workplan 2073-88).
S ismic Issues B0033 Started SBGT support rework (workplan 3003-88).
P0289 Replaced 3 supports in pipe tunnels 3B and 3D (workplan 2071-88).
P0370 Continued structural work on seismic qualification an,d designation of block walls (workplans 1030-87, 3004-88, 2092-87, and 3024-87).
P0361 SMNI rework of torus attached piping and drain supports continued. Workplans 2058-84, 2079-84, 2176-87, and 2230-87 were field completed.
P0859 Continued work on catwalks R9 and 13 (workplan s 2066-87 and 2140-87).
P0946 Started craft work seismic qualification of unit 3 RB conduit (workplan 3038-87).
P0998 Drywell catwelk upper elevation work reached 95% complete. (workplans 2147-8/ and 2148-87).
P2036 Continued additional 79-14 support fixes to CRD return piping (workplan 1036-87).
P2042 Continued RHR support rework (workplan 1035-87).
P2044 Completed craft work on unit 1 RB drain and sump pump 79-14 modifications (workplan 1033-87).
1 P2072 Started additional 19-14 fixes on unit 3 RBCCW system (workplan 3034-87).
P2088 Continued field work on additional 79-14 fixes to fuel pool cooling system (workplan 2274-87).
P2090 Started additional 79-14 fixes on radwaste sump pump discharge system (workplan 2273-87).
1
F MAJOR WORK PERFORMED 12H NARRATIVE ,
soismic Issues P2154 Completed field work on RHRSW and EECW outage (Continued) fixes (workplans 0015-88, 0017-88, and 2062-88). :
P1018 Continued work on drywell MVAC seismic qualification (workplans 2282-87, 2281-87, 2280-87, 2279.a?, and 2278-87).
P7029 Continued repair of lower drywell structural steel (workplan 2234-87).
P7083 Continued craft work on common area tubing seirmic qualification (workplans 0007-88 0008-88, 0009-88, and 0010-83).
P7085 Continued craft work on unit 2 tubing seismic qualification (workplans 2058-88, 2059-88 and 2060-88).
TMI Mods P0324 Continued electrical work on high-range containment radiation monitors (workplan 2009-85). Field completed workplan 2160-86.
P0354 Continued sample line work on stack radiation monitor (workplan 2142-85).
Other P0085 Started reroute of conduit on drywell pressure and temperature upgrade (workplan 2192-87).
P0286 Continued work on yard security lighting (workplans 0023-86 and 0022-86).
P0384 Continued tubing and electrical work on containment purge valves (workplan 2049-86).
P0392 Continued SMNI rework of scram discharge volume supports. Field completed workplan 2137-84.
P0569 Continued support work on RPV vent line (workplans 2051-84 and 2204-84).
P0720 Continued work of jet pump instrumentation lines (workplan 2109-85).
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9 MAJOR WORK PERFORMED KCR . NARRATIVE Other (Continued) P0956 Continued installation of duct and duct supports for new shutdown board room HVAC
. (workplans 2228-87, 2229-87, 2258-87, 2253-87, 2254-87, 2262-87, 2263-87, and 2249-87).
P1001 RHR, RWCU, and Recirculation System support work continued (workplans 2283-87, 2284-87, 2285-87, 2009-88, and 2008-88).
P5269 Installation of supports for uninterruptable domineralized water connection for torus water level transmitters continued (workplans 2292-87, 2065-86, and 2293-87).
P5480 Installation of vessel drain supports continued (workplan 2218-87).
P5291 Continued reactor water level instrument sense line modification (workplans 2153-87, 2134-87, and 2232-86).
P00848 Replaced cable ES2800-II to IEEE standards.
N/A Began tube removal on unit 2 condenser--removed 18,000 of 54,000 tubes.
P7045 Began valve and support modifications for ATWS/ARI (workplan 2115-88).
P7002 Fleid work started of hydrogen water ;
chemistry modifications (workplan 2088-84).
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Paga 44 CHEMISTRY
SUMMARY
MARCH 1988 Primary Coolant Chemisigg 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 a 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 condvetivity and chloride have not been exceeded.
Unit 3 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.
a PR DIARY CTLAM CHE'llSTRY .
- tARCH 1443 pig 3 45 Pa'ameter Unit i Unit 2 Unit 3 .
- 1. Cross 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 (pei/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 ( ci/ml)
High 6.987E-5 6.737E-5 1.45E-4 Low 5.429E-5 4.366E-5 9.643E-5
- Average 6.012E-5 5.602E-5 1.26E-4
- 4. Iodine-131 (pei/ml)
High <8.0$E-7 (6.78E-7 <3.14E-7 Low cl.1:E-7 <3.08E-7 <1.96E-7
- Average <5.64E-? <5.31E-7 <l.05E-7
- 5. Iodine-131: Iodine-133 Ratio High N/A N/A N/A
., Low N/A N/A N/A Average N/A
- N/A N/A i
-, - _n. ,-~~ v , - - , , . , - , + - , ,,-- - - ,-- ,.- --,, , ,, , - . - , - - . - ,
Paga 46
. PRI.'!ARY C00L.\,'iT CHDlISTRY (Cont inued )
STARCH 1988 Parameter Unit 1 Unit 2 Unit 3
- 6. Chloride (ppb)
High (LO <10 <20 Law (10 <10 <10 Average <t0 <10 <20
- 7. pH025"C High 6.1 6.2 6.1 Low 5.S 5.3 5.7 Average 6.0 6.0 6.0
- 8. Conductivity ( peho / c m@ 25 ~'C )
High 0.16 0.77 0.14 Low 0.1L 0.43 0.080 Average 0.14 0.62 0.10 J
t paga 47 t CHEMISTRY
SUMMARY
(Con'tinued) -
I MARCH 1988 Environmental Technical Soecification Reauirements The ambient upstream river temperatures (24-hr. avs max) averaged 53.2'F 4
ranging from a high of 49.0*F on March 16 to 60.6*F on March 31. The downstream temperature varied from 48.6'T on March 1 to 61.2*F on March 30.
The sedimentation pond (DSN 102) remained out of service for the entire month.
The plant did not experience any compliance problems during the month. DSN 110, Unit 1 & 2 office building drain total suspended solids (TSS) concentrations did not exceed the NPDES permit limit of 100 mg/L as it had -
during thy previous three months.
The sewage lagoon (DSN 111) BOD daily average e neentrati n f r the month 5
was 38 mg/L. This exceedance was due to algal growth in the lagoon. The discharge was closed on March 20 and remainder of the month. The TSS average 1
for the month was 43 as/L. The flow averaged 43,930 gallons per day and c varied betvcen 17,856 spd and 60,192 spd. !
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Pcg3 48 AIRDCRNE RELEASE 3'1) t i M eT br i l eiQE SUMMATION CF ALL RELEASES UNIT THIS MONTH A. FISSION AND ACTIVATION GASES
- 1. TOTAL RFLEASE CI , G.0SE 01 '
O. AVERAliE ret. EASE R ATE FOR PERIOD UCI/3EC 2.572 01
- 3. PERCENT OF TECH. SPEC. LIMIT (0.05 CI/SEC) % 0.00E-01 B. IGDINE3
- 1. TOTAL ICDINE - 131 CI 2.44E-05
- 2. AVERACE RELEASE RATE FOR PERIOD UCI/3EC 3.04E-OS
- 3. PERCENT OF TECH. SPEC. L!n!Tt0 4 UCI/SEC) *; 0 00E-01 C. PARTICULATES
- i. PARTICULATES WITH HALF-LIFES , OR = TJ S liAYS CI : 1.44E-04
- 2. AV>IR AtiE RELEASE RA1E FOR PERIOD UCI/SEC : 4.34E-Ob J. PERCENT OF TECH. SPEC. LinIT(0.4 UC,I/3'iC) "
0 00E-01
- 1. GNOMS ALPHA RADI0 ACTIVITY CI ' 1.40E-04 i D. T R I T IUl1
- 1. TOTAL RELEASE CI :.JeE-00
- 0. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 4.812-02
- 3. PERCENT UF TECHNICAL SPECIFICATION LJHIT % 1 54t-0;
- 4. OROUHO LEVEL KELEASE CI 2.C:E-3; G. EL' ATED RhLEASE CI 1.09E-04 (1) BEFORTING PERIOD 35 DAY 3
P:g] 49 -
AIRBORNE RELEASES (CONTINUED)
MARCH 1788 -
ELEVATED RELEASES A. FISSION GASES UNIT THIS MONTH RR-85M CI < 1.17E-01 KR-SS CI : 4.26E 01 RR-r/ CI - 7.92E-00 KR-SS CI 1 01E-G1 XE-133 CI : 1.71E-01 XE-135d CI s 0 30E-01 XE-135 CI , 4.73E-0; XE-133 CI - !.0SE-01 OTHERS(SPECIFY)
TOTAL FOR FERIOD CI 4.3?E 01 B. 10 DINES I-131 CI < 3.75E-06 I-133 CI < 6.53E-00 I-135 CI 1.16E-01 TOTAL FOR FERIOD CI 1.16E-01
Paga 50 AIRBORiiE RELEASE 3 ( C 0ti T I Ni)Eit :
MARCH 1993 ELEVATED RELEASES C. PAR' .LATES UNIT THIS MONTH SR-89 C! < 5 35E-07 SR-90 CI s 1.93E-07 CS-134 CI s 3 06E-06 C3-137 CI 2.17E-06 BA-140 CI 1 17E-05 LA-140 CI 4.73E-04 0 T HE R S ( S P EC I F't )
TOTAL FOR PERIOD CI :.27E-05 D. TRITIUM CI 1.73E-04
Pag 3 51 -
AIRBORNE RELEASES (CONTINUED)
MARCH 1788 GROUHu REl. EASES A. FISSION GASES UNIT THIS MONTH KR-85M CI : ?.27E-02 KR-85 CI - 3.3iE 01 KR-87 CI ~ 4.5?E-01 KR-SS CI : o.65E-01 XE-133 CI < 3.59E-01 XE-135N CI : 3.30E-01 XE-135 CI < 2.14E-01 XE-133' CI s 1.40E 00 GTHERS(SPECIFY)
TOTAL FOR PERIOD CI ' 3.70E 01
Paga 02 AIRBORNE RELEASES (CONTINUED)
- MARCH 1933 GROUNO RELEASES C. PARTICULATES UNIT THIS MONTH SR-89 CI < 3.1;E-06 SR-90 CI < 1.14E-06 CS-134 CI '
, 1.00E-05 CS-137 CI < 0.062-05 B A-110 CI 6.08E-05 LA-140 CI -s 2.03E-03 OTHERS(SPECIFY)
TOTAL FOR FERIOD CI 1.02E-04 D. TRITIUM CI 2.0$E-02
4 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS .
LIQUID RELEASES '
MARCHr 1988 .
RADI0 ACTIVE LIQUID EFFLUENTS
- 1. OROSS RADI0 ACTIVITY UNITS a) TOTAL RELEASE CURIES 1 29E-02 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 7 50E-10 e) PERCENT OF APPLICABLE LIMIT (1E-07 UCI/ML) % 7.50E-01
- 2. TRITIUM a) TOTAL RELEASE CURIES 1 23E-01 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 7.18E-09 c) PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) % ?.39E-04 (1)
- 3. DISSOLVED NOBLE GASES ,.
._____ ....... __ _. t a) TOTAL RELEASE CURIES < 5.46E-04 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML < 3.10E-11 c) PERCENT OF APPLICABLE LIMIT (2E-0.4 UCI/ML) % < 1.59E-05
- 4. GROSS ALPHA RADI0 ACTIVITY a) TOTAL RELEASE CURIES <2.50E-04 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML <1 45E-11
- 5. VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 4.58E 06
..________. ______ .______________ ._. .. l.
- 6. VOLUME OF DILUTION WATER LITERS 1.72E 10 (1) INCLUDES XE-133, Xe-135, AND OTHERS
BROWNS FERRY NUCLEAR PLANT E9' MONTHLY REPORT CALCULATIONS LIQUID RELEASES MARCH 1988 ISOTOPES RELEASED UNITS CI CR-51 < 1 79E-03 MN-54 4.38E-06 CO-58 < 2.25E-04 FE-59 < 4.19E-04 CO-60 2.24E-03 ZN-65 6.70E-04 NB-95 < 1.96E-04 ZR-95 < 3.47E-04 4
MOTC-99M < 1.63E-04 I-131 < 2.20E-04 XE-133 < 4.19E-04 1
CS-134 2 12E-03 XE-135 < 1 27E-04 CS-137 7.84E-03 BA-140 < 8.45E-04 LA-140 < 1 28E-04 CE-141 < 2.78E-04 SR-89 ( 2.05E-04 SR-90 < 1 06E-04
BROWNS FERRY NUCLEAR' PLANT Paga 55 -[
MONTHLY REPORT CALCULATIONS LIQUID RELEASES i MARCHs 1988
- OTHERS UNITS t CI i t
SB-125 1 52E-05 I i l
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Pcgo (6 BROWNS FERRY NUCLEAR PLANT
, MONTHLY REPORT CALCULATIONS LIQUID RELEASES MARCH, 1988 LAUNDRY DRAIN VOLUME RELEASEDI 0.0 GALLONS FLOOR DRAIN VOLUME RELEASEDI '704721 0 0ALLONS WASTE SAMPLE TANK VOLUME RELEASEDI 504820.4 GALLONS DISTILLATE TANK VOLUME RELEASEDt 0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLUME RELEASEDt 00 GALLONS TOTAL VOLUME RELEASED TO THE RIVERt 1209541 5 GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR MONTHi 1 00E-08 UCI/ML A/D LON0EST RELEASE TIME FOR MONTHi 340 MINUTES SHORTEST RELEASE TIME FOR MONTH 1 140 MINUTES TOTAL TIME OF RELEASES FOR MONTH 11333 MINUTES AVERAGE TIME FOR BATCH RELEASESt 276 MINUTES COMPOSITE INFORMATIONt COMPOSITE CI AFTER DILUTION UCI/ML RELEASED UCI/ML SR-09 < 4.48E-08 < 2.05E-04 < 1 19E-11 SR !0 < 2.31E-08 < 1.06E-04 < 6.16E-12 H-3 2.69E-05 '
1.23E-01 7.18E-09 GROSS ALPHA < 5.45E-08 < 2.50E-04 < 1.45E-11 NUMBER OF BATCHES RELEASEDt 41 NUMBER OF ADMINISTRATIVE LIMIT VIOLATIONSI O NUMBER OF TECHNICAL SPECIFICATION VIOLATIONSt 0
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RESIN USAGE REPORT . P ga 57 MARCH 1988 RESIN CONSUMED (CU.FT.) -
- 7. o f Total 31gd POWDEX ECODEX ECOSORB EPIFLOC Total Radvaste Floor Drain Filter 26.8 0 78 0 0 38 116 Waste Demineralizer 30.1 130 0 0 0 0 130 .
Waste Filter 38.4 0 144 0 22 0 166 Fuel Pool Demins 0 0 0 0 0 0 0 Reactor Water Cleanuo Unit 1 0 0 0 0 0 0 0 Unit 2 0 0 0 0 0 0 0 Unit 3 0 0 0 0 0 0 0 Cond. Demins Unit 1 0 0 0 0 0 0 0 Unit 2 4.7 0 20 0 0 0 20 Unit 3 0 0 0 0 0 0 0 Totals 100 130 242 0 22 38 432
4 TUIL CLADDING INTEGRITY PARAMETERS MARCH 1988 pcg3 gg Unit 1 Reactor Water Iodines (uci/sec.)
Date I-131_ I-132 I-133 I-134 I-135 Unit in Outage Fission Cases at Discharme of SJAE (uci/see) 2A11 E12M M31 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-13a I-135 Unit in Outage Fission Cases at Discharte of SJAE (uciliggl Egtg Elgy MR1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-132 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/see)
EA11 E12M M31 3e-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-131 Unit in Outage
WASTE TREATHENT SYSTEM TIS 00EPUTS MARQi 1988 l
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- , Paga 60 TESTING SUPMARY MARCH 1988 Survalliance Testina Unit 0 A total of 139 surveillance tests were completed per 43 different test instructions.
Unit 1 A total of 90 surveillance tests were completed on unit 1 per 36 different test instructions.
Unit 2 A total of 247 surveillance tests were completed on unit 2 per 31 different test instructions.
Unit 3 A total of 65 surveillance tests were completed on unit 3 per 20 different test instructions.
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Pcg3 61 TESTING SU! MARY (Continued)
MARCH 1938 P
1 F
(*hansas. Test, and Erneriments Raouirina Authorization t From the IIRC Pursuant to 10 CFR 50.59 M There were two revisions for unit 1, 2, and 3 technical specifications. -
Chansen. Testa. and treeriments not Raouirina Authorization from ifRC Pursuant to 10 CFR 50.59(a) .
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- i. There was one special test completed for this month. I
- i-4
- ST-8734 Test
Description:
CRD Diagnostic Testing was performed on the 1
! Unit 2 control rod drive mechanisms to access their coridition following a r i prolonged layup period.
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Pcgo 62 REACTOR VESSEL PATICUE USAGE EVALUATION MARCH 1988 The cumulative usage factors for the reactor vessel are as follows:
Usage Paetor Location Unit.1 UniL2 Unit 3 Shell at watet line 0.00620 0.00492 0.00431 Feedvater.nostle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360 9
. CMANCE IN PROCEDURE Pcg3 63 3 m MARCH 1988 ,
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i There were 403 revisions to plant instructions during the month; 394
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instructions were changed primarily for correction, and the remaining 9 revisions related to safe operation of the plant.
i Pt. ANT INSTRUCTION REVISIONS
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MARCH 1988 Cateaory Instruction Reason for Raouest
! Change in 19tI-178 Maintenance of To delete NRC commitment designation i Response to V-Belts Drives to statement about notifying Unit
! LER, IE Operator prior to removing any
) Bulletin, NRC equipment from service. To update
- Inspection precautions section as committed 4
Report, OPQA to via INP0 ISR 003.
- Audit, etc.
$ SDSP 7.6 Maintenance Request Change scops per CAQR BTS7-240, and Tracking revise process of instruction prepared in accordance with latest Tech Spec, change.
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SDSP 17.2 Post Modification To add the requirements of SDSP 17.1 Test Program "Evaluations of changes, tests, and experiments."
SI-4.4.A.1 Standby Liquid Incorporate comments concerning Control Pump Tunctional ECN E-2-P7065 and to correct Test, Unit 2. discrepancies noted in CAQR BTP 870639.
SI 4.4.A.2 Standby Liquid Incorporate comments concerning Control System Tunctional CAQR BTP 870633, correct design Test changes per ECN E-2-P7065.
SI 4.7.B 6 Standby Gas To correct error in scope, add ASTM Treatment Iodine Rer.sval D3803-79 and NRC Inspection, Report 86-11 Efficiency to references.
pago 64 i PLANT INSTRUCTION REVISIONS ,
DECEMBER 1987 Catamory Inst ruc t ion igason for teouest Change in Response to SI 4.10.A.1 Refueling New procedure to replace SI 4.10.A-1, i LER, IE Interlocks Functional Test, SDSP-2.14 review process.
Bulletin, NRC Unit 1.
4 Inspection Report, OPQA Audit, etc. SI 4.10.A.1 Refueling New procedure to replace SI 4.10.A-1 Interlocks Functional Test, SDSP 2.14 review process. l Unit 2.
, SI 4.10.A.1 Refueling dev procedure to replace SI 4.10.A-1, Interlocks Functional Test, SDSP 2.14 review process. '
Unit 3.
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CHANGE IN FACILITY DESIGN pago 65 dARCH 1988 Package Number Descriorion Safety Related ECN P0940 - Conduit Supports (WP&IR 1001-87) Installed / modified Unit I conduit supports in Class I structures, Unit i reactor building, elevation 519' - 0". The ECN was completed.
The modifications ensure that the various safety related conduits are seismically supported. Seismically supporting conduit did not affect any systems operation and provides added assurance that the affected systems vill operate as required to maintain an adequate margin of safety.
ECN P0935 - Conduit Supports (WP&IR 2007-87) - Install / modified conduit Unit 2 supports in the Unit 2 Control Bay. The ECN was completed.
The modifications ensure that the various safety-related conduits are seismically supported. Seismically supporting conduit did not affect any systems operation and provides added assurance that the affected systems vill operate as required to maintain as adequate margin of safety. ,
ECN P0937 - Conauit Supports - (WP&IR 1003-87) - Installed / modified conduit Unit 1 supports in the Unit 1 Control Bay. The ECN vas completed.
The modifications ensure that the various safety-related conduits are seismically supported. Sei:mically supporting cond"it did not affect any systems operation anc provides added assurance that the affected systees vill operate as required to maintain an adequate margin of safety.
CHANGE IN FACILITY DESIGri (Continued) Page 66 MARCH 1988 Packame Number Descriotion ___
Safety Related ECN P0931 - Conduit (WP&IR 2005-87) - Installed supports to Supports - Unit 2 seismically qualify conduits in the Unit 2, reactor building elevation 621' - 639.
The ECN was completed.
The modifications were required to satisfy the seismic requirements for Class I conduits in Category I structures.
ECN P0936 - Conduit (WP&IR 3000-87) - Installed Class IE conduit Support - Unit 3 supports in the Unit 3 Diesel Generator Building. The ECN was completed.
The modifications ensure that the various safety related conduit are seismically supported. Seismically supporting conduit did not affect any systems operation and provides added assurance that the affected systems will operate as required to maintain an adequate margin of safety.
ECN P0938 - Conduit Supports (WP&IR 0002-87) - Installed supports to Common seismically qualify conduits in the Standby Gas Treatment Building, elevation 565'-6 ".
l The ECN was. completed, l
l The modifications ensure that the various l safety-related conduits are seismically
- supported. Seistiically supporting conduit l did not affect any systems operation and provides added assurance that the affected systems vill operate as required to maintain l an adequate margin of safety.
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7 CHANGE IN FACILITY DESIGN (Continued) Page 67 MARCH 1988 ,
Packane Number Descriotion Safety Related ECN P0945 - Conduit (WP&IR 1003-87) - Installed / modified Supports Unit 1 conduit supports in the Unit 1, reactor building, elevation 621' - 0". The ECN was completed.
The modifications ensure that the various safety-related conduits are seismically supported. Seismically supporting conduit did not affect any systems operation and provides added assurance that the affected systems will operate as required to maintain an adequate margin of safety.
ECN P0126 - Various Systeus - (WP&IR 2123-86) - Installed supports per ECN Unit 2 on RPV sensing lines (systems 3 and 64),
panels 25-5A and 6A. A very small portion of the work covered by the ECN was completed.
ECN P3202 - RCIC Systems (WP&IR 2195-87) - Replaced 2-FSV-71-6A Unit 2 and 6B; 2-FSV-71-7A and 7B. The ECN was completed as it only covered Unit 2.
The replacement of the valves with environmentally qualified valves contributes to proper RCIC operation. The modification installed equipment upon which the FSAR and the implied margins of safety are based. The new configuration is now what the original configuration should have been in terms of environmental qualifications and functional capabilities. The margin of safety is not reduced.
ECN P0671 - Fire Protection (WP 3006-87) - Modified sprinkler piping Systems - Unit 3 supports in Battery Room 3 and Battery Board Room 3. A very small portion of the work covered by the ECN was completed.
DCN B00014A - CSSC Doors - (WP&IR 0034-87) - Replaced Huntington, Common No. 61D-160 inflatable seals with prespary EPDM E603, inflatable seals on door 226. The DCN was completed.
The replacement seals are of the same configuration as the old seals. The modification did not adversely affect the function of the reactor building equipment access doors. There was no affect on any other safety related equipment. Therefore, the margin of safety was not reduced.
CHANGE IN FACILITY DESIGN (Continued) Pago 68 MARCH 1988 Packare Number Descriotion Safety Related DCNs B00022A, 23A, 24A (WP&IR 2101-88) - Workplan was written for Fire Protection System - documentation only. Drawings were Units 1, 2, 3 as-constructed to provide appropriate splicing design for the Gamevell 29969 smoke detector leads and the existing Fire Protection System wiring. The DCNs were completed. The detectors will be replaced on as-needed basis by the applicable maintenance procedures. The DCNs were completed.
The modification replaces a Non Class IE terminal board with a water proof splice.
The margin of safety is not reduced because the water proof splice is more reliable than a Non Class IE terminal board in a harsh environment.
ECN PO 126 - Various (WP 2171-84) - Installed conduits and Systems - Unit 2 junction boxes in Board Room 2A and 2B for Division I and II ECCS ATU inverters.
Installed and terminated cables associated with the ECCS ATU inverters. Only a portion of the work covered by the ECN was completed.
ECN P3184 - HPCI System - (WP&IR) - Replaced and calibrated pressure Unit 2 switches PS-73-47A and 473. The ECN was not completed.
ECN P7081 - Various Systems - (WP&IR 2104-88) - As-Constructed drawings to Unit 2 reflect the replacement of the AISI 1018 l motor pinion gear keep with AISI 4140 keys.
l The replacement was for valves 2-FCV-68-003 t
and 079; 2-FCV-73-034, 030 and 044; 2-FCV-74-052, 053, 066, and 067. The ECN was totally completed as it only covered Unit 2.
Replacement of the pinion gear keys with the I stronger material reduced the possibility for l valve operator failure. The function of the l valves remains the same, therefore, the margin of safety was not reduced.
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- CHANGE IN FACILITY DESIGN (Continued)
MARCH 1988 Package Number Descriotion Safety Related ECN P0962 - RER System - (WP&IR 2181-87) - Performed hydrostatic test Unit 2 of Weld made under W.P.2125-87 at penetration X-216. W.P. 2125-87 is in the close-out cycle. Field work has been completed but all paper work is not closed out. ECN P0962 vill be completed when 2125-87 is closed.
ECN P5493 - Reactor Feedwater (WP&IR 2232-87) - Added double end shutoff System - Unit 2 quick connect test fittings with stem protector caps to the reactor water level instruments. The ECN was competed as it only covered Unit 2.
The installation of the test fittings will improve the operation of the affected inst ruments . In particular, the loss of induced air in-leakage will 1) assure correct response to sensed water level and 2) enhance the likely-hood of the Reactor Protection System to respond correctly after instrument calibration. Therefore, the margin of safety was not reduced.
ECN P0795 - Core Spray - (WP&IR 2119-86) - Modifications to various Unit 2 supports to allow LLRT of 275-606 and 2-75-607. A small portion of the work covered by the ECN was implemented.
DCN M00070A - Control Rod Drive (WP&IR 2119-88) - Written for documentation Unit 2 only. Drawings were updated to reflect the substitution of BWR-6 control rod drives for BWR-4 control rod drives. The DCN was completed as it only covered unit 2.
The function of the BWR/6 CRDMs is identical to the 2xisting drives because the same principal of operation is maintained. By utilizing higher strength materials and latest design improvements, the operating reliability increases and maintenance will decrease. Therefore, the margin of safety was not reduced.
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MARCH 1988 Package Number Descriotion Safety Related ECN P0275 - Offsite Power (W.P. 2213-84) - Disconnected cable ES4085-IID Service - Units 1 & 2 from terminal strip ZA inside Panel 2 of the 4-KV Shutdown Board D; spared-out and tagged cable. A very small portion of the work covered by the ECN was completed.
ECN P0671 - Fire Protection (W.P. 1005-87) - Modified Fire Protection System - Unit 1 System sprinkler piping supports in Battery Room 1 and Battery Board Room 1. A very small portion of the work covered by the ECN was completed.
ECN PS213 - RCIC/HPCI - (W.P. 3006-85) - Modified the bonnet flange Unit 3 joints on valves HCV-71-32 and HCV-73-24.
The ECN has now been completed on units 2 and 3.
Performing the modification enhanced leak rate testing of the valves, and this testing ensures the valves safety function can be satisfied. The modified valves perform the same function and meet the same requirements as the valves prior to the modification.
Based on this, the margin of safety was not reduced.
ECN P0872 - Primary (W.P.'s 2057-87, 2060-87, 2062-87) -
Containment Unit 2 Installed HVAC duct, dampers, and supporto for the Reactor Building Ventilation System in the unit # 2 Reactor Building, elevations 593' and 639'. Only a portion of the work covered by the ECN was completed on the workplans.
ECN Pf. .2 - Communications - (WP&IR 0034-86) - Added bays in the communi-Common cation room, control bay, Column R12p, elev.
593.0, for installation of new data switch.
A Small portion of the work covered by the ECN was completed.
CHANGE IN FACILITY DESIGN (Continued)
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MARCH 1988 Package Number Description Safety Related ECN P0859 - CRD System - (WP&IR 2206-87) - Removed RWSPD supports on Unit 2 Unit 2, drywell at various locations. A very small portion of the work covered by the ECN was completed on this workplan.
ECN P3180 - Primary (WP&IR 2104-86) - Fabricated box extension Containment - Unit 2 for penetrations EB, EC, and EE outside Unit 2 drywell.
(WP&IR 2216-86) - Shortened electrical penetration EE. A small portion of the ECN was completed on these two WP& irs.
ECN P0957 - Recirculation - (WP&IR 2172-86) - Safe ends modification System - Unit 2 performed, Unit 2 drywell, elevation 584.
Small portion of the ECN was completed to by WP&IR 2172-86.
ECN P0870 - HVAC System (WP&IR 1020-87) - Rerouted lighting Unit 2 conduit and cables and added new junction box. Regrouted penetration. (Reactor Building, Unit 1, floor elevation 621.251 column lines R/R-2. Only a portion of the work covered by the ECN was completed.
ECN P0814 - HVAC System - (WP&IR 3018-86) - Installed HVAC duct and Unit 3 fire dampers in Shutdown Board Rooms 3EA, 3EB, 3EC, and 3ED.
(WP&IR 3017-86) - Performed the same modification in the Standby Diesel Generator Building. The ECN has been totally implemented.
The dampers installed are seismic Class I and have double fusible closure links. The damper additions were designed to maintain the HVAC's system's seismic qualification and to prevent any degradation of the HVAC's system performance. Fire protection capabilities of the plant were improved .
without adversely affection operation or reliability of any system.
e CHANGE IN FACILITY DESIGN (Continued) Pago 72 MARCH 1988 Package Number Descriotion Safety Related ECN P0930 - Assoc. Electrical (WP&IR 2018-87) - Installed / modified supports System - Unit 2 in Class I structures for interim operation of Unit 2. (Reactor Building, elevation 565'). Only a portion of the work covered by the ECN was completed.
ECN P7033R1 - RHR System (WP&IR 2099-88) - Documentation Only -
System - Unit 1 As-construct drawings to show the addition of a shim 1/16" to 1/4" thick between the inboard bushing and the disc arm on valves 2-FCV-74-54 and 2-FCV-74-68. The ECN was totally completed as it only covered Unit 2.
The modification allows proper seating of the disk on the valve seat to prevent excess leakage past the valve. No other equipment or systems were affected by the modification. The modified valves will perform as required by the Tech Specs.,
therefore, the margin of safety was not reduced.
ECN P7024R1 (WP&IR 2020-88)
ECN P7066R1 (WP&IR 3001-88) - Documentation Only - As RHRSW Unit 2 & 3 construct drawings to show that ASTM A-105 seat rings are to be used as replacements seat rings on valves FCV-23-34, -40,-46, and
-52.
The ECNs were completed.
The margin of safety was not reduced since the modification improved the function of RHRSW heat exchanger discharge control valve and, hence, improved availability of RHRSW System.
ECN P7054 - HPCI System (WP&IR 2000-88) - Regeared operator Unit 2 on HPCI valve 2-FCV-73-002 per MMI-87. The ECN was completed as it only covered unit 2.
The modification improved the safety function of the HPCI System by providing a valve operator which meets the required stroke time and also meets Design Requirements. It provided added assurance that the valve will operate as required to maintain as adequate margin of safety.
n e CHANGE IN FACILITY DESIGN (Continutd) Paga 73 MARCH 1988 .
Packare Number Description Safety Related ECN P3187 - Primary (WP&IR 2173-87) - Replaced Rosemount pressure Containment - Unit 2 transmitters, 2-PT-64-160A&B, model #1153 with Rosemount model #1154. The ECN was completed as it.only covered Unit 2.
The modification provided pressure transmitters that meet IEEE standards that have more stringent testing requirements than previously required. The transmitters function and circuits remained the same. .
Therefore, the modification did not reduce the margin of safety.
ECN P3180 - Primary (WP&IR 2217-86) - Removed interferences ;
Containment - Unit 2 for penetrations EB and EE.
(WP&IR 2099-86) - Removed primary containment electrical penetration EC.
The ECN was not completed.
ECN P0968 - CAD System - (WP&IR 2129-87) - Installed supports for Unit 2 the additional piping and valves installed by WP&IR 2128-87. WP&IR 2128-87 installed block and test valves to allow LLRT of FSV-84-8A-D. Only a portion of the work
- covered by the ECN was completed. ,
ECN P0956 - EECW System - (WP&IR 2063-88) - As-constructed drawings to Unit 2 show physical tie-in of the North EECW piping to supply new SDBR HVAC units cooling water.
No physica1'vork was performed by WP&IR 2063-88. The ECN was not completed.
2CN P0833 - Various Systems Replaced and/or installed 15A fuseblocks.
Unit 2 (WP&IR 2084-87) - on 4KV Shutdown Board D.
(WP&IR 2109-87) - on 4KV Shutdown Board B.
(WP&IR 2107-87) - on 4KV Shutdown Board C.
The ECN was not completed.
ECN P3219/P0956 (WP&IR 2001-88) - Removed concrete pads, HVAC Unit 2 air conditioning supports and grouted concrete anchors. A very small portion of the work covered by the ECNs was completed.
CHANGE IN FACILITY DESIGN (Continued) Page 74 MARCH 1987
' Package Number Descriotion Non-Safety Related P5528 - Yard General - (WP&IR 0019-87) - Erected fence south of Common 500KV switchyard.
DCN B00048A - Control (WP&IR 1000-88) - Fabricated and installed '
Bay Panels - Unit i new handle mechanism on control room cabinets.
The DCN was completed.
ECN P0632 - 4KV Common Bds - (WP 0055-84) - Modified 4KV common boards Common A & B so their normal feeds are from the unit station service transformers and their alternate feeds are from the start buses.
Included a fast manual transfer scheme similar to the transfer scheme of the 4KV unit boards. The ECN was totally completed.
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r-Page 75 CHANGES IN PLANT ORGANIZATION-MARCH 1988 1
There were no changes in plant staff for those positions designated as key i-1 supervisory positions, s
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Pags 76 s
ACCIDENTS MARCH 1988 There was one loss-of-time accident during the month, e
a TENNESSEE VALLEY AUTHORITY-Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 APR 141988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Offico of Nuclear Reactor Regulation Washington, D.C. 20555 Attention: Office of Management Informstloc and Progran Control In the Matter of the ) Docket Mos. 50-259 Tennessee Vallay Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - MARCH 1988 Enclosed is the March 1988 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours.
TENNESS VALLEY A tHORITY J . Walker nt Manager Enclosure cc: Mr. G. E. Cears Mr. C. G. Zech, Director Browns Ferry Project Manager TVA Projects U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 1920 Norfolk Avenue 101 Marietta St., NW, Suite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector Region II Browns Ferry Nuclear Plant Attn: Dr. J. Nelson Grace, Route 12, Box 637 Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power Mr. Ted Marston, Director Operations Electric Power Research Institute Suite 1500 P. O. Box 10412 1100 circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389 \
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An Equal Opportumty Employer 6 ._