ML20195G596
| ML20195G596 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/31/1988 |
| From: | Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8806280064 | |
| Download: ML20195G596 (74) | |
Text
e e, R 9.0 880615 805 Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 JUN 161988 U.S. Nuclear Regulatory Comission
)
ATTN: Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention: Office of Management Information and Program Control In the Matter of the
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 j
i BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - MAY 1988 l
Enclosed is the May 1988 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESS$E VALLEY A HORITY t
I i
b J.
. Walker P nt Managur Enclosure cc: Mr. G. E. Gears Mr. G. G. Zech, Director Browns Ferry Project Manager TVA Projects j
U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue 101 Marietta St., NW, Saite 2900 Bethesda, Maryland 20814 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Comission Browns Ferry Resident pector Region II Browns Ferry-Nuclear Plant Attn:
Dr. J. Nelson Grace, Route 12, Box 637 i
Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 INPO Records Center Institute of Nuclear Power Mr. Ted liarston, Director Operations Electric Power Research Institute Suite 1500 P. O. Box 10412 1100 circle 75 Parkway Palo Alto, California 94304 Atlanta, Georgia 30389 g6280064880531
'R ADOCK 05000259
)
DCD i
o' j
R90 880615 805 MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY MAY 1988 "Safety and Quality are Paramount" 00CKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS OPR-33, OPR-52, AND DPR-68 Sub 'itted by:
4 L
hn G. Walker s
lant Manager t-h t
t t
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 J
Licensee Events Surmary.........................................
10 F.
uffsite Dose Calculation Manual Changes.........................
11 G.
Radwaste Summary................................................
12 1.
Total volume of solid waste shipped off site 2.
Nature of the waste (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 quantitles of spent resin in storage.
6.
Estimated amount of spent resin that will be generated in the following month.
T 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 l
3.
Reactor Histogram (Reactor Powe? Percent)...................
32 I
f I
I
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l l
a rg l
TABLS OF CONTENTS (Continued)
Part III MAINTENANCE
SUMMARY
A.
Electrical Maintenance...........................................
33 B.
In s t rume nt Ma in t ena nc e........................................... 3 6 C.
Mechanical Maintenance...........................................
38 D.
Running Maintenance..............................................
41 E.
Modifications....................................................
42 PART V OTHER REPORTS A.
Chemistry Summary 1.
. Primary Coolant Chemistry.................................. 47 2.
Environmental Technical Specification Requirements.......... 50 3.
A i rbo rne Re le a s e s.......................................... 51 4.
Liquid Releases...................................
......... 56 5.
Resin Usage Report..........................................
60 6.
Fuel Cladding Integrity Parmeters........................... 61 7.
Waste Treatment System Throughputs..............s........... 62 B.
T e s t i n g S u mma r y.................................................. 6 3 C.
Keactor Vessel Fatigue Usage Evaluation..........................
65 D.
Change in Procedures.............................................
66 E.
P lant Ins t ru c t ion Rev is ions...................................... 6 6 F.
Change in Fac ility Des ign ( ECNs )................................. 6 7 G.
Change in Plant Organization.....................................
72 H.
Accidents........................................................
73
e OPERATIONAL SCMMARY e
a C
Page 1 SIGNIFICANT OPERATIONAL EVENTS
SUMMARY
MAY 1988 Unit 1 05/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 6 refueling and modifications continue.
05/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 6 refueling and modifications continue.
Unit 2 05/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 5 refueling and modifications continue.
05/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Cycle 5 refueling and modifications continues.
Unit 3 05/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Environmental qualification work and modifications continue.
05/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.
Environmental qualification work and modifications continue.
Page 2 '
FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
MAY 1988 Unit 1 Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns.
The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date to be determined. The sixth refueling will involve loadins 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), ilPCI 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 monitorin5 modifications H0 sample line modification (LER 81050), and EECW carbon to stainless 22 pipe change out.
Thera 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.
)
Page 3 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
(CONT.)
MAY 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 instrumentation modification (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reductions modifications, modification of masonry walls (IEB 80-11), addition of feedwater 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 valvo 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.
Page 4 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES
SUMMARY
(CONT.)
MAY 1988 Unit 3 Unit 3 was shut down on Merch 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be determined. The sixth refueling outage involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications.
The prior-to-startup unit 3 modifications are environmental qualification of electrical equipment (10CFR50.49), 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 (NUREG 0737), addition of redundant drywell control air supply, RPS voltage monitoring modification H 02 2 ""*E " ti"*'
1 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.
1 There are 0 assemblies in the reactor vessel.
There are 764 assemblies to finish EOC-6, 248 EOC-5, 280 EOC-4, 124 E00-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent fuel storago pool.
The present availablo 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
MAY 1988
.io MSRVs were challenged during the month.
i
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P' age 6 ISSUANCE OF SPECIAL REPORTS MAY 1988 The following special reports are notices of violations issue'd for the month of May 1988.
88-05-04 TS 6.5.1, addresses the requirements for PORC functions.
TS 6.5.1.2.a. requires the following composition.
Chairman:
Plant Manager Alternate Chairman:
Assistant to Plant Manager Alternate Chairman or Member: Technical Services Superintendent Member:
Unit Superintendents (3)
Member:
Maintenance Superintendent Member:
Quality Assurance Supervisor i
Member:
Health Physics Supervisor TS 6.5.1.2.b. states that all alternate chairman and alternate members shall be appointed in writing by the PORC chairman.
TS 61.5.1.8 requires PORC to maintain written minutes of each meeting including expedited meetings.
Contrary to the above, the requirements were not met as follows:
1.
The ecting Maintenance Superintendent who is not authorized by Plant Managers Instruction (PMI) 7.1, Plant Operations Review Committee, to be an alternate chairman, chaired a PORC meeting on March 10, 1988. Also, during the same PORC meeting, and individual acted as an alternate member for the Health Physics Supervisor without being appointed in writing in PMI 7.1.
2.
Written minutes of the expedited p0RC meeting conducted on March 10, 1988, in which a deficient condition with the Reactor Butiding overhead crane was discussed were not maintained.
This is a Severity Level IV Violation (Supplement Il and is applicable to all three units.
88-05-02 10 CFR 50, Appendix B, Criterion X requires that a program for inspection of activities affecting quality shall be established i
and executed by or for the organization performing the activity to verify conformance with the documented instructions, procedures, and drawings for accomplishing the activity.
Browns Ferry Standard Practice 3.2, Quality Control Inspection Program, implements this criterion in section 5.2.1 which states that one of the examples of an activity that shoul( be verified by using QA inspection hold points is satisfactory operation of valves following maintenance.
Page 7 ISSUANCE OF SpECIAL REPORTS (Continusd)
MAY 1988 Contrary to the above, the requirement was not met on November 20, 1987 when a check valve in the Emergency Equipment Cooling Water System (EECW) was improperly installed during the performance of Maintenance Request (MR) number 792717. The valve was found to be installed backwards on March 15, 1988.
Work instructions of the MR explicitly stated to reinstall the valve in the proper orientation. No inspection was performed and documented to verify proper orientation of the check valve following the maintenance activity.
Reversal of this check valve prevented the supply of EECW to the Residual Heat Removal (RHR) punp seal cooler and the RRR pump room cooler from the north EECW header, This is a Severity Level IV Violation (Supplenent I) and is applicable to Unit 2 only.
88-05-08 Technical Specification 6.4 requires the retraining and replacement program for station personnel to be in accordance with ANSI-N18.1-1971, Selection and Training of Nuclear Plant Personnel.
Per Section 5 of ANSI-N18.1-1971 the licensee is required to maintain a training program for re. placement personnel and for retraining necessary to ensure that personnel remain proficient.
This includes General Employee Training (GET).
Item 1.7 of procedure DFPMI-3.3, Specialized Training, specifies regulatory compliance training for all employees.
The training frequency is annual for foremen and overy two years for all others. GET 4.0, Introduction to QA/QC, is requiced to be taken by the employees every two years per procedure PHP 0.202.04.
Contrary to the above, the requirements were not met in that, out of twelve (12) craft personnel arbitrarily selected, the inspector found four foremen and one craf t person delinquent in receiving regulatory compliance retraining, and three craft people delinquent in receiving GET 4 retraining.
For some of the people, the retraining delinquency was greater than one year. Regulatory compliance training was i..stituted in response to the Regulatory ?erformance Improvement Program.
This a Severity Level V Violation (Supplement I) and is applicable to all three units.
88-05-03 10 CFR 50, Appendix B, Criterion V requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings and shall be accomplished in accordance with these instructions, procedures, or drawings.
Page 8 ISSUANCE OF SpECIAL REPORTS (Continued)
MAY 1988 1.
Contrary to the above, the requirements of Surveillance Instruction 0-SI-4. 7B.6, Standby Gas Treatment System Iodine Removal Efficiency were not adhered to for the test on Trains B and C completed on January 12, 1988, and Train A completed on February 16, 1988. of SI 4.7.B.6 requires that the charcoal samples be tested in accordance with ASTM D3803 Standard Test Method for Radlolodine Testing of Nuclear-Grade Gas-Phase Absorbents.
ASTM D3803 requires that the feed period duration and the elution period duration be 60 minutes and 240 minutes respectively. Test data contained in the completed SI data package document that the actual feed duration was 90 minutes (thirty minutes longer than specified) and the actual elution time was 90 minutes (150 minutes shorter than specified).
This is cimilary to the violation cited in Inspection Report Numbers 50-259, 260, 296/86-11.
2.
Contrary to the above, the requirements of Plant Managers Instruction 15.4 (Unique Reporting Requirements) were not adhered to in that the Licensee Reportable Event Determination evaluatlon was not initiated as required to determine the operability of the Unit 2 Residual Heat Removal System lower containment spray header after an inspection (CAQR BFP880052) revealed clogged nozzles due to rust on February 3,1988.
This is a Severity Level V Violation (Suppfament I) and is applicable to all three units.
88-05-01 10 CFR 50, Appendix B, Cr!terion VI requires that metsures shall be established to control the issuance of documents, such as instructions, procedures, and drawings, including changes thereto.
These measures shall assure that documents, including changes, are reviewed for adequacy, approved for release, and properly distributed.
Contrary to the above, Rivision 1 to Temporary Alteration Control Form (TACF) number 3-88-001-111 was not properly reviewel for adequacy, approved for release, and properly distributed. The original TACF was initiated on March 10, 1988 with the majority of the review and approval authorizations obtained on March 13, 1988.
A revision was initiated on March 15, 1988; however, not all of the approval signatures were updated to reflect approval of the revised information in that:
1.
The Operations Supervisor's concurrence signature was dated i
Ma:ch 13, 1988.
l 2.
The shift Engineer's approval of the TACF was dated March 13, 1988.
Page 9 ISSUANCE OF SPECIAL REPORTS (Continued)
MAY 1988 3.
The File Clerk made and distri.buted copies of the TACF on March 15, 1988, although four signatures on the TACF were dated March 16, 1988.
The above information was the only available on the original-TACF form maintained in the Shift Engineer's office and was the condition of the TACF on March 17, 1988.
Similar problems were found with the following TACF's:
2-85-50-24, 2-84-097-57, 2-84-101-64, and 2-85-039-064.
This is a, Severity Level V Violaticn (Supplement I) and is applicable to all three units.
I l
Page 10 LICENSEE EVPNT REPORT (S)
MAY 1988 There were no licensee event reports (LERs) reported to the Nuclear Regulatory Comission in May 1988.
Page i1 OFFSITE DOSE CALCULATION MANUAL CHANGES MAY 1988 No changes were made to the Browns Ferry offsite dose calculation manual during the month.
Page 12 Radwaste Summary May 1988 Common The radwaste system performed as designed.
Approximately 1.05E+06 gallons of waste liquid were discharged containing approximately 3.35E-02 curies of
- activity, i
There were five spent resin shipments and cwo trash shipment during March.
A*='. shipments were to Barnwell, ::C.
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Page 13 Solid Radioactive Waste May 1988 Dewatered Spent Resin Shipments (
Volume of condensate / waste resin shipped:
13.46 Cu.M. (472 Cu.Ft.)
Total curies shipped: _14.2390 Volume of reactor cleanup resin shipped:
O Cu.M. ( 0 Cu.Ft.)
Total curies shipped:
0 Date Shipped Disposal Facilits Type of Resin 04/29/88 Barnwell, SC CWP5 05/06/88 Barnwell,- SC CWP5 05/13/88 Barnwell, SC CWP5 Dry Active Waste (13 Number of drums shipped:
0 Volume:
O Cu.M.
(
0 Co.Ft.)
Total curies shipped 0
Number of boxes shipped:
10 Volume:
27.29 Cu.M.
( 963.2 Cu.Ft.)
Total curies shipped:
0.6007 Date Shior-d Dispos 6L Facility Tvoe of Package 05/11/88 Barnwell, SC Boxes (1) All shipments were by Sole-Use Vehicle
Page 14 Solid Radioactive Waste (Continued)
May 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 0 Cu.Ft.(2) 788 Cu.Ft.
0.00E-00 800 Cu.Ft.('~)
Boxes 465 Cu.Ft.(2) 186 Cu.Ft.
5.58E-01 800 Cu.Ft.C'~)
Uncompacted Drums O Cu.Ft.(2)
O Cu.Ft.
0.00E+00 0 Cu.Ft.(~)
Boxes 498 Cu.Ft.(
302 Cu.Ft.
4.27E-02 600 Cu.Ft.
Resins CWP5 472 Cu.Ft.(q) 655 Cu.Ft.gg) 1.42E+01 450 Co.Ft.(1)
RWCU 0 Cu.Ft.
108 Cu.Ft.(
0.00E+00 35 Cu.Ft.(
TOTALS 1522 Cu.Ft.
1276 Cu Ft.
1.48E+01 2200 Cu.Ft.("'
Total volume of waste shipped during the month:
1,522 Cu.Ft.
Total volume of waste shipped year-to-date:
10,474 Cu.Ft.
Unused 1988 burial volume allocation at Barnwell:
72,32S Cu.Ft (1)
Actual resin volume (2)
Container burial volume (3)
Estimated volume in separators (4)
Does not include resins i
' LIQUID RADWASTE MONTHLY OPERATING REPORT MAY 1988 FLOW RATE (GPM)
CATA PLOTT R HE PRE 12 MONTHS TOTAL RELEASE (CI) 40 _
_ 2 AATE(GPM)
HZ 27.10 30.
t o,.
11.62 AVF-19.80 20 _ [
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T ')T AL 1
s,wsE fen 14I O.05 L*3 0.01 10 _
g.,(-
0.03 0 'LOWRATE
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JUN UL UG kP OCT NOV OEC JAN IB AR R MAY THAOUGHPUTfGALS)
FILTER THROUGHPUTS
,,,7, 0
GALLONS X 10 HI 0.18E+07 I
4 LOW 0.86E+05 AVG 0.12E+07 i
FLOOR ORAIN 3 -
HI O.89E+08 LOW 0.49E+08 AVG 0.75E+0S 2 -
i LAUNDRY
~
mg lsp'h' E' " ;!
:
i HI 0.13E+05
, _ l-0 JUN JUL AUG SEP OCT NOVDEC JAN FEB MAR APR MAY COST OF OPERATION 4 "Ife
" uns THOUSANOS OF DOLLARS WASTE 100.
HI 0.64E+05 LOW 0.19E+05 90 -
AVG 0."J7E+05 80.
70 -
FLOOR ORAIN HI 0.45E+05 60.
d s LOW 0.21E+05 50 _
AVG 0. "40E+05 40 _
LAUNDRY 30 _
HI 0.18E+03 LOW 0.00E+00 AVG 0.49E+02 20 _
.. ]
JUN JUL AUG SEP OCT NOV OEC VAN FEB MAR APR MAY
//
WASTE COLLECTOR SYSTEM LAUNDRY SYSTEM FLOOR ORAIN SYSTEM STARTING 3-87 COSTS INCLUCE RESIN DISPOSAL a
Page 16 REACTOR POWER - MWT UNITS 1, 2,
ANO 3 MA Y 1988 MWT 3500 3000 UNIT 1: OUTAGE 2000 UNIT 2: CUTAGE i
UNIT 3: OUTAGE 1000 500 0'* % %% ***^**@@@@@@@4%#49&O4544444 CMaistry Section DAYS Technical Services Broms Ferry Mtclear Plant REACTOR hA TE9 CONOUCTIVITY UNITS 1, 2,
AND 3 MA Y 1988 UMP 0/CM CONDUCTIVITY 1.75 UNIT 1 1.5 CCsex T:v:rt t.25
'l NIT 2 g............................................................
f 0.75 un 3
O.5
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0.25 EXPECTED RANGE m
A COLD SHUTDOWN s
0 ***9
- * * * * * @ @ $ $ @ @ # D @ @ @ Y $ $ Y @ @ h $ @ 4 @ ACTION L I LIMIT che:Astry Section DAYS COLD ceuTD0wn Technica1 Services Broms Ferry M/ clear Plant i
I REACTOR WA TER CHLOi1IDE UNITS 1, 2.
AND 3 j
MA Y 1988
\\
PPB CH.ORIDE 50---------------------------------------------------------------
UNIT 1 40 CHLCRICE 30 UNIT 2 20 CHLCRICi UNIT 3 to EXPECTED RANGE 0
4L CONDITIONS 0 ***
- @@@@@@@O@@@@@@Y$$4&@fY
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thenistry Section DAYS Technical Services Woms Ferry M/ clear Plant
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Pags 18' BROWNS FERRY NUCLEAR PLANT RadWaste Shipped Cubic Feet
- 10. M O 1988 Allotment 9000 1987 Average r
n 7000 - -
Volume Shipped 1
I 6000 5000 4000 7
3000 l
2000 1000 0
n h?hhhhhhhhhhh$hhhhhhhhhh June 1986 thru Hay 1988 19n0 ct;ewa. rea 411otant - sa m Msc feet 19Re.SMMed-TO-00te
- 14 474 MJC feet INPO PARAMETERS RadWaste Generated Cubic Feet 10,000 1988 Goal 9000
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I 6000 5000 r--
4000 I
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OPERATING STATISTICS w
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Pags 19 OPER,\\ TING DATA REPORT DOCKET NO. 50-259 OATE 06-01-88 COWLETED BY J. D. Crawford TELEPHONE J205) 729-2507 OPERATING STATUS l Notes l
l.
Unit Names Browns Ferry Unit One l
l 2.
Reporting Period: May 1988 l
l 3.
Licensed Thermal Power (Wt): 3293 l
l l
4 Nameplate Rating (Gross We): 1852 l
l l
S.
Design Electrical Rating (Not We) 1065 l
l l
6.
Maxitmn Dependable Capacity (Gross We) 1098.4 l
l 7.
Maximum Dependable Capacity (Not We) 1065 l
l 8.
If Changes Occur in Capacity Ratings (items Nurrber 3 Through 7) Since Last Report, Give Reasons:
N/A l
9 Power Level To Which Restricted, if Any (Not No):
N/A l
- 10. Reasons For Restrictions, If Any:
N/A This Kmth Yr-to-Oate Cumulative
- 11. Hours in Reporting Period 744 3647 121.327
- 12. Nurber of Hours Rea; tor Was Critic 41 0
0 59.521.38
- 13. Reector Reserve Shutdown Hours 0
0 6.997.44
- 14. Hours Generator On-l.ine 0
0 58.267.26
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thormal Energy Generated (WH) 0 0
168.066.787
- 17. Gross Electrical Energy Generated (WH) 0 0
55.398.130
- 18. Net Electrical Energy Generated (M) 4552
-13 % 7 53.692.435
- 19. Unit Service Factor 0
0 48.02
- 20. Unit Availability Factor 0
0 48.02
- 21. Unit Capacity Factor (Using K)C Net) 0 0
41.55
- 22. Unit Capecity Factor (Using DER Net) 0 0
41.55
- 23. Unit Forced Outage Rate 100 100 43.21
- 24. Shutdowns Scheduled Over Nort 6 Mont%s (Type, Date, and Duration of Each):
W
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Comercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY CO M RCIAL OPERATION (9/77)
Page 20 OPERATING DATA REPORT DOCKET NO.
50-260 OATE 06-01-88 COWLETED BY J. D. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS kotes l
l.
Unit Nane:
Browns Ferry Unit Two l
l 2.
Reporting Period: May i988 l
l 3.
Licensed Thermal Powr (Wt): 3293 l
l 4
Nanoplate Rating (Gross %): 1852 l
l S.
Design Electrical Rating (Not % ) 1065 l
l 6.
Maximum Dependable Capacity (Gross % ) 1098.4 l
l 7.
Maximum Dependable Capacity (Not % )
1065 I
l 8.
If Changes Occur in Capacity Ratings (Items Nunber 3 Through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level To Which Restricted, If Any (Not We):
N/A
- 10. Reasons For Restrictions, if Any:
N/A This Month Yr-to-Oate Cumulative
- 11. Hours in Reporting Period 744 3647 116,214
- 12. Nunber of Hours React e Was Celtical 0
0 55,860.03 9
- 13. Reactor Reserve Shutdown Hours 0
0 14,200.44
- 14. Hours Generator On-the 0
0 54,338.36
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (WH) 0 0
153,245,167
- 17. Gross Electrical Energy Generated (WH) 0 0
50,771,798
- 18. Net Electrical Energy Generated (WH)
-2193
-9859 49,173.974
- 19. Unit Service Factor 0
0 46.75
- 20. Unit Availability Factor 0
0 46.75
- 21. Unit Capacity Factor (Using MDC Net) 0 0
39.73
- 22. Unit Capacity Factor (Using DER Net) 0 0
39.73
- 23. Unit Forced Outage Rate 100 100 42.55
- 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 Ccrrercial Operation):
Forecast Achieved __
INITIAL CRITICALITY INITIAL ELECTRICITY CO M RCIAL OPERATION (9/77)
Pags 21 OPERATING DATA REPORT DOCKET No; 50-2 %
DATE 06-01-88 COWLETED BY J. O. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS l Notes l
l.
Unit Names Browns Ferry Unit Three l
l 2.
Reporting Period: May 1988 l
l 3.
Liconsed Thermal Power (Wt): 3293 l
l 4
Nameplate Rating (Gross We): 1152 l
S.
Design Electrical Rating (Not We) 1065 l
6.
Maximum Dependable Capacity (Gross We) 1098.4 l
l 7.
Maxinun Dependable Capacity (Not We) 1065 l
l 8.
If Changes Occur in Capacity Ratings (items Nunter 3 Through 7) Since Last Report, Give Reasons N/A 9.
Pe er Level To Which Restricted, if My (Not We):
N/A
- 10. Reasons For Restrictions, If Any:
N/A This Month Yr-to-Cate Cumulative
- 11. Hours in Reporting Period 744 3647 98,639
- 12. Nunter of Hours Reactor Was Critical 0
0 45,306.08
- 13. Reactor Reserve Shutdown Hours 0
0 5.149.55
- 14. Hours 'anerator On-Li %
0 0
44.194.76
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
131.868,267 _
- 17. Gross Electrical Energy Generated ( WH) 0 0
43,473,760
[
- 18. Net Electrical Energy Generated (MWH)
-8876
-e2.406 42,028,742
- 19. Unit Service Factor 0
0 44.80
- 20. Unit Avallability Factor 0
0 44.80
- 21. Unit Capacity Factor (Using M)C Net) 0 0
40.00 l
- 22. Unit Capaci+y Factor (Using DER Net) 0 0
40.00
- 23. Unit Forced Outage Rate 100 100 46.05
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Oate of Startup To be determined
- 26. Units in Test Status (Prior to Comercial Operation):
Forecast Achieved INITIAL CRITICALITY i
INITIAL ELECTRitiTY CO MERCIAL OPERATION (9/77)
,v
Pags 22 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 i
Unit One DATE 06-01-88 CO R ETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH MAY 1988 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Wet)
(Mde-Net) l
-6 17
-6 2
-6 (8
-6 3
-6 89
-6 4
-6 20
-7 5
4 21
-7 6
-7 22
-6 7
-6 23
-6 8
-6 24
-6 9
-7 25
-6 10 4
26
-4 Ii
-6 27
-5 12
-6 28
-7 13
-6 29
-5 14
-7 30
-6 15
-6 31
-6 16
-5 INSTRUCTIONS i
On this format, list the average daily unit roer level in Mie-Net for each day In the reporting enth. Compute to the nearest whole megawtt, f
I
- Revision (9/77) 1
Page 23 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 Unit Two DATE 06-01-88 COPFLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH MY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-Net)
(MWe-Net) 1
-2 17
-3 2
-3 18
-3 3
-3 19
-3 l
l 4
-3 20
-3 5
-3 21
-4 6
-1 22 1
7
-3 23
-3 8
-2 24
-3 9
-3 25
-3 10
-3 26
-4 II
-3 27
-3 1
12
-3 28
-3 13
-3 29
-3 14
-3 30
-3 15
-3 3l
-3 I
16
-3 INSTRUCTIONS On this formet, 1Ist the average dalIy unit powe Ievei In Mdo-Net for each day in the reporting eenth. Conpute to the nearest whole megawatt.
(9/77)
Paga 24 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-2 %
Unit Three DATE 06-01-88 COWLETED BY J.D. Crewford TELEPHONE (205)729-2507 MONTH MY 1988 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
-2 17
-3 2
-2 18
-2 3
-3 19
-3 4
-2 20
-3 5
3 21
-2 6
-3 22
-2 7
-3 23
-2 8
-2 24
-3 9
-3 25
-3 t0
-3 26
-3
!I
-3 27
-3 12
-3 28
-2 13
-3 29
-2 l4
-3 30
-2 15
-3 31
-2 16
-2 INSTRUCTIONS On this formet, IIst the average daiiy unit power levei In MWe-Net for each day In i
the reporting month. Ca pute to the nearest whole megawatt.
(9/77) l i
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LINil Sill!! DOWNS AND POWER REIMJCTIONS DOCKET NO.
50-260 UNET NAME %n DATE 06-01-88 COMPLETED BY J.D. Crawford REPORT MONHI May TELEFNONE (205) 729-2507 f
6 c
{g 3
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Cause a Cussettsve h
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2 v
6 305 05/01/88 F
744 F
4 Administrative hold to resolve various TVA and NRC concerns.
i 2
1 I l'.nced Reaune.
Mcahnd:
1.sluta C. Instrutsumis S 5 luduled A 1. guy. ment Itailuse ( E s plaini 1 Manual 1.n Psepasasi.no of Data B-Massisen.inte or les:
2 Manual Scrans.
I:nia) Sheets ein Ixcusce C Refuelung 1-Autunuisc Ss.am.
I vens Regwns 11.110 fde INtIRI G-y 4 '
D Regulas n> Rcsaistseine 4 Otlwr ll.splauil 4)l til I
'cyo l Operas.a Isaining A l.sscuse I unanainni I AJnunnesais.c 5
w G Operass.noal I as.n il spl.a.it I sinlas 1 Sane S.unce t*s/ 77 )
II Othen ti y.lauet O
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f
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UNIX SilullM)WNS AND POWER REDUCl3ONS IM)CKET NO.
5G-296 UNIT NAME Three DATE 06 91-88 COMPRETED BY J.D. Crawford RI POR T MONiil Mit y IEt.EPHONE (205) 729-2507 I
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6 157 05-01-88 F
744 4
Administrative liold to resolve various TVA and NRC concerns.
4 J
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I l'.. sad Reau na.
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- 1. slubit G - Insisuctiinis 5 Silicdulcsl A liguipment I aihne II.splain)
! Mai..ul f..s 15cparati ni..f Data Il Mainicsurne..r IcA 2 Mariinal.kraris.
I sissy Sliccas for I.icensee t
C-Rcfucinig 5 Autunusic Sisam.
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I sinbit i. Same S.unce 1**/ 77) ll Oil es il spl.un) i i.-
TVA 73a2A (ON#+m NUCLEAR PLANT OPERATING STATISTICS Page 28 Browns Ferry Nuclear Plant Porlod Hours 744 Month Mw 19 RR ltem No.
Unit No.
UNIT 1 UNIT 2 UNIT 3
- PLAN, 1
Average Hourly Gross Load. kW 0
0 0
0 2
Maximum Hour Net Generation. MWh 0
0 0
0 3
Core Thermal Enerdy Gen. GWD (t)2 0
0 0
0 4
Steam Gen. Thermal Energy Gen., GWD (t)2 r
5 Gross Electrical Gen., MWh 0
0 0
0 3
6 Station Use. MWh 4552 2193 1876 8621 k
7 Net Electrical Gen.. MWh
-4552
-2193
-1876
-8621 (3
8 Station Use. Percent 0
0 0
0 1
0 0
0 0
9 Accum. Core Avg. Exposure, MWD / Ton 10 CTEG This Month,100 BTU 0
0 0
0 11 SGTEG This Month 106 BTU 0
0 0
0 12 13 Hours Reactor Wat 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 Avail. Factor. Percent 0
0 0
0 f
[
17 Generator Avail. Factor. Percent 0
0 0
0 ll*
18 Turbocen. Avail, Factor. Percent 0
0 0
0 i
l 19 Reactor Avail. Factor. percent 0
0 0
0 f
2 20 Unit Avail. Factor. Percent 0
0 0
0 21 Turbine Startues 0
0 0
0 22 R"eactor Cold *Startues 0
0 0
0 j
23 E
y 24 Gross Heat Rate. Btu /kWh 0
0 0
0 l
j 25 Net Heat Rate, Btu /kWh 0
0 0
0
?
E 26 U
27 I
g 28 Throttle Pressure. psig 0
0 0
0 t
g 29 Throttle Temocrature. *F 0
0 0
0
{
30 Exhaust Pressure. InHQ Abs.
0 0
0 0
g 31 Intake Water Temo.,
- F 0
0 0
0 W
32 I
33 Main Feedwater, M lb/hr t
i 34 l
[
35 I
36 37 Full Power Capacity, EFPO (3)
(4)
(4)
(4) 38 Accum. Cycle Full Power Days, EFPO (4)
(4)
(4) j 39 Oil Fired for Generation, Gallons 23.620 i
5 40 Oil Heatino Value. Btu / Gal.
139.800 41 Dianal Generation. MWh 1$9,6 42 Max. Hour Net Gen.
Max. Day Net Gen.
Load MWh Time Date MWh Date Factor, %
2 43 0
0 0
3 R emarks. IFor BFNP this value is MWD /STU and for SGNP and WBNP this value is MWD /MTU.
.,5 2(t) indicates Thermal Energy.
t 3 Information furnished by Reactor Analysis Groun. Charrannnen e
U 4 Administrative Hold f
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w 0
d ta r
v 1
2 3 4 5 6 7 8 9 0 G
0 w
i 5
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g I
z 3 4 s 6 7 e9 0 1
23 4 5 s 7 8 9 0
ia A
e s
s 1
I i
1 1 i 1 1 2 2 2 2 2 2 2 2 2 23 3 t
J_1 V
k o
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T L
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Page 32 REACTOR POWER PERCENT MAY 1988 UNIT i PmCDU 100 so M
10 M
g ADMINISTRATIVE HOLD 40 30 to to 0
% 49 ' * * * *
- f s% @ @ @ @ @ @ @ @ f f 9 @ @ f f @ f f f t UNIT 2 PGCDU 100 90 M
70 60 ADMINISTRATIVE HOLD 3,
40 30 20 to 0-
- * * * * *
- s' s' s4 0 s' @ @ @ @ @ f f f 9 d f f f f f f +
UNIT 3 PGCDU 100 90 M
70 l
so 50 ADMINISTRATIVE HOLO 40 30 to 19 0
- * * *S
- *s's%4@@@@@@@f@@@Yfffffft
__m m
8 MAINTE.. A:. CE
~
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i SUMMA 3Y i
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)
Pags 33 j
i ELL,'TRICAL TECHNICAL SECTION MONTMLY REPnRT MAY, 1988 Unit Connon Major Routine Activities--
Submitted permanent change to SEMI-60, 61, 62 and 63.
Also to SI-4.9.A.2.C(2).
r Submitted temporary change to 0-SI-4.1.B-16.
Wrote new procedures to perform capacity tests on Microwave and Telephone-Battery Banks.
ELECTRICAL EQUIPMENT LIST: 521 drawings were received in May 1988.
1,156 drawings were reviewed.
4,034 drawings are in backlog.
FU1E ENr. RAVING REPORT:
Revision "C" fuse relabeling effort ir complete for units one and two. Unit three is 97 per cent complete and unit 0 MRs for relabeling effort has been submitted to planning.
FUSE CONTROL PROGRAM:
All fuse input sheets were put into EQIS, ending on May 24, 1968. Eight days were lost due to computer problems.
Revision "D" of the 1
fuse and engraving report was locked in.
Operations has not completed the fuse replacement on materials given to them in ectly April 1988.
TSD-E044: Electrical Technical Section received and reviewed a' copy of EBASCO's first calculation. This was completed on May 6, 1988. The cable has been reviewed. Fuse data sheets were received on May 12, 1988 and are being put'into EQIS. Due to eight days of computer problems in May, 1988. ETS should have the fuse engraving reports ready for field work to begin around June 13, 1988 instead of June 1, 1988.
Completed approximately 50 "H" Status MRs and sent them to planning.
Unit 2 start-up tatal is 56.
Tech reviewed SI-4.2.B-40A, SI-4.2.B-42A, and SI-4.2.B-40B.
Submitted permanent change on SI-4.2.B-14.
SRN-G38-22, SRN-G38-24 and SRN-G38-25 were incorporated into electrical maintenance procedures.
Completed two failure investigation reports on CR120A relays.
MRs have been written to check all class 1E latching type HFA relays for inadequate latch engagament.
l n
---e.,-,---,,..c
,.~..,a
~
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F Page 34 2
Riectrical Technical Section Monthly Report UNIT COMMON:
Major Routine Activities--
MRs havo been written for replacement of coils in unit 1 HFA relays needed for unit 2 restart.
PMs have been written te calibrate normally energized DC HFA type relays.
Performed unit 3 SI-4.9. A.3.a.
Preventive maintenance backlog reduction 30 day program was begun on May 2, 1988.
The priority was to determine the validity of the existing program and correct as needed. The main obje?tive was to decrease the 25 per cent late list and resolve as many items as possible.
Nineteen changes were made to the 25 per cent late list, 30 changes were made to the status list and 151 changes were made to the PM scheduled maintenance, excluding RO tasks.
The 151 changes included 90 deferrals, 36 deletions and 25 frequency changes.
Ten out of tolerance investigation depositions of messaring and testing equipment w1re submitted.
CIKCUIT 3REAKER REBUILDS:
4160V 480/250V Total Number of Breakers To Be Rebuilt 303 493 Tctal Rumber of Breakers Kebuilt 9
17 Cospleted This Month 0
0 Waiting on material for breaker rebuilds.
Replaced T70 stator bar on unit 2 generator.
Power Service Shop electricians are working on reassemoly of generator.
Reviewed ECN and DCN packagec for PORC.
G-33, SNG-25 implemented into procedures allows for a discrepancy report instead of a CAQR from plant.
Design will issue CAQR if necessary.
Unit 3 KMG set was put back into service.
Fuse UNID assignment to be the responsibility of DNE on November 3, 1988.
All failure investigations were completed in May 1988.
Three (3) of the failure investigation reports still have corrective action or recurrence controls that need to be put into effect beforo the failure investigations can be closed.
Electrical Technical Section portion complete on commitment 840054002.
1
Pags 35 3LECTRICAL TECHNICAL SECTION MONTHLY REPORT MAY, 1988 i
I.
WORK TIME SCHEDULE l
Received /
Assigne,d_
Completed Open I
Red Folders 1
2 11 Orange Foldars 2
0 12 Yellow Folders 0
0 1
Blue Folders 5
5 6
Purple Folders 0
0 3
Active Engineering Assignments 0
0 20 Engineering Backlog 0
0 65 New Engineering Assignments 1
0 1
Completed Engineering Assignments 0
0 0
II.
COMMITMENT TRACKING Licensing Issues (NCO & SLT)
NCO O
1 17 SLT 0
1 3
PORS Tracking Items (BFC) 0 0
3 CAQR3 1
4 4
Average Age of CAQRs Eight Months
)
Employee Concerns 0
0 1
Safety Issues List 0
0 0
[
l III.
STAFFING LEVELS AND TRAINING Personnel Approved Headcounts Current. Headcounts ASP 3o 31 i
ATL 4
4 HTL 0
0 Contractors 5
5 TOTAL 45 40 IV.
OVERTIME 6.1%
V.
PROCEDURES I
41 Procedures PORC approved 10 Procedures sent to Word Processing VI.
67 Outstanding Status "H" Mks i
0 Outstanding Status "Q" MRs 31 Outstanding Status "K" MRs i
1 1
l
Pago 36 f
I&C TECHNICAL MAY 1988 I.
Work Itam Schedule Received /
Completed Open Assigned Red Folders 1
1 1
Oranse Folders 1
1 7
Yellow Folders 1
0 1
Blue Folders 6
3 6
Purple Folders 2
5 1
Total Assignments Active Engineering Assignments 16 5
39 Engineering Backlog 11 MRs (Status "H" and "Q")
53H 53 II.
Commitment Tracking Licensing Issues (NCO 4 SLT)
NCO 0
0 12 SLT 0
0 3
PORS Tracking Items (BFC) 0 0
2 CAQR (Onsite) 0 3
6 CAQR (Off-site) 0 0
0 Average Age of CAQRs 4.75 months Employeo Concerns 0
0 0
Safety Issues List 0
0 0
III.
Staffing Levels and Training Approved Headcounts Current Headcounts Personnel ASP 17 12 l
ATL 4
4
)
HTL 0
0 i
Contractors 4
TOTAL 21 20
)
IV.
Overtime 8.10%
4 V.
Procedures 37 procedores were sent to Word Processing
\\
t I
Page 37 I&C TECHNICAL MAY 1988 I
L VI.
Maintenance Improvement Plan Items ITEM l
Description l
% Complete l
1 III.H.1 l
M&TE l
60%
IV.B.3 l
M&YE l
60%
IV.C.1 l
Maint. Instructions l
- 1) 100% 2) 90% 3) 33%
IV.C.2 l
Maint. Instructions l
0%
IV.C.3 l
Maint. Instructions l
34%
V.B.2 l
Spares Parts l
0%
V.B.3 l
Spares Parts l
0%
VI.G.2 l
PN l
70%
VIII.B.10 l
Technical Issues l
52%
VIII.D.
l Employee Concerns l
33%
i
SUMMARY
l t
t 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 t.hese instructions are siso being issued.
i i
r 5
l i
i
\\
l l
Pago 38 MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)
MAY 1988 '
Common a
No major noncoutine activities.
1.
Closed the following commitments:
a.
WTB 87-002, R1 - Head "0" Ring Leakage b.
IS Notice 86-007 - Diesel Generator Woodward Governor c.
INPO SOER 85-005 - Internal Flooding of Power Plants Buildings - EECS Pump Room d.
SLT 850934001 - Secondary Containment Blowout Panels e.
R33 880511 672 - 1"B" Diesel Generator Vibration f.
R35 880511 699 - Approval of Master Specification MS-CEB-002 g.
C-29(RO) PF-1060(Rl) - PF Specifications h.
G-29(RO) PF-1066(Rl) - PF Specifications i.
R00 880429 345 - Administrative Control of Slings 2.
The following instructions were approved, revised, or cancelled.
a.
MMI Removal, Replacement, and Inspection of Permall Neutron Shielding at Sacrificial b.
MMI Removal and Replacement of Standby Gas Treatment Filters c.
MMI Scheduled Maintenance of Standby Diesel Generators d.
MMI-? - Removal, Repali, Replacement, and Testing of Control Rod Drives I
e.
KMI Inspection of Secondcry Containment Relief Panels f.
MMI Reactor Core Isolation System Maintenance g.
5:11 High-Pressure Coolant Injectics (HPCI) System Maintenance h.
MMI Control of Measuring Equipment used on Celtical Systems l
1.
MMI Hydraulic Shock and Sway Arrestor - Bergen-Paterson and Grinnell; Unit Removal, Disassembly, Reassembly, and Replacement Procedure I
j.
MMI Installation and Removal of Jet Pumps Seal Plugs and/or Recirculation Outlet Plug
Page 39 MECHANICAL TECHNICAL SECTION MOETHLY REPORT COMMON UNIT ONLY (UNIT 0)
MAY 1988 4
k.
MMI Opening and Closing of Primary Containment Hatches 1.
MMI-102 - Rigging Equipment and Portable Holst Program m.
MMI-117 - Overhead Traveling Bridge Cranes; Inspection. Testing, and Preventive Maintenance HMI-129 - Opening and Closing.of Drywell Personnel Airlock Doors n.
o.
MMI-157 - Inspection, Lubrication, and Replacement of the LPCI MG-Set Couplings and Bearings.
p.
MMI-159 - Sampling Instrumentation Program for verifying correct l
installation of Concrete Expansion Shell Anchors q.
MMI-164 - Temporary Removal and Reinstallation of Pipe Supports r.
MMI-181 - Preventive and Corrective Maintenance of Fuel Pool Cooling Heat Exchangers s.
MMI-182 - Reactor Vessel Internals Visual and Ultrasonic Inspection t.
MMI-183 - SRM/IRM Dry Tube Inspections u.
MMI-188 - Inspection of Concrete Anchors v.
MMI-190 - Control Rod Uncoupling - GE Tool w.
PMI-6.14 - Scaf f old and Temporary Platf orms x.
0-SI-4.7.B.8 - Standby Gas Treatment (SBGT) Trainhousing Door Gasket Seal Test y.
BF-14.49 - Operations of Crancs and Hoists z.
MSI-0-000-PR0017 - General Torquing Guide aa MCI-0-002-PMP001 - Main Condensate (Hotwell) Pump - Ingersoll-Rand Model 36 APKD; Disassembly Inspection, Rework, and Reassembly bb.
MCI-0-002-PMP007 - Condensate Booster Pump Auxiliary 011 Pump; Disassembly Inspection, Rework, and Reassembly ec.
MCI-0-018-PMP004 - Standby Diesel Engine Fuel Oil Transfer Pump; Disassembly Inspection, Rework, and Reassembly dd.
MCI-0-024-PMP001 - Raw Cooling Water Pump - Ingersoll-Rand Model 14AFV; Disassembly, Inspection, Rework, and Reassembly
Pago 40I MECHANICAL TECHNICAL SECTION HONTHLY REPORT COMMON UNIT ONLY (UNIT 0)
MAY 1988 ee.
MCI-0-033-CMP 003 - Service Air Compressor "E" - Norberg Type U-100; Disassembly. Inspection, Rework, and Reassembly ff.
MCI-0-082-ENG007 - Standby Diesel Engine Crank Shaft; Disassembly, Inspection Rework, and Reassembly Eg.
MCI-3-082-FLT006 - Standby Diesel Engine Fuel Filter; Disassembly, Inspection, Rework, and Reassembly 3.
The following Conditions Adverse to Quality Reports (CAQRs) were closed.
NONE 4.
The Mechanical Technical Section devoted 300 hottes to training during the month of May.
4
. RUNN]N3 MA]NTENANCE-REPORTFOR THEMONTH OFMAY. SUPV. JOHN CROWELL 1.
WORK ITEM COMPLETE Pags 41 RECEIVED' ASSIGNED COMPLETED CFEN RED 0
0 0
CRVE O
O O
YE m V 0
0 0
BLUE O
O O
PURPLE O
O O
- 11. COMMITMENTTRACKING UCENSING ISSUES (NCO & SLT)
N'O 0
0 4
SLT 0
0 0
PORS TRACKING ITEMS (BFC) 0 0
0 CKRS 1
3 19 AVERN3EA3ECFCACRS 7 MONTHS i
EMPLOYEECONCERNS 0
0 0
SAFETYISSUES!JST 0
0 0
Ill. STAFPNG LEVELS PERSCtWEL CURRENT HEADCOUNT ASP 88*
ATL 287 HTL 58 APPRENTICES 2.6 TOTAL 459
'7 ENG. AND ASSOC ON t.OAN FROM MTS, ETS, AND l&C TS IV. PROCEDLRES O
PROCEDURES WERE PORC APPROVED O
PROCEDURES SENT TO WORD PROCESSING V.
MBS I
109 OUTSTANDING STATUS 'H" MRS 75 OUTSTANDING STATUS V MRS i
811 COMPLETED MRS THIS MONTH VI.MMOR ROUTINE ACTMTIES ANNUAL CHILLER INSPECTION ELEC.
LAYUP SUPPORT ELEC.
MAINTAIN STD LAB I&C SUPPORT EMI 60- l&C PM ON SYSTEMS 26,23,67 AND 90- l&C Vll.MMOR NONROUTINE ACTIVITIES TRAVEUNG SCREEN REPAIR-MECH.
INTAKE BUTTERFLY VALVE REPAIR MECH.
RTP 64 l&C PROVIDED CFANE OPERATOR SUPPORT FOR REFUEL FLOOA-ELEC.
RTP 3A lac MAINTENANCE ON REFUEL BRIDG2 ELEC.
RTP 75 lac SUPPORT FOR LOPA.OCA TESTING ELEC.
W.P. 2069 86 l&C SUPPORT 2 BFN RTP l/LB l&C l
RPIS PROBE REMOVAL AND REPLACEMENT I&C SUPPORT SI WALKDOWN l&C
Pags 42 MODIFICATIONS MONTHLY REPORT MAY 1988 MAJOR WORK PERFSRMED ECW NARRATIVE Appendix R 70808 Continued conduit and cable work on control power circuits (workplan 2048-87, 2091-87, and 2047-87).
P0819 Started work on emergency lighting upgrade (workplan 1019-87).
P0823 Field completed RHR pump backup control modification (workplan 2151-87).
P0879 Continued work on fire door upgrade (work plans 2068-87 and 2212-87).
P0885 Continued conduit and support work on RB fire detectors (workplans 2012-87, 2013-87, 2014-87, and 2015-87).
P0889 Continued reroute of conduit for separation (workplans 2053-87, 2054-87, 1221-87, 2050-87, 2052-87, and 2049-87).
P0953 Started cable pulling for evacuation alarm panel power feed replacement (workplan 0051-86).
Environmental Qualification P3145 Continued electrical conduit sealing activities (workplans 2070-85 and 2078-85).
P3205 Continued small piping and support work on H02 2 analyzer lines (workplans 2162-87, 2163-87, and 2183-87).
P7036 Started craft work on steam tunnel cable replacement (workplan 2122-88),
i
Page 43 MAJOR WORK PERFORMED ECN NARRATIVE Soismic Issues B0005A Continued replacement of EECW sectionalizing valves (workplan 0012-88).
Field completed workplan 0027-88.
B0012 Started work on drywell steel stiffner places (workplan 2178-88).
WO204A Continued concerted efforts on unit 1 control room panel anchoring.
WO205A Continued concerted efforts on unit 2 control room pane.'. anchoring.
WO206A Continued concerted efforts on unit 3 control room panel anchoring.
P0289 Continued work on EECW and RHRSW dresser coupling replacement (workple s 2137-88, 3031-88, 2224-88, 2163-88, 21,4-88, 3016-88, 1032-88,1015-88, and 1016-88.
P0361 SMMI rework of torus attached piping and drain supports continued.
P0370 Continued structural work on seismic qualification and designation of block walls (workplans 1030-87, 2092-87, 3024-87, and 3036-87).
PC625 Started vent and drolii support work (workplan 2007-88).
P0859 Completed identified craft work on catwalks R9 and 13 (workplans 2066-87 and 2209-86, and 2143-87).
P0944 Completed craft work on seismic rualification of U2, RB conduit (workplan 3040-87).
?
F0945 Completed craft work on unit 1 seismic conduit qualification (workplan 1037-87).
P0946 Completed craft work on seismic qualification of unit 3 RB conduit (workplan 3038-87).
P0998 Completed craft work on drywell catwalk upper c'evation (workplans 2146-87, 2147-87, and 2148-87).
P2044 Continued craft work on unit 1 RB drain and sump pump 79-14 modifications (workplan 1033-87),
s
Pags 44 MAJOR WORK PERFORMED ECN NARRATIVE Saismic Issues (Continued)
P2154 Started field work on RHRSW and EECW trains B and D outage fixes (workplans 0028-88 and 0023-88).
P7018 Completed craft work on drywell KVAC seicmic qualification.
Field completed workplans 2282-87, 2281-87, 2280-87, 2279-87, and 2278-87).
F7029 Continued repair of lower drywell structural steel (workplan 2234-87).
P7083 Continued craft work on common area tubing seirmic qualification (workplans
,007-88,0008-88, 0009-88, and 0010-88).
P7035 Continued craft work on unit 2 tubing seismic qualification (workplans 2058-88, 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, and 2086-85).
P5451 Continued work on stack radiation monitor pressure and temperature compensation mod (workplan 0028-87).
Other B00047A Started work on 2-PS-24-133A upgrade.
M0075A Completed tube removal on unit 2 condenser.
P0085 Continued cerouto of conduit on drywell pressure and temperature upgrade (workplan 2192-87).
P0286 Continued work on yard security lighting (workplans 0021-86 and 0022-86).
P0384 Continued tubing and electrical work on containment purgo valves (workplan 2049-86).
P0392 Continued SMMI rework of scram discharge volume supports.
PO422 Continued work on RPS class 1E protection (workplans 2144-84 and 2143-84).
P0547 Continued replacement of recirculation system check valves'(workplsn 2050-85).
o Page 45 MAJOR WORK PERFORMED ECN NARRATIVE Other (Continued)
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, 2250-87, 2172-88, 2257-87, 2100-88, 2253-87, 2254-87, 2262 87, 2263-87, and 2249-87).
Field completed workplans 2156-87 and 2258-87.
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, 2284-07, 2285-87, 2286-87, 2009-88, and 2008-88).
PS269 Installation of supports for uninterruptable demineralized water connection for torus water level transmitters continued (workplans 2292-87, 2065-86, and 2293-87).
PS291 Continued react +- -1ter level instrument sense line modificati.
workplans 2153-87, 2154-87, and 223b,6).
P5480 Installation of vessal drain supports continued (workplan :!218-87).
P5485 Ccntinued work on SRM and IRM signal cable changeout (workplan 2095-88).
P5539 Started work on RPS system cable replacement (workplan 2210-87).
P7002 Continued field work on hydrogen water chemistry modifications (workplans 2088-84, 2087-88, and 2092-88).
P7006 Continued work on ATU inverter replacement (workplans 2066-88 and 2081-88).
l P7030 Started work on RWCU valve repleccment I
(workplan 2150-88).
P7037 Continued craft work on installation of quick disconnect couplings on testable check valves
)
{
(workplans 2107-88, 2105-88, 2109-88, and 2110-88).
j P7045 Continued valve and support modifications for ATWS/ARI (workplans 2115-88 and 2116-88).
P7117 Completed craft work on 480V AC shutdown board 2B 2148-88). power feed modification (workplan
i Page 46 MAJOR WORK FERFORMED ECN NARRATIVE Other (Continued)
P7048 Continued craft work on reactor water level instrerentation sense line modification (workplan 2003-88, 2085-88, and 2084-88).
Drywoll Fire Recover;r B00046A Continued replacement of damaged cable tray (workplan 2072-88).
B00061A Continued replacement of damaged system 70 conduit and cable (workplan 2112-88).
B00062A Continued replacement of damaged system 68 conduit and cable (vorkplans 2135-88 and 2139-88).
B00063A Started replacement of damaged system 1 conduit and cable (workplan 2162-88).
K00079A Started replacement of damaged cables associated with systems 1, 3, 56, 5 7, 64, and 77 (workplan 2200-88).
WO136 Started and completed craft work associated with emergency pressurization fan 480V power supply rodification (workplan 2138J88).
P3163 Continued drywell cable replacement (workplan 2237-87).
1 P3180 Continued electrical work associated with t
containment penetration replacement (work-plans 2036-87, 2103-87, 2022-87, and 2083-88).
Field completed workplan 2083-88.
p7130 Started and completed craft work associated with CREVs fan power / control feed change (workplan 2171-88).
e a
OTHER R3 PORTS J
1 a
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Pagn 47 CHEMISTRY
SUMMARY
May 1988 Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month.
Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.
This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.
Unit 2 The conductivity of the reactor coolant remained within technical specification and fuel 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 conauctivity 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 I
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.
Page 48 PRIMARY COOLANT CHEMISTRY May 1988 Parameter Unit 1 Unit 2 Unit 3 1.
Gross Radioactivity a.
Crud (filter) (mci /ml)
High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A b.
Filtrate (mci /ml)
High N/A N/A N/A Low N/A N/A
-N/A Average N/A N/A N/A 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 P
3.
Tritium (mci /ml)
High 5.27E-5 4.99E-5 1.39E-4 Low 4.66E-5 4.54E-5 1.24E-4 Average 4.95E-5 4.79E-5 1.30E-4 4.
Iodine-131 (mci /ml)
High
<6.01E-7
<4.77E-6
<3.04E-7 Low
<3.45E-7
<3.60E-7
<1.33E-7 Average
<5.02E-7
<1.63E-6
<2.12E-7 5.
Iodine-131- :odine-133 Hatio High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A i
l
Page 49 PRIMt.RY COOLANT CHEMISTRY (Continued)
May 1988 Parameter Unit 1 Unit 2 linit 3 6.
Chloride (ppb)
High
<10
<10
<10 Low
<10
<10
<10 Average
<10
<10
<10 0
7.
pH925 C High 6.3 6.2 6.2 Low 5.8 5.9 5.9 Average 6.G 6.0 6.1 0
8.
ConductiviMnunho/en@25 0)
High 0.86 0.78 0.32 Low 20.087 0.49 0.084 Averatl,e 0.40 0.60 0.13 P
tage 50 CHEMISTRY
SUMMARY
(Continued)
MAY 1988 Environmental Technical Specification Requirements The ambient upstream river temperature (24-RR AVG. MAX.) varied between 67.1 F on May 1 to 77.3 F on May 31 and averaged 72.2 F.
The downstream temperature ranged from 66.5 F on May 1 to 77.5 F on May 31.
The greatest temperature change was 1.8 F on May 20 and 21.
The sedimentation pond (DSN 102) remained out of service for the entico month while wastewater from the water treatment was routed to a smaller holding pond.
The design process to install a synthetic 1.tner has been initiated.
The sewage lagoon (DSN 11) remained isolated for the entire month and there was no discharge. However, there was a solenoid valve malfunction at the main lift station on May 31 that caused sewage to overflow to the intake forebay.
This was reported to the state in the coucine discharge monitoring report.
e Page 51 AIRBORNE RELEASES (1)
MAY 1908 SUMMATION OF ALL RELEASES UNIT THIS MONTH Ao FISSION AND ACTIVATION GA3ES 1.
TOTAL RELEASE CI
< 6.76E 01 2.
AVERAGE RELEALE RATE FOR PERIOD UCI/SEC
< 2.79E 01 3.
PERCENT OF TECH. SPEC. LIMIT (0.05 CI/SEC) 0.00E-01 B.
IODINES L
i 1.
TOTAL IODINE - 131 CI
< 2.82E-05 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC
< 1.16E-05 3.
PERCENT OF TECH. SPEC. LIMIT (0.4 UCI/SEC) 0.00E-01 F
C.
PARTICULATES 1.
PARTICULATES WITH HALF-LIFES > OR = TO 8 DAYS CI 1.60E-04 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 6.60E-05 3.
PERCENT OF TECH. SPEC. LIMIT (0.4 UCI/SEC) 1.65E-02 4.
GROSS ALPHA RADI0 ACTIVITY CI 4.16E-07 D.
TRITIUM j
i l
1.
TOTAL RELEASE CI 3.72E-02 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.54E-02 3.
PERCENT OF TECHNICAL SPECIFICATION LIMIT 2.65E-02 4.
GROUND LEVEL RELEASE CI 3.72E-02 5.
ELEVATED RELEASE CI
< 1.ESE-04 (1)
REPORTING PERIOD 28 DAYS
.. ~...
~ _
Page 52 AIRBORNE RELEASES (CUNTINUED)
MAY 1988 ELEVATdD RELFASES A.
FISSION GASES UNIT THIS MONTH KR-85M CI
< 2.82E 01 KR-87 CI
< 5.95E-02 KR-88 CI
< 2.61E-01 XE-133 CI
< 1.39E-01 XE-135M CI
< 6.85E-02 XE-135 CI
< 7.25E-02 XE-138 CI
< 5.58E-01 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 2.94E 01 B.
< 1.62E-06 I-133 CI
< 1.30E-05 I-135 CI
< 7.83E-02 TOTAL FOR PERIOD CI
< 7.83E-02
(
Page 53 AIRBORNE RELEASES (CONTINUED)
MAY 1988 ELEVATED RELEASES C.
PARTICULATES UNIT THIS MONTH SR-89 CI
< 2.03E-07 SR-90 CI
< 1.03E-07 CS-134 CI
< 1.38E-06 CS-137 CI
< 3.01E-06 BA-140 CI
< 6.33E-06 LA-140 CI
< 4.30E-11 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 1.10E-05 D.
TRITIUM CI
< 1.58E-04
,a
Page 54 AIRBORNE RELEASES (CONTINUED)
MAY 1988 GROUND RELEASES A.
FISSION GASES UNIT THIS MONTH KR-85M CI
< 9.89E-02 KR-85 CI
< 3.61E 01 KR-87 CI
< 1.69E-01 KR-88 CI
< 2.49E-01 XE-133 CI
< 3.26E-01 XE-135M CI
< 4.79E-01 XE-135 CI
< 7.05E-02 XE-138 CI
< 6.79E-01 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI
< 3.81E 01 B.
< 2.66E-05 I-133 CI
< 5.74E-04 I-135 CI
< 6.06E-01 TOTAL FOR PERIOD CI
< 6.07E-01 l
l
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.Page 55 AIRBORNE RELEASES (CONTINUED)
MAY 1988 GROUND RELEASES C.
PARTICULATES UNIT T.1IS MONTH l
SR-89 CI
< 1.82E-06 SR-90 CI
< 9.42E-07 CS-134 CI 2.20E-05 CS-137 CI 4.86E-05 BA-140 CI
< 8 93E-04
)
LA-140 CI
< 4.00E-05 OTHERS(SPECIFY)
CO-60 CI 8.91E-05 TOTAL FOR PERIOD e
CI 1.60E-04 1
D.
TRITIUM CI 3.72E-02 l
i i
1
Paga 56 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES MAY 1788 RADI0 ACTIVE LIQUID EFFLUENTS 1.
GROSS RADI0 ACTIVITY UNITS a)
TOTAL RELEASE CURIES 2.35E-02 b)
AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.41E-09 c)
PERCENT OF APPLICABLE LIMIT ( 1E-7 UCI/ML )
- ?
1.61E 00 2.
TRITIUM a)
TOTAL RELEASE CURIES 1.52E-01 b)
AVERADE DILUTF.D CONCENTRATION RELEASED UCI/ML 1.05E-03 c)
PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) 3.4?E-04 (1) 3.
DISSOLVED NOBLE GASES a)
TOTAL RELEASE CURIES
< 7 24E-04 b)
AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML
/ 4.??E-11 c)
PERCENT OF APPLICABLE LIMIT (2E-04 UCI/ML)
< 2.49E-05 4.
GROSS ALPHA RADI0 ACTIVITY a)
TOTAL RELEASE CURIES 2.54E-04 b)
AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.74E-11 5.
VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 3.96E 06 6.
VOLUME OF DILUTION WATER LITERS 1.46E 10 (1)
INCLUDES XE-133, XE-135, AND OTHERS
l
. BROWNS FERRY NUCLEAR PLANT Pagn 57 MONTHLY REPORT CALCULATIONS LIQUID RELEASES MAY 1988 ISOTOPES RELEASED UNITS CI CR-51
< 2.21E-03 MN-54 5.99E-05 CO-58
< 2.69E-04 FE-59
< 5.90E-04 CO-60 4.54E-03 ZN-65 7.51E-04 l
NB-95
< 2.33E-04 ZR-95
< 4.27E-04 MOTC-99M
< 1.99E-04 I-131
< 2.97E-04 XE-133
< 5.64E-04 CS-134 3.71E-03 XE-135
< 1.60E-04 CS-137 1.44E-02 BA-140
< 1.11E-03 LA-140
< 1.24E-04 CE-141
< 3.53E-04 SR-89
< 8.35E-05 SR-90
< 5.38E-05 FE-55
< 9.62E-04
.-~.
Pago 58 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATf0NS LIQUID RELEASES MAY 1980 OTHERS UNITS
)
CI SB-125 5.79E-05
Page 59 BROWflS ' FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES MAY.
1988 LAUNDRY DRAIN' VOLUME RELEASED:
12196.1 GALLONS FLOOR DRAIN VOLUME RELEASED:
.875569.9 GALLONS ~
WASTE SAMPLE TANK VOLUME RELEASED:
157777.S GALLONS DISTILLATE TANK VOLUME RELEASED:
423.3 GALLONS LOCATION OTHER THAN RADWASTE' VOLUME RELEASED:
0.0 GALLONS TOTAL VOLUME RELEASED.TO THE RIVER:
1045967.2-GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR MONTH:
3.25E-09 UCI/ML A/D LONGEST RELEASE TIME FOR MONTH:
420 -MINUTES SHORTEST RELEASE TIME FOR MONTH:
5 MINUTES TOTAL TIME OF RELEASES FOR MONTH:
9621 MINUTES AVERAGE TIME FOR BATCH RELEASES *
'41 MINUTES NUMBER OF BATCHES RELEASED:
40 NUMBER GF ADMINISTRATIVE LIMIT VIOLATIONS:
0 NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS:
0 l
1
Pags 60 RESIN USAGE REPORT MAY 1988 RESIN CONSUMED (CU.FT.)
% of Total Bead POWDEX ECODEX ECOSORB EPIFLOC Total Raduste Floor Drain Filter 55.3 0
167 0
0 61 228 i
Waste Demineralizer 35.0 0
124 0
19 1
144 Waste Filter 0
0 0
0 0
0 0
Fuel Pool Demins 1.9 0
8 0
0 0
Unit 1
.5 0
2 0
0 0
2 Unit 2 1.5 0
6 0
0 0
6 l
Unit 3 1.0 0
4 0
0 0
4 i
l Cond. Demins i
Unit 1 0
0 0
0 0
0 0
Unit 2 4.8 0
20 0
0 0
20 Unit 3 0
0 0
0 0
0 0
e Totals 100 0
331 0
19 62 412 i
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Page 61 11JEL CLADDING INTEGRITY PARAMETERS MAY 1988 Unit 1 Reactor Water Iodines (uci/sec.)
Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharte of SJAE (uci/sec),
Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 2 i
Reactor Water Iodir.es (uci/sec.)
Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharte of.9JAE (uci/sec)
Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (uci/sec.)
Date I-131 I-132 I-133 T-134 I-135 Unit in Outage Fission Gases at Discharte of SJAE (uct/sec)
Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outaga
WASTE TREATNENT SYSTEM THROUGHPUTS MAY 1988 x
FLOOR FLOOR FLOOR DRAIN DRAlN DRAIN
,,,gg, m
m m
m G C 8.76E s COLLECTOR FILTER SAMPLE SC 8.76E+05
~
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TANK TANK (2) QFT: 228.00 GAL: 8.76E+05 M 0.NEW 1,'
If LAUNDRY SAL: 0.00E+00 GPD: 4.07E+02 DRAIN
,,,,,3-CANAL TANK GR.3.37Ed4 a 3.0444 GC 1.E @
6AL-9.41E+05 CYCLED MATER GPR d.31E+03 SAL: 1.5GE+05 jk if Y if _
1 2
WASTE WASTE WASTE WASTE GPD: 5.09E+03 COLLECTOR SAMPLE SC 1.58E45 q
FILTER DEMINERALIZER TANK TANK (1) uFT: 144.00 (3) QFT:
C.00
]
SAL-1.07E+06 (1) QFT PONDEX: 124.00.CUFT RESIN E FIBER MIXTimE:
1.30.QFT ECOSORC: 19.00 CONDENSATE 4
2.h44 (2) QFT PONDOC 167.00.CUFT RESIN & FIBER MIXTURC-61.00.QFT ECDSORit 0.00 7.
STORAGE (3) SEAD E3IN TANK
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Page 63 i
TESTING
SUMMARY
MAY 1988 Surveillar.ce Testing Unit Q A total of 130 surveillanc9 tests were completed per 17 different test ins tructions.
i Unit 1 A total of 73 surveillance tests were ecmpleted on unit 1 per 33 different test instructions.
-l Unit 2 A total of 81 surveillance tests were completed on unit 2 per 36 different test instructions.
Unit 3 A total of 69 surveillance tests were completed on unit 3 per 25 different tsst instructions.
l
Page 64 TESTING
SUMMARY
(Continued)
MAY 1988 Chantes. Test and Experiments Rea'tirinx Authorization From the NRC Farsuant te 10 CFR 50.59(a)
There were no revisions for unit 1, 2, and 3 technical specifications.
Chanxes. Test s end Experiments not Requiring i.athorization from NRC Pursuant to 10 CFR 50.59(a)
There was one special test completed for this month.
P.T-8704 Test
Description:
Relay Room Supply Duct Leak Rate Test, Control Bay Elevation 617'.
-, - -., - ~.'
- - {\\
- s
-+
+
+
g
~
e Page 65 REACTOR VESSEL FATIGUE USAGE EVALUATION MAY 1988 The cumlative usage factors for the reactor vessel are as follows:
Usate Factor Location Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 closure studs 0.24204 0.17629 0.14360 I
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Page 66 CHANGE IN PROCEDURE MAY 1988 There were 520 revisions to plant instructions during the month; 519 instructions were changed primarily for correction, and the remaining 1 revisions 'celated to safe operation of the plant.
PLANT INSTRUCTION REVISIONS MAY 1988 Category Instruction
Reason for Request
Change in SI-4.7.B.6 Standby Revised to test sample in accordance Response to Gas Treatment System -
with ASTM D 3803 and verify LER, IE Iodine Removal certificate of compliance Bulletin, NRC Efficiency per CAQR BFN 880275.
Inspection Report. OPQA i
Page 67 CHANGE IN FACILITY DESIGN MAY 1988 Package Number Description Safety Related ECN P0600 -
(2139-86) Removed four 4-inch clips from the Reactor Recire. Sys -
Recire. MG sets brush access covers. The ECN Unit 2 has been fully implemented on all 3 units.
The ECN covered modifying the brush rigging to accept a retractable brush holder and modifying the access covers.
The modification did not alter the function of the exciter.
The access covers will still provide protection for the exciter.
The margin of safety was not reduced.
ECN P0792 -
(WP 2114-86) Installed block, vent, and RHR System - Unit 2 drain valves to allow LLRT of valves 2-74-802 and 2-74-803.
Only a portion of the work covered by the ECN was completed.
ECN L2079 -
(WP 2010-86) Removed PT-76-35 and PT-76-36.
Containment Inerting Removed / spared-out associated cable, conduit System - Unit 2 and piping.
A very small portion of the work covered by the ECN was completed.
ECN P0792 -
(2115-86) Installed / modified RHR supports RHR System -
in unit 2, 593' and 621' of the Reactor Unit 2 Building.
The ECN was not fully implemented.
I ECN P0766 -
(2127-86) Installed a 3/8" line with a check HPCI System -
valve and test connection which connected the Unit 2 aux. oil pump discharge with the EGR oil pump discharge.
The ECN was completed on unit 2.
Work remaining to be done on units 1 and 3.
The modification did not degrade the operating conditions of the plant.
The modified system meets the design and functional requirements of the old system.
Based on this, the margin of safety was not reduced.
]
Page 68 CHANCE IN FACILITY DESICN (Continued)
MAY 1988 Package Number Description Safety Related ECN P0914 -
(3027-86) Replaced /added fuseblocks in the Various Systems -
4KV unit board 3C, 4KV shutdown board 3EA, Unit 3 and 4KV shutdown board 3EB.
Only a portion of the work covered by the ECN was completed.
ECW P0913 -
(WP 1022-86) Keplaced/added fuseblocks in the Various System -
480V shutdown board 1A and the AKV unit board Unit 1 1C.
Only a portion of the work covered by the ECN was completed.
ECN P0962 -
(WP 2125-87) Removed and capped pipe at RHR System -
penetration X-216, top of unit 2 torus.
The Unit 2 hydro test was performed by WP 2181-87.
The ECN was totally completed as it only covered
'anit 2.
Removal of a section of pipe and the installation of two pipe caps did not affect the system under normal operating conditions.
The modification did not change the functional operational configuration of the system.
Based on this, the margin of safety was not reduced.
ECN P0971 -
(WP 2130-87) Installed block and test valves RCIC System -
to allow testing of FCV-71-34,12-742, and Unit 2 minimum flow bypass orifice.
The ECN was not completed.
The hydro is being performed by WP 2150-87.
ECN P7018 -
Removed, replaced, and repaired HVAC supports.
HVAC Supports -
(WP 2281-87) Unit 2 Drywell, elev. 616 (WP Unit 2 2282-87) Unit 2 Drywell elev. 628, (WP 2278-87) Unit 2 Drywell elev. 604.
Only a portion of the work covered by the ECN was completed, i
l I
Page 69 CHANGE IN FACILITY DESIGN (Continued)
MAY 1988 Package Number Description Safety Related ECN P0823 -
(WP 2151-87) Provided switches to disable RHR System -
valves 2-FCV-74-1, 74-12, 74-24, 74-35, and Unit 2 74-48 during normal power operation.
All fieldwork was completed on unit 2.
Work remaining to be implemented on units 1 and 3.
Ine.ddicion of the e itches did not adversely affect the operation of any safety-related equipment.
Based upon safety evaluation and the seismic analysis performed by Design, the margin of safety was not reduced.
ECN P0956 -
(WP 2156-87) Fabricated and installed HVAC HVAC Supports duct supports in the Shutdown Board Room i
Unit 2 2D, elevation 593. A small portion of the work covered by the ECN was completed.
ECN P0671 -
(WP 1004-87) Modified sprinkler connections Fire Protection and piping in Battery Room #1 and Battery System - Units 1 & 3 Board Room #1.
The mechanical portion of the ECN has been completed.
All electrical work has not been implemented.
(WP 3005-87) Modified sprinkler connections and piping in Battery Room #3 and Battery Board Room #3.
The mechspical portion of the ECN for unit 3 has been completed.
The electrical portion of the work covered by the ECN has not been fully implemented on unit 3.
Pags 70 l
\\
CHANGE IN FACILITY DESIGN (Continued) l MAY 1988 Packame Number Description l
Safety Rel ted ECN P7039 -
(WP 2073-88/2074-88/2075-88) Removed old 480V Shutdown Board -
transfocuer TS2B by WP 2073-88.
Installed new Unit 2 environmentally qualified transformer TS2B by WPs 2074-88/2075-88.
Only e portion of the work covered by 6.he ECN was accomplished by these workplans.
(WP 2129-88) performed function test on the new transformer TS2B.
DCN B0005D -
(WP 0027 J8) Replaced sectionalizing valves EECW System -
0-FCV-67-14. -18
-22, and -26 in the s cuth Common EECW heador.
The DCE was not completed.
The modification is being performed in valves in the north EECW header.
ECN P0352 -
(WP 2173-88) The workplan was written for Torus Modification -
documentation only to as-construct drawings.
Unit 2 Work had been previously implemented buy drawings were omitted and not updated.
The ECW ir not complete.
ECH P0956 -
(WP 2064-88) No physical work involved.
The EECW System workplan was written to as-construct drawings Unit 2 for the South EECW tie-in.
The ECN was not totally completed.
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Page 71 l
CHANGE IN FACILITY DESIGN (Continued)
MAY ".)88 Packame Number Description t
Non Safety Related DCN M0099A -
(WP 3012-88) Documentation change only to Reactor Water as-construct drawings to indicate that the Cleanup - Unit 3 RWCU pump motors may be either frame 324TS or 326TS.
When 326TS motors are used as replacements, existing outboard mounting holes in the baseplate will be plugged with new outboard mounting holes drilled and i
tapped.
The DCN was completed.
DCN M0097A -
(WF 1013-88) Documentation change only to i
Reactor Water as-condtruct drawings to indicate that the cleanup - Unit 1 the RWCU pump motors may be either frame 324TS or 326TS. When 326TS motors are used as replacements, existing outboard mounting holes in the baseplate will be plugged with new outboard mounting holds drilled and tapped.
The DCN was completed.
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-Pags 72
(
CHANGES IN PLANT ORGANIZATION MAY 1988 q
There were no changes in plant staff for those positions designated as key supervisory positions.
4
(
o Pags 73 ACCIDENTS MAY 1988 There were three loss-of-time accident during the month.
4
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