ML20147E175
| ML20147E175 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1987 |
| From: | Conway W FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| L-88-99, NUDOCS 8803040314 | |
| Download: ML20147E175 (15) | |
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ANNUAL OPERATING REPORT ST. LUCIE UNITS 1 AND 2 0803040314 871231 DR ADOCK 05000335
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_m INDEX
. Section Page Number Number 1
~ Changes to the Facility as Described 10CFR50. 59 1
in the FSAR 2
Changes in Procedures as Described 10CFR50. 59 2
in the FSAR 3-Tests or Experiments not Described 10CFR50.59 2
in the FSAR
-4 Core Barrel blovement Summary T.S. 4.4.11 8
5 Steam Genemtor In-Service Inspection T. S. 4. 4. 5. 5 9
6 hiangrove Study T. S. 4. 7. 6.1 10 L
7 Personnel Exposure Summary T.S. 6.9.1.5 11 8
Challenges to Pressurizer Code T.S. 6.9.1.6 12 Safety Valves and PORV'S 9
References 13
c' SECTION 1 CHANGES TO THE FACILITY AS DESCRIBED IN THE FSAR 10CFR50.59 (A) (1) I As in past reports, a summary of changes to the facility is not included since this information is being provided at the time of the annual FSAR Update.
These
- reports, two per Unit, will be submitted by separate letter at the required times.
Each Unit will have one report for FSAR changes and one in-depth report on Plant change modification packages.
FPL submitted this past year's information to the NRC in FPL letter L-87-155 dated April 7,
1987 for Unit 2 and FPL letter L-87-295 dated July 20, 1987 for Unit 1.
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.a; SECTIONS 2 AND 3 CHANGES IN PROCEDURES AS DESCRIBED IN THE FSAR 10CFR50.59 (A) (1) il TESTS AND EXPERIMENTS NOT DESCRIBED IN THE FSAR 10CFRSO.S9 (A) (1) ill There were several items which may fit within these categories as titled above. A listing of these tests and procedures is given below; a discussion of each item follows:
1.
Steam Genemtcr sludge lancing during the Unit 2 Refueling Outage of October throu.qh November, and the Unit 1 Refueling Outage of February through ' April.
2.
Steam Genemtor eddy current testing of both Unit 1 and Unit 2.
3.
Increased pH testing in the secondary feedwater system on Unit 1.
4.
Stmightening of the ICI Plate following the bending of the Plate while it was being mised in the vessel.
5.
CEDMCS n'onitorialg by use of a multi-channel data acquisition system on Unit 2.
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SECTIONS 2 AND 3 1.
STEAM GENERATOR SLUDGE LANCING Steam Genemtor sludge iancing was performed during the 1987 Unit
- 2 refueling outage. A high pressure supply hose was connected to pentmtion #SO. Electrical cabling and a low pressure suction hose were also routed through penetration #50.
Electrical cables passed through a 4-inch inner diameter pipe which was sealed with silicon and potting resin to form an airtight seal on the containment side of the penetration. The suction hose was connected to a nipple welded through the flange, and was equipped with a manual isolation valve. The suction hose and the high pressure supply hose wie filled with water or slurry. As the penetration lines were filled with either slurry or water, and the sludge lancing operations. vere performed, Mode 6 containment integrity was preserved.
A similar operation was carried out on Unit 1 during the 1987 Unit 1 refueling outage, with the exception that penetration #E-4 was used. Neither Unit had a significant sludge build-up.
The Facility Review Group reviewed the stmctural analysis for these penetrations and the associated procedural safety analysis, and concluded there were no unreviewed safety questions involved, as
. per 10CFR50.59.
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5 SECTIONS 2 AND 3 2.
STEAM GENERATOR EDDY CURRENT TESTING The Unit 2 S/G Eddy Current Testing was conducted remotely with the data gathering and positioning control equipment operated in a van located outside the containment. The temporary bolted flange arrangement assured that containment integrity was maintained during Mode 6 opemtion.
The assembly was mounted in place of the blind flange plate currently installed at penetmtion #50 inside containment, prior to setting containment integrity.
Since Mode 6 integrity is intended only to-contain airbome gaseous and particulate releases and is not intended to contain pressures consistent with a LOCA. There were no unreviewed safety questions involved.
The Unit 1 test was mn the same way, except that penetmtion #54 was used.
The Facility Review Group reviewed the stmctural plans for this penetration cover and the accompanying safety analysis, and concluded that, as per 10CFR50.59, no unreviewed safety questions existed for this penetration.
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SECTIONS 2 AND 3.
3.
Increased pH Testing in Secondary Feedwater of Unit 1 For the purpose of, corrosion investigation, secondary chemistry on Unit 1 is being tested with higher pH levels.
This procedumily contmiled test allows for the grar'ual increase in secondary pH on Unit 'l by.1 pH unit per month. It has been well documented that basic pH levels (approx. 8.0 to 10.5) will reduce corrosion mte of iron alloy water tmnsport systems. The usual pH level of the secondary system'is 9.6. During the increase, sampling will take place at a minimum of' twice per week. The feedwater is analyzed for Fe and Cu concentrations. The pH increase shall continue until the pH reaches a level of 10.0. This level shall be maintained for one month. During this time, monitoring as specified above will be maintained for Cu corrosion by limiting Cu concentration in the feedwater to less than 1 ppb.
The Factitty Review Group reviewed a safety evaluation for the subject letter of ir.stmction, and based on this evaluation, concluded that there are no unreviewed safety questions, as per 10CFR50.59.
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b SECTIONS 2 AND 3 4.
S' traightening of the ICI Plate On October 25, 1987, at approximately 6:00 P. M.',
the in-core instrument (ICl) plate on Unit 2 was being lifted with the upper guide structure (UGS) lift rig. In the process of lifting the plate, it was bent.
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Prior to the event, the ICI plate was being lifted in artier to facilitate the replacement of the Heated Junction Thermocouple. The plete was lifted 8-inches higher than 'the maximum allowable and, as a result, it was bent.
A special straightening tool was designed by Combustion Engineering which would apply forces to the plate in ortler to straighten it out.
LOI-MM-27 was used to establish proper straightening techniques, tolerances, and subsequent measurements.
The Facility Review Group reviewed all steps of the operation, and it was determined that no unreviewed safety questions, as per 10CFR50.59, existed throughout the event.
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SECTIONS 2 AND 3 5.
- Unit 2 CEDMCS Monitoring -
As a result _ of the droppin.g -of control element assemblies #5 and
- 7 on May 5,1987, a monitoring system was installed on Unit 2.
A multi-channel data acquisition system was installed for monitoring
' the CEDMCS. CEA's #5 and #7 were placed on the maintenance bus.
and signals to these CEA's monitored. Since the only power scnorce to the CEDM remained the CEDM motor generator sets, the CEA's would still drop in the event of an actual Reactor Protective System actuation, or the manual initiation of a reactor trip.
The Facility Review Group reviewed a safety evaluation for this course of action and, based on this evaluation, concluded that there were no unreviewed safety questions, as per 10CFR60.59, i
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SECTION 4 CORE BARREL MOVEMENT
SUMMARY
T.S.
4.4.11 On May 20, 1987,-the NRC issued Amendment No. 80 for Unit 1 which deleted Core Barrel Movement annual reporting requirement.
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SECTION 5 FTEAM GENERATOR IN-SERVICE INSPECTION T.S.
4.4.5.5 The inspection of the St. Lucie Unit #1 and Unit #2 Steam Generators was conducted by Florida Power and Light, Material Codes and Inspection Group, supplemented by FP&L certified Eddy Current personnel and complemented by contractor personnel.
The Eddy Current In-Service inspection of Steam Generators was performed during the 1987 Unit #1 and Unit 2 outages.
The information concerning Eddy current Testing and Tube Plugging were submitted as part of the Owner's Data Report for Inservice Inspection (Form NIS-1) which was submitted in accordance with the provisions of the ASME Code,Section I,
(IWA-6000).
FPL letter L-87-290 for Unit 1 on July 10, 1987 and FPL lette.r L-88-87 for Unit 2 on February 19, 1988.
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SECT 7.ON 6 MANGROVE SURVEY T.S.
4.7.6.1 In accordance with Technical Specification 4.7.6.1.2, FPL has conducted the St.
Lucie Mangrov.a Photographic Survey.
The evaluation has revealed some deterioration of the mangroves east of the power plant when compared to the 1975 baseline condition.
Investigations and research by a consultant, Dr. San Snedaker of the University of
- Miami, have indicated that the deterioration is most probably due to inadequate water exchange inside the mangrove area.
A program to increase the water exchange in these mangroves has been implemented and has resulted in significant, measurable improvement.
The coverage of the area has increased by over 5% dtiring the past year.
An eng3neering evaluation of whether the deterioration has impacted the FSAR criteria was completed in July 1987.
This evaluation concluded that mangroves are not required to maintain the design basis of the St. Lucie site to protect safety-erosion damage.
Therefore, the deterioration the mangroves have experienced does not create a condition of satety cignificance.
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DATE: 01/19/88 FLOFIDA P02ER & LIGHT LOCATION: SL RADIATION EXPOSURE CJNTROL AND TRAINING SYSTEM - RECO:TS
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1987 MAN-REM OEPORT STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL & MAN-REM FOR WORK AND JOB FUNCTIONS A.W9ER OF P!RSONNEL >100 MREM :
TOTAL MAN-REM WORK & JOB FUNCTION STATION : UTILITY : CONTRACT :
STATION : UTILITY : CONTRACT REACTOR OPERATIONS & SURVEILLANC:
MAINTENANCE PERSONNEL 0
0 0
.355 :
.020 :
.03C OPERATING PERSONNEL 3
0 0
.295 :
.000 :
.010 HEALTH PHYSICS PERSONNEL 1
0 0
435 :
.000 :
.045 SUPERVISORY PERSONNEL 0
0 0
.055
.000 :
.000 ENGINEERING PERSONNEL 0
0 0
.035 :
.000 :
.000 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 149 19 114 59.117 :
4.885 :
43.171 OPERATING PERSONNEL 46 0
60 20.223 :
.235 :
22.826 HEALTH PHYSICS PER$0NNiit 24 0
49 14.670 :
.000 :
17.482 SUPERVISORY PERSONNEL 17 1
6 6.804 :
.220 :
1.947 33 ENGINEERING PERSONNEL 5
0 7
1.235 :
.281 :
3.740 m
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INSERVICE IASPECTION C)
MAINTENANCE PERSONNEL 1
O 6
.200 :
.045 :
2.149 OPERATING PERSONNEL 3
1 29 1.680 :
.270 :
46.800 HEALTH PHYSICS PERSONNEL 0
0 0
.015 :
.000 :
.000 m
$)
SUPERVISORY PERSONNEL 0
0 5
.025 :
.025 :
2.485 ENGINEERING PERSONNEL 2
0 20
.435 :
.120 :
23.315 E Q O, y3 SPECIAL MAINTEMANCE b OO MA%NTENANCE PERSONNEL 58 12 145 17.356 :
2.590 :
75.535 L M%
OPERATING PERSONNEL 3
0 22
.760 :
.015 :
13.610 6 hy HEALTH PHYSICS PERSONNEL 1
0 1
.980 :
.000 :
.305 m
SUPERVISORY PERSONNEL 6
1 7
1.865 :
.435 :
2.775 g
ENGINEERING PERSONNEL 0
0
.015 :
.230 :
15.650 m
g3 WASTE PROCESSING 2
O MAINTENANCE PER$0NNEL 8
0 1
2.235 :
.000 :
.501 i
OPERATING PERSONNEL 2
0 2
.550 :
.000 :
.774 HEALTH PHYSICS PERSONNEL 3
2 0
0 1.320 :
.000 :
.190 SUPERVISORY PERSONNEL 4
3 0
2 2
1.975 :
.000 :
.505 ENGINEERING PERSONNEL 0
0 0
.000
.000 :
.000 REFUELING MAINTENANCE PERSONNEL 186 60 2
307 158.876 :
55.732 :
181.577 OPERATING PERSONNEL 64 1
126 30.450 :
.385 :
67.925 HEALTH PHYSICS PERSONNEL 23 2
3 96 17.296 :
.000 :
57.817 SUPERVISORY PERSONNEL 36 3
19 16.850 :
1.110 :
9.127 ENGINEERING PERSONNEL 7
3 40 2.802 :
1.167 19.905
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TOTAL MAINTENANCS PERSONNEL 227 60 468 238.189 63.272 :
303.063 OPERATING PERSONNEL 85 2
173 53.958 :
.905 :
151.945 HEALTH PHYSICS PER$GNNEL s'
29 0
117 34.716 :
.000 :
75.839
$UPERv!$0RY PERSONNEL 38 3
30 27.574 :
1.790 :
16.841 ENGINEERING PERSONNEL 9
3 67 4.522 :
".798 :
62.610 GRAND TOTAL 388 68 855 358.959 :
67.765 : 610.292
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~ SECTION 8 CHALLENGES TO PRESSURIZER CODE SAFETY VALVES AND PORV'S T.S. 6.9.1.6
~As reported in -- earlier Annual Reports, since the ; Unit 2 ^ Technical Specifications require challenges to relief valves to be documented in the
- Monthly. Report, both Unit 1 and Unit -2 challenges have been reported
. in this manner since Janucry 1,1983, and therefore 'will not be included ^
' in this report.
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P. O. BOX 14CDO, JUNO
.ACH, FL 33408-0420 r
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FEBRUARY 2 9 1980, L-88-99 U.S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Gentlemen:
Re:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 1987 Annual ODeratina ReDort Pursuant to Technical Specification 6.9.1.4, the 1987 Annual Operating Report for St. Lucie Units 1 and 2 is attached.
Very truly yours, F. Con @ 7 enior Vice President - Nuclear WFC/GRM/dh Attachment cc:
Dr.
J.
Nelson
- Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRM23.AOR
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l an FPL Group company