ML20128N761
| ML20128N761 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1992 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-93-00013, GNRO-93-13, NUDOCS 9302230385 | |
| Download: ML20128N761 (11) | |
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" ENTERGY INE" F r; ,
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- (,01411 f 4;3 W. T. Cot tle February 17, 1993 .4 , .
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U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Attention: Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 1992 Annual Operating Report GNitO-93/00013 Gentlemen:
Entergy Operations, Inc. is transmitting the Grand Gulf Nuclear Station (GGNS) Unit 1 Annual Operating Report for 1992. This report is in accordance with the reporting program described in Regulatory Guide 1.16, Revision 4, Part C.1.b as modified by the NRC letter to-GGNS dated May 25, 1987 (MAEC-87/0131).
Provided as attachments are:
- 1. A narrative summary of operacing experience during the year 1992,
- 2. Main Steam Line Safety Relief Valvo challenges,
- 3. A tabulated annual report of personnel exposure greater than 100 mrem /yr, and
- 4. A summary of failed fuel indications / inspections.
Yours truly, es r%
WTC/TMC/cg attachments cc: (See Next Page) i o - 220117 fj
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9302230385 921231 PDR ADOCK 05000416- )-
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l l February 17, 1993 GliRO-93/ 00013 Page 2 of 3 cc: Mr. R. H. Bernhard (w/a)
Mr. D. C. Hintz (w/a)
Mr. R. B. McGehce (w/a)
Mr. ft . S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a)
Regional Administrator U.S. liuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555
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Attachment I to GNRO-93/09013 Page 1 of 1
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SUMMARY
OF OPERATING EXPERIENCE 1992 The following is a summary of Grand Gulf Nuclear. Station (GGNS) Unit 1 operating experience for the 1992 calendar year. During 1992,_the
! reactor was critical for 7,349.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with the-generator on line for 7,163.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
On December 29, 1991, a forced shutdown occurred for Recirc Pump 'B' shaft replacement. The plant returned to power on January 10, 1992.
Total duration for this outage was 274 hours0.00317 days <br />0.0761 hours <br />4.530423e-4 weeks <br />1.04257e-4 months <br />.
Grand Gulf 's fifth refueling outage (RFOS) began on April 18, 1992 when the 500kV BKR J5232 was opened. The orioinals goal of 46 days-was -
not obtained. RFOS ended on June 9, 1992, lasting 52 days, 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and 31 minutes, i
On June 18, 1952, a reactor scram occurred due to loss of Elv,tro-hydraulic Control (EHC) fluid pressure during maintenance on EHC. fluid filter. Corrective actions included: Vent ~ plugs removed from filters-and vent valves installed. Mechanics involved were counseled (written -
reprimand) for their failure to adhere to the procedural-requirements.
Plant management now requires direct supervisory attention to-work
! being performed on trip critical systems. A preventative maintenance =
program will be established for three-way valves and their actuators.
Duration hourt were 68.2. (LER-92-013)
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.. actor scram occurred August 4, 1992. This scram was due to a '
'urious low primary cooling water tank level signal when performing a grounding test with the test system malfunctioning. The root cause evalucation and corrective actions taken will~be submitted .in an updated report. This report is scheduled to be completed by March 31, 1993. Duration time was 69.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. (LER-92-017) l On August 26, 1992, the system dispatcher requested power reduction for grid stability during Hurricane Andrew. Duration time 39.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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Attachm*.nt II to GNRO-93/00013 Page 1 of 3 MAIN STEAM SAI"ETY RELIEF VALVE CHALLENGES 1992
- This section contains a summary of main steam line safety relief. valve challenges which occurred during 1992 as reported in the GGNS Monthly Operating Reports for that period. .
The summaries were originally included in the following reports:
June 1992 Report -
GNRO-92/00090 -
dated: July 15,1992 dated: Sept . 14 , 1992 Auc. 1992 Report -
GNRO-92/00115 -
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Attachment II to GNRO-93/00013:
Page 2-of_3 MAIN STEAM BAFETY RELIEF VALVE CHALLFNGES DOCKET NO. 50-416 UNIT 1 COMPLETED BY T. M. Carter TELP0 HONE (601) 437-2401 Date of Occurrence: June 18. 1992 Plant Operating Condition:
Rx Thermal Power 100% Rx Pressure (psia) 1044.7 Rx Mode __1_ >
Rx Power (MWE) 1226 Ex Temperatures 123 F Number of main steam line SRVs: 20 Number of SRVs affected by event 11 Narrative:
On June 18, 1992, a reactor scram occurred due to loss of EHC fluid pressure during maintenance on EHC fluid filter.
The following SRV's actuated automatically once:
B21-F047D, B21-F047A, B21-F051B, B21-F051A, B21-F051K, B21-F047L, B21-F051D, B21-F047H, B21-F051F, B21-F047C, and ' B21-F047G.
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Attachment II to GNRO-93/00013 Page 3 of 3 MAIN BTEAM BAFETY RELIEF VALVE CHALLENGES DOCKET NO. 50-416 UNIT 1 COMPLETED BY T. M. Carter TELEPHONE (601) 437-2401 Date of Occurrence: Auoust 04, 1992 _
Plant Operating Condition:
Rx Thermal Power 1p_Q1 Rx Pressure (psia) 1047.9 Rx Mode 1 Rx Power (MWE) 1225.6 Rx Temperatures 545+F Number of main steam line SRVs: _2S__
Number of SRVs affected by event 2 Narrative:
On August 4, 1992, a reactor scram occurred due to primary water low generator trip.
The following SRV's actuated automatically once:
B21-F051B B21-F051D
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Attachment III to GNRO-93/00013 Page 1 of 4
. GGNS UNIT 1 ANNUAL REPORT RAN-REM EXPOSURE - 1992 This section contains a tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mrem /yr and their associated Man-Rem exposure according to work and job function.
Also included is a tabulation of the number of personnel by exposure range.
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fAttachment[III$to GNRO-93/0001'3 y, ,
ENTERGY OPERATIONS,.INC< 'Page 2.of"41
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SUMMARY
OF;PERSONN~L.MONITORINGEREPORTr FINAL END:0F'THEMYEAR REPORT,FOR!1992- _
NumberJof iEstimated:whole-body-exposure range' ' individuals' i n c e a ch -trl ;ng e ? 9
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No--Measurable Exposure . . ... , .. ... . . .. ,. . . . . . . . . -15561 i.
l Loss'than 0.1 . .... . .. . .... . . ..... . ...... . .. .... '952
- _ 0 .1 to 0.25 . ..... . . . . .. .. . .... ... .. ... ..... 409 .
1 o0.25'to 0.5 . . . .. . ... .. .. . .. ....... 1374: 0
-l 0.5 to 0.75 . ... . ... ... .. ..... .......... -153 0.75.to 1.0 . . . ... , , ,, . 6 9 --
140 tc. 2.0 . . . .. . . .. . . _ . , .. .. ..... :- 6 9 j
- 2. 0. to 3.0 .. . . , . . . . . . .... .. ... .- . . . .. 16:
f3. 0 to 4.0 . . . . . . . . . ... . .. . . . . 0
-410- to 5.0 . . . .. . .. . . ........ . . . . . . . . . . 101 b L5i0 to 6,0 . . . ,, . . .. .. , . . . . . . .... 0-D6 . 0 to 7.0 . . . . . . . . .. . . , ... .. .. 0
' 7-; 0 to 8.0 . . , .. . . .. ... ,.... CF 8 '. 0 ' to 9.0 _. .. .. . . .. . ..... . ...< . .. .0-39.0 .. t o 10.0 .. . . . . .. .. . ... Of 10J0-to'11.0 . . ..... .. .... .. .. IV 11.0 to 12,0 . .. .. . .. . . . . . . ... 0 :- ,
12.0 and-over . . . . . .... . . . .. ... ...... ... 0-
.. Total number of personnel monitored : 35881
.( 1 ) True Totalz Dose (REM) 454.537
-0.421 (1) Average REM per person'
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.RaYietion Protection Manager Date "GeneE51 Manager GGNS 'E D a't e -
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-( 1 ) . Excluding 2508 persons with less than 0 1: REM. The Total ~ Dose on-site
-for 1992 is 484.240 REM.for all:' personnel monitored.
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Attachment Illito GNRO-93/00013!
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-INIIR$Y OPERATIONS, INC.
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. FIRSONNIL AMD-J RIR ---EV E0RX hMD DVi? FUNCTIOM TINAL I@ Di THE VIAR RIPORT FOR 1992
,' - HUMBIR OT PIR$0NNIL OVIR 100 flRIR TOTAL.. RER=
-STATION: : UTILITY- CONTRACT ll0RKIRS STATION 1 . UTILITY- ' CONTRACT UDRKIRS.
, IMPLOVIIS - IMPLOYIES -- A G OTHIRS* IMPLOVIES . '[MPLOVIIS- AND OTHIR$i
' 'RIACTG3 OPS /$URVIILLANCE '
-MAINTINANCE- !? - 0- ' 62 . - 0.242 E f0.000 ' 1.537 -
OPERA L MS 0 1 45 24.736- :0.000 2.100 -
HlALTil PHYSICS 35 -0 57- 13.350- 0.000 20.220~
SUPERUISORY{ 13- 0 44 " 0.321 -0.000 0.624
- ENGINIIRIMC 21 0 14 1.782- ' 0.000 -.
0.254 - 1
- R0!RIMI HAINTINANCE RAINTENANCE. 147 0 SBS 66.781- 0.000 '189.582 OPIRATIONS- 23 1- 45 '1.175 - 0.107 -23.600:
.HIALIM PHYSICS- 36 0 37 5.343 0.000 6.01 2
'SUPIRVISORY 12 0 41 12.715- -0.000 24531 INGIMIIRINC 21 2 46 2.499
.O.244 9.091L iIN-SIRUICI INSPICTIDH-
-GAIRTINAMCI 3' 0 86 0.028 0.000 31.643 - "
-OPIRATIDHS =0 0 7 0.000 0.000 3.786:
WIALTH PHYSICS 2 0 1 0.004 0.000 -0.004' CUPIRVISORY 9 0 55 -0.789 0.000: '21.239
-EQCINIIRINC 2- 0 12 0.436 0.000 ' 0.261-
_SPICIAL 9AINTENANCE GAINTINANCI O- 0 0- 0.000 ~ '0.000 - 0.000-0FIRATIONS. 0 0 0 0.000 - 0.000;- -0.000-HEALTH PHYSICS 0 0 0 .0.000- 0.000 0.000 SUPERVISORY 0 0 0 0.000 0.000 0.000 IRCINIERING 0 0 0. 0.000: 0.000 .0.000-BQSTI PROCIESIMG GAINTINANCI 74 0 48 '1.337' O.000 -1.041 OFIR8tIONS 1 0 1- 0.009 -0.000' 1.579 S ERUI RY 0 0 0 -
0
.INGINIIRINC 0 0 0t 0.000; 0.000- 0.000 RITUILIAC' RAINTENANCI . 62 0 106 0.971. 10.000' 6.992
_OPIRATICMS 7 '1 32 - 0.403 - 0.116 5.854
-HIALTH PHYSICS 19- 0 10 1.484 ' 0.000 2.122 S'JPIRUISORY 2 0- 6 0.1 91 0.000; 0.410 INCINIIRING 5 0 5 0.395- -0.000 1.037
-TOTALS hAINTINANCE 303 0 890 -69.559 0.000- 231 595~
OPIRATIONS: 94 . 2- 130 -26.323~ - 0.'223 ' :.36,919 HIALTH PHYSICS 100 0 115 22.953- :0.000 129.476i SUPIRVISORY ~ 36 - 0 146. 4.01 6 - 0.000 24.934:
IGGIMEIRINC 49 2- 77 5.112. 0.244 10.643 -
. GR9 0 TOTAL 582 4 -1358 127. 63 - 0.467 - ~333.b67
?epprovedby- -- ---- -
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Approved by . --- --
p Radiatica Protection Manager Date General Manager GCNS L Date - i l
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~ Attachment.III_.toLGNRO 93/000131- :i Page - 4 of-:4 -
SPECIAL MAINTENANCE ACTIVITIES.
There were no special= maintenance-activities in 1992.,
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g4 Attachment IV to GNRO-93/00013 Page 1 of_1 FAILED FUEL INDICATIONS / INSPECTIONS -'1992 Offgas and coolant activity analyses performed during Cycle 5 indicated a small number'(1 to 3) of fuel rod failures. During RF05 two 9x9 assemblies, AND-122 and AND-018, and one 8x8 assembly, XNC-827, were identified by sipping as containing failed fuel _ rods.
Siemens Power Corporation identified the failed rods in both - 9x9 assemblies by both eddy current testing and visual examination. Rod-A02 in assembly AND-018 and rod A05 in assembly AND-122 were
.. identified failures. Both failed rods were replaced - by natural uranium rods. The reconstituted bundles were returned to the reactor for subsequent use.
The 8x8 assembly was visually examined during RF05 but the failed' rod could not be examined due to difficulty removing the upper tic plate.
The upper tie plate removal problem led to the additional examination of eleven 8x8 assemblies to support continued operation. Conclusions from the exam indicated that the unexpected differential growth observed would have no adverse impact on continued reactor operation.
XNC-827 was placed in the spent fuel pool for storage until further examination could be performed.
Assemblies XNC-827 and XNC-582 (both 8x8) were further examined in October 1992 to complete the 8x8 differential rod growth exams. Fuel assembly and rod length measurements, eddy current testing, rod diameter, oxide thickness and visual exams were performed on selected rods of each assembly. Rod BOS from assembly XNC-827-was identified i as failed by eddy current testing. The failed rod was returned to the l assembly and will remain with the bundle in the spent. fuel pool.
Root cause evaluation of the f ailed fuel rods has been indeterninate, whereas operational causes have been ruled out (i.e., PCI, debris, handling, chemistry, etc.). The 8x8 differential rod growth
! information has been previously reported under LER 92-009 and an j
information meeting held with the NRC staff on May 22, 1992.
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