ML20064D452
| ML20064D452 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1993 |
| From: | Hutchinson C ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-94-00023, GNRO-94-23, NUDOCS 9403110211 | |
| Download: ML20064D452 (8) | |
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ENTERGY
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C. R. Hutchinson u1
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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 1993 Annual Operating Report GNRO-94/00023 Gentlemen:
Entergy Operations, Inc. is transmitting the Grand Gulf Nuclear Station (GGNS)
Unit 1 Annual Operating Report for 1993. This repcrt 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 operating experience during the year 1993,
- 2. Main Steam Line Safety Relief Valve challenges,
- 3. A tabulated annual report of personnel exposure greater than 100 mrem /yr, and
- 4. A summary of failed fuelindications/ inspections.
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Februa'ry 28, 1994 C
3-94/00023 P
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Mr. R. H. Bernhard (w/a)
Mr. D. C. Hintz (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
- 1 Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a) i Regional Administrator U.S. Nuclear Regulatory Commission Region ll 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 t
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SUMMARY
OF OPERATING EXPER!ENCE 1993 The following is a summary of Grand Gulf Nuclear Station (GGNS) Unit 1 operating experience for the 1993 calendar year. During 1993, the reactor was critical for 7,140.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with the generator on line for 6,846.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
On 1/14/93, power was reduced to approximately 65% for correction of steam leaks along -
with a MSR manway cover steam leak.
On 9/13/93, the reactor scrammed due to a high-pressure core spray system (BG) initiation which occurred due to a failed jet pump beam. II ER 93-008] This scrammed ended a Grand Gulf record run of 403 days. Outage duranon time was approximately 225.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
On 9/23/93 during Startup Mode, the reactor was shutdown due to the source of high air in-leakage to main condenser had not been identified. The source was subsequently identified to be MSR "A" Relief Valve N11F034A flange leak. Outage duration time was approximately 84.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
On 9/28/93, the reactor was shutdown to begin RF06. This was before the original scheduled date due to the inoperable #10 Jet Pump (AD). [LER 93-009]. RF06 was extended due to unplanned work items (e.g., replacement of jet pumps) and more repair time for planned items.
On 11/27/93, the reactor was shutdown while critical due to sulfate concentration exceeding EPRI limit. Duration time for this shutdown was 40.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
On 12/1/93, the reactor was shutdown to fix a condenser air inleakage problem. Duration time was approximately 63.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
On 12/4/93, the unit was taken off line to perform planned turbine overspeed test. Duration time was approximately 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
RFOG ended on December 4 at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />. Outage time was 66 days,21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> and 7 minutes.
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Attachment II to GNRO-94/00023 Page 1,of 1 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES 1993 There were no main steam line safety relief valve challenges occurring in 1993.
Attachment fil to GNRO-94/0023 Page1of4 i
GGNS UNIT 1 ANNUAL REPORT
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l MAN-REM EXPOSURE - 1993 This section contains a tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mrem / year 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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Attachment III to CNRO-94/00023 i
Page 2 of 4
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ENTERGY OPERATIONS, INC.
SUMMARY
OF PERSONNEL MONITORING REPORT FINAL END OF THE YEAR REPORT FOR 1993
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Estimated Whole Body Exposure Range Number of Individuals in Each Range -
No Measurable Exposure 1405 Less than 0.1 963 0.1 to 0.25 388 0.25 to 0.5 269
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0.5 to 0.75 122 0.75 to 1.0 40 1.0 to 2.0 23 2.0 to 3.0 2
3.0 to 4.0 0
4.0 to 5.0 0
j 5.0 to 6.0 0
6.0 to /.0 0
7.0 to 8 0 0
8.0 to 9.0 0
9.0 - to 10.0 0
10.0 to 11.0 0
11.0 to 12.0 0
12.0 and over 0
Total number.of personnel monitored 3212 True Total Dose (REM)(1) 302.594 Average REM per person (1) 0.359 e
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. Radiation Protectiop Manager Date Plant Manager Date
. (1) Excluding 2368 persons with less than 0.1 REM. The Total Dose on site for 1993 is 331.855 REM for all personnel monitored 4
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1 Att. Ill to GNRO-94/00023-P ge 3 of 4
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ENTERGY OPERATIONS, INC.
PERSONNEL AND REM BY WORK AND DUTY FUNCTION FINAL END YEAR REPORT FOR 1993 NUMBER OF PERSONNEL OVER 100 MREM TOTAL REM STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS REACTOR OPS / SURVEILLANCE MAINTENANCE 3
0 14 0 033 0.000 0 201-OPERATIONS 63 0
5 21.880 0.000 1.490 i
HEALTH PHYSICS 29 1
43 6.387 0 005 4 048 SUPERVISORY 12 0
45 0.291 0.000 0.945 ENGINEERING 19 0
4 0 962 0.000 0 115 ROUTINE MAINTENANCE MAINTENANCE 128 0
500 51.337 0 000 150.646 OPERATIONS 31 0
4 325 0.000 0 315 HEALTH PHYSICS 28 1
44 8.303 0 115 12.015 I
SUPERVISORY 10 0
38 2.358 0 000 4 533 ENGINEERING 18 0
11 2.309 0 000 1.642 IN-SERVICE INSPECTION MAINTENANCE O
O 47 0 000 0 000 2.559 OPERATIONS 7
0 0
0 443 0.000 0 000 HEALTH PHYSICS 7
0 4
0 029 0.000 0.006 SUPERVISORY 9
0 28 0 419 0.000 6.367 ENGINEERING 1
0 0
0 006 0,000 0 000
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SPECIAL MAINTENANCE MAINTENANCE O
O O
0 000 0 000 0 000 OPERATIONS 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 ENGINEERING 0
0 0
0 000 0.000 0 000 WASTE PROCESSING MAINTENANCE 51 0
22 0.745 0 000 1.009 OPERATIONS 0
0 1
0.000 0.000 1.095 HEALTH PHYSICS 4
0 1
1,151 0 000 0 017 SUPERVISORY 0
0 0
0.000 0 000 0 000 ENGINEERING 0
0 0
0.000 0 000 0 000 4
REFUELING MAINTENANCE 56 0
128 0.763 0.000 21.250 OPERATIONS 7
0 1
0.535 0 000 0 702 HEALTH PHYSICS 14 1
20 1.122 0 002 2.197 SUPERVISORY 7
0 6
0.121 0.000 0 869 ENGINEERING 7
0 1
0 550 0.000 0.057 TOTALS MAINTENANCE 238 0
711 52.878 0 000 175.665 OPERATIONS 108 0
11 26 813 0.000 3002 HEALTH PHYSICS 82 3
112 16 992 0.122 18.283 SUPERVISORY 38 0
117 3189 0.000 12.714 ENGINEERING 45 0
16 3.827 0.000 1.814 GRAND TOTAL 611 3
967 103.699 0.122 212.078 Approved by:
dd T - DT Plant Manader, Operations Date Approved by: C' ecus 0 - H m
' Radiation Protection M) nager Date
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Attachment III to CNRO-94/00023 Page 4 of 4 SPECIAL MAINTENANCE ACTIVITIES There were no special maintenance activities in 1993.
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Attachment IV to GNRO-94/00023 Page1ofI FAILED FUEL INDICATIONS / INSPECTIONS - 1993 Failed fuel assessments performed during Cycle 6 including offgas and coolant activity analyses and flux tilting predicted one large failure in either XNC-703 (8x8 due for discharge) or AND-043 (9x9 twice burnt but not due for discharge). AND-043 was consequently discharged early to preclude the need for sipping during the outage. AND-043 was replaced by a bundle previously marked for discharge. A subsequent inspection and identification of the leaking assembly is scheduled for June 1994. Offgas and coolant activity analyses performed since the startup for Cycle 7 indicate that the reactor is operating failure free.
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