ML18101A572
| ML18101A572 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 12/31/1994 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18101A571 | List: |
| References | |
| NUDOCS 9503010346 | |
| Download: ML18101A572 (14) | |
Text
I PUBLIC SERVICE ELECTRIC & GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 PAGE: 1 OF2 DATE: 02/14/95 SALEM 1 REGULATORY GUIDE 1.16 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM REPORT PERIOD BY WORK AND JOB FUNCTION 01/01/94-12/31/94 NUMBER OF PERSONNEL TOTAL MAN-MREM WORK AND JOB FUNCTION I> 100 MREMI
!PERSONNEL GROUPING)
STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
&OTHERS & OTHERS REACTOR OPERATION I SURVEILLANCE MAINTENANCE 0 0 0 253 24 9 OPERATING 0 0 0 107 22 6 HEALTH PHYSICS 0 0 0 210 0 0 CHEMISTRY 0 0 0 16 4 0 SUPERVISORY 0 0 0 28 0 0 ENGINEERING 0 0 0 47 17 0 l&C 0 0 0 10 0 0 SECURITY 0 0 0 0 0 25 ROUTINE MAINTENANCE MAINTENANCE 18 6 7 n69 1680 3040 OPERATING 2 0 0 2466 238 51 HEALTH PHYSICS 10 0 0 2760 190 559 CHEMISTRY 0 0 0 50 3 0 SUPERVISORY 0 0 0 235 10 24 ENGINEERING 1 0 0 531 244 17 l&C 0 0 4 54 1 1059 SECURITY 0 0 0 10 0 0 INSERVICE INSPECTION MAINTENANCE 0 0 n 0 0 21 OPERATING 0 0 0 1 0 o*
HEALTH PHYSICS 0 0 0 0 0 0 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 0 0 0 ENGINEERING 0 0 0 0 0 0 l&C 0 0 0 0 0 0 SECURITY 0 0 0 0 0 0 SPECIAL MAINTENANCE MAINTENANCE 0 2 4 210 442 1585 OPERATING 0 0 0 29 93 95 HEALTH PHYSICS 0 0 0 211 1 138 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 1 0 0 ENGINEERING 0 0 0 2 16 8 l&C 0 0 0 0 0 22 SECURITY 0 0 0 0 0 6
( 9503010346 950223 PDR ADOCK 05000272 R PDR
PUBLIC SERVICE ELECTRIC & GAS COMPANY HANCOCK'S BRIDGE, NJ 08038
- PAGE: 2 OF2 DATE: 02/14/95 SALEM 1 REGULATORY GUIDE 1.16 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM REPORT PERIOD BY WORK AND JOB FUNCTION 01/01/94-12/31/94 NUMBER OF PERSONNEL TOTAL MAN-MREM WORK AND JOB FUNCTION (> 100 MREMI (PERSONNEL GROUPING)
STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS &OTHERS WASTE PROCESSING MAINTENANCE 0 0 1 43 33 123 OPERATING 1 0 0 172 25 0 HEALTH PHYSICS 4 0 1 1453 0 402 CHEMISTRY 0 0 0 O* 0 0 SUPERVISORY 0 0 0 2 0 0 ENGINEERING 1 0 0 167 67 0 l&C 0 0 0 0 0 0 SECURITY 0 0 0 0 0 0 REFUELING MAINTENANCE 0 0 0 109 0 183 OPERATING 0 0 0 61 0 0 HEALTH PHYSICS 0 0 0 15 0 0 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 3 0 0 ENGINEERING 0 0 0 0 0 0 l&C 0 0 0 0 0 0 SECURITY 0 0 0 0 0 0 TOTAL MAINTENANCE 18 8 12 8384 2179 4961 OPERATING 3 0 0 2836 378 152 HEALTH PHYSICS 14 0 1 4649 191 1099 CHEMISTRY 0 0 0 66 7 0 SUPERVISORY 0 0 0 269 10 24 ENGINEERING 2 0 0 747 344 25 l&C ' 0 0 4 64 1 1081 SECURITY 0 0 0 10 0 31 GRAND TOTAL 37 8 17 17025 3110 7373 COLLECTIVE DOSE FOR SALEM 1 BY TLD DURING 1994 WAS 27.614 PERSON-REM PERSONNEL EXPOSURE AND MONITORING REPORT FOR EXPOSURE YEAR 1994 NRC DOCKET NUMBER 50-272 LICENSEE: PUBLIC SERVICE ELECTRIC & GAS COMPANY DATE: 02/14/95
ENCLOSURE 2
HANCOCK'S BRIDGE, NJ 08038 PUBLIC SERVICE ELECTRIC & GAS COMPANY PAGE: 1 OF2 DATE: 02/14/95 SALEM 2 REGULATORY GUIDE 1.16 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM REPORT PERIOD BY WORK AND JOB FUNCTION 01/01/94-12/31/94 NUMBER OF PERSONNEL TOTAL MAN-MREM WORK AND JOB FUNCTION I> 100 MREMI (PERSONNEL GROUPING!
STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
&OTHERS & OTHERS REACTOR OPERATION I SURVEILLANCE MAINTENANCE 0 0 0 200 55 64 OPERATING 0 0 0 167 12 10 HEALTH PHYSICS 0 0 0 154 3 61 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 1 12 0 ENGINEERING 0 0 0 41 17 1 l&C 0 0 0 1 1 0 SECURITY 0 0 0 0 0 25 ROUTINE MAINTENANCE MAINTENANCE 1 6 4 2342 1869 3510 OPERATING 0 0 1 1801 321 317 HEALTH PHYSICS 2 2 0 1450 477 700 CHEMISTRY 0 0 0 48 0 0 SUPERVISORY 0 0 0 146 7 85 ENGINEERING 1 0 0 347 249 66 l&C 0 0 0 88 9 219 SECURITY 0 0 0 10 0 10 INSERVICE INSPECTION MAINTENANCE 0 11 8 100 2186 4566 OPERATING 0 3 0 1 453 0 HEALTH PHYSICS 0 0 0 0 0 0 CHEMISTRY 0 0 0 0 48 0 SUPERVISORY 0 0 0 8 0 47 ENGINEERING 0 1 1 4 388 487 l&C 0 0 0 2 0 2 SECURITY 0 0 0 0 0 0 SPECIAL MAINTENANCE MAINTENANCE 0 0 0 0 0 0 OPERATING 0 0 0 0 0 0 HEALTH PHYSICS 0 0 0 0 0 0 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 0 0 0 ENGINEERING 0 0 0 0 0 0 l&C 0 0 0 0 0 0 SECURITY 0 0 0 0 0 6
I PUBLIC SERVICE ELECTRIC & GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 PAGE: 2 OF2 DATE: 02/14/95 SALEM 2 REGULATORY GUIDE 1.16 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM REPORT PERIOD BY WORK AND JOB FUNCTION 01/01/94-12/31/94 NUMBER OF PERSONNEL TOTAL MAN-MREM WORK AND JOB FUNCTION I> 100 MREMI (PERSONNEL GROUPING)
STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS & OTHERS WASTE PROCESSING MAINTENANCE 0 0 1 43 33 123 OPERATING 1 0 0 172 25 0 HEALTH PHYSICS 4 0 1 1388 0 400 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 2 0 0 ENGINEERING 1 0 0 167 67 0 l&C 0 0 0 0 0 0 SECURITY 0 0 0 0 0 0 REFUELING MAINTENANCE 23 15 190 8584 5188 73730 OPERATING 4 2 31 3570 918 13206 HEALTH PHYSICS 20 0 50 7305 160 15319 CHEMISTRY 0 0 0 107 9 0 SUPERVISORY 4 0 3 604 0 2368 ENGINEERING 0 1 0 308 571 296 l&C 0 0 8 398 34 2522 SECURITY 0 0 0 2 0 0 TOTAL MAINTENANCE 24 32 203 11269 9331 81933 OPERATING 5 5 32 5711 1729 13533 HEALTH PHYSICS 26 2 51 10297 640 16480 CHEMISTRY 0 0 0 155 57 0 SUPERVISORY 4 0 3 761 19 2500 ENGINEERING 2 2 1 867 1292 850 l&C 0 0 8 489 44 2473 SECURITY 0 0 0 12 0 41 GRAND TOTAL 61 41 298 29561 13112 118140 COLLECTIVE DOSE FOR SALEM UNIT 2 BY TLD DURING 1994 WAS 161.435 PERSON-REM PERSONNEL EXPOSURE AND MONITORING REPORT FOR EXPOSURE YEAR 1994 NRC DOCKET NUMBER 5Q-311 LICENSEE: PUBLIC SERVICE ELECTRIC & GAS COMPANY DATE: 02/14/95
ENCLOSURE 3
I PUBLIC SERVICE ELECTRIC & GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 PAGE: 1OF2 DATE: 02/14/95 HOPE CREEK REGULATORY GUIDE 1.16 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM REPORT PERIOD BY WORK AND JOB FUNCTION 01/01/94-12/31/94 NUMBER OF PERSONNEL TOTAL MAN-MREM WORK AND JOB FUNCTION I> 100 MREMI (PERSONNEL GROUPING)
STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS & OTHERS REACTOR OPERATION I SURVEILLANCE MAINTENANCE 7 0 4 1981 189 2170 OPERATING 57 0 0 17448 133 49 HEALTH PHYSICS 21 0 9 4911 40 4154 CHEMISTRY 5 0 0 1485 4 0 SUPERVISORY 0 0 0 43 20 13 ENGINEERING 0 0 1 176 212 198 l&C 0 0 0 124 4 0 SECURITY 0 0 0 0 3 192 ROUTINE MAINTENANCE MAINTENANCE 9 0 6 3667 654 1867 OPERATING 4 0 0 992 129 24 HEALTH PHYSICS 0 0 0 554 15 312 CHEMISTRY 0 0 0 0 0 0 SUPERVISORY 0 0 0 0 0 13 ENGINEERING 2 0 0 232 113 4 l&C 7 0 0 2577 25 32 SECURITY 0 0 0 0 2 19 INSERVICE INSPECTION MAINTENANCE 0 4 c;~ 383 956 19560 OPERATING 0 4 2 72 1333 366 HEALTH PHYSICS 0 0 5 112 0 1255 CHEMISTRY 0 1 0 0 241 0 SUPERVISORY 0 0 1 34 1 348 ENGINEERING 0 3 1 0 987 322 l&C 0 0 0 10 0 0 SECURITY 0 0 0 0 0 1 SPECIAL MAINTENANCE MAINTENANCE 49 7 139 16024 2829 70625 OPERATING 15 4 2 6820 791 1560 HEALTH PHYSICS 23 2 19 5710 522 6109 CHEMISTRY 0 0 0 65 0 0 SUPERVISORY 0 0 0 86 67 47 ENGINEERING 1 2 2 223 996 475 l&C 12 0 2 3269 5 1137 SECURITY 0 0 0 0 0 0
PUBLIC SERVICE ELECTRIC & GAS COMPANY HANCOCK'S BRIDGE, NJ 08038
- PAGE: 2 OF2 DATE: 02/14/95 HOPE CREEK REGULATORY GUIDE 1.16 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM REPORT PERIOD BY WORK AND JOB FUNCTION 01/01/94-12/31/94 NUMBER OF PERSONNEL TOTAL MAN-MREM WORK AND JOB FUNCTION I> 100 MREMI (PERSONNEL GROUPING)
STATION UTILITY CONTRACT STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS & OTHERS WASTE PROCESSING MAINTENANCE 0 0 0 81 158 39 OPERATING 0 0 1 199 25 1078 HEALTH PHYSICS 13 0 3 4460 3 1188 CHEMISTRY 0 0 0 5 0 0 SUPERVISORY 0 0 0 29 0 0 ENGINEERING 0 0 0 0 263 0 l&C 0 0 0 174 0 0 SECURITY 0 0 0 0 0 0 REFUELING MAINTENANCE 43 20 146 13821 7076 62841 OPERATING 36 7 3 9723 1846 1130 HEALTH PHYSICS 13 1 37 4345 613 12601 CHEMISTRY 0 0 0 30 9 0 SUPERVISORY 0 0 1 309 44 396 ENGINEERING 1 2 0 413 605 441 l&C 30 0 8 10195 92 2264 SECURITY 0 0 0 0 0 37 TOTAL MAINTENANCE 108 31 347 35957 11862 157132 OPERATING 112 15 8 35254 4257 4207 HEALTH PHYSICS 70 3 73 20092 1193 25619 CHEMISTRY 5 1 0 1585 254 0 SUPERVISORY 0 0 2 501 132 817 ENGINEERING 4 7 4 1044 3176 1440 l&C 49 0 10 16349 126 3433 SECURITY 0 0 0 0 5 249 GRAND TOTAL 348 57 444 110782 21005 192897 COLLECTIVE DOSE FOR HOPE CREEK BY TLD DURING 1994 WAS 325.940 PERSON-REM PERSONNEL EXPOSURE AND MONITORING REPORT FOR EXPOSURE YEAR 1994 NRC DOCKET NUMBER 50-354 LICENSEE: PUBLIC SERVICE ELECTRIC & GAS COMPANY DATE : 02/14/95
I ENCLOSURE 4
e I 1994 STEAM GENERATOR REPORT OVERVIEW The Inspections performed during 1994 were limited to Unit 2 and were conducted during the Unit 2 Eighth Refueling outage.
- The original scope was comprised of 20% full length bobbin and 20% top of hot leg tubeshee~ RPC in steam generator 22, 23 and 24. Steam generator 21 's program was 100%
full length bobbin and 100% top of hot leg tubesheet RPC in order to locate the 0.066 GPD primary to secondary leakage source. In addition, a twelve hour window was allotted for RPC testing of dented hot leg tube support plate intersections.
INSPEC'fIONS PERFORMED:
+ TOP OF TUBESHEET RPC INSPECTION The tube expansions in the steam generators at Salem Unit i and Salem Unit 2 were made using the WEXTEX process (explosive expansions). History ofWEXTEX units has shown some cracking in the expansion transition. Cracking of the \VEXTEX region can be axial, circumferential or oblique in orientation as detected by RPC. According to Westinghouse letter WOG-WEX-92-06 ("RPC Inspection and Leakage Monitoring Guidelines") the extent of circumferential cracking and the extent to which an axial indication extends into the transition zone are critical measurements.
- Steam Generator 21 had three indications, namely RlS ClO, R12 C16 and Rl2 C69, reported during the 100% program. All of these indications were axial in orientation and were contained entirely below the bottom of the WEXTEX transition. All three were ID initiated and resembled PWSCC previously found at both Salem units. Residual stress from the WEXTEX expansion process was the likely cause for these indications.
- Steam Generators 22 did not have any RPC indications reported during the inspection. 708 tubes were inspected which represents 20. 9% of the steam generator.
- Steam Generators 23 did not have any RPC indications reported during the inspection. 708 tubes were inspected which represents 20.9% of the steam generator.
- Steam Generator 24's initial 20% program (708 tubes) was expanded by 204 tubes in accordance with Tech. Specs. after two indications, R26 C42 and R7 C45, were reported.
These two indications, like those reported in S/G 21, were axially oriented and below the bottom of the WEXTEX transition. Again, they were ID initiated and resembled PWSCC, most likely caused by residual stresses from the WEXTEX expansion process. A total of 912 tubes were inspected which represents :?7% of the steam generator.
PSE&G requested Westinghouse's Steam Generator Technology and Engineering group to review the eddy current data collected for the tubes identified above to assess the significance of the cracks with respect to structural adequacy under the requirements of Reg. Guide 1.121.
1
2 - COLD LEG THINNING All four steam generators have had thinning at peripheral tube cold leg support plate intersections.
No t~1bes were plugged for this degradation mechanism. The growth rate of previous indications was six percent or less. New indications appe<tred in tubes that had not been bobbin tested since 1988. Overall, the rate of thinning appears to have slowed or stopped.
3 - OD INDICATIONS AT NON-DENTED SUPPORT PLATES Most of the previous Distorted Indications reported at the support plate intersections were down graded this outage to INR's. (Indications Not Reportable). The reason for this change is now these intersections appear to have deposits on each edge and the signal that was previously reported was actually just a gap in these deposits. However, there were some indications that did not fit into this category. They were distorted on bobbin and required further clarification by RPC testing. The number of intersections RPC tested for this reason by steam generator were:
Steam Generator No. of Intersections Inspected 21 10 22 1 23 *5 24 7 These RPC tests did not show any degradation thus there is no confirmed presence of ODS CC at the support plates in any steam generator.
4 - OD INDICATIONS AT COLD LEG TOP OF TUBESHEET These indications are similar to the support plate indications mentioned above, in that the signals are usually distorted by the presence of a deposit. Again, this deposit is most likely responsible for the corrosion occurring.
Two indications were detected above the cold leg top of tubesheet. One in S/G 23, R32 C27, was located at TSC + 0.77" and appeared to be caused by wastage induced by sludge on the top of the tubesheet. The depth of this indication was 38%. The second indication, SIG 21, R6 C85, was located at TSC + 5.65". This indication appeared to be related to a buff mark, but the wall loss measured 38%. Both of these indications were preventively plugged.
+ RPC OF DENTED SUPPORT PLATE INTERSECTIONS Twelve hours were allocated for sample testing of dented support plate intersections in each steam generator. The dents were selected based on measured amplitude from bobbin data. Approximately 200 dents from each steam generator were selected for testing. The initial number for the inspection was based on the testing rates from Unit 1 (1993), where the most intersections tested in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> was 170. The aim of this testing is to detect the presence of circumferential indications.
Circumferentially oriented indications can not be seen by bobbin probes. The number of intersections inspected is shown in the table below:
3
Salem's structural limit for 100% through-wall axial cracks in the free span region is calculated to be 0.41" in length. The tubes identified were found in SIG 21 and SIG 24; the pertinent measurement data are summarized below:
Steam Generator Uppermost Indication Origin Measured Corrected Row- Column Elevation Len 2th Length SIG 21 Rl5 ClO BWT-0.20 SAI ID 0.39" 0.42" SIG 21 Rl2 Cl6 BWT-0.60 SAI ID 0. 7G" 0.71" SIG 21 Rl2 C69 BWT- 0.41 MAI ID 1.08" (1) 0.99" SIG 24 R7 C45 BWT - 2.47 SAI ID 0.56" 0.50" SIG 24 R26 C42 BWT- 0.44 SAI ID 0.44" 0.43" (1): Overall length BWT: Bottom of WEXTEX Transition SAI: Single Axial Indication MAI: Multiple Axial Indications While these crack lengths did exceed the structural length limit for free span tubing, it was determined there was no consequence either to the inspection scope or with respect to risk to the public safety because all of these cracks were confined within the tubesheet BELOW the bottom of the WEXTEX transition. In these circumstances there was no possibility of a tube burst in the event of the occurrence of a design basis pressure transients during the cycle just completed, nor rs such risk possible for similar cracks should they appear during operation in the next cycle.
Westinghouse stated the possibility existed that the 0.066 GPD leak observed prior to the end of the cycle in SIG 21 arose from one or more of the tubes identified in the list above. Any of the crack indications observed may have a least a small segment that is through-wall. Leakage from cracks in the fully expanded tube section would be suppressed by the contact pressure, but some minor fraction of the potential leakage could be observed if the crack tips reside in the first 0.7" below the bottom of the WEXTEX transition, where a small diameter taper from full expansion t!lay exist. In this region of taper, ieakage is gap limitec.; ,i.:i opposed to contact pressure limited.
All three tubes in 21 SIG had their uppermost crack tips within the gap limited leakage length.
+ BOBBIN INSPECTION There were four different types of degradation detected during the bobbin inspection. They are:
1- AVB WEAR All four steam generators have had some wear at the anti-vibration bars. Steam generator 23 had one indication measuring 41% at AV2 in R30 C50. This indication forced a 204 tube expansion in accordance with Tech. Specs. The depth had grown from 34% in 1991, 2R6 inspection.
This tube was plugged. The growth rates for AVB indications seems to have slowed, as this was the only indication, previous or new, to go over the forty percent line in any of the four steam generators. Typically, the AVB wear progresses to a certain point, then slows or stops altogether.
2
Steam Generator Number of dented Intersections Inspected 21 159 22 151 .
23 155 24 178 No indications were detected in this inspection program.
THE FOLLOWING TUBES IN 21THROUGH24 STEAM GENERATORS WERE t>LUGGED DURING 2R8 AS A RESULT OF EDDY CURRENT INDICATIONS:
Steam Generator Row Column Reason 21 15 10 SAI @, TSH > 40%
21 12 16 SAl @ TSH > 40%
21 12 69 MAI @, TSH > 40%
21 6 85 38% laJ. TSC + 5.65" 23 32 27 38%@, TSC + 0.77" 23 30 50 41% laJ. AV2 24 26 42 SAI laJ. TSH > 40%
24 7 45 SAI @, TSH > 40%
Definitions SAI - single axial indication TSC - Tubesheet cold leg side MAI - multiple axial indication AV# - indication located at this Anti-vibration TSH - Tubesheet hot leg side bar Current Tube Plugging Status Steam Generator Steam Generator Steam Generator Steam .Generator 21 22 23 24 Tubes previously plm!!!ed 112 121 112 133 New tubes plugged this outa2e 4 0 2 2 Total tubes plu!!!!ed 116 121 114 135 4
~ -
THE FOLLOWING IS A
SUMMARY
OF THE MOST SEVERE INDICATION PER TUBE FOUND IN EACH STEAM GENERA TOR INDICATION 21 SIG 22 SIG 23 SIG
- 24 SIG MBM 26 7 12 2 DI 8 1 7 5 1-19 % 18 9 19 34 20-29 %
- 32 13 26 24 30-39 %
- 13 9 10 14 40-49 %
- 0 0 0 1 SAi 2 0 2 0 MAI 1 0 0 0 TOTAL 100 39 76 80
- Reportable Indication per NRC Regulatory Guide 1.83 July, 1975 Rev. 1 11 InService Inspection of Pressurized Water Reactor Steam Generator Tubes" Definitions NIBM - Manufacturing Buff Mark DI - Distorted Indication SAI - Single Axial Indication MAI - Multiple Axial Indication STEAM GENERA TOR SLUDGE LANCING RESULTS Steam Generator 21 22 23 24 Amount of sludge Removed 41 lbs. 45.5 lbs. 61 lbs. 31.5 lbs.
5