ML18096B310
| ML18096B310 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 12/31/1992 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N93031, NUDOCS 9303040277 | |
| Download: ML18096B310 (14) | |
Text
Public Service Electric' and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236; Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear OperaHons _
FEB 2 5 1993 NLR-N93031 United States Nuclear Regulatory Commission Document Control Desk
'Washington, DC 20555 Gentlemen:
TECHNICAL SPECIFICATION 6.9.1.5 ANNUAL REPORTS SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Public Service Electric and Gas Company (PSE&G) hereby* submits the enclosed Annual Reports for Salem and Hope Creek Generating Stations, in accordance with Technical Specification 6.9.1.5.a and 6-.9.1.5.b of Appendix A to Facility Operating License Nos.
Pursuant to. Technical specification 6.9.1.5.a, Enclosures 1, 2,
- and 3 are submitted for Salem Unit 1, Sal~m Unit 2, and Hope Creek Unit 1, respectively.
These enclosures contain. tabulations on an annual basis of the number of station, utility and other personnel receiving exposures greater than 100 mrem/year and their associated man rem exposures according to work and job function for each unit.
These tabulations are intended to supplement the requirements of 10CFR20, Section 20.407.
Pursuant to the Technical Specification 6.9.1.5.b of Appendix A to Facility Operating Licenses DPR-70 and DPR-75, Enclosure 4 is submitted for Salem Unit 1-. documents the results of the Steam Generator tube inservice inspections performed during the 10th Refueling Outage of Salem Unit 1.
Salem Unit 2 did not have any steam generator tube inspections in 1992.
The Annual Report for Challenges to Main Steam Line Safety/Relief Valves for the Hope Creek Generating Station, required by Technical Specification 6.9.1.5.b of App~ndix A to Facility Operating License No. NPF-57, is being transmitted separately.
9303040277 921231 PDR ADOCK 05000272 R
PDR 04f\\Q10
Document Control Desk NLR-N93031 2
Should you have any questions or comments regarding this submittal, please contact us.
Sincerely, Enclosures (4)
FEB 2 5 1993
Document Control Desk NLR-N93031 3
c Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD-20852 Mr. s. Dembek, Licensing Project Manager
- u. s. Nuciear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 FEB 2 5 1993
ENCLOSURE 1 PUBLIC SERVICE _ELECTRIC PAGE: 1OF2 AND GAS COMPANY DATE: 02/18/93 HANCOCK'S BRIDGE; NJ 08038.
REGULATORY GUIDE 1.16 REPORT PERIOD SALEM UNIT 1 FROM: 01/01/92 STANDARD FORMAT FOR REPORTING TO: 12/31/92 NUMBER OF PERSONNEL AND PERSON-REM BY WORK AND JOB FUNCTION NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON-MREM WORKANDJOBFUNcriON STATION UTIUIY CONTRACT STATION UTIUIY CONTRACT (PERSONNEL GROUPING)
- EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLO:YEES WORKERS&
&OTIIERS
.OTIIERS Reactor Operations and Surveillance Maintenance 14 0
4 6185 19 3455 Operating 0
0 0
32 0
31 Health Physics 3
0 0
832 0
233
- Chemistry 0
0 0
8 0
0 Supervisory 0
0 0
3 7
5
- Engineering 0
0 0
113 6
36 l&C 0
0 0
58 0
78 Securit}'
0 -
0 0
0 0
5 Routine Maintenance Maintenance 4
0 18 4024 132
. 9559 Operating 0
0 0
1521 0
. 326 Health. Physics 8
0 4
3176 153 3141 Chemistry 0
0 0
228 0
10 Supervisory 0
0 0
22 32 29 Engineering.
0 0
0 342 32 60 l&C 0
0 0
93 0
80 Security 0
0 0
0 0
101 Inservice Inspection Maintenance 0
0 0
0 0
21 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
- o
_Security 0
0 0
0 0
0 Special Maintenance Maintenance 2
0 2
1014 0
903 Operating 0
0 0
42 0
0 Health Physics 6
0 3
1552 0
660 Chemistry 0
0 0
13 0
0 SuperviSory 0
0 0
5 7
0 Engineering 0
0 0
30 0
1 l&C 1
0 0
157 0
28 Security 0
0 0
3 0
79
ENCLOSURE 1 (CONT')))
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 SALEM UNIT 1 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND PERSON-REM BY WORK AND JOB FUNCTION PAGE: 2 OF 2
. DATE: 02/18/93 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01/01/92 TO: 12/31/92 NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON~MREM WORKANDJOBFUNCI10N STATION Ul1LlTY CONTRACT STATION Ul1LlTY CONTRACT (PERSONNEL GROUPING)
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS&
&OTIIERS O'IHERS Waste Processing Maintenance 0
0 0
56 0
2 Operating 0
0 0
6 0
7 Health Physics 0
0 0
32 0
32 Chemistry 0
0
- o 0
0 0
Supervisory 0
0 0
0 0
0 Engineering 0
0 0
11 0
0 l&C.
0 0
0 1
0 0
SecuritY 0
0 0
0 0
0 Refueling*
Maintenance 66 0
411 20787 187 187192 Operating 7
0 0
3407 0
376 Health Physics 24 0
42 8316 0
17918 Chemistry 0
0 0
72 0
0
. Supervisory 1
4 1
239 1285 558 Engineering 4
1 5
1134 360 1990 l&C 1
0 8
313 0
1663 Securify 0
0 0
- o.
0 45 Total Mainte,nance 86 0
435 32o66 338 201132 Operating 7
0 0
5008 0
740 Health Physics 41 0
49 '.
13908 153 21984 Chemistry 0
0 0
321 0
10 Supervisory 1
4 1
269 1331 592 Engineering 4
1 5
1630.
398 2087.
l&C 2
0 8
622 0
1849 Security 0
0 0
3 0
230 '
Grand Total:
141 5
498 53827 2220 228624
- Personnel Exposure and Monitoring Report for NRC Docket Number: 50-272 Exposure Year: 1992 Licensee: Public Service Electric and Gas Company Date: 02/18/93 Total Exposure for Salem Unit 1 by TLD during 1992 was. 286.489 person-rem.
PUBLIC SERVICE ELECTRIC Ai""JD GAS COMPANY HANC9CK'S BRIDGE, NJ 08038 SALEMUNIT2 ENCLOSURE2 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND PERSON-REM BY WORK AND JOB FUNCTION PAGE: 1OF2 DATE: 02/18/93 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01/01/92 TO: U/31/92 NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON-MREM WORKANDJOBFUNCTION srATION UllLl1Y CONrRACT srATION Ul1LITY CONrRACT (PERSONNEL GROUPING)
EMPLOYEES
. EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS&
&OTIIERS OTIIERS Reactor Operations and Suiveillance Maintenance 3
0 0
2054 4
1784
. Operating 0
0 0
65 0
8 Health Physics 1
0 0
489 0
136 Chemistry 0
0 0
3 0
0 Supervisory 0
0 0
1 5
3 Engineering 0
0 0
96 37 11 l&C 0
0 0
7 0
99 Security 0
0 0
1 0
3 Routine Maintenance Maintenance 2
0 2
3513 134 5835 Operating 0.
0 0
1419 0
313 Health Physics 7
0 4
3008 153 3031 Chemistry 0
0 0
208 0
10 Supervisory 0
0 0
15 37 30 Engineering 0
0 0
438 23 63 l&C 0
0 0
98 0
142 Security 0
0 0
0 0
101 Inservice Inspection Maintenance 0
0 0
27 0
11 Operating 0
0 0
0 0
0 Health Physii:s 0
0 0
8 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
7 0
0 Security 0
0 0
0 0
0 Special Maintenance Maintenance 2
0 0
1173 1
536 Operating
- 0.
0 0
35 0
0 Health Physics 5
0 2
984 0
553 Chemistry 0
0 0
13 0
0 Supervisory 0
0 0
9 3
0 Engineering 0
0 0
35 0
4 l&C 1
0 0
155 4
0 Security 0
0 0
3 0
79
ENCLOSURE 2 (CONT'D)
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 SALEM UNIT2 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND PERSON-REM BY WORK AND JOB FUNCTION PAGE: 2 OF 2 DATE: 02/18/93 REGULATORY GUIDE 1.16 REPORT PERIOD -
FROM: 01/0i/92 TO: 12/31/92 NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON-MREM WORK AND JOB FUNCI10N STATION Ul1LITY CONrRACT STATION UI1LilY CONrRACT (PERSONNEL GROUPING),
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES.
EMPLOYEES WORKERS&,
&OIHERS OIHERS Waste Processing Maintenance 0
0 0
56 0
2 Operating 0
0 0
6 0
7
}:I~alth Physics 0
0 0
32 0
32 Chemistry 0
0 0
0 0
0 Supeivisory 0
0 0
0 0
0 Engineering
- o.
0 0
11 0
0 l&C 0
0 0
1 0
0 Security 0
0 0
0 0
0 Refueling.
Maintenance 27
. 0 270 10519 120
'85400 Operating 0
0 0
1647 0
210 Health Physics 16 0
27 5370 1
7807 Chemistry 1
0 0
247 0
1 Supeivisory 1
3 0
168 610 125 Engineering 2
0 0
1361 150 341 l&C 1
0 6
263 0
1804 Security 0
0 0
19 0
272 Total
- Maintenance 34 0
272 17342 259 93568 Operating 0
0 0
3172 0
538.
Health Physics 29 0
33 9891 154 11559 Chemistry 1
0 0
471 0
11 Supeivisory
. 1 3
0 193 655 158 Engineering 2
0 0
1941 210 419 l&C 2
0 6
531 4
2045 Security 0
0 0
23 0
455 Grand Total:
69 3
311 33564 1282 108753 Personnel Exposure and Monitoring Report for NRC Docket Number: 50-311 Exposure Year: 1992 Licensee: Public Service Electric and* Gas Company Date: 02/18/93.
Total Exposure for Salem Unit 2 by TLD during 1992 was 144.615 person-rem.
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 HOPE CREEK ENCLOSURE 3 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND PERSON-REM BY WORK AND JOB FUNCTION PAGE: 1OF2 DATE: 02/18/93 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01/01/92 TO: 12/31/92 NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON-MREM WORKANDJOBFUNCllON sr.ATION Ul1LilY CONTRACT 5rATION Ul1I.ITY CONTRACT (PERSONNEL GROUPING)
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES
.WORKERS&
&CYillERS CYillERS Reac.tor Operations and Surveillance Maintenance 1
0 0
1789 132 895 Operating 3
0 0
1910 46 104 Health Physics 1
o*
1 1612 93 978 Chemistry 1
0 0
505 54 2
Supeivisory 0
0 0
59 1
30 Engineering 0
0
- o 364 67 44 l&C 0
0 0
39 0
0 Security 0
0 0
1 0
108 Routine Maintenance Maintenance 0
0 1
553 0
1532 Operating 0
0 0
15 0
0 Health Physics 0
0 0
2 5
63 Chemistry 0
0 0
0 0
0 Supeivisory 0
0 0
0 0
0 Engineering 0
0 0
84 19 34' l&C 0
0 0
1109 0
2 Security 0
0 0
0 0
6 lnseivice Inspection Maintenance 15 1
153 4678 678 94039 Operating 3
0 0
1048
.o 0
Health Physics 4
0 9
1024 0
4649 Chemistry 1
0 0
251 0
0 Supeivisory 0
0 0
137 0
79 Engineering 3
0 0
- 1177 42 3*
I&C 0
0 0
6 0
0 Security 0
0 0
0 0
0.
Special Maintenance Maintenance 54 2
125 19226 744 58386 Operating 41 1
2 14207 293 1278 Health Physics 32 1
33 12126 298 9202 Chemistry 6
1 0
1397 397 3
Supeivis6iy 1
0 0
439 24 39 Engineering 5
2 1
1905 897*
414 I&C
- 23 0
1 6312 0
. 332 Security 0
0 1
6 0
586
ENCLOSURE 3 (CONT'D)
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 HOPE CREEK STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND PERSON-REM BY WORK AND JOB FUNCTION
- PAGE: 2 OF 2 DATE: 02/18/93 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01/01/92
- TO: 12/31/93 NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON-MREM WORKANDJOBFUNCDON SI'ATION urn.rrY CONTRACT SI'ATION
.urn.rrY CONTRACT (PERSONNEL GROUPING)
EMPWYEF.S
- EMPWYEF.S WORKERS EMPWYEF.S EMPWYEF.S WORKERS&
&OTIIERS OTIIERS Waste Processing Maintenance 0
0 0
104 0
8 Operating 0
0 0
101 0
28 Health Physics' 3
0 2
516 0
4o9 Chemistry 0
0 0
0
- O 0
Supeivisory 0
0 0
0 0
0 Engineering-0 0
0 233 0
0 l&C 0
0 0
54 0
0 Security 0
0 0
- 0.
0 0
Refueling Maintenance 63 4
215 21488 1009 115281 Operating 23 1
4 5710 178 1087 Health Physics 22 1
44 9702 179 17060 Chemistry.
0 o*
0 148 0
0 Supeivisory 4
2 0
790 242 74 Engineering 2
2 4
792 742 895 l&C 36 0
- 0.
15146 0
4 Security 0
0 0
15 0
109 Total Maintenance 133 7
494 47838 2563 270141 Operating 70 2
6 22991 517 2497 Health Physics 62 2
89 24982 575 32361 Chemistry 8
1 0
2301 451 5
Supeivisory 5
2 0
1425 267 222 Engineering 10 4
5 4555 1767 1390 l&C 59 0
1 22666 0
338 Security 0
0 1
22 0
809 Grand Total:
347 18 5%
126780 6140 307763 Personnel Exposure and Monitoring Report for NRC Docket Number: 50-354 Exposure Year: 1992 Licensee: Public Service Electric and Gas Company Date: 02/18/93 Total Exposure for Hope Creek by TLD during 1992 was 436.153 person-rem.
J
ENCLOSURE 4 SALEM UNIT 1 ANNUAL REPORT FOR 1992 STEAM GENERATOR TUBE INSERVICE INSPECTION Examinations of the number 11, 12, 13 and 14 steam generators were preformed by Westinghouse NSD under the coordination of the ISI group during the Salem Unit 1 10th refueling outage.
The Eddy Current examination scope complied with Engineering's recommendation of performing 100% examination of all steam generator tubes over a six year period.
The Eddy Current examination scope is detailed below:
11 S/G:
12 S/G:
21% of the tubes (712) were inspected using a bobbin coil probe.
This sample included 102 tubes randomly selected to satisfy technical specification requirements and all tubes with indications noted during previous refueling outages.
20% of the tubes (680) were inspected with a rotating pancake probe to address the concern of Expansion Zone Pure Water Stress Corrosion Cracking at the hqt leg tube sheet (WEXTEX) for steam generators manufactured using explosive tube expansion techniques.
7% of the tubes (237) were inspected using a rotating pancake probe at multiple support plate intersections for detection of ODSSC.
22% of the tubes (743) were inspected using a bobbin coil probe.
This sample included 102 tubes randomly selected to satisfy technical specification requirements and all tubes with indications noted during previous refueling outages.
20% of the tubes (678) were inspected with a rotating pancake probe to address the concern of Expansion Zone Pure Water Stress Corrosion Cracking at the hot leg tube sheet (WEXTEX) for steam generators manufactured using explosive tube expansion techniques.
7% of the tubes (240) were inspected using a rotating pancake probe at multiple support plate intersections for detection of ODSSC.
1 of 5
. J
13 S/G:
14 S/G:
ENCLOSURE 4 21% of the tubes (711) were inspected using a bobbin coil probe.
This sample included 102 tubes randomly selected to satisfy technical specification requirements and all tubes with indications noted during-previous refueling outages.
20% of the tubes (687) were inspected with a rotating pancake probe to addres.s the concern 6f Expansion Zone Pure Water Stress Corrosion Cracking at the hot leg tube sheet (WEXTEX) for steam generators manufactured using explosive tube expansion techniques.
7% of the tubes (241) were inspected using a rotating pancake probe at multiple support plate intersections for detection of ODSSC.
21% of the tubes (733) were inspected using a bobbin coil probe. - This sample included 102 tubes randomly selected to satisfy technical specification requirements and all tubes with indications noted during previous refueling outages.
20% of the tubes (678) were inspected with a rotating pa~cake probe to address the concern of Expansion Zone Pure Water Stress Corrosion Cracking at the hot leg tube sheet (WEXTEX) for steam generators manufactured using explosive tube expansion techniques.
7% of the tubes (241) were inspected using a rotating pancake probe at multiple support plate intersections for detection of ODSSC.
Eddy Current Results 11 S/G:
- The 102 randomly selected tubes, to satisfy Technical Specifications, revealed no indications equal to or exceeding the 40% plugging limit (defective tubes) and less than 5% of the inspected tubes were degraded, thus a scope expansion was not required.
- All other examination results were satisfactory thus there were no tubes plugged and no scope expansions required.
2 of 5
12 S/G:
13 S/G:
14 S/G:
ENCLOSURE 4
- The 102 randomly selected tubes to satisfy Technical Specifications revealed no indications equal to or exceeding the 40% plugging limit
{defective tubes) and less than 5% of the inspected tubes were degraded, thus a scope expansion was not required.
One tube in the non technical specification sample was plugged due to eddy current indications exceeding the 40% technical specification plugging limit.
- The 102 randomly selected tubes to satisfy Technical Specifications revealed no indications equal to or exceeding the 40% plugging limit (defective tubes) and less than 5% of the inspected tubes were degraded, thus a scope expansion was not required.
- Two tubes with indications (including dent.
analysis) from previous refueling outages were plugged due to eddy current indications exceeding the 40% technical specification plugging limit.
- One tube in the non technical specification sample was preventively plugged due to tube degradation in the 35 to 39% range.-
- The 102 *randomly selected tubes to satisfy Technical Specifications revealed no indications equal to or exceeding the 40% plugging limit (defective tubes) and less than 5% of the inspected tubes were degraded, thus a scope expansion was not required.
One tube with an indication from a previous refueling outage was preventively plugged due to.tube degradation in the 35 to 39% range.
One tube in the non technical specification sample was preventively plugged due to tube degradation in the 35 to 39% range.
3 of 5
Steam Extent of Gener:ator Exam.
11 Full length Bobbin Coil RCP at Support
, Plates RCP of Tubesheet 12 Full length Bobbin Coil RCP at Support Plates RCP of 'Tubesheet 13 Full' length Bobbin Coil RCP at Support Plates RCP of 'Tubesheet 14 Full length Bobbin Coil RCP at Support Plates RCP of 'Tubesheet Sub-'Ibtal Full length Bobbin Coil RCP at Support Plates RCP of Tubesheet
'IOI7Ui ENCLOSURE 4 No. of Tubes Inspected 712 237 680 743 240 678 711 241 687 733 241 678 2899 959 2723 6581 4 of 5 Tube with Indications
<20%
20-39%
>40%
9 16 0
0 0
0 0
0 0
20 41
- 1.
0 0
0 0
0 0
8 10 1
0 0
0 0
0 1
15 39 0
0 0
0 0
0 0
52 106 2
0 0
0 0
0 1
52 106 3
- 1
ENCLOSURE 4 Additional Steam Generator Work
- A.
Helium leak detection was performed on #11 steam*generator to locate the source of primary to secondary leakage.
No position evidence of primary to secondary leakage was observed using the Helium Leak Detection Technique however tubesheet video scan during helium pressurization revealed an excessive amount of boron deposits observed surrounding the explosive plugs located in Row 1 Column 91 hot leg and Row 1 Column 2 in the cold leg.
The explosive plugs in these locations were remotely machined and replaced with short standard type Inconel 690 mechanical plugs.
B.
All explosive plugs in bo.th legs Of #11 steam generator were scheduled for replac.ement.
These plugs were* located at Row 1 Columns 1-5 and 90~94 in both legs, twenty total.
Due to difficulties encountered while attempting to machine the explosive plugs and time constraints, only six of the twenty plugs were removed.
Four of these plugs were reported as having both boron deposits surrounding them during helium pressurization and were successfully removed (see above).
In addition,* 'the explosive plugs in Row 1 Column 5 hot and cold were removed and replaced with a short standard type Inconel mechanical plug.
Current Status of Steam Generators At this time, the total number of tube plugs in the Salem Unit 1 Steam Generators are as follows:
S/G 11 S/G 12, S/G 13 S/G 14 Plugs repaired*this outage 6
0 0
0 New tubes plugged this outage 0
1 3
2 Tubes previously plugged 104 120 109 141
'Ibtal tubes plugged 104 121 112 143 5 of 5