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| issue date = 12/31/1990 | | issue date = 12/31/1990 | ||
| title = Annual Operating Repts for 1990 for Salem & Hope Creek Generating Station. W/910228 Ltr | | title = Annual Operating Repts for 1990 for Salem & Hope Creek Generating Station. W/910228 Ltr | ||
| author name = | | author name = Labruna S | ||
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | ||
| addressee name = | | addressee name = | ||
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=Text= | =Text= | ||
{{#Wiki_filter:.! 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 | {{#Wiki_filter:.! | ||
-Nuclear Operations FEB 2 8 1991_ NLR-N91036 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | Public Service Electric and Gas | ||
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. DPR-70, DPR-75, and NPF-57. Pursuant to Technical Specification 6.9.1.5.a, Enclosures 1,2, and 3 are submitted for Salem Unit 1, Salem Unit 2, and Hope Creek Unit 1, respectively. | .Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations FEB 2 8 1991_ | ||
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 10 CFR 20, Section 20.407. Pursuant to Technical Specification 6.9.1.5.b, Enclosure 4 is submitted for Salem Unit 2. Enclosure 4 documents the results of steam generator tube inservice inspections performed during the 5th Refueling Outage of Salem Unit 1 in May 1990. Salem Unit 1 did not have any steam generator tube inspections in 1990. 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 Appendix A to Faciiity Operating** | NLR-N91036 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | ||
License No. NPF-57 is being transmitted separately. | 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. | ||
11001 I/ 1 | DPR-70, DPR-75, and NPF-57. | ||
Pursuant to Technical Specification 6.9.1.5.a, Enclosures 1,2, and 3 are submitted for Salem Unit 1, Salem 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 10 CFR 20, Section 20.407. | |||
*1 | Pursuant to Technical Specification 6.9.1.5.b, Enclosure 4 is submitted for Salem Unit 2. Enclosure 4 documents the results of steam generator tube inservice inspections performed during the 5th Refueling Outage of Salem Unit 1 in May 1990. Salem Unit 1 did not have any steam generator tube inspections in 1990. | ||
(>100 MREM) TOTAL MAN-MREM WORK.AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) | 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 Appendix A to Faciiity Operating** License No. NPF-57 is being transmitted separately. | ||
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS & OTHERS &01HERS Reactor Operations and Surveillance Maintenance 0 0 1 196 0 481 Operating 1 0 0 1674 0 55 Health Physics 1 0 2 838 0 745 Chemistry 0 0 0 7 0 0 Supervisory 0 0 0 0 0 5 Engineering 0 0 0 30 5 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 tine Maintenance Maintenance 6 0 4 4398 46 3240 Operating 0 0 0 1448 0 24 Health Physics 6 0 1 1939 35 922 Chemistry 0 0 0 62 0 1 Supervisory 0 0 0 5 126 1 Engineering 1 0 0 356 6 0 l&C 0 0 0 33 0 121 Security 0 0 0 10 0 57 Inservice Inspection Maintenance 0 0 0 0 0 9 Operating 0 0 0 2 0 0 Health Physics 0 0 0 7 0 0 Chemistry 0 0 0 0 O* 0 Supervisory 0 0 0 0 0 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 19 0 8 5322 21 3019 Operating 0 0 0 265 0 0 Health Physics 1 0 2 685 2 679 Chemistry 0 0 0 9 0 0 I Supervisory 0 0 0 2 44 10 Engineering 0 0 0 99 15 0 I&C 0 0 0 71 0 24 Security 0 0 0 0 0 16 | 11001 I/ 1 | ||
--* 1 | |||
Document Control Desk 2 FEB 2 8 1991 NLR-N91036 Should you have any questions or comments regarding this submittal, please contact us. | |||
(>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) | sincerely, Enclosures C Mr. J. c. Stone Licensing Project Manager - Salem Mr. Stephen Dembek Project Manager - Hope Creek Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 | ||
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS &01HERS & 01HERS Waste Processing Maintenance 0 0 0 13 0 28 Operating 0 0 0 0 0 0 Health Physics 1 0 0 404 0 72 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 35 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 fueling Maintenance 15 0 6 6258 35 5212 Operating 0 0 0 358 0 0 Health Physics 4 0 0 1183 0 348 Chemistry 0 0 0 7 0 0 Supervisory 0 0 0 30 29 2 Engineering 1 0 0 329 71 86 l&C 0 0 0 9 0 254 Security 0 0 0 0 0 6 Total Maintenance 40 0 19 16187 102 11989 Operating 1 0 0 3747 0 79 Health Physics 13 0 5 5056 37 2766 Chemistry 0 0 0 85 0 1 Supervisory 0 0 0 37 234 18 Engineering 2 0 0 814 97 86 l&C 0 0 0 113 0 399 Security 0 0 0 10 0 79 Grand Total: 56 0 24 26049 470 15417 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-272 Licensee: | |||
Public Service Electric and Gas Company DATE: 01/26/91 tal exposure for Salem Unit 1 by TLD during 1990 -42.20 person-rem | *1 | ||
*- ~ '. r if l i | |||
(>100 MREM) TOTAL MAN-MREM WORKANDJOBFUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) | PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 1OF2 SALEM UNIT 1 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | ||
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS & OTHERS &OTHERS i Reactor Operations and Surveillance Maintenance 0 0 0 .29 2 30 Operating 0 0 0 128 0 29 Health Physics 0 0 0 231 0 54 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 1 0 Engineering 0 0 0 6 0 0 I&C 0 0 0 1 0 0 Security 0 0 0 0 0 0 tine Maintenance Maintenance 0 0 3 1976 53 2794 Operating 0 0 0 1356 0 18 Health Physics 4 0 1 1732 35 920 Chemistry 0 0 0 57 0 1 Supervisory 0 0 0 4 122 2 Engineering 0 0 0 185 3 0 I&C 0 0 0 23 0 110 Security 0 0 0 10 0 57 Inservice Inspection Maintenance 0 0 0 79 0 248 Operating 0 0 0 0 0 0 Health Physics 0 0 0 8 0 32 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 0 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 0 0 25 2068 9 10082 Operating 0 0 0 123 0 0 Health Physics 0 0 0 579 2 193 Chemistry 0 0 0 72 0 0 Supervisory 0 0 0 0 78 11 Engineering 0 0 0 142 19 5 I&C 0 0 0 20 0 45 Security 0 0 0 0 0 3 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 SALEM UNIT2 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | (>100 MREM) TOTAL MAN-MREM WORK.AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS | ||
(>100 MREM) TOTAL MAN-MREM WORKANDJOBFUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) | & OTHERS &01HERS Reactor Operations and Surveillance Maintenance 0 0 1 196 0 481 Operating 1 0 0 1674 0 55 Health Physics 1 0 2 838 0 745 Chemistry 0 0 0 7 0 0 Supervisory 0 0 0 0 0 5 Engineering 0 0 0 30 5 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 tine Maintenance Maintenance 6 0 4 4398 46 3240 Operating 0 0 0 1448 0 24 Health Physics 6 0 1 1939 35 922 Chemistry 0 0 0 62 0 1 Supervisory 0 0 0 5 126 1 Engineering 1 0 0 356 6 0 l&C 0 0 0 33 0 121 Security 0 0 0 10 0 57 Inservice Inspection Maintenance 0 0 0 0 0 9 Operating 0 0 0 2 0 0 Health Physics 0 0 0 7 0 0 Chemistry 0 0 0 0 O* 0 Supervisory 0 0 0 0 0 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 19 0 8 5322 21 3019 Operating 0 0 0 265 0 0 Health Physics 1 0 2 685 2 679 Chemistry 0 0 0 9 ~ 0 0 I | ||
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS & OTIIERS & OTIIERS Waste Processing Maintenance 0 0 1 13 0 182 Operating 0 0 0 0 0 0 Health Physics 5 0 1 1450 0 201 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 35 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 .fueling Maintenance 73 1 227 30029 454 139092 Operating 5 0 0 2812 0 32 Health Physics 21 1 42 6790 277 20067 Chemistry 0 0 0 51 0 0 Supervisory 0 0 0 54 147 59 Engineering 2 0 0 986 123 183 I&C 0 0 2 178 0 819 Security 0 0 0 2 0 141 Total Maintenance 73 1 256 34194 518 152428 Operating 5 0 0 4419 0 79 Health Physics 30 1 44 10790 314 21467 Chemistry 0 0 0 180 0 1 Supervisory 0 0 0 58 383 72 Engineering 2 0 0 1319 145 188 I&C 0 0 2 222 0 974 Security 0 0 0 12 0 201 Grand Total: 110 2 302 51194 1360 175410 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-311 Licensee: | Supervisory 0 0 0 2 44 10 Engineering 0 0 0 99 15 0 I&C 0 0 0 71 0 24 Security 0 0 0 0 0 16 | ||
Public Service Electric and Gas Company DATE: 01/26/91 . | |||
(>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) | --* 1 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 SALEM UNIT 1 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | ||
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS &OTHERS &OTHERS Reactor Operations and Surveillance Maintenance 4 0 9 2751 249 3505 Operating 34 1 0 9145 289 23 Health Physics 19 1 6 4170 282 2162 Chemistry 6 1 0 1664 240 0 Supervisory 0 0 0 35 11 22 Engineering 2 0 0 657 77 5 l&C 1 0 0 585 0 2 Security 0 0 0 3 0 122 utine Maintenance Maintenance 0 0 0 561 43 1448 Operating 1 0 0 292 0 0 Health Physics 12 1 0 3185 177 563 Chemistry 2 0 0 593 74 0 Supervisory 0 0 0 0 0 58 Engineering 0 0 0 96 23 31 l&C 0 0 0 1417 0 0 Security 0 0 0 5 0 37 Inservice Inspection Maintenance 0 0 1 52 5 227 Operating 0 0 0 1 0 0 Health Physics 0 0 0 82 0 0 Chemistry 0 0 0 3 0 0 Supervisory 0 0 0 4 0 0 Engineering 0 0 0 60 19 0 l&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 59 2 132 26220 580 48710 Operating 3 0 0 1908 8 15 Health Physics 34 0 9 14930 7 3158 Chemistry 0 0 0 90 19 0 Supervisory 1 1 1 424 167 703 Engineering 3 3 2 1117 4020 399 l&C 35 0 0 9563 0 95 Security 0 0 1 0 0 208 | (>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS | ||
&01HERS & 01HERS Waste Processing Maintenance 0 0 0 13 0 28 Operating 0 0 0 0 0 0 Health Physics 1 0 0 404 0 72 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 35 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 fueling Maintenance 15 0 6 6258 35 5212 Operating 0 0 0 358 0 0 Health Physics 4 0 0 1183 0 348 Chemistry 0 0 0 7 0 0 Supervisory 0 0 0 30 29 2 Engineering 1 0 0 329 71 86 l&C 0 0 0 9 0 254 Security 0 0 0 0 0 6 Total Maintenance 40 0 19 16187 102 11989 Operating 1 0 0 3747 0 79 Health Physics 13 0 5 5056 37 2766 Chemistry 0 0 0 85 0 1 Supervisory 0 0 0 37 234 18 Engineering 2 0 0 814 97 86 l&C 0 0 0 113 0 399 Security 0 0 0 10 0 79 Grand Total: 56 0 24 26049 470 15417 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-272 Licensee: Public Service Electric and Gas Company DATE: 01/26/91 tal exposure for Salem Unit 1 by TLD during 1990 - 42.20 person-rem | |||
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 1OF2 SALEM UNIT2 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | |||
Public Service Electric and Gas Company DATE: 01/26/91 tal Exposure for Hope Creek by TLD during 1990 -195.97 person-rem | (>100 MREM) TOTAL MAN-MREM WORKANDJOBFUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS | ||
Stress relief heat treatment was performed on the Row 2 U-Bend regions of all four steam generators. | & OTHERS &OTHERS i Reactor Operations and Surveillance Maintenance 0 0 0 .29 2 30 Operating 0 0 0 128 0 29 Health Physics 0 0 0 231 0 54 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 1 0 Engineering 0 0 0 6 0 0 I&C 0 0 0 1 0 0 Security 0 0 0 0 0 0 tine Maintenance Maintenance 0 0 3 1976 53 2794 Operating 0 0 0 1356 0 18 Health Physics 4 0 1 1732 35 920 Chemistry 0 0 0 57 0 1 Supervisory 0 0 0 4 122 2 Engineering 0 0 0 185 3 0 I&C 0 0 0 23 0 110 Security 0 0 0 10 0 57 Inservice Inspection Maintenance 0 0 0 79 0 248 Operating 0 0 0 0 0 0 Health Physics 0 0 0 8 0 32 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 0 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 0 0 25 2068 9 10082 Operating 0 0 0 123 0 0 Health Physics 0 0 0 579 2 193 Chemistry 0 0 0 72 0 0 Supervisory 0 0 0 0 78 11 Engineering 0 0 0 142 19 5 I&C 0 0 0 20 0 45 Security 0 0 0 0 0 3 | ||
A number of tube plugs were replaced with new Inconel 690 plugs or modified with a plug-in-a-plug (PIP) . Details of the above activities, including extent of inspections, test results, tubes plugged, and plugs replaced or modified are described in the following attached data excerpted from the Salem 2 5th Refueling Outage 90 Day Report. | |||
2.0 Technical Specification 4.4.6.0 -Steam Generator Tube Eddy Current Inspection. | PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 SALEM UNIT2 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | ||
2.1 The original eddy current examination scope is detailed below: 2.1.1 Twelve (12%) percent Tech. Spec. examination in #23 Steam Generator. | (>100 MREM) TOTAL MAN-MREM WORKANDJOBFUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS | ||
2.1.2 A non-tech spec. sample of eight hundred and eleven (811) tubes conducted in #23 S/G to try and comply with EPRI's recommended guidelines of conducting 100% examination of all the steam generator tubes over a period of six (6) years. This sample represented an additional 25% of this generator. | & OTIIERS & OTIIERS Waste Processing Maintenance 0 0 1 13 0 182 Operating 0 0 0 0 0 0 Health Physics 5 0 1 1450 0 201 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 35 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 | ||
2.1.3 Examine all .previous indications in the remaining steam generators | .fueling Maintenance 73 1 227 30029 454 139092 Operating 5 0 0 2812 0 32 Health Physics 21 1 42 6790 277 20067 Chemistry 0 0 0 51 0 0 Supervisory 0 0 0 54 147 59 Engineering 2 0 0 986 123 183 I&C 0 0 2 178 0 819 Security 0 0 0 2 0 141 Total Maintenance 73 1 256 34194 518 152428 Operating 5 0 0 4419 0 79 Health Physics 30 1 44 10790 314 21467 Chemistry 0 0 0 180 0 1 Supervisory 0 0 0 58 383 72 Engineering 2 0 0 1319 145 188 I&C 0 0 2 222 0 974 Security 0 0 0 12 0 201 Grand Total: 110 2 302 51194 1360 175410 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-311 Licensee: Public Service Electric and Gas Company DATE: 01/26/91 | ||
(#'s 21, 22 and 24) . . 2.1.4 Perform a 10%. sample (330 tubes) of the sheet region of #24 Steam Generator using a motorized rotating pancake probe to look for industry concerns from tube expansion by the WESTEX method. This sample was concentrated in the kidney region because of the high ty of indications due to sludge buildup. / 2.1.5 Examine five (5) tubes with previous indications in the hot leg support plate region using both a bobbin and motorized pancake probe. This was performed to address an industry concern with through wall cracking occurring at the support plate that may not be identified with the bobbin probe inspection. | . t a l exposure for Salem Unit 2 by TLD during 1990 - 229.40 person-rem | ||
Page 7 of 18 | |||
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 1OF2 HOPE CREEK DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | |||
(>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS | |||
2.2 Tech. Spec. | &OTHERS &OTHERS Reactor Operations and Surveillance Maintenance 4 0 9 2751 249 3505 Operating 34 1 0 9145 289 23 Health Physics 19 1 6 4170 282 2162 Chemistry 6 1 0 1664 240 0 Supervisory 0 0 0 35 11 22 Engineering 2 0 0 657 77 5 l&C 1 0 0 585 0 2 Security 0 0 0 3 0 122 utine Maintenance Maintenance 0 0 0 561 43 1448 Operating 1 0 0 292 0 0 Health Physics 12 1 0 3185 177 563 Chemistry 2 0 0 593 74 0 Supervisory 0 0 0 0 0 58 Engineering 0 0 0 96 23 31 l&C 0 0 0 1417 0 0 Security 0 0 0 5 0 37 Inservice Inspection Maintenance 0 0 1 52 5 227 Operating 0 0 0 1 0 0 Health Physics 0 0 0 82 0 0 Chemistry 0 0 0 3 0 0 Supervisory 0 0 0 4 0 0 Engineering 0 0 0 60 19 0 l&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 59 2 132 26220 580 48710 Operating 3 0 0 1908 8 15 Health Physics 34 0 9 14930 7 3158 Chemistry 0 0 0 90 19 0 Supervisory 1 1 1 424 167 703 Engineering 3 3 2 1117 4020 399 l&C 35 0 0 9563 0 95 Security 0 0 1 0 0 208 | ||
in No. 23 Steam Generator revealed no pluggable indications. | |||
In the .non-tech. | PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 HOPE CREEK DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL | ||
spec. sample there were tubes with indications of cold leg thinning and/or anti-vibration bar wear which exceeded the Tech Spec. plugging limit. Based on these examination results and Jn complying with EPRI lines of examining the area's of concern, the tion plan was expanded to include 100% of all the tubes in #23 Steam Generator between Rows 20 and 46. This expansion program showed more evidence of cold leg thinning and/or AVB wear therefore additional tions were performed to include all the tubes down through row 6 to ensure the indications were only occurring in the higher row tubes. Examinations of the lower row tubes showed no evidence of these tions. The examinations were also expanded into #21 S/G to include all the tubes between Rows 30 and 46 and the tubes between Columns 30 through 70 on Rows 28 and 29. The same type of indications were also being found in the higher row tubes of #21 S/G, so the decision was made' to examine all the tubes in #22 S/G between Rows 28 through 46 (except for the periphery tubes which were inspected during the previous outage) and in #24 S/G all the tubes between rows 28 through 46 and the periphery tubes, three columns deep, between rows 6 through 19. The examinations in #22 and #24 Steam Generators showed that this same condition was also occurring in the higher row tubes. All tubes exceeding the tech. spec. limit of > 40% degradation of nominal tube thickness were mechanically plugged with verification.performed by PSE&G personnel. | (>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS | ||
& OTIIERS & OTIIERS Waste Processing Maintenance 3 0 7 1718 31 3512 Operating 5 0 0 1560 0 0 Health Phsics 21 0 0 9406 8 200 Chemistry 0 0 0 33 1 0 Supervisory 0 0 0 134 2 59 Engineering 0 0 0 360 0 0 l&C 0 0 0 38 0 0 Security 0 0 0 2 0 5 fueling Maintenance 4 0 52 2516 144 20584 Operating 2 0 0 816 47 0 Health Physics 6 0 11 1572 0 2483 Chemistry 0 0 0 0 0 0 Supervisory 0 0 1 12 4 131 Engineering 0 0 0 136 29 0 I&C 4 0 0 1582 0 3 Security 0 0 1 3 0 209 Total Maintenance 70 2 201 33818 1052 77986 Operating 45 1 0 13722 344 38 Health Physics 92 2 26 33345 474 8566 Chemistry 8 1 0 2383 334 0 Supervisory 1 1 2 609 184 973 Engineering 5 3 2 2426 4168 435 l&C 40 0 0 13185 0 100 Security 0 0 2 13 0 581 Grand Total: 261 10 233 99501 6556 88679 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-354 Licensee: Public Service Electric and Gas Company DATE: 01/26/91 tal Exposure for Hope Creek by TLD during 1990 - 195.97 person-rem | |||
ISI SUBMITTAL TO SALEM UNIT 2 ANNUAL OPERATING REPORT FOR 1990 STEAM GENERATOR TUBE INSERVICE INSPECTION Eddy current inspection was performed by Westinghouse Nuclear Service Division on all four steam generators at Salem Unit 2 during April of 1990. Inspections were performed with standard Westinghouse/Zetec equipment, including the SM10W No Entry Fixture, the MIZ-18A digital multifrequency eddy current system, using .720, .700 and .680 dia. bobbin coil probes. In addition, a special sample was selected from #24 S.G. for inspection with motorized rotating pancake coil probes in the tube sheet region and tube support plate interfaces. Stress relief heat treatment was performed on the Row 2 U-Bend regions of all four steam generators. A number of tube plugs were replaced with new Inconel 690 plugs or modified with a plug-in-a-plug (PIP) . | |||
Details of the above activities, including extent of inspections, test results, tubes plugged, and plugs replaced or modified are described in the following attached data excerpted from the Salem 2 5th Refueling Outage 90 Day Report. | |||
2.0 Technical Specification 4.4.6.0 - Steam Generator Tube Eddy Current Inspection. | |||
2.1 The original eddy current examination scope is detailed below: | |||
2.1.1 Twelve (12%) percent Tech. Spec. examination in #23 Steam Generator. | |||
2.1.2 A non-tech spec. sample of eight hundred and eleven (811) tubes conducted in #23 S/G to try and comply with EPRI's recommended guidelines of conducting 100% examination of all the steam generator tubes over a period of six (6) years. This sample represented an additional 25% of this generator. | |||
2.1.3 Examine all .previous indications in the remaining steam generators (#'s 21, 22 and | |||
: 24) . . | |||
2.1.4 Perform a 10%. sample (330 tubes) of the tube-sheet region of #24 Steam Generator using a motorized rotating pancake probe to look for industry concerns from tube expansion by the WESTEX method. This sample was concentrated in the kidney region because of the high probabili-ty of indications due to sludge buildup. | |||
/ | |||
2.1.5 Examine five (5) tubes with previous indications in the hot leg support plate region using both a bobbin and motorized pancake probe. This was performed to address an industry concern with through wall cracking occurring at the support plate that may not be identified with the bobbin probe inspection. | |||
Page 7 of 18 | |||
2.2 Tech. Spec. ~xaminations in No. 23 Steam Generator revealed no pluggable indications. In the .non-tech. | |||
spec. sample there were tubes with indications of cold leg thinning and/or anti-vibration bar wear which exceeded the Tech Spec. plugging limit. Based on these examination results and Jn complying with EPRI guide-lines of examining the area's of concern, the inspec-tion plan was expanded to include 100% of all the tubes in #23 Steam Generator between Rows 20 and 46. This expansion program showed more evidence of cold leg thinning and/or AVB wear therefore additional examina-tions were performed to include all the tubes down through row 6 to ensure the indications were only occurring in the higher row tubes. Examinations of the lower row tubes showed no evidence of these indica-tions. The examinations were also expanded into #21 S/G to include all the tubes between Rows 30 and 46 and the tubes between Columns 30 through 70 on Rows 28 and | |||
: 29. The same type of indications were also being found in the higher row tubes of #21 S/G, so the decision was made' to examine all the tubes in #22 S/G between Rows 28 through 46 (except for the periphery tubes which were inspected during the previous outage) and in #24 S/G all the tubes between rows 28 through 46 and the periphery tubes, three columns deep, between rows 6 through 19. The examinations in #22 and #24 Steam Generators showed that this same condition was also occurring in the higher row tubes. | |||
All tubes exceeding the tech. spec. limit of > 40% | |||
degradation of nominal tube thickness were mechanically plugged with verification.performed by PSE&G personnel. | |||
Page 8 of 18 | Page 8 of 18 | ||
2.3 In addition to the eddy current inspections, the Row 2 tubes in all four (4) steam Generators were U-bend heat treated. Eddy current was performed in the*u-bend region to verify the proper heat affected zone had been achieved. ~ | |||
23 Full Length U-Bend Verify | NOTE: All the row one (1) tubes in all four (4) Steam Generators are currently plugged. | ||
------------ | 2.4 Results of the examinations are as follows: | ||
Steam Extent of No. of Tubes Tubes with Indications (3) | |||
Total 6491 86 84 40 | Generator Exam. Inspected < 20% 20-39% > 40% | ||
21 Full Length 940 20 19 6. | |||
U-Bend Verify 95 ( *) N/A N/A N/A 2.2 Full Length 896 6 10 3 U-Bend Verify 94 N/A N/A N/A 23 Full Length 2801 46 40 11 U-Bend Verify 94 N/A N/A N/A 24 | |||
-------------~- | |||
Full Length 1142 14 15 20 U-Bend Verify 94 N/A N/A N/A Tube sheet 330 0 0 0 Support Plate 5 0 0 0 | |||
----------------------------~------------------------------------------- | |||
Sub-Total Full Length 5779 86 84 40 U-Bend Verify 377 N/A N/A N/A Tubesheet 330 0 . 0 0 Support Plate 5 0 0 0 Total 6491 86 84 40 | |||
* One tube in Row 3 was heat treated inadvertently. | * One tube in Row 3 was heat treated inadvertently. | ||
Page 9 of 18 | Page 9 of 18 | ||
2.5 Some of the other S/G work for this outage included installing a plug-in-plug {PIP) fix for the Inconel 600 plug material which was identified as having a bad heat number. This fix was applied to all the Row 1 hot leg plugs between columns 6 and 90 in all four (4) steam generators, except for eight (8) tubes previously iden-tified as leaking or having a high potential to leak in | |||
#24 S/G. These plugs were manually pulled and a new Inconel 690 plug installed. Some of the Row 1 tubes were unable to have a PIP installed so the existing plugs were removed and replaced with new Inconel 690 plugs. | |||
2.6 Current Status of the steam Generators At this time the total number of tubes plugged in the Salem Unit 2 Steam Generators are as follows: | |||
Generator # 21 22 23 24 Tubes Plugged 102 100 111 111 NOTE: In the Steam Generator's 21-24, the first five (5) and the last Five (5) tubes in row 1 were mechanically plugged because of a generic wearing problem on the tubes, due to the vibration of the tube lane blocking device. The remaining tubes in Row 1 were plugged because there was evidence in two (2) of the steam generators of the onset of stress corrosion cracking in the u-bend area. | |||
Page 10 of 18 | |||
21 STEAM GENERATOR LOCATION AND PERCENTAGE OF WALL THICKNESS | |||
iINDICAHON LISTING - CUMUL - E:OTH LEGS SaHH Unit 1 PNJ -21151 13-Ma~-90 14!50 | |||
-----+----t----+----+----+------+-----+---t----+-----t-----+----+------t---*----t------------- ------------------------------------t | |||
, MTE ROU COL CE-~ CE-E PROE:E T'i'PE IHD LOCH DlCHl IHCH2 CHAN VOLTS DEG TAPEI COMENTS I | |||
+--------t----+----+----+----t------t-----+---+----+-----+----~----+------+---t----+--------------------------------------------------t I I I | |||
!=========================================================================:============================================================! | |||
I I I I 34 17 TLC TEH 720 EE rnR 7H 28 |
Latest revision as of 15:35, 17 March 2020
ML18095A775 | |
Person / Time | |
---|---|
Site: | Salem, Hope Creek |
Issue date: | 12/31/1990 |
From: | Labruna S Public Service Enterprise Group |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NLR-N91036, NUDOCS 9103080087 | |
Download: ML18095A775 (48) | |
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 Operations FEB 2 8 1991_
NLR-N91036 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, Salem 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 10 CFR 20, Section 20.407.
Pursuant to Technical Specification 6.9.1.5.b, Enclosure 4 is submitted for Salem Unit 2. Enclosure 4 documents the results of steam generator tube inservice inspections performed during the 5th Refueling Outage of Salem Unit 1 in May 1990. Salem Unit 1 did not have any steam generator tube inspections in 1990.
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 Appendix A to Faciiity Operating** License No. NPF-57 is being transmitted separately.
11001 I/ 1
Document Control Desk 2 FEB 2 8 1991 NLR-N91036 Should you have any questions or comments regarding this submittal, please contact us.
sincerely, Enclosures C Mr. J. c. Stone Licensing Project Manager - Salem Mr. Stephen Dembek Project Manager - Hope Creek Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
- 1
- - ~ '. r if l i
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 1OF2 SALEM UNIT 1 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL
(>100 MREM) TOTAL MAN-MREM WORK.AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS &01HERS Reactor Operations and Surveillance Maintenance 0 0 1 196 0 481 Operating 1 0 0 1674 0 55 Health Physics 1 0 2 838 0 745 Chemistry 0 0 0 7 0 0 Supervisory 0 0 0 0 0 5 Engineering 0 0 0 30 5 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 tine Maintenance Maintenance 6 0 4 4398 46 3240 Operating 0 0 0 1448 0 24 Health Physics 6 0 1 1939 35 922 Chemistry 0 0 0 62 0 1 Supervisory 0 0 0 5 126 1 Engineering 1 0 0 356 6 0 l&C 0 0 0 33 0 121 Security 0 0 0 10 0 57 Inservice Inspection Maintenance 0 0 0 0 0 9 Operating 0 0 0 2 0 0 Health Physics 0 0 0 7 0 0 Chemistry 0 0 0 0 O* 0 Supervisory 0 0 0 0 0 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 19 0 8 5322 21 3019 Operating 0 0 0 265 0 0 Health Physics 1 0 2 685 2 679 Chemistry 0 0 0 9 ~ 0 0 I
Supervisory 0 0 0 2 44 10 Engineering 0 0 0 99 15 0 I&C 0 0 0 71 0 24 Security 0 0 0 0 0 16
--* 1 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 SALEM UNIT 1 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL
(>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
&01HERS & 01HERS Waste Processing Maintenance 0 0 0 13 0 28 Operating 0 0 0 0 0 0 Health Physics 1 0 0 404 0 72 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 35 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 fueling Maintenance 15 0 6 6258 35 5212 Operating 0 0 0 358 0 0 Health Physics 4 0 0 1183 0 348 Chemistry 0 0 0 7 0 0 Supervisory 0 0 0 30 29 2 Engineering 1 0 0 329 71 86 l&C 0 0 0 9 0 254 Security 0 0 0 0 0 6 Total Maintenance 40 0 19 16187 102 11989 Operating 1 0 0 3747 0 79 Health Physics 13 0 5 5056 37 2766 Chemistry 0 0 0 85 0 1 Supervisory 0 0 0 37 234 18 Engineering 2 0 0 814 97 86 l&C 0 0 0 113 0 399 Security 0 0 0 10 0 79 Grand Total: 56 0 24 26049 470 15417 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-272 Licensee: Public Service Electric and Gas Company DATE: 01/26/91 tal exposure for Salem Unit 1 by TLD during 1990 - 42.20 person-rem
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 1OF2 SALEM UNIT2 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL
(>100 MREM) TOTAL MAN-MREM WORKANDJOBFUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS &OTHERS i Reactor Operations and Surveillance Maintenance 0 0 0 .29 2 30 Operating 0 0 0 128 0 29 Health Physics 0 0 0 231 0 54 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 1 0 Engineering 0 0 0 6 0 0 I&C 0 0 0 1 0 0 Security 0 0 0 0 0 0 tine Maintenance Maintenance 0 0 3 1976 53 2794 Operating 0 0 0 1356 0 18 Health Physics 4 0 1 1732 35 920 Chemistry 0 0 0 57 0 1 Supervisory 0 0 0 4 122 2 Engineering 0 0 0 185 3 0 I&C 0 0 0 23 0 110 Security 0 0 0 10 0 57 Inservice Inspection Maintenance 0 0 0 79 0 248 Operating 0 0 0 0 0 0 Health Physics 0 0 0 8 0 32 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 0 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 0 0 25 2068 9 10082 Operating 0 0 0 123 0 0 Health Physics 0 0 0 579 2 193 Chemistry 0 0 0 72 0 0 Supervisory 0 0 0 0 78 11 Engineering 0 0 0 142 19 5 I&C 0 0 0 20 0 45 Security 0 0 0 0 0 3
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 SALEM UNIT2 DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL
(>100 MREM) TOTAL MAN-MREM WORKANDJOBFUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTIIERS & OTIIERS Waste Processing Maintenance 0 0 1 13 0 182 Operating 0 0 0 0 0 0 Health Physics 5 0 1 1450 0 201 Chemistry 0 0 0 0 0 0 Supervisory 0 0 0 0 35 0 Engineering 0 0 0 0 0 0 I&C 0 0 0 0 0 0 Security 0 0 0 0 0 0
.fueling Maintenance 73 1 227 30029 454 139092 Operating 5 0 0 2812 0 32 Health Physics 21 1 42 6790 277 20067 Chemistry 0 0 0 51 0 0 Supervisory 0 0 0 54 147 59 Engineering 2 0 0 986 123 183 I&C 0 0 2 178 0 819 Security 0 0 0 2 0 141 Total Maintenance 73 1 256 34194 518 152428 Operating 5 0 0 4419 0 79 Health Physics 30 1 44 10790 314 21467 Chemistry 0 0 0 180 0 1 Supervisory 0 0 0 58 383 72 Engineering 2 0 0 1319 145 188 I&C 0 0 2 222 0 974 Security 0 0 0 12 0 201 Grand Total: 110 2 302 51194 1360 175410 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-311 Licensee: Public Service Electric and Gas Company DATE: 01/26/91
. t a l exposure for Salem Unit 2 by TLD during 1990 - 229.40 person-rem
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 1OF2 HOPE CREEK DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL
(>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
&OTHERS &OTHERS Reactor Operations and Surveillance Maintenance 4 0 9 2751 249 3505 Operating 34 1 0 9145 289 23 Health Physics 19 1 6 4170 282 2162 Chemistry 6 1 0 1664 240 0 Supervisory 0 0 0 35 11 22 Engineering 2 0 0 657 77 5 l&C 1 0 0 585 0 2 Security 0 0 0 3 0 122 utine Maintenance Maintenance 0 0 0 561 43 1448 Operating 1 0 0 292 0 0 Health Physics 12 1 0 3185 177 563 Chemistry 2 0 0 593 74 0 Supervisory 0 0 0 0 0 58 Engineering 0 0 0 96 23 31 l&C 0 0 0 1417 0 0 Security 0 0 0 5 0 37 Inservice Inspection Maintenance 0 0 1 52 5 227 Operating 0 0 0 1 0 0 Health Physics 0 0 0 82 0 0 Chemistry 0 0 0 3 0 0 Supervisory 0 0 0 4 0 0 Engineering 0 0 0 60 19 0 l&C 0 0 0 0 0 0 Security 0 0 0 0 0 0 Special Maintenance Maintenance 59 2 132 26220 580 48710 Operating 3 0 0 1908 8 15 Health Physics 34 0 9 14930 7 3158 Chemistry 0 0 0 90 19 0 Supervisory 1 1 1 424 167 703 Engineering 3 3 2 1117 4020 399 l&C 35 0 0 9563 0 95 Security 0 0 1 0 0 208
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08083 PAGE: 2 OF 2 HOPE CREEK DATE: 01/26/91 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 MAN-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/90 TO: 12/31/90 NUMBER OF PERSONNEL
(>100 MREM) TOTAL MAN-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GROUPING) EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTIIERS & OTIIERS Waste Processing Maintenance 3 0 7 1718 31 3512 Operating 5 0 0 1560 0 0 Health Phsics 21 0 0 9406 8 200 Chemistry 0 0 0 33 1 0 Supervisory 0 0 0 134 2 59 Engineering 0 0 0 360 0 0 l&C 0 0 0 38 0 0 Security 0 0 0 2 0 5 fueling Maintenance 4 0 52 2516 144 20584 Operating 2 0 0 816 47 0 Health Physics 6 0 11 1572 0 2483 Chemistry 0 0 0 0 0 0 Supervisory 0 0 1 12 4 131 Engineering 0 0 0 136 29 0 I&C 4 0 0 1582 0 3 Security 0 0 1 3 0 209 Total Maintenance 70 2 201 33818 1052 77986 Operating 45 1 0 13722 344 38 Health Physics 92 2 26 33345 474 8566 Chemistry 8 1 0 2383 334 0 Supervisory 1 1 2 609 184 973 Engineering 5 3 2 2426 4168 435 l&C 40 0 0 13185 0 100 Security 0 0 2 13 0 581 Grand Total: 261 10 233 99501 6556 88679 Personnel Exposure and Monitoring Report for NRC Docket Exposure Year: 1990 Number: 50-354 Licensee: Public Service Electric and Gas Company DATE: 01/26/91 tal Exposure for Hope Creek by TLD during 1990 - 195.97 person-rem
ISI SUBMITTAL TO SALEM UNIT 2 ANNUAL OPERATING REPORT FOR 1990 STEAM GENERATOR TUBE INSERVICE INSPECTION Eddy current inspection was performed by Westinghouse Nuclear Service Division on all four steam generators at Salem Unit 2 during April of 1990. Inspections were performed with standard Westinghouse/Zetec equipment, including the SM10W No Entry Fixture, the MIZ-18A digital multifrequency eddy current system, using .720, .700 and .680 dia. bobbin coil probes. In addition, a special sample was selected from #24 S.G. for inspection with motorized rotating pancake coil probes in the tube sheet region and tube support plate interfaces. Stress relief heat treatment was performed on the Row 2 U-Bend regions of all four steam generators. A number of tube plugs were replaced with new Inconel 690 plugs or modified with a plug-in-a-plug (PIP) .
Details of the above activities, including extent of inspections, test results, tubes plugged, and plugs replaced or modified are described in the following attached data excerpted from the Salem 2 5th Refueling Outage 90 Day Report.
2.0 Technical Specification 4.4.6.0 - Steam Generator Tube Eddy Current Inspection.
2.1 The original eddy current examination scope is detailed below:
2.1.1 Twelve (12%) percent Tech. Spec. examination in #23 Steam Generator.
2.1.2 A non-tech spec. sample of eight hundred and eleven (811) tubes conducted in #23 S/G to try and comply with EPRI's recommended guidelines of conducting 100% examination of all the steam generator tubes over a period of six (6) years. This sample represented an additional 25% of this generator.
2.1.3 Examine all .previous indications in the remaining steam generators (#'s 21, 22 and
- 24) . .
2.1.4 Perform a 10%. sample (330 tubes) of the tube-sheet region of #24 Steam Generator using a motorized rotating pancake probe to look for industry concerns from tube expansion by the WESTEX method. This sample was concentrated in the kidney region because of the high probabili-ty of indications due to sludge buildup.
/
2.1.5 Examine five (5) tubes with previous indications in the hot leg support plate region using both a bobbin and motorized pancake probe. This was performed to address an industry concern with through wall cracking occurring at the support plate that may not be identified with the bobbin probe inspection.
Page 7 of 18
2.2 Tech. Spec. ~xaminations in No. 23 Steam Generator revealed no pluggable indications. In the .non-tech.
spec. sample there were tubes with indications of cold leg thinning and/or anti-vibration bar wear which exceeded the Tech Spec. plugging limit. Based on these examination results and Jn complying with EPRI guide-lines of examining the area's of concern, the inspec-tion plan was expanded to include 100% of all the tubes in #23 Steam Generator between Rows 20 and 46. This expansion program showed more evidence of cold leg thinning and/or AVB wear therefore additional examina-tions were performed to include all the tubes down through row 6 to ensure the indications were only occurring in the higher row tubes. Examinations of the lower row tubes showed no evidence of these indica-tions. The examinations were also expanded into #21 S/G to include all the tubes between Rows 30 and 46 and the tubes between Columns 30 through 70 on Rows 28 and
- 29. The same type of indications were also being found in the higher row tubes of #21 S/G, so the decision was made' to examine all the tubes in #22 S/G between Rows 28 through 46 (except for the periphery tubes which were inspected during the previous outage) and in #24 S/G all the tubes between rows 28 through 46 and the periphery tubes, three columns deep, between rows 6 through 19. The examinations in #22 and #24 Steam Generators showed that this same condition was also occurring in the higher row tubes.
All tubes exceeding the tech. spec. limit of > 40%
degradation of nominal tube thickness were mechanically plugged with verification.performed by PSE&G personnel.
Page 8 of 18
2.3 In addition to the eddy current inspections, the Row 2 tubes in all four (4) steam Generators were U-bend heat treated. Eddy current was performed in the*u-bend region to verify the proper heat affected zone had been achieved. ~
NOTE: All the row one (1) tubes in all four (4) Steam Generators are currently plugged.
2.4 Results of the examinations are as follows:
Steam Extent of No. of Tubes Tubes with Indications (3)
Generator Exam. Inspected < 20% 20-39% > 40%
21 Full Length 940 20 19 6.
U-Bend Verify 95 ( *) N/A N/A N/A 2.2 Full Length 896 6 10 3 U-Bend Verify 94 N/A N/A N/A 23 Full Length 2801 46 40 11 U-Bend Verify 94 N/A N/A N/A 24
~-
Full Length 1142 14 15 20 U-Bend Verify 94 N/A N/A N/A Tube sheet 330 0 0 0 Support Plate 5 0 0 0
~-------------------------------------------
Sub-Total Full Length 5779 86 84 40 U-Bend Verify 377 N/A N/A N/A Tubesheet 330 0 . 0 0 Support Plate 5 0 0 0 Total 6491 86 84 40
- One tube in Row 3 was heat treated inadvertently.
Page 9 of 18
2.5 Some of the other S/G work for this outage included installing a plug-in-plug {PIP) fix for the Inconel 600 plug material which was identified as having a bad heat number. This fix was applied to all the Row 1 hot leg plugs between columns 6 and 90 in all four (4) steam generators, except for eight (8) tubes previously iden-tified as leaking or having a high potential to leak in
- 24 S/G. These plugs were manually pulled and a new Inconel 690 plug installed. Some of the Row 1 tubes were unable to have a PIP installed so the existing plugs were removed and replaced with new Inconel 690 plugs.
2.6 Current Status of the steam Generators At this time the total number of tubes plugged in the Salem Unit 2 Steam Generators are as follows:
Generator # 21 22 23 24 Tubes Plugged 102 100 111 111 NOTE: In the Steam Generator's 21-24, the first five (5) and the last Five (5) tubes in row 1 were mechanically plugged because of a generic wearing problem on the tubes, due to the vibration of the tube lane blocking device. The remaining tubes in Row 1 were plugged because there was evidence in two (2) of the steam generators of the onset of stress corrosion cracking in the u-bend area.
Page 10 of 18
21 STEAM GENERATOR LOCATION AND PERCENTAGE OF WALL THICKNESS
iINDICAHON LISTING - CUMUL - E:OTH LEGS SaHH Unit 1 PNJ -21151 13-Ma~-90 14!50
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I I I I 37 .37 TEC TEH 720 EE DI 2H ,OO ,OO Ml ,67 5'5 10 !RESULT Of DISCREPANC\' RESOLUTION I I I I
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PAGE 2 TUBES 19
' ,INDICflTfON LISTIH6 - CU~UL - E:OTH LE&S PNJ -21151 IHSPECTIOH: Apr-90 13-H~y-90 14:50
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PAGE 3 TUE:ES
' , HIDICATIOH LISTIH& - CUliUL - f:OTH LE&S Sal.:H Uoit I. PHJ -21151 IHSPECTIOH: Apr-90 13-Ha~-90 14:50
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PAGE 4 TUE:ES 36
' .IHDICATIOH LISTING - CUMUL - ~OTH L£GS SakH Unit 2 PHJ -21151 IHSPECTIOH! Apr-90 13-Ma~-90 14!50
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' .moICA TIOH LISTING - CUMUL - (:OTH LEGS SaltH Unit 2 PHJ -21151 IHSPECTIOH: Apr-90
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22 STEAM GENERATOR LOCATION AND PERCENTAGE OF WALL THICKNESS
IN~ICATIO~ LISTIH6 - P.OTH LE6S CUl\ULATIVE
~"' Unit 2 PHJ -22151 IHSPECTIOH: Apr-90
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PAGE 3 TOTAL TUE:ES 27
23 STEAM GENERATOR LOCATION AND PERCENTAGE OF WALL THICKNESS
- INDICATION LISTING - E:OTH LEGS CUMULATIVE s'al~H Un i't 2
. PNJ -23151 IMSPECTIO~: Apr-90 9-Mi)y-90 17!40
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I 17 18 TEC TEH 720 EE 33 2H .oo .oo 1 ,36 151 46 IRESULT Of DISCREPANCY RESOLUTION 17 1B TEC TEH 720 EE 15 Al'3 ,OO .OO M2 ,40 46 IRESllLT OF DISCREPANCY RESOLUTION 17 lB TEC TEH 720 EE 15 All4 ,OO ,OO N2 .36 46 I Rf SULT Of I) ISCREPANC\' RESOLUTION I
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PAGE 1 TIJE:ES 1"
IHDICATIOH LISTING - E:OTH LEGS CUl'iULATIVE
- Sal~H Unit 2 PHJ -23151 IHSPECTIOH! Apr-90 9-l'iay-90 17!40
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I I I 38 27 TEC TEH 720 EE 31 3H -.06 .oo l'il .25 123 30 !RESULT or DISCREPAHCY RESOLUTIOH I I !
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I I I 26 32 TEC TEH 720 EE [ll 4H .oo .oo l'il .31135 16 !RESULT or DISCREPAHCV RESOLUTIOH I I
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I I 41 32 TEC TEH 720 EE 37 1C .OO .(*0 l'i1 ,37 117 10 l+CUSTOl'irn DECISION TO PLUG 41 32 ----------------------------------------------------------------1-CUSTOl'iER [l(CISION HOT TO RETEST I I
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I I l I 42 33 TEC TEH 720 EE DI 2H .oo .oo l'il .2s 127 30 !RESULT or DISCREPANCY RESOLUTION I I I I
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40 40 TEC TEH 720 EE PID AV3 .oo .oo ti2 9.51 19 I>>>>> POSITIVE I.D, ESTAE:USHEO <<<<<
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INDICATION LISTING - BOTH LEGS CUNULATIVE SahH Uni't 2 ?NJ -23151 INSPECTION: Apr-90
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INDICATION LISTING - [:OTH L£GS cunULATIV£
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IHDICATIOH LISTIHG - COTH LEGS CUMULATIVE Sal~H Un i't 2 PHJ -23151 IHSPECTIOH: Apr-90 9-Ma':l-90 17:40
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PAGE 11 Tllf:ES 1C*2
INDitATION LISTING - E:OTH LEGS CUMULATIVE PHJ -23151 INSPECTION: Apr-90
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- INDICATION LISTING - BOTH LEGS cunULATIVE Sal;?H U,n i 't 2 PHJ -23151
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I I I 25 80 TEC TEH 720 EE 13 AV4 +00 .OO N2 .30 38 !RESULT OF DISCREPANCY RESOLUTION I I
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- INDICATION LISTING - E:OTH LEGS CUNULATIVE SileH Unit 2 PHJ -23t51
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PAGE 1
- IRDICATIOH LISTING - CUNUL - E:OTH LEGS
?HJ -24151 INSPECTION: Apr-90 16-Na~-90 12!17
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I I I 33 31 TEC TEH 720 EE DI 1H ,OO ,OO N1 ,34 122 3 !RESULT OF DISCREPAHCV RESOLUTION I .3.3 .H ?H ?H RPC ER HDD ,OO ,OO 1 12 I I 33 31 6H 6H RPC ER HDD .oo .oo 1 12 I I 33 31 SH SH R:)C ER HDD .oo ,OO 1 12 I I 33 31 4H 4H RPC ER HDD ,OO ,OO 1. 12 I I 33 .31 .3H 3H RPC ER HDD .OO ,OO 1 12 I I 33 31 2H 2H RPC ER HDD .OO .OO 1 12 I I 33 .31 1H 1H RPC ER HDD .OO .OO 1 12 I I SS-Si:-p 33 31 TEC TEH 720 [£: IHR 1H , 00 , 00 Ni 1 I RESULT OF DISCREPAHC\' ~:ESOLUTIOH I 37-Hov 33 31 TEC TEH 720 Ef: Cir 1H ,OO .OO Ni 1.68 145 18 !RESULT or ~ISCl<EPAHCV RESOLUTION I I
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I I I 29 35 TEC TEH 720 EE DI 2H .oo .oo n1 .2.} 106 17 !RESULT or DISCREPAHC\' RESOLUTION I I I
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PAGE 2 TIJE:ES 11
- ~ INDICAJION LISTING - CUMUL - f:OTH LEGS S~li;q; Un H 2 PHJ -24151 16-M~g-90 12:17
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I I I I 33 38 TEC TEH 720 EE 25 AV1 .oo +00 M2 1+65 18 I I I 33 38 TEC TEH 720 EE 4S AV2 .OO ,OO M2 9.21 18 !RETEST FOR POSITIVE I.D, I I 33 38 TEC TEH 720 EE 31 AV3 .OO .OO M2 2.S1 13 I I I 33 38 7C TEH 720 ED PID AV2 .oo .oo 112 8.64 29 !))))) POSITHIE I+D+ ESH1E:LISHED {((({ I I I I
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I I I I 38 52 TEC TEH 720 EE 1S AV4 .OO .C*O M2 .97 22 I I I I I
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I I I 41 53 TEC TEH 720 EE 10 AV1 .OO .OO M2 .46 22 I I 41 53 TEC TEH 720 EE 14 AV3 .oo .OO M2 .69 22 I I 41 53 TEC TEH 720 EE 18 AV4 .OO .OO N2 .95 22 I I I
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I I I I 45 54 TEC TEH 72v EE 16 AVl .OO .OO M2 .85 23 I I 88-S>?p 45 54 TEC TEH 720 EE: HOO , 00 , 00 1 2 I I SB-Sep 45 54 TEC TEH 720 EE: DHT 7H .OO .OO Nl 14.94 180 2 !RESULT OF HOH-RESOLUTION ITEM ADD OR CHANGE I 87-Hov 45 54 TEC TEH 720 EB HDD .OO .oo 1 12 I I 87-Hov 45 54 7H 7H 72C* EE: DHT 7H .OO .OO Ml 7.43 12 ICDS DEilT AHALVSIS I I
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33 56 TEC TEH 720 EE 42 AV3 .oo . .C*O M2 6.12 23 !RETEST FOR POSITIVE r.o.
33 56 TEC TEH 720 EE 14 AV4 .OO .OO M2 .67 23 I 33 56 7C TEH 720 ED PID AV2 .oo .oo M2 6.19 29 f))))) POSITIVE I.D. ESTAf:LISHED <<<<<
33 56 7C TEH 720 ED PID AV3 .oo .oo n2 5.66 29 I))))) POSITIVE I.D. ESHIE:LISHrn { <<((
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I 33 57 TEC TEH 720 EE 16 AV1 .oo +00 M2 ,59 3 !RESULT Of DISCREPflNCV RESOLUTION I I 33 57 TEC TEH 720 EE 15 AU2 .oo .OO N2 .52 3 !RESULT Of DISCREPAHCV RESOLUTION !
I 33 57 TEC TEH 720 EE 26 AV4 .oo .oo n2 1.81 3 I I I 88-Sep 33 57 TEC TEH 720 EE: 27 AV4 .oo .OO M2 1+10 2 I I I 87-No~* .}.3 57 TEC TEH 720 ££: 27 AV4 .OO .oo N3 t.12 125 23 I I I I
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I I I 44 59 TEC TEH 720 EE i3 2C +2i .oo Hi .68 i49 3 !RESULT or DISCREPAHCV RESOLUTION I S~p 44 59 TEC TEH 720 rn 9 2C *00 *00 ni t 60 145 2 I "THIS ANALYSIS rs rnon REVIEU or PRIOR AHAL nrs I
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PAGE 5 TUE:ES 34
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PAGE 6 TUBES 42
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I I I I 33 79 TEC TEH 720 rn DI 3C .oo .oo n1 .51 133 28 !RESULT or DISCREPAHC~' ~'.ESOLUTIOtl I I 87-Hov 33 79 TEC TEH 720 EE: HDD .OO .OO 1 11 I I I I I
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PAGE 7 TOTAL TUE:ES 44