ML18096A551
| ML18096A551 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 12/31/1991 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N92024, NUDOCS 9203100095 | |
| Download: ML18096A551 (13) | |
Text
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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 1992 NLR-N92024 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 10CFR20, Section 20.407.
Pursuant to Technical Specification 6.9.1.5.b, Enclosure 4 is submitted for Salem Unit Nos. 1 and 2.
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 Facility Operating License No. NPF-57 is being transmitted separately.
Should you have any questions or comments regarding this submittal, please contact us.
Enclosures 09001~'
..... tJ 9203100095 911231 kDR ADOCK 05000272 PDR Sincerely,
Document Control Desk NLR-N92024 2
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 -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. s. Dembek, Licensing Project Manager
- u. s. Nuclear Regulatory Commission MS 14 E-21 Washington, DC 20555 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 8 1992
ENCLOSURE 1 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 PAGE: 1OF2 SALEM UNIT 1 DATE: 02/25/92 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 PERSON-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/91 TO: 12/31 /91 NUMBER OF PERSONNEL
(>100 MREM)
TOTAL PERSON-MREM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT (PERSONNEL GR9UPING)
EMPLOYEES EMPLOYEES WORKERS EMPLOYEES EMPLOYEES WORKERS
& OTHERS
& OTHERS Reactor Operations and Surveillance Maintenance 6
0 5
3555 3
3115 Operating 0
0 0
74 0
9 Health Physics 5
0 0
1913 0
232 Chemistry 0
0 0
0 0
0 Supervisory 0
1 0
0 194 9
Engineering 0
0 0
268 39 24 l&C 1
0 0
732 0
206 Security 0
0 0.
1 0
0 Routine Maintenance Maintenance 7
1 30 3246 198 12141 Operating 12 0
5 3388 0
1147 Health Physics 33 0
25 11990 55 9073 Chemistry 0
0 0
386 6
7 Supervisory 0
1 0
28 209 14 Engineering 2
0 0
897 164 45 l&C 0
0 0
65 0
236 Security 0
0 0
2 0
224 lnservice Inspection Maintenance 0
0 46 93 9
14910 Operating 0
0 0
2 0
0 Health Physics 0
0 0
57 0
82 Chemistry 0
0
.o 0
0 0
Supervisory 0
0 0
0 3
0 Engineering 0
0 0
15 1
25 l&C 0
0 0
0 0
0 Security 0
0 0
0 0
0 Special Maintenance Maintenance 0
0 0
391 13 353 Operating 0
0 0
49 0
6 Health Physics 0
0 0
173 0
50 Chemistry 0
0 0
2 0
0 Supervisory 0
0 0
19 15 2
Engineering 0
0 0
72 5
0 l&C 0
0 0
32 0
0 Security 0
0 0
3 0
165
ENCLOSURE 1 (CONT'D)
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 SALEM UNIT 1 STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND PERSON-REM WORK AND JOB FUNCTION NUMBER OF PERSONNEL
(>100 MREM)
WORK AND JOB FUNCTION STATION UTILITY CONTRACT (PERSONNEL GROUPING)
EMPLOYEES EMPLOYEES WORKERS
& OTHERS Waste Processing Maintenance 0
0 0
Operating 0
0 0
Health Physics 0
0 0
Chemistry 0
0 0
Supervisory 0
0 0
Engineering 0
0 0
l&C 0
0 0
Security 0
0 0
Refueling Maintenance 63 2
333 Operating 7
0 0
Health Physics 12 0
26 Chemistry 0
0 0
Supervisory 1
3 0
Engineering 6
0 0
l&C 0
0 8
Security 0
0 0
Total Maintenance 76 3
414 Operating 19 0
5 Health Physics 50 0
51 Chemistry 0
0 0
Supervisory 1
5 0
Engineering 8
0 0
l&C 1
0 8
Security 0
0 0
Grand Total:
155 8
478 Personnel Exposure and Monitoring Report for NRC Docket Number: 50-272 Exposure year: 1991 Licensee: Public Service Electric and Gas Company Date: 02/25/92 Total Exposure for Salem Unit 1 by TLD during 1991 was 337.759 person-rem.
PAGE: 2 OF 2 DATE: 02/25/92 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01/01/91 TO: 12/31/91 TOTAL PERSON-MREM STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS
& OTHERS 45 0
40 0
0 0
399 0
92 0
0 0
1 6
0 3
0 0
0 0
0 0
0 12 20962 360 214685 1603 0
12 6749 0
15751 118 2
2 121 1325 272
. 1847 304 249 410 0
1593 9
0 369 28292 583 245244 5116 0
1174 21281 55 25280 506 8
9 169 1752 297 3102 513 343 1239 0
2035 15 0
746 59720 2911 275128
ENCLOSURE 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 PAGE: 1OF2 SALEM UNIT 2 DATE: 02/25/92 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 PERSON-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/91 TO: 12/31/91 NUMBER OF PERSONNEL
(> 100 MREM)
TOTAL PERSON-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 5
0 0
2042 2
762 Operating 0
0 0
194 0
60 Health Physics 1
0 0
1050 0
79 Chemistry 0
0 0
0 0
0 Supervisory 0
0 0
0 27 18 Engineering 0
0 0
147 22 15 l&C 0
0 0
2 0
189 Security 0
0 0
0 0
0 Routine Maintenance Maintenance 0
0 6
2954 138 4937 Operating 0
0 1
1415 0
585 Health Physics 14 0
5 3821 55 2515 Chemistry 0
0 0
355 4
7 Supervisory 0
0 0
19 103 17 Engineering 0
0 0
566 21 83 l&C 0
0 0
70 1
191 Security 0
0 0
2 0
224 lnservice Inspection Maintenance 0
0 42 334 0
24615 Operating 1
0 0
159 0
1 Health Physics 3
0 12 866 0
3704 Chemistry 0
0 0
4 0
0 Supervisory 0
0 0
0 1
0 Engineering 2
0 0
275 0
0 l&C 0
0 0
0 0
0 Security 0
0 0
0 0
0 Special Maintenance Maintenance 4
0 1
1489 44 807 Operating 0
0 0
22 0
6 Health Physics 1
0 0
440 0
64 Chemistry 0
0 0
6 0
0 Supervisory 0
0 0
19 37 2
Engineering 0
0 0
75 45 0
l&C 0
0 0
32 0
37 Security 0
0 0
3 0
165
ENCLOSURE 2 (CONT'D)
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 SALEM UNIT 2 STANDARD FORMAT FOR REPORTING.
NUMBER OF PERSONNEL AND PERSON-REM WORK AND JOB FUNCTION NUMBER OF PERSONNEL
(> 100 MREM)
WORK AND JOB FUNCTION STATION UTILITY CONTRACT
{PERSONNEL GROUPING)
EMPLOYEES EMPLOYEES WORKERS
& OTHERS Waste Maintenance 0
0 0
Operating 0
0 0
Health Physics 0
0 0
Chemistry 0
0 0
Supervisory 0
0 0
Engineering 0
0 0
l&C 0
0 0
Security 0
0 0
Refueling Maintenance 18 0
130 Operating 0
0 0
Health Physics 11 0
14 Chemistry 0
0 0
Supervisory 0
1 0
Engineering 1
0 1
l&C 0
0 5
Security o'
0 0
Total Maintenance 27 0
179 Operating 1
0 1
Health Physics 30 0
31 Chemistry 0
0 0
Supervisory 0
1
- O Engineering 3
0 1
l&C 0
0 5
Security 0
0 0
Grand Total 61 217 Personnel Exposure and Monitoring Report for NRC Docket Number: 50-311 Exposure Year: 1991 Licensee: Public Service Electric and Gas Company Date: 02/25/92 Total exposure for Salem Unit 2 by TLD during 1991 was 120.468 person-rem.
PAGE: 2 OF 2 DATE: 02/25/92 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01 /01 /91 TO: 12/31/91 TOTAL PERSON-MREM STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS
& OTHERS 40 0
0 0
0 0
266 0
29 0
0 0
1 6
0 3
0 0
0 0
0 0
0 0
6649 142 46482 998 0
124 3100 0
3821 15 0
0 94 362 89 732 65 141 94 0
1094 4
0 173 13508 326 77603 2788 0
776 9543 55 10212 380 4
7 133 536 126 1798 153 239 198 1
1511 9
0 562 28357 1075 91036
ENCLOSURE 3 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HANCOCK'S BRIDGE, NJ 08038 PAGE: 1OF2 HOPE CREEK DATE: 02/25/92 STANDARD FORMAT FOR REPORTING REGULATORY GUIDE NUMBER OF PERSONNEL AND 1.16 PERSON-REM WORK AND JOB FUNCTION REPORT PERIOD FROM: 01/01/91 TO: 12/31/91 NUMBER OF PERSONNEL
(> 100 MREM)
TOTAL PERSON-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 5
1 4
2270 180 1774 Operating 7
0 2
2020 47 459 Health Physics 1
1 1
1521 293 651 Chemistry 5
1 0
1136 217 0
Supervisory 0
0 0
30 3
26 Engineering 1
0 0
446 21 9
l&C 0
0 0
18 0
2 Security 0
0 0
5 0
325 Routine Maintenance Maintenance 0
0 6
272 1
2933 Operating 0
0 0
34 0
0 Health Physics 0
0 0
0 0
84 Chemistry 0
0 0
0 0
0 Supervisory 0
0 0
0 2
0 Engineering 0
0 0
61 34 49 l&C 0
0 0
1271 0
3 Security 0
0 0
10 0
0 lnservice Inspection Maintenance 1
0 136 335 0
63532 Operating 0
0 0
0 0
0 Health Physics 0
0 0
47 0
116 Chemistry 1
0 0
284 0
0 Supervisory 0
0 0
49 135 0
Engineering 1
1 0
327 749 28 l&C 0
0 2
0 0
659 Security 0
0 0
0 0
68 Special Maintenance Maintenance 53 2
56 18780 418 21049 Operating
. 41 1
7 12969 208 2840 Health Physics 35 1
19 16731 191 6521 Chemistry 3
0 661 134 0
Supervisory 0
0 1
179 65 229 Engineering 4
5 2
1683 791 421 l&C 32 0
0 9615 0
35 Security 0
0 1
14 0
592
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 WORK AND JOB FUNCTION NUMBER OF PERSONNEL
(>100 MREM)
WORK AND JOB FUNCTION STATION UTILITY CONTRACT (PERSONNEL GROUPING)
EMPLOYEES EMPLOYEES WORKERS
& OTHERS Waste Processing Maintenance 1
0 3
Operating 0
0 0
Health Physics 8
0 1
Chemistry 0
0 0
Supervisory 0
0 0
Engineering 0
0 0
l&C 1
0 0
Security 0
0 0
Refueling Maintenance 58 2
312 Operating 21 1
7 Health Physics 20 0
48 Chemistry 1
0 0
Supervisory 0
1 2
Engineering 2
1 2
l&C 31 0
0 Security 0
0 0
Total Maintenance 118 5
517 Operating 69 2
16 Health Physics 64 2
69 Chemistry 10 2
0 Supervisory 0
1 3
Engineering 8
7 4
l&C 64 0
2 Security 0
0 Grand Total:
333 19 612 Personnel Exposure and Monitoring Report for NRC Docket Number: 50-354 Exposure Year: 1991 Licensee: Public Service Electric and Gas Company Date: 02/25/92 Total exposure for Hope Creek by TLD during 1991 was 372.963 person-rem.
PAGE: 2 OF 2 DATE: 02/25/92 REGULATORY GUIDE 1.16 REPORT PERIOD FROM: 01/01/91 TO: 12/31/91 TOTAL PERSON-MREM STATION UTILITY CONTRACT EMPLOYEES EMPLOYEES WORKERS
& OTHERS 344 0
2652 139 0
24 3916 4
162 1
0 0
4 0
0 240 0
0 158 0
0 0
0 7
20234 355 125390 5393 205 1993 7947 0
13952 319 8
0 260 283 396 849 217 1760 8941 0
60 146 0
92 42235 954 217330 20555 460 5316 30162 488 21486 2401 359 0
522 488 651 3606 1812 2267 20003 0
759 175 0
934 119659 4561 248743
~*
SALEM UNIT 1 STEAM GENERATORS During Salem Unit 1 9th refueling outage examinations on number 11, 12, 13 and 14 Steam Generators were performed by the Westing-house (NSD), coordinated by the ISI Group.
The Eddy current examination scope is detailed below:
A.
One hundred (100) percent of the tubes in each steam Generator were examined.
Three (3) percent of the tubes (103) in 11, 12, 13 and 14 Steam Generators were selected to satisfy Technical Specification requirements.
The remaining ninety-seven (97) percent of tubes in 11, 12, 13 and 14 Steam Generators were done in addition to the required Tech. Spec. exam.
B.
Twenty (20) percent of the tubes in number 11, 12, 13 and 14 steam Generators were examined using a rotating pan-cake coil (RPC) due to industry concerns from tube expan-sion by the WEXTEX method.
This sample was concentrated in the kidney region because of the high probability of indications due to sludge buildup.
- c.
Eddy current Exams
(% of Tubes) llSG 12SG 13SG 14SG Full length Bobbin Coil(l) 100%
100%
100%
100%
Rotating Pan-cake Coil (2) 20%
20%
20%
20%
(1)
From tube sheet, hot leg side, to tube sheet cold leg side.
(2)
Performed in the Steam generator Kidney Region.
Eddy current Results A.
The Technical Specification sample in number twelve (12)
Steam Generator revealed an indication in one tube which exceeded the Tech. Spec. plugging limit (40%).
Therefore the exam was expanded to a 2S sample (206 tubes) in this Generator.
This exam revealed an additional indication in one tube which exceeded the Tech. Spec. plugging limit (40%).
The sample was then expanded to 4S sample (412 tubes).
The results of the 4S sample showed no addition-al indications that required plugging.
PAGE 1 OF 5
- (cont'd)
- B.
The Technical Specification samples in number 11, 13 and 14 steam Generators revealed no indications which exceed-ed the 40% plugging limit.
- c.
Rotating Pancake Coil examination results revealed a single circumferential indication in one tube in 14 steam Generator, row 14, column 67.
The rotating pancake coil exam was expanded to include the immediate adjacent tubes.
No additional indications were noted.
No circum-ferential indications were noted in number 11, 12 and 13 Steam Generators.
NUMBER OF TUBES WITH INDICATIONS IDENTIFIED DURING 1R9 OUTAGE (Including Tech. Spec. sample)
<20%
20 to 39%
~40%
(wall penetrations) 11 Steam Generator (1) 9 9
1 12 steam Generator 4
40 8
13 Steam Generator (2) 8 7
2 14 Steam Generator (3) 14 18 3
(1)
In addition, row 31 column 79 had restricted access to a.680 probe.
Using a.650 probe revealed a 34%
cold leg indication.
This tube was preventively plugged.
(1)
Bobbin inspection of row 7 column 3 and row 12 column 3 had revealed distorted indications.
Subse-quent RPC inspection revealed single axial indica-tions of indeterminate depth in these two tubes.
In addition, row 33 column 78 had restricted access to a.680 probe.
These three tubes were preventively plugged.
(2)
Bobbin inspection of row 6 column 67 revealed dis-torted indications.
Subsequent RPC inspection revealed single axial indication of indeterminate depth.
In addition, row 18 column 11 had restricted access to a.680 probe and row 14 column 67 had a single circumferential indication( see c. above)
These three tubes were preventively plugged.
All tubes with an indication of ~40% degradation of nominal tube thickness were plugged for Tech. Specs.
and all tubes with an indication of 35% to 39%
degradation of nominal tube thickness and restricted access and were preventively plugged.
PAGE 2 OF 5
- (cont'd)
- U-bend Heat Treatment A.
U-bend Heat Treatment was performed on all of Row Two Tubes in the 11, 12, 13 and 14 Steam generators.
Eddy current was performed post U-bend heat treatment to verify the proper heat affected zone was achieved.
Current A.
In 12 S/G row 2 column 63 was missed during the U-bend heat treatment process and was mechanically plugged as preventive maintenance.
status of the 11. 12, 13 and 14 Steam Generators.
At this time the total number of tubes plugged in the Salem Unit 1 Steam generators are as follows:
Generator #
11 12 13 14 Tubes plugged 104 120 109 141 In 11, 12, 13 and 14 Steam generators, the first five (5) and the last (5) tubes in row 1 were initially plugged because of a generic wearing problem on the tubes due to the tube lane blocking device vibrating.
The remaining tubes in row 1 were plugged because there was evidence of the onset of stress corrosion cracking in the U-bend area.
PAGE 3 OF 5
- (cont'd)
- SALEM UNIT 2 STEAM GENERATORS During Salem Unit 2 sixth refueling outage examinations on number 21 and 23 Steam Generator were performed by the Westinghquse NSD, and coordinated by the ISI Group.
The Eddy Current examination scope is defined below:
21 S/G - Inspections were performed on 52% of the tubes
{l,739) with bobbin coil.
The sample included 204 tubes randomly selected to satisfy technical speci-fication requirements and tubes with indications noted during previous refueling outages.
In addition, the inspection included 50% of the tubes {l,694) with a Rotary pancake Coil {RPC).
These exams address the concern of Expansion Zone Pure Water Stress Corrosion Cracking at the hot leg tube sheet for steam generators manufactured using explosive tube expansion (WEXTEX) techniques.
23 S/G - Inspection performed on 55% of the tubes {l,851) with bobbin coil.
Sample included 204 tubes random-ly selected to satisfy technical specification requirements and tubes with indications noted during previous refueling outages.
- In addition inspection of the 50% of the tubes (1,694) with RPC to address the concern of Expansion Zone Pure Water Stress Corrosion cracking at the hot leg tube sheet for steam generators manufactured using explosive tube expansion (WEXTEX) techniques.
Eddy Current Results 21 S/G -
The 204 randomly selected tubes to satisfy Technical Specification revealed no indications equal to or exceeding the 40% plugging limit (defective tubes) and satisfied the less than 5% of the inspected tubes were degraded thus a scope expansion was not required.
6 tubes with indications from previous refueling outages were plugged due to indication growth ex-ceeding technical specification plugging limit or preventively due to tube degradation being in the 35 to 39% range.
PAGE 4 OF 5
- (cont'd)
- 1 tube in the non technical specification sample was preventively plugged due to tube degradation in the 35 to 39% range.
1 tube was plugged due to a single axial indication noted during RPC inspection which was estimated to
- exceed the 40% plugging limit.
23 S/G -
All inspection results were satisfactory thus there were no tubes plugged and no scope expansion re-quired as a result of eddy current inspection per-formed.
Additional Work Performed 2R6 In response to NRC Bulletin No. 88-02 "Rapidly Propagat-ing Fatigue Cracks in Steam generator Tubes" and as*a consequence of the steam generator tube rupture event which occurred at Virginia Power's North Anna Unit 1 plant, an engineering evaluation was completed by West-inghouse for Public Service Electric and gas Co. to identify potential tubes* susceptible to vibration induced fatigue.
Eight tubes were identified as being suscepti-ble to the occurrence of fatigue cracking.
To preclude this occurrence, Public Service Electric and Gas decided to remove eight tubes from service with installation of a cable type tube damper, a solid mechanical plug in the hot leg tube ends and a sentinel plug in the cold leg tube end.
The intent of the insertion of the cable-type damper into a potentially susceptible tube is to modify the tube U-bend system by changing its damping character-istics thus decreasing the resultant U-bend displacement and hence the susceptibility to tube fatigue cracking.
The use of a sentinel plug on the cold leg assures for
.early detection of any primary to secondary leakage.
Any leakage detected would be small, controlled amount less than the Technical Specification limit for primary to secondary leakage.
The work performed during 2R6 to address this issue is shown below:
21 S/G -
2 tubes -
R9C59 & R9C60 22 S/G -
5 tubes -
R8C61, RlOC46, RlOC50, R11C16 & R11Cl7 23 S/G -
1 tube R8C59 NUMBER OF TUBES WITH INDICATIONS IDENTIFIED DURING 2R6 OUTAGE (Including Tech. Spec. sample)
<20%
20 to 39%
~40%
(wall penetrations) 21 Steam Generator 16 40 1
23 Steam Generator 36 26 0
PAGE 5 OF 5