ML18101B293
| ML18101B293 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 03/25/1996 |
| From: | Olshan L NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M94797, TAC-M94798, NUDOCS 9603270254 | |
| Download: ML18101B293 (39) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 March 25, 1996 LICENSEE:
Public Service Electric & Gas Company FACILITY:
Salem Nuclear Generating Station, Units 1 and 2
SUBJECT:
RESULTS OF SALEM STEAM GENERATOR TUBE INSPECTIONS (TAC NOS. M94797 AND M94798)
On March 5, 1996, members of Public Service Electric & Gas Company (PSE&G, the licensee) met with the Nuclear Regulatory Commission (NRC) in Rockville, Maryland, to discuss the results of the steam generator tube inspections for Salem Nuclear Generating Station, Units 1 and 2. is a list of the meeting attendees. is a copy of the slides that were used in the licensee's presentation.
The licensee informed the NRC, that even though the inspections in Unit 1 are not complete, there have been a significant number of the inspected.tubes (approximately 30%) that have indications at the tube support plate elevations. These indications include both inside and outside diameter initiated indications which are either axially or circumferentially oriented.
In addition, a number of indications, which have been referred to as shallow outside diameter (SOD) indications, have been identified. Similar indications have been found in Unit 2; however, the degradation observed in Unit 2 is not as extensive as that observed in Unit 1 (i.e., approximately 2% of the tubes may r~quire repair in Unit 2).
To provide a further understanding of the nature and significance of the SOD indications and the other indications detected during the inspections, the licensee discussed their plans for removing several tubes for destructive evaluation.
The licensee currently intends to remove tubes from both Units 1 and 2.
The NRC requested that the licensee submit their evaluation of the field eddy current data for all tubes removed for destructive examination prior to commencing the destructive analysis.
The licensee also discussed several options for addressing the large number of potentially repairable indications detected in Unit 1.
These include raising the allowable limit for plugged tubes to 20%, electro-sleeving the tubes, and replacing the steam generators.
The licensee proposed another meeting in May, 1996, to present available results of the pulled tube examinations and to update the NRC on the licensee's plan for dealing with the Unit 1 steam generators.
The NRC P1ervtD ~*
NSC FILE CENTER COPY. '
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r indicated that if the licensee concludes, based on the results of the pulled tube evaluation, not to repair all of the indications detected at the tube support plate elevations (e.g., SOD indications), the licensee should discuss their basis for this conclusion with the NRC as soon as practical.
Docket Nos. 50-272/311
/SI Leonard N. Olshan, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1.
List of Attendees
- 2.
Copy of Slides cc w/encls:
Licensee and Service List DISTRIBUTION via Hard Copy Docket File (w/encl. 1 & 2)
PUBLIC (w/encl. 1 & 2)
PDI-2 Reading (w/encl. 1 & 2)
OGC ACRS DISTRIBUTION via E-Mail WRussell/FMiraglia RZimmerman SVarga JZwolinski JStolz LOlshan (w/encl. 1 & 2)
MO' Brien EJordan DBrinkman GHornseth KKarwoski JKopeck MModes JMuscara PRush TSull i van JTsao WDean LNicholson, RGN-I (w/encl. 1 & 2)
JStrosnider OFFICE I-2/PM NAME
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r indicated that if the licensee concludes, based on the results of the pulled tube evaluation, not to repair all of the indications detected at the tube support plate elevations (e.g., SOD indications}, the licensee should discuss their basis for this conclusion with the NRC as soon as practical.
Docket Nos. 50-272/311
Enclosures:
- 1.
List of Attendees
- 2.
Copy of Slides Leonard N. Olshan, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/encls:
Licensee and Service List I
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Public Service Ele~ic & Gas Company W
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Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street NW Washington, DC 20005-3502 Richard Fryling, Jr., Esquire Law Department - Tower SE
- 80 Park Place Newark, NJ 07101 Mr. Clay Warren General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hanc_ocks Bridge, NJ 08038 Mr.* Lou i s Storz Sr. Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Mr. Charles S. Marschall, Senior
- Resident Inspector Salem Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Maryland Office of People's Counsel 6 St. Paul Street, 21st Floor Suite 2102 Baltimore, Maryland 21202 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne, PA 19087 Mr. Elbert Simpson Sr. Vice President - Nuclear Engineering Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem NucJ.iir Generating Station, Units lWd 2 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Frank X. Thomson, Jr., Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Ms. P. J. Curham MGR. Joint Generation Department Atlantic Electric Company P.O. Box 1500 6801 Black Horse Pike Pleasantville, NJ 08232 Carl D. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington~ DE 19899 Public Service Convnission of Maryland Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806 Mr. Leon R. Eliason Chief Nuclear Officer & President-Nuclear Business Unit Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
I SALEM STEAM GENERATOR TUBE INSPECTION RESULTS MEETING LIST OF ATTENDEES D. Brinkman L. 01 sh an G. Hornseth K. Karwoski J. Kopeck M. Modes J. Muscara P. Rush T. Sullivan J. Tsao R. Dulee D. Garchow P. Thomson H. Abendroth G. Alberti D. Airozo R. Coe L. Connor W. Cross D.. Goetcheus P. Gunter D. Hansen A. Kapsalopoulon R. Kankus J. Riccio T. Sutter MARCH 5, 1996 ORGANIZATION NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/OPA NRC/RGN-1 NRC/RES NRC/NRR NRC/NRR NRC/NRR PSE&G PSE&G PSE&G Atlantic Electric Dusquesne Light Nucleonics Week Framatome Technologies Southern Technical Services Southern Technical Services Tennessee Valley Authority Nuclear Info & Resource Service Arizona Public Service NJ Dept. of Environmental Protection PECO Energy Company Public Citizen Bechtel ENCLOSURE 1
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> Introduction
> Salem Unit 1/Unit2 inspections and findings
> Tube Pull Action Plan
> Regulatory Guide 1.121 impact
> Response to previous questions
> Future course of action
> Question and Answer
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GAR CHOW GAR CHOW DU LEE DU LEE DU LEE GAR CHOW
> Steam generator overview
> Failure mechanisms
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i' ;1, > liube inspection
~. requir_ements
~'* method
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> Bobbin Coil
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- comPlete
> Plus Point Probe*
- continuing wi.th data aquisition
- issue resolution in progress
Unit 1 Status Steam Generator Tubes per S/G
- Tubes Previously..
Plugged (w/%)
Tubes Inspected Hot.Leg Cold Leg Potential Repairs 11
- 12 13 14 Total 3272 3263 3266 3243 13044.
116 125 122 145 508 3.4% 3.7% 3.6% 4.3%
3.7%
1.901 3263 1754 1536 8454 1901 3263 1754 1536 8454 851 3263 1059' 747 5920 412 1458 626 283 2779
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S/G 14 C/L MRPC S/G 13 C/L MRPC S/G 12 C/L MRPC S/G 11 C/L MRPC S/G 14 H/L MRPC S/G 13 H/L MRPC S/G 12 H/L MRPC S/G 11 H/L MRPC S/G 14 Bobbin S/G 13 Bobbin S/G 12 Bobbin S/G 11 Bobbin ECT Inspection Status Salem Unit 1 I
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1 0 20 30 40 50 60 70 80 90 100 Percent Complete
(f) 200 z
0
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0
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a:
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INTERSECTION COMPARISON SALEM-1 SG-12 TSH DENTS(O)
ID CIRC(1)
SOD(O) z o-i=+-~~-+--#-~-4---.~-+--+-~~~~~
OD AXIAL(33)
ID AXIAL(10)
< 2 20 40 60 80 1 00 1 20 140 1 60 180 200 10 30 50 70 90 110 130 150 170 190 DENT VOLTAGE
INTERSECTION COMPARISONS Cf) 2000 6 1000 1600 1-(§ 1400 0
1200 z
1000 LL 0
a:
w (l) 800 600 400 200 SALEM-1 SG-12 ALL TSP HOT
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< 2 20 40 60 80 1 00 1 20 1 40 1 60 1 80 200 1 0 30 50 70 90 110 130 150 170 190 DENT VOLTAGE
3000 2500 2000 1500 1000 500 0
3000 2500 2000 1500
.1000 500 0
S/G 11 S/G 13.
Dent Elevation Distribution Salem Unit 1 (3/1/96) 3000 2500 2000 1500 1000 500 0
3000 2500 2000 1500 1000 500 S/G 12 e
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S/G 14
SIG 11 400 300 200 100 0
SIG 13 Indication Elevation Distribution Salem Unit 1 (3/1/96)
,l SIG 12 400 300 200 100 I o I _ __ ____
c,~'t' TSH 1H 2R--3H--4H ___ 5H--5w--1H*- SOD's 400 I 300 I I 200 SIG 14 100 0 ~"'-,;--'c,:AL TSH 1 H 2H 3H -4i:c Si-f~~!fs~D's
> Hot Leg inspections 1 OOo/o complete
> Results within current plugging limits
> Evaluation of data ongoing
Unit 2 Status e
Steam Generatdr 21
. 22 23 24 Total Tubes per SIG '.::
3272. 3267 3274 3253 13066
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- Tubes Previously 116
' 121 114 135 486 Plugged (w/%)
3.4% 3.6% 3.4% 4.0%
3.6%
Tubes Inspected 3272 3267 3274 3253 13066 Potential Repairs
- 51.
62 32 120 265
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S/G 24 C/L MRPC S/G 23 C/L MRPC S/G 22 C/L MRPC S/G 21 C/L MRPC S/G 24 H/L MRPC S/G 23 H/L MRPC S/G 22 H/L MRPC S/G 21 H/L MRPC S/G 24 Bobbin S/G 23 Bobbin S/G 22 Bobbin S/G 21 Bobbin ECT lnspeetion *Status*
- Salem Unit 2 I
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0 10 20 30 40 50 60 70 80 90 100 Percent Complete
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200 z
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100 LL 0
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- J INTERSECTION COMPARISON SALEM-2 SG-22 TSH DENTS(O) *
~____,,.....~____,-------~__,.~.___,,.._-r---r-___ ___,. 0 D CIR C (0)
ID CIRC(O)
SOD(O)
OD AXIAL(7) z o~~~~~-?-+~~~~~~~ ID AXIAL(39)
< 2 20 40 60 80 1 00 1 20 140 160 180 200 1 0 30 50 70 90 11 0 130 1 50 170 190 DENT VOLTAGE
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INTERSECTION COMPARISON (f) 4000 z
0
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0 0 z LL 3500 3000 2500 2000 0
1500 a:
~ 1000
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500
- J SALEM-2 SG-22 ALL TSP HOT
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ID CIRC(O)
SOD(7)
OD AXIAL(1) z o-+'--'-;-4-~~~~-+-~--+-~'---4--~~~-+--+--<
< 2 20 40 60 80 1 00 1 20 140 1 60 180 200 10 30 50 70 90 110 130 150 170 190 DENT VOLTAGE ID AXIAL(1)
10 8
6 4
28 SIG 21 SIG 23 Indication Elevation Distribution Salem Unit 2 (3/1/96) 10 8
6 4
2 0
34 85 SIG 22 SIG 24
.AXIAL
- CIRC
- 6H
?H _ SOO's
SIG 21 1600 1200 800 400 SIG 23 1600 1200 Dent Elevation Distribution Salein Unit 2 (3/1/96) 1600 1200 800 400 S/G 22
. 0-5 v
- 6 - 100 v o --*-
101-2oov TSH 11*r-2f-f--3R--4H"""sH*-*-6H-1H"- 200 + v 1600* I 1200 800 400 O T-*sH
- 1- -H SIG 24 2H. -3H -- 4H-. 5H -6H -7H
> Unit 1 - No quick solutions
- > Unit 2 - Focus on Restart
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> Tube selection criteria
- Obtain shallow OD indication samples
- Characterize TSP intersections
- Characterize degradation at tubesheet
> Unit 2 tubes to be pulled from SIG 24
- Row 11
- Row 13
- Row 21
- Row 11
- Row 19
- Row.20 Column 27 Column 36
- Column 71 Column 31 Column 45 Column 26*.
> Unit 1 tubes to be pulled *will be identified during Marc.h
UNIT 2 Tube pull operation complete NRC update Preliminary tube pull results Regulatory Guide 1.121 Evaluation Presentation of results to NRC UNIT 1 NRC update Selection of tubes to be pulled Tube pull operation complete Preliminary tube pull -results Regulatory Guide 1.121 Evaluation March March April April May March March April May May
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>UNIT 1
- SIG 12 Row 3 Column 10 at TSP 1
>UNIT 2
- SIG 22 Row 14 Column 53 at tubesheet
- SIG 22 Row 14 Column 56 at tubesheet
- SIG 22 Row 19 Column 61 at tubesheet
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- 1. PROVIDE ECT SCOPE AND BASIS*
Full length bobbin of 100°/o of unplugged tubes PlusPoint of all TSP intersections and tubesheet expansion transitions RPC of 1 OOo/o of Row 2 U-bends in each SIG
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Provide Types and Sizes* of Indications Detected
+Unit 1 e Number of Tubes Evaluated 9840
- Axial and Circumferential Indications
+Unit 2 o Number of Tubes Evaluated 13066 I
e Axial and Circum.ferential Indications
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- 3. DISCUSS THE REPAIR CRITERIA
- USED AT THE PLANT DURING THIS CYCLE AND IN THE PAST
> All bobbin coil indications greater than
- 40°/o in depth are repaired
> All crack-like indic~tions are repaired
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- 4. PROVIDE A TUBE INTEGRITY ASSESSMENT FOR THE INDICATIONS DETECT.ED The Reg. Guide 1.121 tube integrity assessment is in progress.
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- 5.
Comparison of Salem Dented Locations to Other Plants
+ Similar axial and.circumferential indications
+ Salem unique with shallow OD indications e Limited industry data with Plus Point e Indications found at non-dented locations
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- 6. PROVIDE A DISCUSSION OF OTHER DIAGNOSTIC TESTING BEING PERFORMED
- Unit 1
> UT testing of 45 HL _intersections*
> Tube pulls (,.__,to be determined)
> In-situ pressure testing Unit 2
> Tube pulls (,.__,6)
> In-situ pressure testing
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- 7. DISCUSS LEAKAGE MONITORING, AND LEAKAGE OBSERVED IN LAST CYCLE
> Leakage was barely detectable on Unit 1 with radio-chemical analysis of ion exchange resin columns temporarily placed in S/G blowdown
> No leakage observed in Unit 2 during last cycle
> Leakage monitoring by rad monitors at condenser vacuum pump exhaust and SIG blowdown lines
> N16 monitors will be on line for next cycle
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- 8. PROVIDE GRAPHS FOR THE DISTRIBUTION OF CRACK LIKE INDICATIONS AND PLUG LOCATION
> Tubesheet maps will b*e made available as analysis activities are completed t
> Graphs showing the distribution of dent voltages and indications for the current - -
1 Unit 1 and Unit 2 *inspection status are included in the handout.
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- 9. DESCRIBE THE FINAL SCOPE OF STEAM GENERATOR TUBE
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> The final scope was previously described.
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- 10. FOR INDICATIONS IN SPECIFIC AREAS OF THE S/G PROVIDE A TABLE
. WITH DETAILED INFORMATION
> The requested information details will be provided as soon as analysis of the Unit 1 and Unit 2 ECT data is complete C"
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> Evaluate tube* pull data
>Evaluate repair options
- electrosleeving, welded tube
> Evaluate replac*ement options
> Management decision on course of action
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> Evaluate tube pull results
> Determine mitigati*o*n timing
> Plug indications
> Complete Regulation Guide 1.121 analysis
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