ML17256A749
| ML17256A749 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/02/1983 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LSO5-83-06-006, LSO5-83-6-6, NUDOCS 8306060255 | |
| Download: ML17256A749 (20) | |
Text
June 2, 1983 Docket No. 50-244 LS05-83-"06-006 LICENSEE:
ROCIIESTER GAS AND ELECTRIC CORPORATION FACILITY:
R. E. Ginna Nuclear Power Plant
SUBJECT:
SUMMARY
OF HAY 20, 1983 MEETING WITH ROCHESTER GAS AND ELECTRIC CORPORATION TO DISCUSS TI.IE STEW GENERATOR SLEEVING PROGRAM DISTRIBUTION D
~ NSIC DCrutchfield HSmith GDick OELD ELJordan JMTaylor ACRS (10)
SEPB SVarga DVassallo RClark JStolz HFConrad LFrank On Hay 20, 1983, members of the NRC staff met with representatives of Rochester Gas and Electric Corporation (RGEE) and Babcock and Wilcox (BGW) to discuss the steam generator tube sleeving Iprogram for Ginna.
The licensee presentations included sleeve installation, testing and analyses of the test results.
The attendance list (Enclosure 1) and a copy of the non-proprietary slides used in the presentations (Enclosure
- 2) are enclosed, Copies of the proprietary slides are av'ailable through the NRG licensing project manager.
During the Spring, 1983 refue1ing outage, a totals of 78 s1eeves were installed; 28 tubesheet
Problems were encountered with the installation of the regular sleeves.
After inspecting the steam generator tubes and performing laboratory tests, it was determined that the tubes wer'e tightly held at the tube support
- plates, "locked up," thereby preventing uninhibited thermal growth.
During the sleeving process, the tubes bulged resulting in unacceptable seals.
The licensee modified the sleeving technique including cr'eating bulges in the tubes before sleeving.
Analyses of the stresses induced by the tube Rpresleeving" technique as well as a reanalysis of the ef>>
feet of tube lockup on Hain Steam Line Break were made and presented to the staff.
The licensee will formally submit the information to the staff by Hay 25, 1983.
The staff will review it and issue a Safety Evaluation before permitting Ginna to achieve criticality which is currently scheduled for June 8, 1983.
8306060255 830602 PDR ADOCK 05000244 P
Enclosures:
As stated Original signed by/
George F. Dick, Jr., Project Iianager
~9 Operating Reactors Branch 85 Division of Licensing OFFICE 0 SURNAMEIP DATE Ip D
OR 5
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3Reo 06/dA/83
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Per.II. a t;ial.d 06/+/83 NRG FORM 318 (10.80) NRCM 0240 OFFICIAL RECORD COPY USGPOs 1981~~980
I
CC Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue, N.
W.
Suite 1100 Washington, D. C.
20036 Mr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.
E. Ginna Plant c/o U.
S.
NRC 1503 Lake Road
- Ontario, New York 14519 Director, Bureau of Nuclear Operations State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U.
S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Thomas E. Murley, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 U. S. Environmental Protection Agency Region II Office ATTN:
Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comoission Washington, D. C.
20555 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Jay Dunkleberger New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Mr. John E. Maier Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
ENCLOSURE 1
ATTENDANCE LIST MAY 20 1983 MEETING Name George Dick Thomas Meyer Paul Ayres H. F.
Conrad M.
1J. Henig Dennis Crutchfield James Gutzwi lier Lyle Bohn Louis Frank George J.
Vames Charles M. Weber R.,C. Mecredy Albert E. Curtis III Title Project Manager Technical Manager Mgr. Materials Eng. Lab.
Sr. Materials Engineer Business Manager
- Chief, ORBfr5 Hgr. Steam Gen.
Eng. Services Or anization NRC RG&E B&W NRC B&W NRC Materials Engineer Mgr.- Structural Analyst Hgr.- Manuf. Tech. Section Hgr. Nuclear Energy Mgr. Material Engineering NRC B&W, Lynchberg B&W, Alliance Research RG&E RG&E Mgr. Field & Tooling Services B&W
ENCLOSURE 2
6INNA STATION STEAM GENERATOR SLEEVING NRC NEETING NAY 20, 1983 AGENDA I,
INTRODUCTION II, SPRI NG 1983 SLEEVI NG
- III, TUBE LOCKUP IY, TEST RESULTS Y,
ANALYSES VI, SLEEVE INSPECTION VI I,
SUMMARY
BOB NECREDY TOM NEYER JIM HUTTON PAUL AYRES GEORGE YAMES AL CURTIS BOB NECREDY
Ginna Station Steam Generator Sleeving NRC Meeting 20.
1983 S rin 1983 Summar Number Categor S/G~AS G-B U/T Exam Tested
~Ance ted Pressure Test Tested Accepted Fall 1980 0
Spring 1981 0
16 Spring 1983 o tubesheet 4
24 15 N/A 13 N/A N/A N/A o 36" 0
19 19 o 36" PTD 0
22 17 17 0 28" PTD o pulled o plugged o repairs Notes 0
9 (1) 0 1
(2) 0, 3
(3)
(4) 0 1
4 N/A N/A N/A N/A N/A N/A
. N/A N/A N/A N/A N/A N/A (1) in progress'2) includes 1,'8 inch brazed sleeve and 1 tubesheet sleeve (3) 3 explosive plugs wj.th very minop leakage not repaired this outage (4) leaking explosive plug
Gonna Station Steam Generator Sleeving NRC Meeting 9
Current~Sleeve Status Outacte Fall 1980 TS 0
S G-A 0
0 TS 0
S/G-B 0
36 Total 5
5 Spring 1981 0
Spring 1983 4
0 0
0 0
0 (1) 24 0
(2) 9 16 16 41 78 Totals 4
0 0
24 9
62 99 Notes il) in addition, l has been plugged based on eddy current exam (2) in addition, 1 has been plugged due to an expansion problem
Ginna Station Steam Generator Sleeving NRC Meeting 9
~bk A.
Verification o,
bulge test 3 tubes, S/G B
27,28, 30 mil bulge o
tube pulls secondary side R45 C52 8400 lbs.
R45 C47 8200 lbs.
o braze comparison Ringhals tests Ginna results o
cold lockup bulge size B.
Axial Load Tests o
Combustion Engineering tube rupture 5/18/82 report o
test conditions locked at support plate varied lateral restraint o
axial deflection
.120" to.622" o
bowing
.459" to 3.659" o
axial loads 2500 lbs. to 3100 lbs.
o minor effect on tubing
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I ROCHESTER GAS AND ELECTRIC STEAN GENERATOR SLEEVE TO TUBE BRAZE ULTRASONIC INSPECTION 05 98 1VU 108 CPU 278 511 568 C DKGHKEU)
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Ginna Station Steam Generator Sleeving NRC Meeting 1
3 Tube Locku (cont'd)
C.
Normal 0 exatin Transients o
Denting Users Group Report WTD-SM-76-080 o
assumptions 44 Series Steam Generator tubes locked at support plate peripheral tube locked in hot condition o
transients primary hydro (before lockup) cold shutdown (after lockup) hot standby (boil dry)
fatigue.usage -transients other than filling dry S/G have negligible effect;
.013 for worst tube with 40 cycles of filling dry S/G o
EPRI Report NP-1479 similar results for a C-E steam generator
- not a design transient for Ginna steam generators.
Ginna Station Steam Generator Sleeving NRC Meeting 1
Tube Locku (cont'd)
D.
Main Steam Line Break o
original analysis
-'assumed tube free
. resistance plate installed o
N reanalysis tubes locked at support plates resistance plate removed o
qualitative description o
previous results wrapper load diff. press.
drag turbulence 155 lbs.
load
=
65 lbs.
= 130 in.
lb'0 in. lbs.
o highest loads on periphery tubes o
load combination pressure
+ MSLB
5~
55 5 555 5555'I STCAM OUTLET fERSORATCO fLATE INST EXTRACTOR ITNO TIER)
EO IS C5 O
Llli O
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I LU CT'L STEAM rITN IAXSTVRE CAR5IITNER tRCSSURC TAI5 I
ISTEAM DIME DRAIN fISCS I
i.-j]
LEVEL CONINOL SCNCATCR fEEDNATER OIIWDVCED SSTD OONNCOMER TISSU AINIVLARRNNI U SEND TVSES TTUBE 4VNDLE ASSEMSLTI CTcAM rATCR TUSC SVtfORTSIS)
TORTEO TO PEINNT fLON Cf STEAM rATER MIXTURE STAT ROO LONER SMELL rATTR ENTERS AIC 40IUISI SEATSIS 5 ~
5 5
WKONOLE CUTER I
T5 5 LL DRAIN CONKECDON SN5MANY MANNAY CIXLANT CNANNEL MOTTLE COOLANI CNANNCL
Ginna Station Steam Generator Sleeving NRC Meeting l~l, 1
Mechanical Pro erties
- Annealed, Cold Drawn Inconel 600 Tubin 0.2% yield STRENGTH tensile STRENGTH elongation Metals Handbook SB-163 R44 C55 R42 C55 R45 C52 R17 C41 30-.50,000 35,000 min.
56-62,000*
45,000*
80-100,000 80,000 min.
53,000 avg.
92,800 avg.
51,900 avg.
90,800 avg.
50-35 30 min.
>-28 28 39 31 based on hardness correlations
Description of structure Load comparison Results of analysis Conclusions "P
SEE DETAIL B 36" REF 22 1/4 SEE DETAIL A
P2 Pj(TUBE)
Pg (SLEEVE)
V Sleeve design for locked-in condition meets th-'-:
---structural requirements of the ASME Boiler and
".-"ressure Vessel Code,Section III, Subsection, N 8 when subjected to the loadings specified in "Design Criteria Ginna Station Steam Generator Tube Sleeves"
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