ML17258A624
| ML17258A624 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/25/1982 |
| From: | Lyons J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LSO5-82-02-121, LSO5-82-2-121, NUDOCS 8203110012 | |
| Download: ML17258A624 (10) | |
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Docket No. 50-244 LS05-82-02-121 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 25, 1982 LICENSEE:
Rochester Gas and Electric Corporation FACILITY:
R. E. Ginna SUBJECT'.
SUMMARY
OF FEBRUARY 10, 1982 MEETING WITH RGRE TO DISCUSS RESTART PROGRAM FOLLOWING GINNA'S TUBE RUPTURE ACCIDENT
'n Wednesday, February 10,
- 1982, members of the NRC staff met with representatives of Rochester Gas and Electric Corporation (RGEE) to discuss the requirements to be met. prior to restart of the R. E. Ginna Nuclear Power Plant.
RGEE had scheduled the startup of Ginna for Monday, February 15,
- 1982, and proposed operation until the scheduled May 15, 1982 refueling outage, at which time the plant would be shut down and eddy current tests (ECT) of the steam generators (S/G) would be performed.
RGEE presented information on the cause and corrective action for the tube located in the w'edge area that ruptured.
In addition', there was a description of Power Operated Relief Valve (PORV) modifications and discussion of emergency procedures.
The attendance list is enclosed.
RGEE has performed extensive ECT of all tubes in both S/Gs.
The ruptured tube in the "B" S/G has been inspected from the primary side using fiber.
optics and a'videotape of the rupture was shown at the meeting.
RGEE postu-lates that the suspected failure me'chanism is localized'echanical loading in wedge'rea 4 between the tube sheet and the first support plate, contrib-uting to stress corrosion.
During the last refueling outage (May 1981) an OD 'flaw of <20/ was detected in the ruptured tube.
The Technical Specifications plugging limit is >40/ degr adation.
One other tube previously had shown a
similar rate of degradation (i.e. 0-75/ in 6 months) and another tube had'een pulled in April 1978 after ECT had shown a bulge in the tube at the same general elevation of the rupture.
Both of these tubes were in the same wedge area as the ruptured tube.
In addition to the ruptured tube,'RGEE has plugged 20 additional tubes in the "B" steam generator because of intergrannular attack or wastage indica-tions.
The licensee concluded that there are no other defects in either the "A" or "B" S/Gs.
Future actions by RGEE include a fiber optics investi-gation of the secondary side of the "B" generator..
They will also perform a structural ahalysis of the wedge area, a review of thermalhydraulic design and operation, reinspection during the mid-May refueling outage and determi-nation of a long. term solution.
During the May outage, RGhE plans to plug any tube that develops an OD wall loss in'he wedge areas by the time of.
that. inspection.
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The staff'oncluded at this-point in the meeting that there was not sufficient technical basis presented to permit the Ginna plant to return to operation'.
Specifically, the staff felt that prior to restart, RGhE should:
1.
Finish the fiber optic inspection of the secondary side of "B" S/G including inspection for loose parts; 2.'btain the S/G designer's opinion on the effects of plugging in the wedge area; and 3.
Provide a more complete basis for operating for the proposed 3 months.
In addition, the licensee is to continue.to explore ways of removing the ruptured tube for analysis.
The staff made it clear to the licensee that NRC permission would be rtquired prior to return to operation.
RGKE continued their presentation with a discussion of the pressurizer PORV failure, its causes and corrective actions.
The licensee has concluded, based on bench testing and inspection, that a previous modification to the exhaust vent of the solenoid valve to reduce closure. times was the cause of the failure.
They proposed as a.solution to remove the restriction in the exhaust line and.place a check valve in the air/nitrogen line to the PORV.
The check valve will allow full flow to the PORV and an orifi,ce in the disc will limit the flow in the vent mode to ensure proper operating times during the opening and closing of the PORV.
In addition, the licensee wil3 inspect all other PORVs to ensure that restrictions in the solenoid valve exhaust vent are not used.
's a final point, RG5E gave a brief discussion of the procedures used during.the transient.
Further review of the procedures is on'going by the NRC staff, Mestinghouse and the licensee.
Enclosure:
List of Attendees James E. Lyons P~ oject Manager perqting Reactdrs Branch 85 DivÃion of Licensing cc w/enclosure:
See next page
LIST OF ATTENDEES H. Denton, NRC/NRR D. Eisenhut, NRC/DL R. Vollmer, NRC/DE G.
R.
W.
H.
W.
C.
D, T.
-F.
D, P.
C. Lainas, NRC/DL C. Haynes, NRC/Region I H. Johnston, NRC/DE B. Kister, NRC/Region I S. Hazelton, NRC/DE Y. Cheng, NRC/DE Crutchi'ield, NRC/DL G. Colburn, NRC/DL C. 'Cherny, NRC/DE R. Buci, Jr.,'CRS G. Easley, NRC/DSI Ahern,'P L. B. Marsh, NRC/OCM J.
W. Roe, NRC/OCM B.
E.
G.
F.
J.
D. Liaw,'NRC/OCM F. Goodivin, NRC/NRR R. Mazetis, NRC/DSI SChroeder, NRC/DST Laaksonen, NRC/DSI B.-Mills, NRC/IE S.
E.
J.
T.
R.
P.
S.
S.
D.
W.
D. Reynolds, NRC/Region-. I G, Case, NRC/NRR T. Wiggins, NRC/Region I.
T. Martin, NRC/Region I L, Nelson, NRC/Region III
- Hinsberg, McGraw Hill
- Cannon, McGraw Hill
- Bryan, NRC/DHFS
- Ziemann, NRC/DHFS Lan'ning, NRC/AEOD I. Villalva, NRC/IE G..Lanik, NRC/IE R. Mattson, NRC/DSI T.
W.
J.
H. Julian;. Westinghouse C. Hirst, Westinghouse E:, Volpenhein, Westinghouse Oat, Granwelt News Service J. Collins, IE
- Lyons, NRC/DL Wert, Rochester Democrat 5 Chronicle
cc w/enclosure:
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
'ew York, New York 10047 Resident Inspector R.
E. Ginna Plant c/o U. S.
NRC 1503 Lake Road
.Agency Building 2 Empire State Plaza Albany,.New York 12223 Rochester Public Library,.
115 South Avenue Rochester, New York 14604 Supervisor.of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 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 Commission Washington, D. C.
20555 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 Commission Washington, D. C, 20555 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement 631 Park Avenue Ki,ng of Prussia, Pennsylvania 19406 Mr. John E. Maier
,Vice President Electric and Steam Production Rochester Gas and Electric'Corporation 89 East Avenue Rochester, New York 14649 Mr. Stanley York, Chairman
.Wisconsin Public Service Commission 4802 Sheboygan Avenue Madison, Wisconsin
. 53705
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The staff concluded at this point in the meeting that erg~was-pot sufficient technical basis presented to permit the Ginna p4a9M~o return to operation.
Specifically, the staff felt that prior to restart, RGEE should:
1.
Finish. the fiber optic inspection of the secondary side of "B" S/G including inspection for loose parts; 2.
Obtain the S/G designer s opinion on the effects of plugging in the wedge area; and 3.
Provide a more complete basis for operating for the proposed 3 months.
. In addition, the licensee is to continue, to explore ways of removing the ruptured tube for analysis.
The staff made it clear to the licensee that NRC permission would be required prior to return to operation.
RGEE continued their presentation with a discussion of the pressurizer PORV failure, its causes and corrective -actions., The licensee has 'concluded, based on bench testing and inspection, that a previous modification to the exhaust vent of the solenoid valve to reduce closure. times was the cause of the failure.
They proposed as a.solution to remove the restriction in the exhaust line and.place a check valve in the air/nitrogen line to the PORV.
The check valve will allow full flow to the PORV and an orifi.ce in the disc will limit. the flow in 'the vent mode to ensure proper operating'imes during the opening and closing of the PORV.
In addition, the 1'icensee wi 13 inspect all other PORVs to ensure that restrictions in the solenoid valve exhaust vent are not used.
~ As a final point, RGKE gave a brief discussion of the procedures used during the transient.
Further review of the procedures is ongoing by the NRC staff, Westinghouse and the licensee.
Enclosure:
List of Attendees cc w/enclosure:
See next page Jame E.
Lyon ~
P oject Manager perating Reactcrs
'Branch s5 DiMvion of Licensing OFFICE/
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OFFICIAL R ECOR D COPY USQPO: 1991 -SS5-950
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.Docket NRC PDR Local PDR NSIC ORB85 RF J.. Heltemes D. Eisenhut G. Lainas.
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Leonard D. Crutchfield H. Smith ORB'P5 PM - J.
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T. Ippolito W. Russell OELD 0IRE OSD
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.Participants:
- W. H;; Johnston H. Denton R. Vollmer W. Hazelton C. Y. Cheng T. G. Colburn F. B. Cherny-,l P.
G. Easley.
L. Marsh
. J.
Roe B. D.LL'iaw E; G..Goodwin G. R. Mdzetis F. Schroeder J.
Laaksonen B. Mills E.
G.
Case S.
Bryan D. Ziemann W. Lanning I. Villalva, IE G. Lanik; IE R..Mattson W. J. Collins, IE R.
C. Haynes, R'egion H. B. Kister, Region AS.
D. Reynolds, Jr.,
T. T. Martin, Region J. T. Wiggins, Regio R. L. Nelson, Region A. Hem, AP ons I
I Region I I
n I
.III (sC gP DISTRIBUTION FOR MEETING
SUMMARY
P. Hinsberg, McGraw Hill S..Cannon, McGraw Hi.ll H. Julian, llqstinghouse C. Hirst, Westinghouse E. Volpenhein, Westinghouse T. Oat, Granwelt News Service M. Weet, Rochester Democrat 5'.:Chronicl I
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