ML17308A232
| ML17308A232 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/09/1986 |
| From: | Tourigny E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606130035 | |
| Download: ML17308A232 (8) | |
Text
Docket No. 50-335 June 9, 1986 LICENSEE: Florida Power and Light Company (FP&L)
FACILITY: St. Lucie Plant, Unit No.
1
SUBJECT:
SUMMARY
OF MAY 29, 1986 MEETING WITH FP&L AND NRC STAFF REGARDING UNIT 1 STEAM GENERATOR OPERABILITY Introduction u
Florida Power and Light Company (FP&L), the licensee, informed the staff that as a result of recent investigations of steam generator tube eddy current
- data, 17 steam generator tubes in Unit 1 had indications which exceed the 40Ã plugging limit.
As a result of this new information, the licensee met with the staff on Thursday, May 29, 1986 in Bethesda, Maryland.
The meeting was chaired by the NRC Project Manager for St. Lucie.
The agenda for the meeting is contained in Enclosure l.
Enclosure 2 identifies the meeting attendees.
A summary of the meeting follows.
~Sumaar Each steam generator was completely eddy current tested during the last outage (Winter 1985).
The licensee removed three steam generator tubes from the A
generator because many of the current eddy current test signals could not be characterized.
These tubes were sent to Babcox and Wilcox (B&W) for further investigation.
The steam generators were subsequently declared to be operable and Unit No.
1 was returned to service.
As a result of the B&W investigation, the licensee determined that 13 tubes in generator A and 4
tubes in generator B had tubes that exceeded the 40% plugging limit.
A tube that exceeds the plugging limit is called a defective tube and needs to be plugged.
The defective tubes in generator A ranged from 41K through-wall to 66K through-wall; the defective tubes in generator B ranged from 42%
through-wall to 59Ã through-wall.
The deterioration mechanism was attributed to intergranular attack (IGA).
The licensee believed that continued operation for the remainder of the cycle was acceptable because the steam generators'.0 gallon per minute primary to secondary leakage technical specification was the governing technical specification.
The staff's position was that the steam generator operability technical specification was also applicable and either a technical specification change was needed or the unit would have to shut down.
The licensee subsequently agreed to apply for an emergency technical specification change in order to permit Unit 1 to continue operation.
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~Fol 1 owu By 'application dated Nay 30, 1986, the licensee applied for an emergency technical specification change.
The licensee proposed to operate the Unit for up to 30 days on the basis that
( 1) the deterioration mechanism, IGA, has not progressed significantly over the last cycle (cycle 6); (2) there is presently no primary to secondary, leakage in the steam generators; (3) a tube would be expected to leak before, it breaks; (4) an administrative leakage limit of 0.3 gpm for both generators will be in effect; and (5) the tubes will be plugged when the unit shuts down.
The staff issued the technical specification
- change, as proposed, on May 30, 1986.-
Enclosures:
As stated E.
G. Tourigny, Project Manager PWR Project Directotate ¹8 Division of PWR Licensing-B cc w/enclosures:
See next page PWR¹8 ETouri y,
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Mr.
C. 0.
Woody Florida Power 8 Light Company St.
Lucie Plant CC:
Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.
NRC 7585 S.
Hwy A1A Jensen Beach, Florida 33457 State Planning 8 Development Clearinghouse Office of Planning 8 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Harold F. Reis, Esq.
Newman 8 Holtzinger 1615 L Street, N.W.
Washington, DC 20036 Norman A. Coll, Esq.
McCarthy, Steel, Hector and Davis 14th Floor, First National Bank Building Miami, Florida 33131 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis, County Administrator St.
Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 Mr. Charles B. Brinkman, Manager Washington - Nuclear Operations Combustion Engineering, Inc.
7910 Woodmont Avenue
- Bethesda, Maryland 20814 Mr. Allan Schubert, Manager Public Health Physicist Department of Health and Rehabilitative Services 1323 Winewood Blvd.
Tallahassee, Florida 32301 Regional Administrator, Region II U.S.
Nuclear Regulatory Commission Executive Director for Operations 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323
Enclosure 1
NRC/FP8L Meeting On St. Lucie Steam Generators Purpose of Meeting FPKL Introduction Technical Presentations Technical Specification Change Summary Follow Up Actions
Enclosure 2
FPSL/NRC Steam Generator Meeting May 29, 1986 Attendance List Name Ed Tourigny F. Schroeder Dennis Crutchfield C.
Y. Cheng Wm. J. Collins D.
H. Jaffe A. R. Herdt Ashok Thadani D. A. Sager H.
N. Paduano J.
E.
Moaba I
M. Robles J.
M. Westhoven John J. Hutchinson Charles R. Frye W. J. Harris Fred Allenspach W. J. (Bill) Heilker L.
W. Pearce Emmett Murphy Charles M. Molnar Charles Brinkman John Hall J.
Rajan R. V. Crlenjak P. L. Pace Mike Schoppman Affiliation NRC St. Lucie Project Manager NRC PWR-B NRC PWR-B Technical Support NRC/NRR/PWR-B/EB NRC/I E/EGCB NRC/PWR-B/PD-8 NRC-Region II, Chief, EB NRC/PWR-B FPL-St. Lucie Plant, Manager FPL-Mgr. Nuc Energy Svcs.
FPL-Section Sup.-Materials, Codes 5 Inspection CE - Senior Nuclear Engineer CE FPSL Babcock 5 Wilcox Combustion Engineering NRC/PWR-B/FOB CE, Nuclear Component Eng.
Chatt.
FPSL-Operations Supervisor-St. Lucie Plant NRC CE Licensing CE-Bethesda CE NRR/NRC NRC-SRI-St. Lucie FPL-Licensing FPL-Licensing (PSL Project)
MEETING
SUMMARY
DISTRIBUTION Licensee:
Florida Power and Light Company
- Copies also sent to those people on service (cc) list for subject plant(s).
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