ML20141E282
| ML20141E282 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/16/1997 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | Cottle W HOUSTON LIGHTING & POWER CO. |
| References | |
| GL-95-03, GL-95-3, TAC-M92276, TAC-M92277, NUDOCS 9705200390 | |
| Download: ML20141E282 (5) | |
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g* "thg4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 2066tH1001 k *,* *,o#
May 16, 1997 Mr. William T. Cottle Executive Vice-President &
General Manager, Nuclear Houston Lighting & Power Company South Texas Project Electric 1
Generating Station 1
P. O. Box 289 Wadsworth, TX 77483
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES," DATED APRIL 28, 1995, FOR SOUTH TEXAS PROJECT, UKITS 1 AND 2 (STP)
(TAC NOS. M92276 AND M92277)
Dear Mr. Cottle:
On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic i
i.
Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," to all
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holders of operating licenses or construction permits for pressurized-water reactors. The NRC issued GL 95-03 for three principal reasons:
(1)
Notify addressees about the safety significance of the recent steam generator tube inspectior, findings at Maine Yankee Atomic Power Station.
(2)
Request that all addressees implement the actions described within the generic letter.
(3)
Require that all addressees submit to the NRC a written response regarding implementation of the requested actions.
In addition, GL 95-03 alerted addressees to the importance of performing comprehensive examinations of steam generator tubes using techniques and equipment capable of reliably detecting the types of degradation to which the steam generator tubes may be susceptible. The staff also noted that the i
performance of steam generator tube examinations is controlled, in part, by I
Appendix B to Title 10, Part 50, of the Code of federa7 Regulations (10 CFR 0
Part 50).
In GL 95-03, the NRC staff also requested that licensees take the following
.d) actions:
(1)
Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to determine the applicability to their plants.
soooss NRC FR.E CENTER COPY 9705200390 970516 PDR ADOCK 05000498 p
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(2)
'On the basis of the evaluation'in Item (1) above, as well as past i
inspection scope and results, susceptibility to circumferential cracking, threshold of detection, expected or' inferred crack growth
[
rates, and other relevant factors, develop a safety assessment i
justifying continued operation until the next scheduled steam generator tube inspections.
(3)
Develop plans for the next steam generator tube inspections as they i
pertain to the detection of circumferential cracking. The inspection plans should address, but not be limited to, scope (including sample 1
expansion criteria, if applicable), methods, equipment, and criteria l
(including personnel training and qualification).
To document the outcome of these actions, the NRC staff requested that addressees prepare and submit'the following:
L (1)
A safety assessment justifying continued operation, predicated on the evaluation performed.in accordance with requested actions 1 and 2 (above).
(2)
A su'nmary of-the inspection plans developed in accordance with requestPd action 3 (above) and a schedule for the next planned j
inspection.
In response to GL 95-03, you provided letters dated June 27, October 2 and October 23, 1995, for STP. These submittals provided the information requested by GL 95-03; therefore TAC Nos. M92276 and M92277 are closed.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
If you have any questions regarding this matter, please contact Tom Alexion at 301-415-1326.
Sincerely, f
s ens /
uru Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV i
Office of Nuclear Reactor Regulatien Docket Nos. 50-498 and 50-499 cc:
See next page 1
p.
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1 May 16, 1997 I
(2)
On the basis of the evaluation in Item (1) above, as well as past inspection scope and results, susceptibility to circumferential cracking, threshold of detection, expected or inferred crack growth rates, and other relevant factors, develop a safety assessment justifying continued operation until the next scheduled steam generator tube inspections.
(3)
Develop plans for the next steam generator tube inspections as they pertain to the detection of circumferential cracking. The inspection plans should address, but not be limited to, scope (including sample expansion criteria, if applicable), methods, equipment, and criteria (including personnel ~ training and qualification).
To document the outcome of these actions, the NRC staff requested that addressees prepare and submit the following:
1 (1)
A safety assessment' justifying continued operation, predicated on the
]
evaluation performed in accordance with requested actions 1 and 2 i
(above).
(2)
A summary of thS inspection plans developed in accordance with requested ac'. ion 3 (above) and a schedule for the next' planned inspection.
In response to GL 95-03, you provided letters dated June 27, October 2 and October 23, 1995, for STP. These submittals provided the information requested by GL 95-03; therefore TAC No:1. M92276 and M92277 are closed.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
If you have any questions regarding this matter, please contact Tom Alexion at 301-415-1326.
Sincerely, Orig. signed by Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 cc: See next page Document Name: STP92276.1Tp 0FC PO4-11, A\\
PD4-1 NAME TAlexiM[ CHawesAf#t/
DATE h h97
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COPY (hES)NO YES/N0 V 0FFICIAL RECORD COPY
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DISTRIBUTION FOR GL 95-03 DATED: May 16, 1997 Docket. File (2).
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.JRoe' EAdensam (EGA1) l WBeckner CHawes TAlexion TGwynn, RIV KKarwoski, EMCB SDenhek, SPO-L OGC ACRS l
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Mr. William T. Cottle Houston Lighting & Power Company South Texas, Units 1 & 2 cc:
Mr. David P. Loveless Jack R. Newman, Esq.
Senior Resident Inspector Morgan, Lewis & Bockius U.S. Nuclear Regulatory Comeission 1800 M Street, N.W.
P. O. Box 910 Washington, DC 20036-5869 Bay City, TX 77414 Mr. Lawrence E. Martin Mr. J. C. Lanier/M. B. Lee General Manager, Nuclear Assurance Licensing i
City of Austin Houston Lighting and Power Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth, TX 77483 Austin, TX 78704 Rufus S. Scott Mr. M. T. Hardt Associate General Counsel Mr. W. C. Gunst Houston Lighting and Power Company City Public Service Board P. O. Box 61867 P. O. Box 1771 Houston, TX 77208 San Antonio, TX 78296 Joseph R. Egan, Esq.
Mr. G. E. Vaughn/C. A. Johnson Egan & Associates, P.C.
Central Power and Light Company 2300 N Street, N.W.
P. O. Box 289 Washington, DC 20037 Mail Code: N5012 Wadsworth, TX 74483 Office of the Governor ATTN: Andy Barrett, Director INP0 Environmental Policy Records Center P. O. Box 12428 700 Galleria Parkway Austin, TX 78711 Atlanta, GA 30339-3064 Arthur C. Tate, Director j
Regional Administrator, Region IV Division of Compliance & Inspection i
U.S. Nuclear Regulatory Commission Bureau of Radiation Control 611 Ryan Plaza Drive, Suite 400 Texas Department of Health Arlington, TX 76011 1100 West 49th Street Austin, TX 78756 Dr. Bertram Wolfe 15453 Via Vaquero Texas Public Utility Commission Monte Sereno, CA 95030 ATTN: Mr. Glenn W. Dishong 7800 Shoal Creek Blvd.
Judge, Matagorda County Suite 400N Matagorda County Courthouse Austin, TX 78757-1024 1700 Seventh Street Bay City, TX 77414 O