ML17354A508
| ML17354A508 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point, Saint Lucie  |
| Issue date: | 05/21/1997 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| GL-95-03, GL-95-3, TAC-M92278, TAC-M92279, TAC-M92284, TAC-M92285, NUDOCS 9705230288 | |
| Download: ML17354A508 (8) | |
Text
gPS,R 500q
~
rVQ'
~
+
0 Cy 0O IIll p
Vg
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 May 21, 1997 Mr. Thomas F. Plunkett President Nuclear Division Florida Power and Light Company P.O.
Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES,"
FOR TURKEY POINT UNITS 3 AND 4 AND ST.
LUCIE UNITS 1
AND 2 (TAC NOS.
- H92284, M92285,
- M92278, AND M92279)
Dear Mr,
. Plunkett:
On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03, "Circumferential Cracking of Steam Generator Tubes," to all 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 inspection 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 al'erted 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 performance of steam generator tube examinations is controlled, in part, by
.Appendix B to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50).
In GL 95-03, the NRC staff also requested that licensees take the following actions:
(1)
Evaluate recent operating experience with respect to the detection and sizing of circumferential indications to determine the applicability to their plants.
(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.
9705230288 970521.
PDR ADQCK 05000250 P
PDR cmpv
,i
Hr. T. Plunkett (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)
A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested actions 1
and 2
(above).
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for the next planned inspection.
In response to GL 95-03, you.provided letters dated June 22,
- 1995, October 11,
- 1995, January 16,
- 1996, and February 27, 1996 for Turkey Point Units 3 and 4
and June 23, 1995 and December 11, 1995 for St.
Lucie Units 1 and 2.
These submittals provided the information requested by GL 95-03; therefore TAC Nos.
- H92284, H92285,
- H92278, AND H92279 are closed.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
H If you have any questions regarding this matter, please contact Richard Croteau at (301) 415-1475.
'I Sincerely, Frederick J.
Heb on, Director Project Directorate II-3 Division of Reactor Projects I/II
'ffice of Nuclear Reactor Regulation Docket Nos.'50-335, 50-389, 50-250 and 50.-251 cc:
. See next page
a 1
'I'
~
2-
~
Mr. T. Plunkett
- f
-~ >-'(S)
~
~'evelop 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)
A safety assessment justifying continued operation, predicated on the evaluation performed in accordance with requested actions 1 and 2
(above):
(2)
A summary of the inspection plans developed in accordance with requested action 3 (above) and a schedule for the next planned inspection.
If you have any questions regarding this matter, please contact Richard Croteau at (301) 415-1475.
Sincerely, In response to GL 95-03, you provided letters dated June 22,
- 1995, October ll,
- 1995, January 16,
- 1996, and February 27, 1996 for Turkey Point Units 3 and 4
and June 23, 1995 and December ll, 1995 for St.
Lucie Units 1 and 2.
These submittals provided the information requested by GL 95-03; therefore TAC Nos.
- M92284, M92285,
- M92278, AND M92279 are closed.
For your information, the staff's findings regarding this issue are contained in NUREG-1604, "Circumferential Cracking of Steam Generator Tubes."
E Original signed by
'rederick J.
- Hebdon, Project Project Directorate II-3 Division of Reactor Projects I/II Office'of Nuclear Reactor Regulation cc:
See next page
. DISTRIBUTION
. Docket File OGC ~
KKarwoski PUBLIC ACRS St.
Lucie Rdg.
Turkey Pt.
Rdg.
- JJohnson, RII Docket Nos.
50-335, 50-389, 50-250 and 50-251 SVarga SDembek I g DOCUMENT NAME:
G: iTURKEYiSG CRACK. LTR To receive a copy of this document, Indicate in the box:
"C" = Copy without attachment enclosure "E" = Co with attachment enclosure "N" = No co y OFFICE PDII-3/PM PDII-3/LA PDII-3/PM PDII-3/D HAHE DATE RCroteau 05/4 /97 BClayton 05/
( /97 Lviens 05/
/ 7 OFFICIAL RECORD COPY FHebdon 05/<'I/97
h
~
~
)4
Mr. T.
F. Plunkett Florida Power and Light Company TURKEY POINT PLANT CC:
M. S.
- Ross, Attorney Florida Power 8 Light Company P.O.
Box 14000 Juno
- Beach, FL 33408-0420 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast 'Financial Center Miami, Florida 33131-2398 Mr. Robert J.
Hovey, Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035 Armando Vidal County Manager Metropolitan Dade County ill NW 1 Street, 29th Floor Miami, Florida 33128 Senior Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear Regulatory Commission P.O.
Box 1448 Homestead, Florida 33090 Mr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW., Suite 23T85
- Atlanta, GA 30303-3415 Attorney General Department of Legal Affairs The Capitol Tallahasse'e, Florida 32304 Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL'3035 Mr. H.N.
- Paduano, Manager Licensing L Special Programs Florida Power and Light Company P.O.
Box 14000 Juno
- Beach, Florida 33408-0420 Mr. Gary E. Hollinger Licensing Manager Turkey Point Nuclear Plant 9760 SW. 344th Street Florida City, FL 33035 Mr. Kerry Landis U.S. Nuclear Regulatory Commission
. 61 Forsyth Street, SW., Suite 23T85
- Atlanta, GA 30303-3415
A
=l
<r la