ML17346A897
| ML17346A897 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/26/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Williams J FLORIDA POWER & LIGHT CO. |
| References | |
| TAC-56875, TAC-56876, NUDOCS 8503130481 | |
| Download: ML17346A897 (5) | |
Text
Docket Nos.
50-250 and 50-251 February 26, 1985 Distribution Mr. J.
W. Williams, Jr., Vice President Nuclear Energy Department Florida Power and Light Company Post Office Box 14000 Juno Beach, Florida 33408
Dear Mr. Williams:
Reference:
Tac Nos.
56875 and 56876 NRC PDR L PDR ORB¹l RDG HThompson OELD EJordan BGrimes JPartlow DMcDonald CParrish ACRS (10)
BElliot Gray file
SUBJECT:
REACTOR PLANT SURVEILLANCE MATERIAL PROGRAM -
PROPOSED LICENSE AMENDMENT, TURKEY POINT PLANT UNITS 3 AND 4 By letter dated February 8, 1985, you requested license amendments to combine the reactor materials surveillance programs of Unit 3 and Unit 4 into a single integrated program which will conform to the requirements of 10 CFR 50 Appendices G and H.
We are in the process of reviewing the Safety Evaluation (SE) provided with your submittal in support of your proposed license amendments.
We have enclosed a request for additional information (RAI).
This information is needed to confirm and clarify the details provided in your submittal.
We request a prompt reply to the RAI in order to meet our current review schedule and allow for implementation of the proposed program during the upcoming Unit 3 outage.
We are available to discuss the RAI and provide any clarification necessary.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
/s/DMcDonald for S.
Varga Steven A. Varga, Chief Operating Reactors Branch ¹1 Division of Licensing
Enclosure:
As stated cc w/enclosure:
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W. Williams, Jr.
Florida Power and Light Company Turkey Point Plants Units 3 and 4
cc:
Harold F. Reis, Equire Newman and Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Norman A. Coll, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Fl or ida 33131-2398 Mr.
Ken N. Harris, Vice President Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 Mr.
M. R. Stierheim County Manager of Metropolitan Dade County Miami, Florida 33130 Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear Regulatory Commission Post Office Box 57-1185 Miami, Fl orida 33257-1185 Regional Radiation Representative EPA Region IV 345 Courtland Street, N.W.
- Atlanta, GA 30308 Intergovernmental Coordination and Review Office of Planning 8 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Administra tor Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 James P. O'Reilly Regional Administrator, Region II U.S Nuclear Regulatory Comnission Suite 2900 101 Marietta Street
- Atlanta, GA 30303 Martin H. Hodder, Esquire 1131 N.E. 86th Street Miami, Florida 33138 Joette Lorion 7269 SW 54 Avenue Miami, Flor ida 33143 Mr. Chris J. Baker, Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 Attorney General Department of Legal Affairs.
The Capitol Tallahassee, Florida 32304 Mr. Allan Schubert, Manager Public Health Physicist Department of Health and Rehabilitative Services 1323 Winewood Blvd.
Tallahassee, Florida 32301
CLOSURE RE(UEST FOR ADDITIONAL INFORMATION TURKEY POINT PLANT UNITS 3 5 4 INTEGRATED REACTOR SURVEILLANCE PROGRAM I)
Are the materials and designs for the cores, thermal shield, core barrels and vessels the same for each unit?
2)
Is the figure in Attachment 3 representative for units 3 and 4?
3)
What are the materials (base metals and weld metals) in the beltline of each vessel.
Indicate the material specification, heat nos. (flux and weld wire), amounts of Cu, Ni, 5 P and initial RTNDT for each matl.
How were initial RTNDT, Cu, Ni 5 P determined?
4)
How was it determined that SA 1101 was the limiting matl.?
What is the projected end of life RT for the matl.
and how does it compare with the values for other ma%ials in the beltline?
5)
Describe the excore dosimetry program and how it will be used to determine the peak neutron fluence for each vessel?
Has bench marking been completed?
6)
Are the neutron specturm and neutron flux the same for each vessel at the peak fluence locations?
Are the neutron spectrum and neutron flux the same for capsules T,
V and X in each vessel?
How will the dosimetry from one vessel be used to estimate the neutron fluence 8
spectrum for each vessel?
7)
What is the end of life peak neutron fluence at the kT location?
How wasthe value and the value for end of life peak neutron fluence at the inside surface determined?
8)
What is the projected neutron fluence to be received by each capsule at the time of its withdrawal?
Does the withdrawal sch.
comply with ASTM E-185-82?
If it does not, state the reason why the requested schedule is more appropriate.
Where numbers, calculation methods and programs are reported, provide references and letter identification for submittal of the information to the NRC.
Were these documents approved by the NRC?