ML17229A070

Forwards RAI Re Pressurized Thermal Shock Evaluation for Plants

ML17229A070
Person / Time
Site:	Saint Lucie
Issue date:	10/15/1996
From:	Wiens L NRC (Affiliation Not Assigned)
To:	Plunkett T FLORIDA POWER & LIGHT CO.
References
TAC-M95484, TAC-M95485, NUDOCS 9610170215
Download: ML17229A070 (4)

Text

Hr. Thomas F. Plunke President, Nuclear Di ion Florida Power and Light Company Post Office Box 14000 Juno

Beach, Florida 33408-0420 October 15, 1

6

SUBJECT:

RE(VEST FOR ADDITIONAL INFORMATION PRESSURIZED THERMAL SHOCK EVALUATION ST.

LUCIE, UNITS 1

AND 2 (TAC NOS.

H95484 AND H95485)

By letter dated Hay 14, 1996, Florida Power and Light Company (FPL) submitted a pressurized thermal shock (PTS) evaluation for St. Lucie Units 1 and 2.

The NRC staff has identified additional information which is needed to complete its assessment of this evaluation.

The specific questions are listed on the enclosed Request for Additional Information (RAI).

A response to this RAI is requested within 30 days of receipt to support completion of our review by the date requested by FPL.

The FPL submittal included CEOG report CEN-405-P which presented two approaches for CE owners to apply Regulatory Position 2. 1 of Regulatory Guide 1.99, Revision 2 when the limiting material of the vessel is not in the surveillance program.

One of these approaches, the Margin Reduction Approach (MRA), would use the plant specific surveillance data to reduce the margin to be added to the predicted temperature shift.

The HRA does not give a sound technical basis for the proposed reduction factors, especially since the limiting material is not present in the subject or a host reactor vessel.

In addition, the HRA proposes a methodology that is not in accordance with the pressurized thermal shock rule.

Therefore, the staff intends to conduct no further review on Section VI. of CEN-405-P which describes the MRA.

If you have questions concerning this issue, please contact me at (301) 415-1495.

Sincerely, Origi.na] (signed by.

Leonard A. Wiens, Senior Project Manager Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Docket No. 50-335 and 50-389

Enclosure:

Request for Additional Information cc w/enclosure:

See next page Distribution Docket File PUBLIC St.

Lucie Rdg.

SVarga JZwolinski ALee KWichman OGC ACRS DOCUMENT NAME:

G:iSTLUCIEiSLPTS.RAI To receive a copy of this document, indicate in the box:

"C" = Copy without attachment enclosure "E" = Co y with attachment/enclosure "N" = No co y OFFICE PDII-3/PH y~

PD I I-3/LA Lifien BCIayton PDII-3/D FHebdon f

DATE 10/

9b10170215 9bi015 PDR ADOCK 05000335 P

PDR 10/15/96 10/

/9 OFFICIAL RECORD COP'I

~

REQUEST FOR ADDITIONAL INFORMATION The staff requires additional information in order to complete its review of the Florida Power and Light pressurized thermal shock (PTS) evaluation.

The submittal consisted of three parts:

"St. Lucie Unit 1 Reactor Vessel Beltline Materials End of License Assessment of RTpys" "St. Lucie Unit 2 Reactor Vessel Beltline Materials End of License Assessment of RTpys" Proprietary and non-proprietary copies of the Combustion Engineering Owner's Group (CEOG) report CEN-405-P, Revision 3, "Application of Reactor Vessel Surveillance Data for Embrittlement Management" Responses to the following questions are necessary to complete the staff review of the submittal.

1)

Provide the actual cold leg temperatures for each cycle for both St. Lucie Unit 1 (SL-1) and Beaver Valley Unit 1 (BV-1) in support of the integrated surveillance approach.

Page A-7 of the submittal discusses "nominal inlet temperatures" as listed in the UFSAR and "assumed cold leg temperatures."

The actual cold leg temperatures for each cycle are needed for both units in order for the staff to determine the applicability of the BV-1 surveillance data to the SL-1 reactor vessel.

2)

Determine if there are other initial test data (Charpy, Drop Weight and RT>><<

values) for heats

305424, 90136,

83642, 83637 and 3P7317.

ProvMe a listing of each initial reference temperature

value, including the source of the data.

If other data are available, justify the initial reference temperature values that appear in Table 4 (page A-14) and Table 2 (page B-5) of the submittal for the heats listed above.

3)

Provide the neutron flux for the BV-1 surveillance capsule and the SL-1 vessel to clarify the conclusion that the neutron flux values are within an order of magnitude of each other.

4)

Provide details on the equivalence of the BV-1 neutron spectra to that of SL-1 to quantify the conclusion on page A-6 of the submittal that "the irradiation behavior of the BV-1 surveillance specimen [is]

therefore comparable to the SL-1 limiting weld material."

ENCLOSURE

Mr. T. F.,Plunkett Florida Power and Light Company ST.

LUCIE PLANT CC:

Jack Shreve, Public Counsel Office of the Public Counsel c/o The Florida Legislature 111 West Madison Avenue, Room 812 Tallahassee, Florida 32399-1400 Senior Resident Inspector St. Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.

Hwy A1A Jensen

Beach, Florida 34957 Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 J.

R.

Newman

Morgan, Lewis

& Bockius 1800 M Street, NW.

Washington, DC 20036 John T. Butler, Esquire

Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. Thomas R.L. Kindred County Administrator St. Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. Charles

Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Regional Administrator Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 H.

N. Paduano, Manager Licensing

& Special Programs Florida Power and Light Company P.O.

Box 14000 Juno

Beach, Florida 33408-0420 J.

A. Stall, Site Vice President St.

Lucie Nuclear Plant P. 0.

Box 128 Ft. Pierce, Florida 34954-0128 J. Scarola Plant General Manager St.

Lucie Nuclear Plant P.O.

Box 128 Ft. Pierce, Florida 34954-0128 Mr. Kerry Landis U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323-0199 E. J.

Weinkam Licensing Manager St. Lucie Nuclear Plant P.O.

Box 128 Fort Pierce, Florida 34954-0128