ML20248D735: Difference between revisions

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==SUBJECT:==
==SUBJECT:==
CRYSTAL RIVER UNIT 3 - HIGH ENERGY LINE BREAK (HELB) CRITERIA FOR ANALYSIS OF PIPING OUTSIDE CONTAINMENT The NRC staff has stated its position th0t the postulation of HELBs outside containment is based on the AEC letter from A. Gianbusso to applicants and licensees dated in December,1972. This remains the licensing basis for CR-3.
CRYSTAL RIVER UNIT 3 - HIGH ENERGY LINE BREAK (HELB) CRITERIA FOR ANALYSIS OF PIPING OUTSIDE CONTAINMENT The NRC staff has stated its position th0t the postulation of HELBs outside containment is based on the AEC letter from A. Gianbusso to applicants and licensees dated in December,1972. This remains the licensing basis for CR-3.
By letter dated March 31, 1989, Florida Power Corporation (FPC) submitted Impell Report 03-0920-1186, Rev. O, entitled Pi    J e Rupture Analysis Criteria Outside the Reactor Building (Impell reoort). In that su)mittal, FPC stated that it intends to use ANSI B31.1,1967, for determining the high stress locations while adopting the stress criteria for postulating breaks and cracks stated in Standard Review Plan (SRP) 3.6.2, Branch Technical Position (BTP) 3-1, Rev4 0 (1975),
By {{letter dated|date=March 31, 1989|text=letter dated March 31, 1989}}, Florida Power Corporation (FPC) submitted Impell Report 03-0920-1186, Rev. O, entitled Pi    J e Rupture Analysis Criteria Outside the Reactor Building (Impell reoort). In that su)mittal, FPC stated that it intends to use ANSI B31.1,1967, for determining the high stress locations while adopting the stress criteria for postulating breaks and cracks stated in Standard Review Plan (SRP) 3.6.2, Branch Technical Position (BTP) 3-1, Rev4 0 (1975),
and the elimination of arbitrary intermediate breaks, as permitted by SRP 3.6.2, BTP 3-1, Rev. 2 (1987). We had indicated that this was not acceptable for the following reasons:
and the elimination of arbitrary intermediate breaks, as permitted by SRP 3.6.2, BTP 3-1, Rev. 2 (1987). We had indicated that this was not acceptable for the following reasons:
: 1. The basis for the calculation of the highest stresses due to occasional and sustained loading prescribed in the Giambusso letter is the Winter 1972 Addendum to the 1971 Edition of ASME Section III, Subsection NC.
: 1. The basis for the calculation of the highest stresses due to occasional and sustained loading prescribed in the Giambusso letter is the Winter 1972 Addendum to the 1971 Edition of ASME Section III, Subsection NC.

Latest revision as of 13:54, 8 March 2021

Requests That Impell Rept 03-0920-1186,Rev 0, Pipe Rupture Analysis Criteria Outside Reactor Bldg, Be Revised & Modified to Include Listed Conditions,Per NRC Approval to Calculate High Energy Line Breaks,Per ANSI B31.1 1967
ML20248D735
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 09/28/1989
From: Silver H
Office of Nuclear Reactor Regulation
To: Wilgus W
FLORIDA POWER CORP.
References
NUDOCS 8910040382
Download: ML20248D735 (3)


Text

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%, *....p September 28, 1989 Docket No. 50-302 Mr. W. S. Wilgus Vice President, Nuclear Operations t.

Florida Power Corporation ATTN: Manager, Nuclear Operations Licensing P. O. Box 219-NA-21 Crystal River, Florida 32629

Dear Mr. Wilgus:

SUBJECT:

CRYSTAL RIVER UNIT 3 - HIGH ENERGY LINE BREAK (HELB) CRITERIA FOR ANALYSIS OF PIPING OUTSIDE CONTAINMENT The NRC staff has stated its position th0t the postulation of HELBs outside containment is based on the AEC letter from A. Gianbusso to applicants and licensees dated in December,1972. This remains the licensing basis for CR-3.

By letter dated March 31, 1989, Florida Power Corporation (FPC) submitted Impell Report 03-0920-1186, Rev. O, entitled Pi J e Rupture Analysis Criteria Outside the Reactor Building (Impell reoort). In that su)mittal, FPC stated that it intends to use ANSI B31.1,1967, for determining the high stress locations while adopting the stress criteria for postulating breaks and cracks stated in Standard Review Plan (SRP) 3.6.2, Branch Technical Position (BTP) 3-1, Rev4 0 (1975),

and the elimination of arbitrary intermediate breaks, as permitted by SRP 3.6.2, BTP 3-1, Rev. 2 (1987). We had indicated that this was not acceptable for the following reasons:

1. The basis for the calculation of the highest stresses due to occasional and sustained loading prescribed in the Giambusso letter is the Winter 1972 Addendum to the 1971 Edition of ASME Section III, Subsection NC.
2. The basis for the calculation of the stresses in SRP 3.6.2 BTP 3-1, Rev. 0 was the 1974 Edition of ASME Section III which incorporated the Winter 1972 Addendum. The equation for calculating the expansion stresses in this edition is different from the 1971 Edition and yields equal or higher stresses than those calculated using the equation in the 1971 Edition (which is also the same as that in ANSI B31.1,1967). Therefore, using the expansion stress formulation of ANSI B31.1,1967, and the stress criteria of SRP 3.6.2, BTP 3-1, Rev 0 is less conservative than using the expension stress formulation required by the BTP.
3. There are no specific provisions in ANSI B31.1, 1967 for the calculation of the moments ano stresses due to sustained end occasional loads. The actual method by which these stresses were determined at CR-3 is therefore unknown. In addition, the intensification factors which were specified for fittings other than those listed in ANSI B31.1,1967 are also unknown.

OFDI en 00403e2 s9 cme i i FDR ADOCK 05000302 F PDC

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Mr. W. S. Wilgus September 28, 1989 In view of these considerations and uncertainties we performed an assessment of the conditions under which stress calculations based on ANSI B31.1,1967 would be acceptable for HELB calculations. These conditions are summarized as follows.

a. Occasional loads include seismic and safety relief valve loads.
b. The moment components due to occasional and sustained loads are combined by absolute sum (if they are combined directly), prior to the calculation of the resultant bending moment.
c. The calculated bending stresses due to sustained plus occasional loads are amplified directly by the corresponding stress intensification factor for the fitting or location being evaluated.
d. Stress intensification factors for fittings not listed in ANSI B31.1,1967 are included and justified, as appropriate.
e. The corresponding stress criteria for HELB postulation are those listed in the Giambusso letter.

If these conditions cannot be met, then the postulation of breaks and cracks should be based on SRP 3.6.2, BTP 3-1 Rev. 0 (1975).

FPC has provided information in its letter of July 19, 1989 which states that its calculation of stresses based on ANSI B31.1,1967 conforms essentially with the conditions listed above. We find this acceptable, but we will require that the appropriate sections of the Impell report be revised and modified accordingly to include these conditions and state that they have been satisfied at CR-3.

We also find acceptable the proposed elimination of arbitrary intermediate breaks per SRP 3.6.2, BTP 3-1, Rev. 2 (1987).

Sincerely, Original signed by Harley Silver, Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:

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- Florida Power Corporation Generating Plant cc:

Mr. A. H. Stephens State Planning and Development General Counsel Clearinghou se Florida. Power Corporation Office of Planning and Budget l MAC - ASD Executive Office of the Governor l

P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee, Director Chairman.

Nuclear Plant Operations Board of County Commissioners

Florida Power Corporation Citrus County P. O. Box 219-NA-2C 110 North Apopka Avenue Crystal River, Florida 32629- Inverness, Florida 32650 Mr. Robert B. Borsum Mr. Rolf C. Widell, Director Babcock & Wilcox Nuclear Operations Site Support Nuclear Power Generation Division Florida Power Corporation 1700 Rockville Pike, Suite 525 P.O. Box 219-NA-2I Rockville, Maryland 20852 Crystal River . Florida 32629 Senior Resident Inspector Mr. Gary L. Boldt Crystal. River Unit 3 Vice President, Nuclear Production U.S. Nuclear Regulatory Comission Florida Power Corporation 15760 West Powerline Street P. O. Box 219-SA-2C Crystal River, Florida 32629 Crystal River, Florida 32629 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Administrator Department of Environmental Regulation Power Plant Siting Section

' State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 l

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