ML20214T248
| ML20214T248 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/28/1987 |
| From: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| To: | Mckenna E NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR FYR-87-55, NUDOCS 8706100175 | |
| Download: ML20214T248 (5) | |
Text
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Tel phons (617) 872-8100 TWX 710'380-7619 YANKEE ATOMIC ELECTRIC COMPANY Mk 1671 Worcester Road, Framingham, Massachusetts 01701
. YANKEE
~
May 28, 1987 FYR 87-55 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Ms. Eileen McKenna, Project Manager Project Directorate I-3 Division of Reactor Projects I/II
Reference:
(a) License No. DPR-3 (Docket No. 50-29)
Subject:
SEP Topic III-6, Technical Information
Dear Ms. McKenna:
The attached letter from Cygna Energy Services is being submitted in support of our response to specific questions raised by your technical consultant, Mr. Mark Russell of EG&G. The information contained in the attached letter was discussed by telephone and was found to be satisfactory to the staff and your consultant.
The analysis of the reactor and pressurizer head vent piping, mentioned on Page 2 of the Cygna letter was performed entirely by Yankee Atomic Electric Company.
As we reported by telephone, the maximum Equation 12 stress is 11,574 psi.
Equation 12 combines stresses due to deadweight, pressure, seismic inertia, and Seismic Anchor Motion (SAM). The seismic stress is based on Yankee Composite Spectra (YCS).
The allowable Equation 12 stress for this piping problem is 28,620 psi (1.8 S ).
Since the total stress is less than half the allowable doubling h
the YCS seismic stress to approximate NRC spectra level will not result in pipe overstress.
8706100175 870528 1
kg PDR ADOCK 05000029 P
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. United States Nuclear Regulatory Commission May 28, 1987 Attention:
Ms. Eileen McKenna Page 2 FYR 87-055 i-t This reactor and pressurizer-head vent piping problem was also discussed by telephone and found to be acceptable.
Very truly yours, 4
' YANKEE ATOMIC ELECTRIC COMPANY M
G. Papanic, Jr.
+
Senior Licensing Engineer Licensing CP/ljp
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Attachment 4
1 cc: USNRC Region I j
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2121 N. Cahfornia Blvd-, Suite 390, Walnut Creek. CA 94596 415/934-5733 May 15,1987 86063.039 Mr. Bruce W. Holmgren Yankee Atomic Electric Company 1671 Worcester Road Framingham, MA 01701
Subject:
Seismic Anchor Motion Stresses in Piping Yankee Rowe SEP Piping Job No. 36063
Dear Bruce:
Based on discussions held between Cygna, YAEC, and the NRC on May 5,1987 as well as discussions between Cygna and EG&G on May 13, 1987, we are providing a summary of the piping problems in question per EG&G's evaluation. The topic of discussion was the acceptability of certain safe shutdown problems for SAM loading.
Each problem previously classified as "not acceptable" may be dispositioned as follows:
Main Coolant Bleed - This problem is outside the VC and will be evaluated to NRC spectra and DC-1, Rev. 4 criteria.
Additionally, the Equation 12 stresses were compared to an allowable of 1.2S
- h RC Pump Vents - This problem is a cantilever and has no SAM stresses. The equation 12 stresses are as follows: gravity = 320 psi, pressure = 3920 psi, and YCS = 14300 psi.
RC Loop Bypass Vents - This problem is a cantilever and has no SAM stresses.
RC Loop Safety Valves - The line is tied back to the 5" bypass line. Relative motions are nonexistent and stresses are generally low.
Cygna has reevaluated the seismic portion of the line with it tied back to the bypass line. Equation 12 stresses, considering a doubled YCS stress for NRC loading, is below the 1.8S limit. The Equation 12 stresses are as follows: gravity =
h negligible, pressure = 740 psi, and YCS = 13500 psi.
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Mr. Bruce Holmgren 86063.039 May 15,1987 Page 2 Steam Generator Drains (SP-SG-2, -3) - These problems are cantilevers and have no SAM stresses.
Steam Generator Vents - These lines are anchored to the steam generator frame and have no relative displacements (SAM & TAM).
Steam Generator WRL - These lines are carbon steel.
Steam Generator Differential Pressure - The SAMs for this line are negligible. Displacements are on the order of 0.1".
Pressurizer WRL - The SAM stresses for both the upper and lower legs are low, about 15% of the thermal stresses. If doubled, the SAM stress can be combined with the thermal, TAM, gravity, and pressure stresses to meet Equation 14 allowables.
Pressurizer NRL - The SAM stresses in the upper leg are about 35% of the thermal stresses. At the lower leg's nozzle, the SAM stresses are about 50%
higher than the thermal stresses. In both cases, the SAM stresses can be doubled and added to the thermal, TAM, gravity, and pressure stresses to meet Equation 14 allowables.
Pressurizer Pressure - The line is currently qualified to Equation 13. The SAM stresses are low compared to the thermal stresses ( less than 10%). The SAM stresses can be doubled and added to the thermal, TAM, gravity, and pressure stresses to meet Equation 14 allowables. The Equation 12 stresses are as follows: gravity = 11240 psi, pressure = 1680 psi, and YCS = 20430 psi.
Reactor and Pressure Vent - Cygna did not have a detailed breakdown of stresses for this problem. YAEC will look into the calculation to determine its status.
Shutdown Cooling No.121 - This problem will be reevaluated for the revised VC spectra and SAMs.
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ers_ L' Mr. Bruce Holmgren 86063.039 May 15,1987 Page 3 We hope that this information is adequate to close out the remaining open items in the piping scope. If more information is necessary, please contact Darlene Leong or Nancy Williams.
Very truly yours, V b W cN S u M.N. Shulman Project Manager MNS/am cc:
Mr. D. LeFrancois (YAEC)
Mr. D. Fucito (YAEC)
Mr. T. Cheng (USNRC)
Mr. M. Russell (EG&G)