ML20210S784
| ML20210S784 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 05/07/1976 |
| From: | Maccary R Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1635 NUDOCS 8605290400 | |
| Download: ML20210S784 (3) | |
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.i boeket No.: 50-508,2509 MS No.: 27-112
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s R. C. DeYoung, 'Assis' tant Director for Light Water Reactors Division of Project Management WASHINGTON PU3LIC POWER SUPPLY SYSTEM. DOCKET NOS: 50-508, 50-509 Plant Name: Wohington Nuclear Project !b. 3 (WNP-3) & No. 5 (W'{F-5) f.
Docket Husbers: 53-503, 500 Licensing Stage: PSAR Responsible Branch & Project Manager: LWR 3 A. Bournia Responsible Si> Branch t, Technical Reviewer: MEB, F. Cherny. P. Chen Requested Coupletior. Date:
$--7-76 Description taf, Response: Supplseent to Safety Evaluation Report Review Status. Complete Attached as the MED input to ' this supplement is a response to the question raised,in the ACRS letter of 4-16-76 regarding the design of the reactor vessel' supports. The question relates to the geaeric concaru which has been raised.gbout theeaffects of the transient asymmetric differcutial prechure loanZ*that act on the reactor internals and around the exterior of i
thJ reactor vessel resulting from a postulated pipe rupture at a reactor vessel nozzle _ safe end.
Assurance must be provided that these loads are adequately acco6ated for in the design of the vessel supports.
Since the UPPSS 3 & 5 plants are CESSAR reference plants, we have assumed l
that the applicant will adopt the solution to this gesteric probler which has been cousaitted to by Combustion EngineerinR on the CESSAR docket. %c CE
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cous:itment has been addressed in section 3.9.1.5 of the CESSAR SER. and we noted this in our letter of 8-28-75 which transmitted the M13 input for SER acetions 3.6 and 3.9.2.5.
Ia'additioa. since that time, the LTPSS 3 T 5 applicait has addressed this h
subject in a letter to NRC datei 12-31-75.
'Ihe applicant ins provided du l '
acceptahle cocnitment that the WPPSS 3 & 5 vessel supports will be designed j
with the feferencel -loads taken into account.
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Since the applicant s letter does not refer specifically to CESSAR, we have referred only to the applicant's commitment in our attached input.
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2-Also, for clarifica tion,we note that the 4-16-76 ACRS Ictter reference.d above was transmitted to ME3 by }!r. A. Bournia's letter of 4-19-76 Lu DSS Branch Chiefs.
Mr. Bournia's letter provided recommendations as to vhieb. ' CSS branches might be involed in addressing specific questions raised in the ACRS letter. The Mechanical Engineering Branch was listed for providing responses to paragraphs 2, 6 and 7 of the ACES letter. We have determined that paragraph 2 should be addressed by MEB. This input is attached. The Structural Engineering Branch will address paragraphs 6 and 7 in separate correspondence.
R. R. Maccary, Assistant Director for Engineering ec:
R. E. Heineman, SS Division of Systesm Safety O. Parr, PM J. P. Knight, SS A. Bournia, FM
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}!ECHANICAL ENGINEERING BRANCH DIVISION OF SYSTEMS SAFETY WASHINGTON NUCLEAR PROJECT No. 3 and 5
' SUPPLEMENT TG SAFETY EVALUATION REPORT 5.2.1 Design 'of Reactor Coolant Pressure Boundary Components The ACRS in their letter of April 16, 1976 to NRC Acting Chairman M. A. Rowden stated that a generic questica has arisen concerning loads on the reacter vessel support structure for certain postulated loss-of-coolant accident.s in pressurized water reactors. The letter further stated that the matter should be resolved for WNP-3 and WNP-5 in a manner satisfactory to the staff.
By letter dated November 26, 1975 f rom O. D. Parr to J. J. Stein, we requested the applicant to verify that the final design procedures would account for transient asymmetric pressure loads on the reactor vessel supports.
In a letter dated December 31, 1975, from M. O. Strand to B. C. Rusche, the applicant stated that it is their intent that the final design of the reactor vessel support system vill take into account these asymmetric pressure loads in combination with appropriate LOCA and seismic loads.
The applicant further reated that the results of these analyses and the final desigr. parameters for the supports will be incorporated in the Final Saf ety Analysis Report.
We consider this to be an acceptable commitment, and, that accordingly, the design of the reactor vessel supports is acceptable for the constractior permit stage of review, t-l l
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