ML20210T108
| ML20210T108 | |
| Person / Time | |
|---|---|
| Site: | Satsop |
| Issue date: | 12/19/1975 |
| From: | Maccary R Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1662 NUDOCS 8605290728 | |
| Download: ML20210T108 (5) | |
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acopensible Breesh med Teoksisel Bortseeres A F. Charey, F. Y. Glas Requested coupletisa Date: 1/5/78 Somerspados of neopease: Safety Bueleetten esport Seetsen 3.6 l ;,
Review Status: Under Review Siamo the write up of the WB M impot an Aegnet 38,19FS. the app 1Seest hee enheitted ( sore *= to the PSAR (up to Amandamot 36) een e' topieel report ETR-1002. These sehmittele teve ehemsed the statue of;the asa-CESSAR eyes items for this pleet sa Gne 8s11 ewing useners r
Section 3.6 g.
l (1) The applimmat has referseeed a top 1&ol report ETR-1002 entitled g '..y
" Design ceasiderettoes for the Proteesten fuem the W 9est of Fipe Rapture." This report has been deems 11y eutadsted to M C ht..
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MECHANICAL ENGINEERING BRANCH DIVISION OF TECHNICAL REVIEW WASHINGTON NUCLEAR PROJECT No. 3 & No. 5 g
SAFETY EVALUATION REPORT 3.6 Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping
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With respect to piping systems located inside containment, the applicant states that the criteria to be employed for determination of the systems which are evaluated, the locations and types of piping breaks which are postulated, and the protection measures against pipe whip to be provided, will be consistent with the acceptable criteria of Regulatory P
Guide 1.46, " Protection Against Pipe Whip Inside Containment."
The methods used for formulating the hydro dynamic forcing functions induced by postulated pipe rupture and the dynamic analysis for the resulting pipe whip motion provide an acceptable basis fbr restraint design. The use of these methods will provide reasonable assurance that the containment structure, unaffected system components, and those systems important to safety which are in close proximity to the systems in which postulated pipe failures are assumed to occur, will be l
protected. These provisions for protection against the dynamic effects associated with pipe ruptures and the resulting discharging coolant, provide reasonable assurance that, in the event of the combined loadings q imposed by an earthquake of the magnitude of the safe shutdown earthquake and a concurrent single pipe break at one of the design basis break N
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I locations, the following conditions and safety functions will be accommodated and assured:
(a) the magnitude of a design basis loss-of-coolant accident cannot i
be aggravated by potentially multiple failures of piping, and (b) the reactor emergency core cooling systems can be expected to
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perform their intended function.
The criteria used for the identification, design, and analysis of pip ing systems inside containment where postulated breaks may occur constitute an acceptable design basis in meeting the applicable requirements of Criteria 1, 2, 4, 14, 15, 31 and 32 of the NRC General Design Criteria.
With respect to piping systems located outside containment, the applicant will designate design basis break locations throughout all high energy piping systems. These postulated break locations will be chosen on the basis of highest relative stress, or significant changes in flexibility of the piping. The protection to be provided against the dynamic effects of postulated pipe breaks and discharging fluids in piping systems containing high energy fluids and located outsidc the containment is adequate to prevent damage to structures, systems and components to the extent considered necessary to assure the maintenance e
of their structural integrity. Such protection will provide reasonable assurnace that the safe shutdown of the reactor can be accomplished and maintained as needed.
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In addition, for those piping systems not considered as high energy systems, the applicant will postulate sufficient leakage cracks to assure that I
essential equipment and components are protected from fluid spraying, flooding, and consequent environmental conditions developed. This is consistent with criteria set forth in U. S. Nuclear Regulatory Commission Standard Review Plan 3.6.2.
The applicant has submitted a topical report, ETR-1002 " Design Consideration for the Protection f rom the Effect of Pipe Rupture", which defines in more detail criterin which will be used in providing protection for postulated pipe ruptures including the analytical methods employed to assess the consequence of the postulated events. The report is presently under review. Tite resolution of this item will be reported on in a supplement to this Safety Evaluation Report.
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