ML17325B051

Interim Acceptance Criteria for Safety-Related Piping Sys.

ML17325B051
Person / Time
Site:	Cook
Issue date:	12/09/1988
From:	Williams J AMERICAN ELECTRIC POWER SERVICE CORP.
To:
Shared Package
ML17325B050	List: ML17325B049 ML17325B051
References
PROC-881209, NUDOCS 8812130083
Download: ML17325B051 (5)

Text

AMERICAN ELECTRIC POWER SERVICE CORPORATION DESIGN DIVISION MECHANICAL DESIGN SECTION

~Scb 'ct Interim Acceptance Criteria for Safety Related Piping Systems Plant A licabilit Donald C. Cook Nuclear Plant Units 1 & 2 Ori inator Mech. es. g. En Date

~Arcval Mech. Des. Sec . gr.

8812130083 ADGCK 05000315 881205'DR P PDC

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1. 0 INTRODUCTION:

Donald,",C. Cook FSAR (hereinafter called FSAR, Ref.. 4) defines- design bases for various seismic category piping system. These bases provide sufficient safety margin for continued plant operation such that the plant safety is not compromised. However, during an evaluation of a specific plant condition, identified via a problem report, if the limits of the design bases for piping and its support systems are exceeded, operability of the piping system during a DBE will be assured by meeting the limits of these criteria (Note: Expeditious processing and 'nterim reportability requirements are defined in AEPSC Procedure GP 15.1). These criteria will provide justifications for continued plant operation. Modifications required to return the piping and support system within the design bases limits shall be made by the next refueling outage or sooner.

2.0 SCOPE

These criteria are applicable tc all safety re.lated piping and associated support systems of the Donald C. Cook Nuclear Plant.

3.0 CRITERIA

3.1 Pi in S stem Acce tance Criteria An analysis of the affected piping system shall be performed in accordance with ASME Section Service Level D limits (Equation 9) for loading III NC-3600

. condition associated with Design Basis Earthquake (DBE). Increased damping values as permitted by Code Case N-411 shall be used for DBE analysis.

S + S + SD < 2.4 S (Ref. 1, Appendix F)

Where S = Longitudinal Pressure Stress S

w

= Dead wt. stress plus stresses due to other Mechanical loads SD = Design Basis Earthquake Stress S = Material Yield Stress at Design Temp.

NOTE: For pipe sizes 2.5 inches and larger, use an allowable stress of 2.0 S in the above equation.

3.2 Pi e Su ort Acce tance Criteria 3.2.1 In addition to the support loads developed in 3.1, thermal loads and other applicable displacement induced loads (e.g. seismic anchor movements) shall be included to define design loads for each component support associated with

~ J 4

the piping system. These supports will then be evaluated in accordance with the limits prescribed in Appendix F (Ref. 1) subsubarticle F-1370.

3 ' ' For anchor bolts, use a factor of safety of 2 against ultimate shear and tension values, instead of the values given in Structural Design Standard SDS-88 which has large factor of safety. For catalog items, prorate load capacities based on a factor of safety of 2.

3 2 ' Manufacture's one time load capacity shall be used for hydraulic snubbers.

4.0 CONCLUSION

These criteria provide allowable values greater than the FSAR, however, these values are based on the current codes, standards and practices applicable to the design of Nuclear Power Plants.

5.0 REFERENCES

1. American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Codes, Section III, 1983 edition.

2. ASME code case N-411 (Approval date February 20, 1986)

3. ~ "Steel Construction Manual", American Institute of Steel Construction

4. Donald C. Cook Nuclear Plant, updated Final Safety Analysis Report (FSAR)