ML18054B103

Forwards Interim Operating Criteria for IE Bulletin 79-14 Verification to Resolve NRC Concerns Noted in Insp Rept 50-255/89-24.Criteria Will Be Used to Make Operability Determinations Re Piping & Pipe Supports

ML18054B103
Person / Time
Site:	Palisades
Issue date:	11/13/1989
From:	Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18054B104	List: ML18054B103 ML19332B867
References
IEB-79-14, NUDOCS 8911210112
Download: ML18054B103 (12)

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NllCHl&AN"S PROGRESS General Offices: 1945 West Parnall Road, Jackson,' Ml 49201 * (517) 788-0550 November 13, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

INTERIM OPERATING CRITERIA FOR IE BULLETIN 79-14. REVERIFICATION By letter dated October 26, 1989, Consumers Power Company submitted an action plan to resolve NRC concerns identified during inspection 50-255/89-024.

In that submittal Consumers Power Company committed to develop and seek NRC approval of interim operating criteria to be used in cases where structural loads are found which exceed the FSAR code allowables during IE Bulletin 79-14 reverification. The Attachment contains the interim operating criteria.

These criteria are to be implemented for an interim period only. It is intended to implement modifications to resolve deficiencies and bring them within FSAR code allowables by the next refueling outage or sooner after identificatio~. The criteria proposed herein are provided for implementation with regard to all identified discrepancies involving piping and pipe supports at Palisades.

The stress analysis value of 2.0 S for the interim piping operability criteria is selected on the basis ~f prior NRC approval of this value for similar purposes. This allowable is adequate to ensure strain control when combined with linear elastic analysis methods and dynamic events which introduce limited energy input. The appropriateness of this limit has been substantiated by inelastic analysis methods and dynamic testing.

All discrepancies uncovered by NRC Region III Inspectors during the recent snubber reduction inspection and all discrepancies found during the Palisades Plant initiated 1989 maintenance outage IE Bulletin 79-14 sampling inspection 8911210112 891113 PDR Q

OC1189-0010-NL02 AI:*OC:K 05000255 PDC A OMS ENERGY COMPANY

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.' Nuclear Reg~latory .mmission 2 Palisades Nuclear Plant IE Bulletin 79-14 Reverification November 13, 1989 have been reanalyzed and found to be within the FSAR allowables or will be modified such that they will meet FSAR allowables prior to start up. The attached criteria will be used to make operability determinations on future discrepancies.

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Ralph R Frisch Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC1189-0010-NL02

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 CRITERIA FOR DETERMINING JUSTIFICATION FOR CONTINUED OPERATION WHEN-ENCOUNTERING DISCREPANCIES IN "AS-BUILT" SAFETY-RELATED PIPING November 13, 1989 8911210113 891113 PDR ADOCK 05000255 Q PDC 9 Pages OC1189-0010-NL02

CRITERIA FOR DETERMINING JUSTIFICATION FOR CONTINUED OPERATION WHEN ENCOUNTERING DISCREPANCIES IN "AS-BUILT" SAFETY-RELATED PIPING CONSUMERS POWER COMPANY.

PALISADES PLANT 0Cl 189-0010-NL02

TABLE OF CONTENTS PAGE

1.0 INTRODUCTION

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3.0 CONCLUSION

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4.0 REFERENCES

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1.0 INTRODUCTION

AND SCOPE These criteria are intended to provide the operability determination requirements for safety-related piping and associated supports if it is determined that stresses exceed allowables presented in the Palisades Plant Updated FSAR (Reference 1). These criteria permit operation for an interim period only. Modifications will be made which return the system to within FSAR allowables.

These criteria are intended to be used to expeditiously perform necessary evaluations to determine interim operability and not to delay appropriate actions.

2.0 CRITERIA 2.1 Piping Operability Criteria The piping analysis shall be in accordance with ANSI B31.1, 1973 Edition (Reference 2) with the load combination stress limit defined below *. The 1973 Edition of ANSI B31.1 is judged to be a comprehensive and updated consolidation of all of the requirements of earlier editions of B31.1 used at Palisades. This edition constitutes use of a single reference encompassing all licensing requirements and is compatible with current computer software used by Consumers Power Company. The design loading conditions to be applied in the analysis shall include the Safe Shutdown Earthquake.

OC1189-0Q10-NL02

I 2

Following are the pipe stress criteria for justifying continued operation of the plant:

(Ref. 2 Equation 11)

And

[SLP + SWT + SSSE ~ 2.0 Sy] (Ref. 2 Equation 12)

Where: s1 p = Longitudinal Pressure Stress SWT = Dead Weight Stress SSSE = Stresses Resulting From Safe Shutdown Earthquake S = Material Yield Stress (Reference 3 Appendices) y Code Case N-411 allows for increased damping values, independent of pipe diameter, for seismic analysis. Therefore, increased damping values, in accordance with Reference 4, will be acceptable when performing these analyses to meet operability. If the piping stress analysis exceed the value of 2.0 S , or pipe supports do not y

meet their operable limits (see Sect. 2.2), then additional iterative analysis of the piping may be required. The iterative analysis may OC1189-0010-NL02

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.. 3 use the knowledge that a support is not capable of withstanding* the loads, and can be removed from the analysis. The Code Case N-411 analysis will be an alternative analysis procedure to that of the original piping seismic design methodology. Analysis employing Code Case N-411 will be performed based upon the requirement of US NRC Regulatory Guide 1.84, Rev. 26. (Reference 5)

For cases where piping secondary stresses (stresses induced by restraint of free end thermal displacement, thermal anchor movements or seismic anchor movements) are determined to exceed FSAR allowables, a specific case by case approach will be used to determine interim operability.

2.2 Pipe Support & Hanger Operability Criteria As a first step in evaluating the support, a linear elastic analysis method will be used to determine the stress and forces in the support members. In addition to the loading in Section 2.1, the support loads must include pipe thermal loads, restraint of free end thermal displacement and anchor motion. The stresses and forces calculated for each support member shall be compared with the allowables in the FSAR, Chapter 5.10.1.2 criteria for the SSE (Reference 1) combination except as modified below.

OC1189-0010-NL02

4 A. Structural Steel Tension Ft = 1.20 Sy but

< 0.70 Su Bending Fb = 1.20 Sy but

< 0.70 Su Shear Fv = 0.72 SY but

< 0.42 Su Combined Stress For axial compression and bending or axial tension and bending, use AISC Paragraph 1.6., (Ref. 6)

B. Anchor Bolts Use Factor of Safety of 2 against ultimate tension and shear values.

C. Snubbers Hydraulic: Load < manufacturers one time load capacity.

Movement < total travel D. Springs Load within catalog range without bottoming out OC1189-0010-NL02

5 E. All remaining Catalog Items The maximum of the following:

1. Manufacturer's published faulted load rating.

2. When faulted allowables are not given and the factor of safety is specified in the catalog for the normal operating allowable, a design allowable shall be scaled to a safety factor of 2.

3. When the catalog item is designed to 831.1 and no safety factor is given, a design allowable twice the catalog value.

4. When test data is available, the design allowable shall have a safety factor of 2.0.

5. For a simple component item where an analysis can be performed, the allowable shall be 0.5.of the ultimate stresses or strength.

Where: Ft =Allowable Tensile Stress Fb = Allowable Bending Stress Fv = Allowable Shear Stress . I OC1189-0010-NL02

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6 SY = Specified Minimum Yield Stress at Temperature (See Note 1)

Su = Specified Minimum Tensile Stress at Temperature FS = Factor of Safety Note 1: Actual yield strength may be used where CMTR's are available for the material.

If a support fails using the linear elastic method, then a more refined analysis may be performed using plastic analysis techniques.

The plastic analysis will follow the design rules of ASME Section III9 Appendix F, (Ref. 1).

3. 0 CON CL US ION If the above criteria cannot be met, reportability per 10 CFR 50 must be evaluated and system operability requirements per Plant Technical Specifications must be evaluated and appropriate actions taken.

4.0 REFERENCES

1. Palisades Plant Updated Final Safety Analysis Report.

2. ANSI 831.1, 1973 Power Piping.Code.

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3. American Society of Mechanical Engineers, Boiler and Pressure Vessel Codes,Section III, 1983 Edition, through Winter 1985 Addenda.

4. American Society of Mechanical Engineers, Boiler and Pressure Vessel Codes, Case N-411, Dated 9/17/84.

5. US Nuclear Regulatory Commission Regulatory Guide 1.84, Design and Fabrication Acceptability, ASME Section III, Division 1, July 1989, Rev. 26.

6. "Manual of Steel Construction", Amer.ican Institute of Steel Construction, Inc., Seventh Edition, 1980. '

OC1189-0010-NL02

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