ML18066A355

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Dockets Supplemental Info in Support of Relief Request RR-13,in Response to Series of 981221 Telcons with Nrc.Util Will Incorporate Info Into Rev of Engineering Analysis EA-C-PAL-98-1939-01 & Submit Rev Under Separate Cover
ML18066A355
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/22/1998
From: Haskell N
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9812300295
Download: ML18066A355 (8)
v • d • e


Text

{{#Wiki_filter:~-- A CMS Energy Company Palisades Nuclear Plant Tel: 616 764 2276 27780 Blue Star Memorial Highway Fax: 616 764 2490 Covert, Ml 49043 Nathan L. Hallkall Director. Licensing December 22, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT SUBMITTAL OF SUPPLEMENTARY INFORMATION IN SUPPORT OF RELIEF REQUEST NO. RR-13 In a letter dated December 20, 1998, Consumers Energy Company submitted for NRC approval a request for relief from certain requirements of Section XI of the ASME Boiler and Pressure Vessel Code. In response to questions raised during a series of telephone conference calls on December 21, 1998, additional supplementary 

   *. information was transmitted by fax to facilitate staff review. The purpose of this letter is to docket that supplementary information.

Attachment 1 provides a brief discussion of reasons why seismic loading cases are not controlling in the analysis of Primary Coolant Pump casing bolt stresses. Attachment 2 discusses the additional casing bolt stress and fatigue considerations which would result from eccentricity due to bolt wastage. Consumers Energy will incorporate this information into a revision of Engineering Analysis EA-C-PAL-98-1939-01 and submit the revised analysis under separate cover. In addition to the technical information, Consumers Energy Company provided an additional commitment relating to methods of monitoring for Primary Coolant System leakage. That commitment is restated below. .[J<ULfl ' 1 1 9812300295 981222 ' PDR ***ADOCK* 05000255 _, P . PDR .:

  • 2

SUMMARY

OF COMMITMENTS This letter contains two new commitments and no revisions to existing commitments. The new commitments are:

1. The information provided in Attachments 1 and 2 will be incorporated into a revision of Engineering Analysis EA-C-PAL-98-1939-01. The revised analysis will be submitted to the NRC.
2. With the plant at steady state power, if a Primary Coolant System leak rate calculation indicates an unidentified leak rate in excess of 0.3 gpm, or the containment sump level trend indicated by the Plant Process Computer indicates a change in unidentified sump inleakage rate in excess of 0.2 gpm, a confirmatory Primary Coolant System leak rate calculation will be performed as soon as possible. If the confirmatory calculation verifies that the unidentified Primary Coolant System leak rate is greater than 0.3 gpm, and the reason for this leak rate is not understood, action will be initiated within 24 hours to place the plant in Hot Standby. Before the plant is returned to power operation, it will be verified that indication of leakage was not a result of significant additional degradation of Primary Coolant Pump P-50A.
      *~

athan L. Haskell rector, Licensing CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector - Palisades Attachment

ATTACHMENT 1 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 SUBMITTAL OF SUPPLEMENTARY INFORMATION IN SUPPORT OF RELIEF REQUEST NO. RR-13 DISCUSSION OF SEISMIC LOADING CASES IN ANALYSIS OF PRIMARY COOLANT PUMP CASING BOLT STRESSES

EA-C-P AL-98-1939-01

  • Seismic Design Considerations The initial seismic design of Palisades NSSS components was conducted in a very simplistic, static manner. In the 1986 time frame, Palisades elected to use the ASME Section III, Code Case N 411-1 damping in conducting seismic response spectrum analysis. This entailed using the response spectrum curves provided Palisades by the NRC via NUREG/CR 1833.

The implementation of these curves required the detennination of seismic anchor movements for piping attached to the primary coolant system. At about the same time, it was necessary for Palisades to detennine time history input to the reactor vessel in order to conduct nonlinear seismic analysis on the new fuel bundles. Each of these analysis demands required that the primary coolant system vessels and piping be decoupled from the stick building model for the development of an interaction model. The vessels themselves ( reactor vessel, steam generator, pressurizer and primary coolant pumps ) were characterized by stick* model members. This enabled the analysts to calculate seismic loads directly at critical cross sections. This experience demonstrated that the interaction of the primary coolant system components with the concrete internal structure was such that the combined system/structure (original lumped mass) model was adequate for overall structural response and the seismic loading as previously calculated by the static ZP A methods was acceptable. The seismic loading was very modest and noncontroling with respect to the other load cases and the siesmic anchor movements of the primary coolant components could be ignored. This is the basis for the conclusion that seismic loadings cases and combinations are not limiting in the analysis of primary system components.

ATTACHMENT 2 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 SUBMITTAL OF SUPPLEMENTARY INFORMATION IN SUPPORT OF RELIEF REQUEST NO. RR-13 CASING BOLT STRESS AND FATIGUE CONSIDERATIONS DUE TO ECCENTRICITY OF DEGRADED PRIMARY COOLANT PUMP CASING BOLTS 

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