ML18057A437

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Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment
ML18057A437
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/31/1990
From: Slade G
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009060051
Download: ML18057A437 (35)
v • d • e


Text

  • i consumers Power GB Slade General Manager POWERINli MICHlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 August 31, 1990 Nucl.ear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

UPPER SHELF ENERGY IN REACTOR BELTLINE Consumers Power Company's July 16, 1990 response to NRC letter dated May 14, 1990 concerning upper shelf energy (USE) qualification of the Palisades reactor beltline material stated that recent analysis had resulted in the preliminary conclusion that the beltline material would be qualified (USE no less than 50 ft-lbs) until 2032. Thus, there would be no reason for Consumers Power Company (CPC) to qualify the material in accordance with Section V.C. of 10CFR50 Appendix G.

CPC's July 16, 1990 letter further states that the final results of our recent analysis would be submitted before September 1, 1990. The attachment to this letter is our recent analysis which concludes that the Palisades reactor beltline material USE will remain at greater than 50ft-lbs until the year 2032 - well beyond the scheduled end-of-plant life in the year 2011.

Gerald B Slade General Manager CC Administrator, Region III, USNRC NRC Resident Inspector-Palisades Attachment

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9009060051 900831 PDR ADOCK 050002~5 P PDC OC-0890-0402-NL02 A CMS ENERGY COMPANY

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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 LOW UPPER SHELF ENERGY MATERIAL IN REACTOR VESSEL BELTLINE (PLATE MATERIAL IN TRANSVERSE DIRECTION)

(FINAL)

August 31, 1990 33 Pages OC-0890-0402-NL02

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  • 0 AJ::t %* J
  • . Affected Revision Items Affected By This EA Yes No Required Identify* Closeout

.. Other EAs tf;J. 0 No EA--P-PT5-9o-o 11

2. Design Documents Elec E-38 through E-49 0 i:l
3. Design Documents Mech M259, M664, M665 0 1J 4.0 LICENSING DOCUMENTS 4.1 Final Safety Analysis Report (FSAR) 0 ll 4.2 Technical Specifications 0 ~

4.3 Standing Order 54 0 M 5.0 PROCEDURES 5.1 Administrative Procedures 0 ~

5.2 Working Procedures 0 ~

5.3 Tech Spec Surveillance Procedures 0 ct 6.0 OTHER DOCUMENTS 6.1 Q-List 0 )g

,.2 Plant Drawings 0 ~

6.3 Equipment Data Base 0 ~

6.4 Spare Parts (Stock/MMS) 0 ~

6.5 Fire Protection Program Report 0 L'il (FPPR) 6.6 Design Basis Documents 0 ~

6.7 Operating Checklists 0 Ill 6.8 SPCC/PIPP Oil and Hazardous Material Spill Prevention Plan 0 is 6.9 EEQ Documents 0 lfJ Do any of the following'~ocuments need to be generated as a result of this EA:

Yes No

1. Corrective Action Document? 0 TS Reference
2. Safety Evaluation? 0 Reference f¥l
3. EEQ Evaluation Sheet? 0 Reference l¥l Is PRC Review of this EA Required? 0 ~

ICompleted By ()*p~j~ Date S-(?.:2/ 90

  • Identify Section, No, Drawing, Document, etc.

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Proc No GRE-02 Attachment l Revision 2 Page 1 of 1 REACTOR ENGINEERING DEPARTMENT EA REVIEW CHECKLIST Review Step Comments Reviewer

1. Have the appropriate pro-cedural requirements been satisfied?
2. Was an appropriate design method used?
3. Are assumptions adequately described and reasonable?
4. Were the inputs correctly selected and incorporated into the design?
5. Are the acceptance criteria sufficient to allow verif ica-tion that design requirements have been satisfactorily accomplished?
6. Is the output reasonable compared to input?
7. Have the design interface requirements been satisfied?
8. Are the applicable codes, standards and regulations properly identified and are their requirements met?
9. Are the appropriate quality assuranc*rrequirements met?
10. Have apP,topriate certified computer!programs been used?
11. Is an FSAJl, Tech Spec, Tech Spec Basis, Design Basis Document or Procedure Revision required?

fm0486-000lb-91-154

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Proc No 9.11 Attachment 5 Revision 4 Page 1 of 1 TECHNICAL REVIEW CHECKLIST This check~fi~~provides guidance for the review of engineering analyses.

Answer que ',~:. s Yes or NO, or N/A if they do not Apply. Document all conments o~:. '10 form. Satisfactory Re so 1 ut ion of convnents and comp1et ion of this checklfst is noted by Technically Reviewed Signature on the Initiation and Review record block of form 3619.

(Y, N, N/A)

1. Are all constants, variables and formulas correct and properly applied? * {'
2. Are all inputs and assumptions valid and the Basis for their use documented?
3. Is Vendor Information used as inputs addressed correctly in the analysis?
4. If the analysis argument departs from Vendor N/A Information/Reconmendations, is the departure I justification documented?

5.

6.

Have the proper input codes, standards and design principles been specified?

Have the input codes, standards and design principles been t

properly applied? 1 fQ..

7. Has the use of engineering judgement been documented and justified? ic
8. Has the objective of the analysis been met?

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10.

Are all calculated values correct?

Are assumptions accurately described and reasonable?

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ll. Have administrative requirements such as numbering and format been satisfied? t

12. Have ag,;;1,1inor (Insignificant) ~rro~s b~en. id~ntified? If ~

Yes; I~~*fy on 3110 form and JUst1fy rns1gn1ficance.

13. Does ~~l)~1s involve welding? If Yes; verify the ~

followfrig information is accurately represented on analysis drawing(s).

  • Material Being Joined
  • Thickness of Material Being Joined
  • Appropriate Weld Symbology

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