ML18019A337

Requests Authorization to Use Code Case N-411 for Revised Damping Values & Code Case N-397 for Response Spectra Peak Shifting.Discussion of How Code Cases Will Be Used & Justification for Use Encl

ML18019A337
Person / Time
Site:	Harris
Issue date:	08/21/1985
From:	Cutter A CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NLS-85-279, NUDOCS 8508290195
Download: ML18019A337 (6)

Text

J REGULA INFORMATION DISTRIDUTIO STEM (RIDS)

ACCESSION NBR: 8508290195 DOC e DATE: 85/08/21 NOTARIZED; NO DOCKET FACIL:50-000 BYNAME Shearon Harris Nuclear Power Plant~ Unit l~ Carolina 05000000 AUTH AUTHOR AFF ILIATION CUTTER~A.B~ Carolina Power L Light Co ~

RECIP.NAME RECIPIENT AFFILIATION DENTON,HE RE Office of Nuclear Reactor Regulationi Director

SUBJECT:

Requests authorization to use Code Case N-411 for revised damping values 8 Code Case N-397 for response spectra. peak shifting. Discussion of how code cases will be used 8 Justsfication for use encl, DISTRIBUTION CODE: 0001D COPIES RECEIVED:LTR ENCL SIZE'.

TITLE': Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME'RR/DL/ADL LTTR ENCL ID CODE/NAME LTTR ENCI.

0 NRR LB3 BC 1 0 NRR LB3 LA 1 0 BUCKLEY'S 01 1 1 INTERNAL: ACRS 41 6 6 ADM/LFMB'E 1 0 ELD/HDS 1 0 F ILE 1 1 IE/DEPER/EPB 36 1 1 IE/DQAVT/QAB21 1 1 NRR ROE M.L 1 1 NRR/DE/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13  ? 2 NRR/DE/GB 28 2 2' NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 NRR/DE/SAB 20 1 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEBOO 1 NRR/DHFS/LQB 32" NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DSI/AEB 26 1 1 NRR/DSI/ASB 1 1 NRR/DSI/CPB 10 1 1 NRR/DSI/CSB 09 1 1 NRR/DSI/ICSB 16 1 1 NRR/DS I/METB 12 1 1 NRR/DSI/PSB 19 1 1 NR - B 22 1 1 NRR/DS I/RSB 23 1 1 E 04 1 1 RGN2 3 3 R /MIB 1 0 EXTERNAL: 24X 1 BNL (AMDTS ONlY) 1 1 DMB/DSS (AMDTS) 1 1 LPDR 03 1 NRC PDR 02 1 1 NSIC 05 1 1 PNL'RUEL'pR 1 1 TOTAL NUMBER OF COPIES REQUIRED+ LTTR 52'NCL

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CNK Carolina Power & LIght Company SERIAL: NLS-85-279 AUG 3 1>sss Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-II00 REQUEST FOR APPROVAL OF CODE CASES N-Ol 1 and N-397

Dear Mr. Denton:

Carolina Power R Light Company (CPRL) hereby requests authorization pursuant to 10 CFR 50.55a(a)(3) for use of Code Case N-Ol 1 for revised damping values and Code Case N-397 for response spectra peak shifting (Summer 1980 Addendum of ASME Section III, Appendix N, paragraph N-1226.3(d)). provides a discussion of how the Code Cases will be used and justification for their use.

To support current SHNPP schedules, we request your response by September 20, 1985.

If you have any questions on this subject, please contact Mr. 3ames Kloosterman at (919) 836-8055.

Yours very truly, A. B. utter - Vice resident Nuclear Engineering R Licensing ABC/3DK/ccc (17683DK)

Attachment Cct Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. 3. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)

Wake County Public Library Mr. 3. L. Kelley (ASLB) 8508290195i85082i

'PDR

. ADOCK - 05000e0O,,'DR 411 Fayettevitte Street o P. O. Box 1551 o Raleigh. N. C. 27602 gaol li

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ATTACHMENT 1 I. Dam in Values for D namic Anal sis of Pi in The damping values in Code Case N-011 may be used as an option to the values given in FSAR 3.7.1.3 for response spectra analysis of piping. The N-011 values will be used for reanalysis of any system designed for seismic loads for 79-10 as-built reconciliation, plant modifications or support/snubber optimization. Either the damping values currently given in the FSAR 3.7.1.3 or Code Case N-011 will be selected for each analysis. A combination of the two damping criteria will not be used. Code Case N-011 will not be used for time history analysis. Potential increased displacements from any reanalysis will be reviewed to assure that they can be accommodated.

3ustif ication NUREG-1061, Volume 2, Section 2.2 provides a discussion of the acceptable level of quality and safety of Code Case N-Ol l.

The damping values in Code Case N-011 have been recommended by the PVRC Task Group on Damping and have been published in Welding Research Council Bulletin 300. These damping values reduce excessive conservatism in current requirements and will result in significant reductions in predicted pipe response.

This will result in reduced cost when evaluating deviations between as-constructed piping and hanger systems, and the designed systems. Additional savings will be recognized from these damping values by allowing the elimination of snubbers on existing piping and use of fewer snubbers and other seismic supports on piping added or modified by plant modifications. Reduced radiation exposure during Inservice Inspections will also be realized. Furthermore, overall reliability of the piping will be increased due to reduced probability of snubber failure and reduced thermal stress in new and modified piping due to fewer seismic supports. Since the original design of piping used the damping values in FSAR Table 3.7.2-16 for Class 1 piping systems (including reactor coolant loop) 12 inches and larger and Regulatory Guide 1.61 for Balance of Plant systems, there are still considerable conservatisms which can be considered as additional justification for using higher damping values.

II. Res onse S ectra Shiftin As an alternative to the method of spectra broadening for piping analysis described in FSAR 3.7.2.9 Code Case N-397 (Summer 1980 Addendum of ASME Section III, Appendix N, paragraph N-1226.3(d)) may be used.

3ustif ication NUREG-1061, Volume 2, Section 2.3 provides a discussion of the acceptable level of quality and safety of Code Case N-397.

(1768JDK/ccc)

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