ML18019A337
| 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 FACIL:50-000 Shearon Harris Nuclear Power Plant~ Unit l~ Carolina AUTH BYNAME AUTHOR AFFILIATION 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:
DOCKET 05000000 RECIPIENT ID CODE/NAME'RR/DL/ADL NRR LB3 LA INTERNAL: ACRS 41 ELD/HDS 1 IE/DEPER/EPB 36 NRR ROE M.L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 20 NRR/DHFS/HFEBOO NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGN2 EXTERNAL: 24X DMB/DSS (AMDTS)
NRC PDR 02 PNL'RUEL'pR COPIES LTTR ENCL 0
1 0
6 6
0 1
1 1
1 1
1
?
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 3
3 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME NRR LB3 BC BUCKLEY'S 01 ADM/LFMB'E F ILE IE/DQAVT/QAB21 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32" NRR/DL/SSPB NRR/DSI/ASB NRR/DSI/CSB 09 NRR/DS I/METB 12 NR B
22 E
04 R
/MIB BNL (AMDTS ONlY)
LPDR 03 NSIC 05 COPIES LTTR ENCI.
1 0
1 1
1 0
1 1
1 1
1 0
1 1
2 2'
1 1
1 1
0 1
1 1
1 1
1 1
1 1
1 1
0 1
1 1
1 1
TOTAL NUMBER OF COPIES REQUIRED+
LTTR 52'NCL
F H
i';
CNK Carolina Power & LIght Company AUG 3 1>sss SERIAL: NLS-85-279 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)).
Attachment 1 provides a discussion of how the Code Cases willbe 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, ABC/3DK/ccc (17683DK)
Attachment A. B.
utter - Vice resident Nuclear Engineering R Licensing Cct Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
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
4
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 willbe 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 willbe selected for each analysis.
A combination of the two damping criteria willnot be used.
Code Case N-011 willnot be used for time history analysis.
Potential increased displacements from any reanalysis willbe reviewed to assure that they can be accommodated.
3ustification NUREG-1061, Volume 2, Section 2.2 provides a discussion of the acceptable level of quality and safety of Code Case N-Oll.
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 willresult in significant reductions in predicted pipe response.
This willresult in reduced cost when evaluating deviations between as-constructed piping and hanger systems, and the designed systems.
Additional savings willbe 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 willalso 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.
3ustification 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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