ML20044C617
| ML20044C617 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/01/1993 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20044C618 | List: |
| References | |
| NLS-93-100, NUDOCS 9304090306 | |
| Download: ML20044C617 (5) | |
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i k r' N$1b IC'ME M*i h a m ":K:*4 2 Carolina Power & Light Company or==racrammanrcra April 1,1993 SERIAL: NLS-93-100 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REVISION TO DESIGN GUIDE FOR CIVIL / STRUCTURAL OPERABILITY REVIEWS (DG-il.20)
Gentlemen:
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The purpose of this letter is to submit to the NRC Revision 4 to Carolina Power & Light Company's (CP&L) Nuclear Engineering Department. Design Guide for Civil: Structural Operability Reviews, Design Guide Number DG-il.20 (Enclosure 1).
Revision 4 tt Design Guide Number DG-II.20 has incorporated recommendations f rom the third party review which we committed to perform in our July 23,1992 letter. These recommendations included consolidation of Civil / Structural Operability Criteria for CP&L nuclear operating f acilities into one document. Additionally, the recommendations of Generic Letter 91-18, "Inf ormation to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability" have been incorporated into the Design Guide. These recommendations included entena for other structural items in addition to piping and pipe supports.
Revision 2 of Design Guide DG-ll.20 was the basis f or an SER dated October 8.1992-This SER should be revised to reflect the operability criteria now contained in Revision 4 of the subject Design Guide. Attached f or your convenience is an outline of the significant 000023 p,,e \\ i l
93o4090306 930301 PDR ADOCK 05000324 p
i Document Control Desk NLS-93-100 / Page 2 I
changes to Design Guide DG-il.20 from Revision 2 to Revision 3 and from Revision 3 to Revision 4 (Attachment 1),
f Please refer any questions regarding this submittal to Mr. D. B. Waters at (919) 546 3678.
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Yours very truly, O
O D. C. McCarthy Manager Nuclear Licensing Section SHC/shc (DG-il20.000) i Attachment i
i Enclosure cc:
Mr. S. D. Ebneter i
Mr. P. D. Milano Mr. R. L. Prevatte l
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REVIEW OF DESIGN GUIDE DG-il.20 REVISIONS
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i Rev. 2 to Rev. 3 NOTES
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1)
Added Appendix 1 - Piping operability criteria by l
Stevenson & Associates 4
2)
Temporary condition time limit not to exceed next 1
Refueling Outage (RFO) 3)
Temporary conditions require 50.59 safety evaluation (except DTOP) 4)
No change in component / structure allowable stress limits 5)
Pipe Stress allowables:
Rev.2 Rev.3
.9 Sy 2.4 Sh 2.0 Sy 1
3Sm
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Rev. 3 to Rev. 4 1)
Cannot use PRA for Operability 2)
All operability reviews to be documented on EER's 3)
Temporary conditions at BNP to be reported to the STSI coordinator 4)
Added EFl's (Engineenng Follow-up items) 5)
Documents STSI criteria used for DTOP (M021) in Attachment D 6)
Piping allowable stresses unchanged except for additional firnit placed on Deadweight Stress Dwt <.9 Fy 3
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7)
Structural STSI criteria broken down into two categories (a)
Structural (Non Pipe Support):
I (1)
All stresses < 1.6 X normal allowable stresses 2.
(uses plastic section modulus)
(2)
Shear stresses < 1,4 X normal allowable shear stress 3
for Deadweight loading (b)
Mechanical (Pipe Supports):
Rev.3 Rev.4 Tensile
.9 Fy 1.2 Sy < 0.7 Su 1
~
Shear
.6 Fy
.72 Sy <.42 Su 1
Shear (Dwt only)
N/A
.55 Sy.
3 Bending - Compact Sect.
1.5 Fb <.9 Fy i x Sy where f = z/s 1
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- Non-compact 1.5 Fb <.9 Fy 1.11 Syl.79.002(bf /2ti)(SyP [
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Compression 1.5 Fa <.9 Fy
.67 X Critical Buckling 1
i Welds
.45 Su
.48 Su
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Bolts-Tension N/A Sy <.7 Su 1
Shear N/A
.6 Sy <.42 Su 1
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Component Std. Supt.
N/A 1.2 Sy/Ft <.7 Su/Ft 1
Snubbers N/A Attach. D U-Bolts N/A Attach. D EA3 Off-Axis Clamp N/A Attach. D Expansion Bolts F.S. = 2 F.S. = 2 1
Nelson Studs F.S. = 1.4 F.S. = 1.4 j
i NOTES 1
Criteria in accordance with Generic Letter 91-18 1
2 Criteria in accordance with Standard Review Plan i
3 Criteria more stringent than requirements of 1 or 2 1
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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 -
i NRC DOCKET NOS. 50-325 & 50-324 I
OPERATING LICENSE NOS. DPR-71'& DPR-62 DESIGN GUIDE FOR CIVIL / STRUCTURAL OPERABILITY REVIEWS DESIGN GUIDE NUMBER DG-il.20 f
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