ML18003B111
| ML18003B111 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/19/1985 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-85-137, NUDOCS 8504230425 | |
| Download: ML18003B111 (6) | |
Text
REGULATORY FORMATION DISTR IBUTIO Y
M (R IDS)
ACCESSION NBR 8504230425 DOC ~ DATE ~ 85/04/ 1 9 NOTARI'ZED NO, DOCKET FACIL:50-400 Shear on Harris Nuclear Power Planti Unit 1E Carolina 05000400 AUTH,NAME AuTHoR AFFILIaTION ZIMMERMANES;R, Carolina Power L Light Co.
RECIP ~ NAME RECIPIENT AFFILIATION DENTONEH.RE Office.- of Nuclear Reactor Regulationc Director
SUBJECT:
Forwards revised Page 2 to 850114 submittal re elimination of postulated pipe breaks in RCS primary loop<
DISTRIBUTION CODE:
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TITLE: Licensing. Submittal:
PSAR/FSAR Amdts 8, Related Correspondence NOTES:
RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL: ACRS 41 ELD/HDS1 IE/DEPER/EPB 36 NRR ROEEM ~ L NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/OSI/CPB 10 NRR/OS I/ICSB 16 NRR/DSI/PSB 19 NRR/OSI/RSB 23 RGN2 EXTERNAL: BNL(AMDTS ONLY)
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yO SQO Carolina Power & Light Company IIPR 1 rJ 1985 SERIAL: NLS-85-137 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.50-000 ELIMINATIONOF POSTULATED PIPE BREAKS
~ IN THE REACTOR COOLANT SYSTEM PRIMARY LOOP
Dear Mr. Denton:
In accordance with recent discussions between our staffs, Carolina Power R Light Company has revised page 2 of our previous submittal, NLS-80-517 dated 3anuary 10, 1985 on this subject.
The attachment to this letter is a substitute page 2 for the January 10 letter with revision bars in the right-hand margin identifying the areas changed.
The other pages of the 3anuary 10 letter and its enclosures remain as previously submitted.
If you have any questions on this subject, please contact David McCarthy at (919) 362-2010 or (919) 836-7715.
Yours very truly, SRZ/JDK/crs (1000NLU)
Enclosure S. R.
tmmerman Manager Nuclear Licensing Section Cct Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. J. Nelson Grace (NRC-RII)
Mr. Keith Wichman (NRC-MTEB)
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. J. H. Carpenter (ASLB)
Mr. 3. L. Kelley (ASLB) 8504230425 8504-19 PDR ADQCK 05000400 A
PDR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602 cpu/
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~a Mr. Harold R. Denton Page 2 Containing a Postulated Circumferential Through Wall Break") envelopes the site-specific parameters of the SHNPP Unit 1. The reports have been prepared in accordance with the NRC guidance delineated in Generic Letter 80-00 (which also documents the Staff's acceptance of WCAP-9558).
Sco e of Exem tion Re uest Elimination of consideration of postulated circumferential and longitudinal breaks in the RCS primary loop piping would have the following effects on the Shearon Harris design:
Eliminate the need to design for pipe whip, jet impingement, and the dynamic effects (including asymmetric effects) of reactor cavity pressurization and pr imary component subcompartment pressurization due to primary loop pipe breaks.
Eliminate the need for pipe whip restraints (including shims) and jet impingement shields on primary loop piping associated with the primary loop pipe breaks defined in the Final Safety Analysis Report (FSAR).
Eliminate primary loop loss-of-coolant accident (LOCA) dynamic effects and loading conditions on other structures including the primary system components, primary loop piping, maintenance access platforms, branch line piping, and branch line supports (branch line LOCA loads would be retained in the design basis).
Granting of the requested exemption would not affect the following:
Emergency Core Cooling System (ECCS) design bases.
Containment design bases.
Equipment qualification bases.
Engineered Safety Features systems response.
Design of RCS heavy component supports.
Granting of this exemption willresult in significant benefits in terms of cost savings attributable to construction/installation of restraints, shims, and deflectors, and will provide reduced occupational radiation exposure over the life of the unit. Removal of restraints (and shims) willallow for better insulation of the RCS piping thus helping to reduce containment heat loads.
Further, restraint (and shim) removal willreduce personnel exposures due to future plant inspection and maintenance activities. Our savings estimates are presented in Enclosure l.
Reference (2) indicates that the NRC acceptance of the leak-before-break concept on a case-by-case basis is predicated on the Applicant's leak detection capability to detect the leakage from the postulated through-wall crack utilizing the guidance of RegUlatory Guide 1.05.
The Shearon Harris Reactor Coolant Pressure Boundary Leakage Detection System has been designed consistent with the guidelines of Regulatory Guide 1.05 for detecting and monitoring leakage and is described in the FSAR Section 5.2.5.
The specific reports (WCAP-10699 and WCAP-10700) show that there is a large margin between
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