ML20004D029
| ML20004D029 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/02/1981 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 NO-81-960, NUDOCS 8106080213 | |
| Download: ML20004D029 (5) | |
Text
{{#Wiki_filter:* Dd gJ Carciina kwer i..;nt Ocmeany June 2,1981 File: NG-3514(B) NO-81-960 s ep ~ Office of Nuclear Reactor Regulation th ,h. s ATTENTION: Mr. T. A. Ippclito, Chief ,E Operating Reactors Branch No. 2 y $ 0 0 g S 1 P ' -10 i g,g[g United States Nuclear Regulatory Commission p. Washington, D. C. 20555 \\.5 ^ w BRUNSWICK STEAM ELECTRIC PLANT UNIT NO. 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 RELIEF REO.UEST FROM CERTAIN IN-SERVICE INSPECTION REQUIREMENTS
Dear Mr. Ippolito:
Summary This letter requests relief from performing certain Category l "B-D" volumetric examinations required per ASME Section XI, Winter 1974 l edition with the Summer 1975 addenda. This relief is being requested on a one-time basis for the April, 1981 Brunswick Unit No. 1 outage. The Category "B-D" examinations being deferred will be performed during l the 1982 Brunswick Unit No. 1 refueling outage (Reload 3) by mechanized ultrasonic examination. Justification for the postponement of these examinations is given below. Discussion Manual ultrasonic examination of certain ASME Class I welds had been scheduled to be performed during the Brunswick Unit No. 1 April, 1981 outage. Performing examinations of these scheduled Class I l welds would have brought the completed examinations up to the per-l centages required per ASME Section XI Code for the first inspection period of Brunswick Unit No. 1. Among these scheduled examinations were certain Category "B-D" welds (full penetration welds of nozzles in vessels). It was anticipated that, even though this outage was not a refueling outage, the radiation levels at the nozzles would be low enough to permit the required examinations to be performed manually. However, once the insulation and shielding had been removed to obtain access to the examination areas, it was found that the radiation levels were much higher than anticipated. The radiation levels of the sche-duled Category "B-D" examination areas were monitored from 7 to 40 R on contact. (A copy of the radiation level surveys is attached for your information.) At this time it was decided that from an ALARA view-l point, the examinations could not be performed. Because of this deci- [g i sion, we requested that Southwest Research Institute, the original Id y / s
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contract preservice inspection group, review the preservice inspection data for the Category "B-D" examination areas and determine if there were any significant indications which could lead to propagation. The results of that review are attached and indicate that no significant indications were found. Specific Request The examination areas for which specific schedule relief is required are nozzles N8A & N8B (4" jet pump instrumentation) and NilA & N113 (2" instrumentation). In addition to these nozzles, we are also requesting relief for five welds on the three-inch diameter control rod drive discharge line which were to be inspected during the April, 1981 outage per the requirements of NUREG-0313, Revision 1. The radiation levels on this line are between 5 and 30 R/ hour. Schedule Once the ALARA problems became known, this issue was dis-cussed by plant management personnel with Mr. J. Blake of Region II of the NRC and with Mr. C. Metcalf of Kemper Insurance who is the authorized nuclear inspector. Following these discussions, the current program of postponing certain examinations until the Reload 3 refueling outage, when they will be performed using mechanized equip-ment, was adopted. Please advise us if you do not concur with this plan. Please contact my staff should you have any questions regarding this information. Yours very truly,
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f.E.Utley i y E j Executive Vice President Power Supply and Engineering & Construction l CSB/je (7127) l Attachments cc: Mr. J. P. O'Reilly Mr. D. F. Johnson 1 ~, _. _.. - -.
'S OUT H WE ST RE S E A R C H INS TIT UTE eos r oss.c s caawen :mo s=o cus.sn ea a s.o s * = =>.ro m o. r u e s m s4 - is m en.u i s cun e.s.w srs a4 reu.s w.1 e.m rce: w nu c May 20, 1951 Doc. No. 17-5162(34) Mr. C. 1. Dietz General Ear.ager 3 runs -ick Stamm Ilectric ?! ant r Catelina Fever and Light Ccepany l P. O. Ecx 10429 ~ Southport, North Carolina 28461 ~
Subject:
E m matien of P,runswick Steam Electric Plant. Unit 1 Raactor Pre 4aure Vessel No==le-to-Vessel Welds
Dear Mr. Dietz:
I Dua to the high radiation exposurt levels experte:;ced at the 3rMck l Steam Electric Plant, Unit 1, Reactor Pressure Vessel (RFV) nozzle-to-vs.ssel velds. Carolina Power and Light Company (CP4L) requested relle.f l from the Nuclear Regulatory Comnasion (NRC) for the ar**17*tions of I these velds on the N8 and N11 nozzles. In order for the NRC to approve this request, the NHC has asked that the pee. service n r-n= tion (PSI) g data of all RPV cozzle-to-vessel velds be reviewed to determine whether indication.s vers observed at that time which would require periodic examination to verify that indication growth had not occurred. Er. Joe l M. Revett of CF&L has requested that Southwest Research Institute perform i this review. - This review has been performed and it was observed that only 04egres spot i indications unre recorded. No indications requiring p2riodie evaluation were obse Wed. If you have any que-stions or.ccuaents, please call. Sincerely. jf? cC W ~^ James M. Ageld [ Proj ect.Macsger Nuclear Inroe ti=n Engineeruz Section of En5 neerimg 5e. vices Department 1 bjm cc: Mr. Jce M. He%. RODR ORIGINAL Td3. M "h.. yL'- . c49 auro *>o c., r, s .,y. s --r--~~.
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