ML19345A277
| ML19345A277 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/22/1976 |
| From: | Wambach T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8011180495 | |
| Download: ML19345A277 (5) | |
Text
{{#Wiki_filter:I 4* ( r UNITO STATES N2-{ '8 e NUCLEAR REGULATORY COMMISSION y* W ASHINGTON, D. C. 20566 g = g ,f e ~.- DOCKET N0.: 50-29 DATE: September 22, 1976 ].r
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Yankee Atomic Electric Company (YAEC) LICENSEE: _.w.... - FACILITY: Yankee-Rowe(YR) [ ~ 14, 1976, TO DISCUSS THE NEED
SUMMARY
OF MEETING HELD ON SEPTEMBER FOR ONSITE TESTING TO ENSURE THE PRESENCE AND DISTRIBUT[ RACK EXPANSION AT MATERIAL INCORPORATED IN THE PROPOSED SPENT FUEL YANKEE-ROWE v: On September 14, 1976, representatives of YAEC met with the NRC staff 25, 1976 letter expressing a need for onsite to discuss the NRC August testing to verify that the Boral poison strips are present in the Spent Fuel Racks that are to be added for additional storage capacity A list of attendees is enclosed as Attachment 1. i at Yankee-Rowe. Significant points are discussed below. YAEC stated that their objective for the meeting was.to convince the ~ =..; NRC staff that onsite testing was not necessary because of the extensive Quality Assurance Program utilized for the procurement and fabrica' tion a of the Spent Fuel Racks together with the conservatism of the design as They stated they would demonstrate from the results of their analyses.that th to complete the installation of the racks by the next refueling in ...... = = May 1977 or they would not be able to unload a full core subsequent to
- .x that refueling.
First, YAEC described their Quality Assurance for fabrication of the fuel racks, the significant points of which are given on Attachment 2 to this su-mry, a handout at the meeting. In response to NRC questions, YAEC C and the Boral sheets. described also the Qaulity Control for the B4 This included certifications received from the B4C supplier, sample =- analysis of Aluminum powder - B C mix both by the fabricator and 4 independent analysis, and sample analysis from pressed sheets both byNRC the fabricator ind independent analysis. Assurance Program for the B4C and Boral sheets be submitted on the Yankee-Rowe docket to supplement the fabrication Qaulity Assurance Program. The presented the results of their subcriticality analyses. Then YAEC If it is assumed that 50% of the K= for the present design is 0.778. Boral strips are missing uniformly throughout the racks (i.e., only one strip would be in place between each row and column), the K= is 0.927, However, the NRC criterion would still within the NRC required 0.95. not be satisfied if all the Boral were missing in a localized area of the
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(' ( . -... = Meeting Sumary for Yankee-Rowe September 22, 1976 1 YAEC stated that the probability of half of the poison strips ~ Pool. being missing should be acceptably low based on their extensive Quality
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Assurance Program. YAEC did not think there was any need for onsite testing to verify the =m. YAEC susgested that, if NRC insisted on a presence of the Boral strips. test, they could weigh the modules (approx. 14,000 lbs.). YAEC stated b ~ that using a neutron source and detector in each storage position would at best show that one poison strip was in place. They also gave an =% = estimate of $100 per storage position for time and manpower to perfom such testing. This was based on 5 or 6 people for the test and one half
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=..;. ~ hour per storage position for a total labor cost of approximately $30,000. ...;[: They could give no estimate for the cost of the test setup because they T.;;. had not given it enough thought. h: NRC then stated that if the added assurance that the recessary poison r= =r was in place could be gained at a not unreasonable cost by onsite testing, then onsite testing should be perfomed. NRC asked that YAEC investigate f onsite testing in more detail and propose testing which could ensure that the necessary amount of Boral poison was in place. YAEC should document the associated analysis that establishes that the amount of Boral ~~.= verified results in a K= of less than 0.95. The analytical results presented at this meeting appeared to be appropriate using the 50% Boral ~ NRC stated that spot checking each uniformly distributed in the racks. storage position face (by a themal peutron source and detector system) ... = combined with the QA Program would provide adequate assurance that the Lccessary Boral was in place and that the conservatism of their design, should be documented by formal submittal of their analytical results I. demonstrating what the necessary amount of Boral is to meet the require-ment of a K= less than 0.95. mL Y$4 YY~ v Thomas V. Wambach, Backup Project Manager Operating Reactors Branch #1 ~~ Division of Operating Reactors
Enclosures:
~ 1. List of Attendees 2. Quality Assurance Program for Spent fuel Rack Poison Placement .cc w/ encl: See next page
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( Att Sment 1 ' = ~ ~ LIST OF ATTENDEES FOR MEETING WITH YANKEE ATOMIC _ SEPTEMBER 14, 1976 M kee Atomic fi: J.R. Hoffman l E. E. Pilat D. Denver [;_. f ' *.^ NRC j.. J. Conway B. Buckley . irs E. Lantz W. Butler B. Russell t -- T. Wambach A. Schwencer ( -( T 1;;;;; .,2 m V.g YANKEE ATOMIC ELECTRIC COMPANY 65 =E ; QUALITY ASSURANCE PROGRAM FOR SPENT FUEL RACK POISON PLAC ~ - EACH CAVITY HAS A UNIQUE SERIAL NUMBER - EACH POISON-STRIP IS TRACEABLE TO THE SHEET IT IS CUT FROM - EACH CAVITY NUMBER, THE POIS0N STRIP SERIAL 7] NUMBERS AND ITS POSITION IN THE COMPLETED RACK IS ,g =~ RECORDED ON A DRAWING WHICH IS PART OF THE FINAL DATA PACKAGE - AS AN INDEPENDENT CHECK, EACH COMPLETED CAVIlY IS +- WEIGHED TO COMPARE AGAINST STANDARD WEIGHT OF ONE EMPTY CAVITY AND EIGHT STRIPS OF POISON MATERIAL - THE AVERAGE WEIGHT OF ALL CAVITIES IS 136 LB, WITH A RANGE OF 133-138 1/2 LB. THE WEIGHT OF ONE. " SIDE" 0F POISON IS 15 LB; THUS NO POISON COULD HAVE BEEN OMITTED. ? 1 7 7 '
00 (...!., t, f. = Meeting Sunmary for Yankee-Rowe September 22, 1976 ps, '.. i..-{..s..f. .+. ?: =:: ..M' V. A. Moore cc: Licensee
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G. Knighton NRC PDR B. Yo ingblood .,. =,,..... LOCAL PDR T ORB #1 Reading W. Regan B. C. Rusche R. H. Vallmer Jf Ri= D. Bunch E. G. Case J. Collins R. Boyd
- .5 R. Heineman W. Kreger
~ ~ ~ V. STello M. L. Ernst R. Ballard H. Denton ss D. J. Skovholt M. Spangler su... W. P. Gamill P. Collins C. Heltemes J. Stepp ~= L. Hulman R. Houston I== R.' P. Denise T. J. Carter S. M. Sheppard
- =.Z T. Speis
~ _::= R. Clark OR PM ~~ D. B. Vassallo R. Fraley, ACRS (16) y J. Stolz OI&E(3) u= K. Kniel OELD 9 Principal Staff Participants
- 0. Parr S. VArga R. R. Maccary bec:
T. B. Abernathy, TIC J. R. Buchanan, NSIC r-J. Knight S. Pawlicki I. Sihweil g D. J. Ross p P. Check p T. Novak Z. Rosztoczy R. L. Tedesco V. Benaroya G. Lainas T. Ippolito K. R. Goller D. Ziemann G. Lear R. Reid D. G. Eisenhut L. Shao R. Baer W. Butler B. Grimes r:- e m ..7lJ -,,. _}}