ML19329D695
| ML19329D695 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 11/30/1976 |
| From: | Zwetzig G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003160314 | |
| Download: ML19329D695 (4) | |
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NUCLEAR REGULATORY COMMISSION 7
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November 30, 1976 DOCKETS NOS.: 20-269/270/287/289/,302/312/313/320/346 VENDOR:
B. BC0CVs & WILC0X COMPANY (B&W)
FACILITIES:
OCONEE 1, 2, AND 3 RANCHO SECO-1 ARKANSAS NUCLEAR ONE-1 THREE MILE ISLAND 1 AND 2 DAVIS-BESSE 1 CRYSTAL RIVER -3
SUMMARY
OF MEETING HELD ON NOVEMBER 3, 1976, TO DISCUSS B&W'S PROPOSED REACTOR VESSEL INTEGRATED SURVEILLANCE PROGRAM On November 3,1976, representatives of B&W and some of the cwners of B&W reac:crs met with the staff to discuss several matters related to surveillance of B&W reactor vessels including a possible Integrated Surveillance Program for reactor vessel materiais. A list of attendees is attached.
Holder Tube Status The first topic discussed was the status of the redesigned Surveillance Specimen Holder Tubes (SSHT's).
B&W reported that redesigned SSHT's had been installed at Davis-Besse 1 and Crystal River 3.
The acceptability of the new design is being tested during the Hot Functional Test currently underway at Davis-Besse 1.
Reports describing the new design and the instrumentation to be used during the tests at Davis-Besse 1 have been submitted to the NRC for review.
B&W plans to request a meeting with the staff to discuss the results obtained from the Davis-Besse 1 tests as soon as the results are available.
Integrated Reactor Vessel j'rveillance Program The next topic discussed was a contemplated Integrated Reactor Vessel Surveillance Program (IRVSP) for B&W 177 fuel assembly reactors.
B&W representatives stated that the IRVSP would be discussed in a generic sense only and askcd that the record reflect that no utilities have yet comitted to the program.
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Meeting Summary for Novomber 3,1976 As background for the program, B&W reported the projected times at which tt 2 vessels at the various B&W plants would reach an upper shelf energy of 50 ft-lbs.
In many cases it appeared that this limit would be reached well before the end of reactor life.
Per 10CFR50, Appendix G, Paragraph V.C., when this limit is reached, additional measures are required to assure continued reactor vessel integrity. One of these measures is the performance of a fracture analysis for the vessel in question.
B&W noted that because only limited experimental data are currently available for use in such an analysis one of the objectives of the IRVSP was to include specimens which would be useful in developing additional experimental data. B&W also described how the data could be used in fracture mechanics analyses.
B&W next reported that information developed over the past year on the effects of copper and phosphorus impurities on weld sensitivity leads them to the conclusion that all limiting welds in B&W vessels are not represented in the current sets of sur-veillance specimens.
Accordingly their plan for an IRVSP also includes provisions for replacing some of the current specimens which do not represent limiting welds with specimens which do.
Staff questioning clarified the fe at that the IRVSP being discussed by B&W at this meeting differed fra the IRVSP's previously requested by Arkansas-1 and Rancho Seco.
In those requests there was no sub-stantial change in the makeup of the surveillance specimen sets from those initially installed in these reactors.
B&W described three testing alternatives they were considering to develop additional fracture toughness data:
1.
Research oriented capsules in the reactor vessel surveillance progran.
2.
Test reactor irradiation program.
3.
Combination of test reactor and operating reactor irradiation.
B&W then described the composition of the capsules that would be employed, hcw the capsules would be utilized in an integrated Reactor Vessel Surveillance Program for the various testing alternatives, the schedule by which data would be available, and the advantages and disadvantages of each testing option.
The description also addressed how B&W's definition of the needed exposure data could be obtained without exposing any specimens in Crystal River 3 during its first operating cycle.
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l-fleeting Sumary for 3-
!!ovember 3,1976 l-Surveillance Speciren !! alder Tu5e Installation i
l BfM described the procedure which would be followed in installing redesigned SSHT's in irradiated racctors.
This would involve l
removal of all fucl froa the reactor to the spent fuel storape l
pool and re:.. oval of the core su? port structure fren the vessel j
to the internals storage stand in the fuel transfer canal.
Utilizing l
water shielding, the holder tubes would then be installed under-l
-water using long-handled, specially designed tools operated from platforms and bridges above the water shielding.
Sfi.1 also described l
some of the problens involved in the installation, such as drilling l
and tapping blind holes in the core barrel, shir.aing to obtain proper alignment, etc.
B1U stated that to date they have only de-veloped a fraction of the tcols required for the installation.
They also expressed thqir view that all needed irradiation data could be obtained frca DEU plants about the startup so that there was no need I
to install the holders in irradiated plants.
theded Acticn i
BT3! stated that the folicwing action was needed:
I 1.
HRC permit operation of Crystal River-3 during first cycle without surveillance speci: ens.
2.
"PC approve integrated surveillance prograa at Davis-Cesse, THI-2 and Crystal River-3.
3.
IIRC indicate licensing usefulness of specimen irradiation data from test reactors.
t 4.
EfM to supply cdditional inforcatien on proposed integrated surveil-I lance prograu on a generic basis until such inforc.ation is needed i
on a spccific docket. DUl will also schedule a neeting with the
!!RC in the near future on the subject of neutron fluence prediction.
l The staff advised Bl.N that~ items 1 and 2 were currently under active
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review and that. item 3 would'be studied.
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i G. B. Zwetaig, Project Pan ver Operating Reactors Branch M I
Division of Operating Reactors 1
Attachnent:
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MEETING WITH B&W NOVEMBER 3,1976 B&W ACRS W. J. Keyworth E. G. Igne L. H. Bohn C. D. Thompson Consumers Power Company A. L. Lowe, Jr.
A. F. Eckert A. John Birkle E. O. Hooker C. E. Barksdale Arkansas Power & Light R. R. Steinke K. E. Suhrke Donald A. Rueter D. H. Roy Garry G. Young Duke Power _
R. O. Sharpe Meted J. J. Moran Florida Power Coro.
J. Alberdi J. T. Rodgers NRC D. K. Davis G. B. Zwetzig W. E. Converse R. P. Snaider D. Neighbors R. Reid R. Klecker P. Randall V. Noonan J. R. Hawthorne P. A. Kiefer J. E. 0uzts J. A. Dyer K. C. Hoge L. Shao W. Hazelton
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