ML18078A408
| ML18078A408 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/07/1978 |
| From: | Zech G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811220259 | |
| Download: ML18078A408 (5) | |
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NOVEMBER 7 7978 Docket No. 50-272 Licensee:
Facility:
S,ubject:
Public Service Electric & Gas Company (PSE&G)
Salem Nuclear Generating Station, Unit No. l
SUMMARY
OF MEETING HELD ON OCTOBER 3, 1978, TO otscuss*
PSE&G 1 S PROPOSED SPENT FUEL POOL MODIFICATION /.\\T SALEM UNIT NO. l On October 3, 1978, w~ met with ~epresentatives of.PSE&G, Exxon Nuclear and Brooks and *Perkins, to discLlss the outstanding matters w1th regard to the proposed expansion of the Salem Unit No. l spent fuel pool (SFP) storage capacity.
- A'list of attendees i~ enclosed.
Significant discussions *are summarized, below.
i:Je reviewed, in general, the licensee's responses of July 31 and August 22, 1978 to the staff's request for additional information
.dated \\.li:me.:.:2~, ~ l9 Z?. He al so discussed the 1icensee 1 s responses to information needs that had been identified in conversations with the licensee since our June 23, 1978 letter. These responses and remaining areas of concer11 are discussed belm"I.
The Request numbers refer to those contained in our June 23, 1978 letter.
!tequ_~st ft__~5 This request was for detailed information to show that the 2.0S linear elastic limit for the faulted condition is in accordance with F-1370 of ASME Section III, Appendix F.
We indicated that the licensee ha'd not provided adeqaate information tvith respect to buckling stresses and therefore sufficient basis did not exist to support its GOnclusions.
The licensee agreed to provid~ additicinal information.
This request dealt with the ahi 1 i ty of the new racks to withstand the acciden~al drop from the maxirnur:i t~ansport height o! ~my items 1r1hich will A'l:il be carried over the racks.
He rndicated that the licensee had not -
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MlC FO~ ~18 (9*76) NRCM 0240
- u*.s. GOVERNMENT PRINTING OFFICE: 1978 - 265 - 769-
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I 1-e Meeting Summary for PSE&G.,- NOVEMBER j' adequately identified the most energetic* load and thus, that load that would potentially cause the most damage to spent fuel in the.
event of an accident.
The 1 icensee. agreed to review its respon_se to this qu~stion.
K~qyest #13_
This request requested a summary of the material properties used in the rack structural analyses.
The licensee'~ response addressed the material properties of the stainless steel only.
The licensee agreed to verify in wri.ting that no other materials used in the racks were assumed to provide any structura 1 support.
He.- requested that thelicerisee provide additional, information to support the selection of the c*oefficien_ts of friction assumed in the linear and ~on-linear elastic analyses.
iJe reEjuested that the licensee provide additional information to support its assumption that not more than one fuel rack could be in contact \\'Jith the SFP wall when analyzing a seismic event.
Reque"Sti fi:_~
With rega!"d to the seismic analysis of the new*storage racks, we requested that the licensee address whether frequency shifts were considered and why such shifts are acceptable considering that a fixed base model was assurned.
_Requ~~-t_ #20 W~ requested that the license~ describe the effects, if any, of any displacement -:,r;; strains on the integrity of the boral material within the stainless steel fuel cell, and the basis for the acceptability of such loads.
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In response to earlier conversations between the staff and the licensee with regard to a boral sheet swelling phenomenon observed, at. other reactor facilities, the licensee and its consultants provided a detailed description of the manufacturing and qu9l ity control procedures employed in the.fabrication of the boral sheets* and t~e stdrage _racks for Salem
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~C FORM 318 (9*76) NRCM 0240
- U.S. GOVERNMENT PRINTING OFFICE: 1978
- ZB5. - 769
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Meeting Summary for PSE&G NOVEMBER 7 1978 Unit No. 1.
The problem involves the exposure of the alumi.num,
~1hi ch encases the bora 1, to the SFP, water once the racks are-i nsta 11 ed and the resultant evolution of hydrogen gas which has
. caused the inner stainless *steel wall of storage cells to swell im1ard... The licensee e.xpTaine'.d-.whyT, in view *of the h.igh quality manufa~turing methods used. it does not expect the welds on the stainless steel racks to leak and thereby to cause a similar problem at Salem.
We questioned the precautions that were planned in transporting the racks to the Salem site and.the receipt inspections to.be used.
~'le also asked whether pre-anodizing of the aluminum surfaces had* been considered as a precaution against hydrogen evolution after installation
- in the SFP.
The licensee's consultant, Exxon Nuclear, stated that anodizing had been considered, but that the potential for dama~e to the boral sheets was too great and that the quality control mea*sures would be too involved for items as large as the ooral sheets.
OFFIC!l:~
BURNAM!'!~
DATEi!J>-
i1Jith regard to potential cr"iticality concerns caused by the movement of fuel assemblies due tri the swellinef of the boral sheets in adjatent storage locations, the licensee demonstrated that the movement of fuel assemblies would tend to be awaj from one another (towards *center of the can) and therefore k effective would tend to decrease.
Any change would be minimal.
The licensee summarized the preliminary findings of a forthcoming report which wi-11 discuss potential corrosion problems of the spent fuel ~ack materials) i.e., aluminum, boral and ~tainless steel,* ove~
the licensed life of the plant. The final report is expected in approximately three months.
The licensee stated that based on test data and operating experience to date, corrosion of the boral material is not expected to be a problem in that no transport of the poison material will occur over the life of the_ plant. Similarly3 based on tests conduct~d by the licensee's consultant to simulaie the environ-ment of the SFP, the projected effects of corrosion on the stainless steel and aluminum materials are not expec.ted to be significant~
The licensee stated that it preferred not to drill 11 vent" holes at the top of each storage cell such that *any hydrogen gas generated would be vented off, suth as has been done in the case of two other facilities with similar rack designs.
We indicated that it vmuld have to be assumed that some leakage would occur and that therefore the licensee would have to show vJhy this would not cause a sign~ficant problem.
The licensee was requested to discuss how any *swelling would be detected, ho111 it
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Meeting Sl.1mmary for PSE&G
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NOVEMBER 7 1978 would be dealt with, and how a fuel assembly could be removed without significant damage occuring to the assembly.
Enclosure:
List of Attendees cc:
See next page priglnal s'igned b~
Gary G. Zech, Project Manager Operating Reactors Branch #1 Division of-Operating Reactors OFFICE:~
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MlC FORM 318 (9-76) NRCM 0240
- U.S. G~O~~RNMENT PRINTING OFFIC~: 1978 - 2CUi - 709
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NRC STAFF MEETING HITH PUBLIC SERVICE ELECTRIC f?, G.l\\S CO. (PSE&G)
October 3, 1978 MRC
-G.ll. Zech A. Schwencer W. Russell K. Herring F. Almeter E" Lantz J. Stone List of Attendees Brookhaven National lab J~t.foeks, --- ---- ~-------
Conner Moore
,'?i. Corber
-K. 1L--EiTfS -- ------
American Electric Power Service-Cor2oration "J:-t:-:-1:Tz\\~el te_r ____ ---------- --------
PSE&G
- 1:--:-JC. Li den t,( 0. Bandei ra Exxon Nuclear s.-1r~ --rHcfd i e-E. E. Garrett T. G. Eckhart
\\'!;.J. Nechodorn Brooks & Perkins R:-c~---Karzmor-ENCLOSURE 1
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- me FORM 318 c'9-76) NR9'f 0240
- U.S. GOVERNME:N~ PRINTING OFFICE: 1978 - ZGB - 769