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LEAR CEIULATORY COMMIT $lON WAsHIN' ton,6. C. 20$55 -
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3 LICENSEE: JERSEY CE)frRAL POWER AND LIGff COMT\\NY (JCP4L)
FACILITY: OYSTER CREEK NUCLEAR GENERATING STATION
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DOCKET NO.:
50-219 i
SLDNARY OF MEETING HELD ON JULY 24, 1975 10 DISCUSS THE GE(YTECHNICAL STUDY FOR THE FOUNDATION OF THE PROPOSED LIQUID / SOLID RADWASTE BUILDING On' July 24, 1975, a meeting was held with representatives of General Public Utilitie's Service Corporation, (GPUSC) to discuss NRC staff concerns 'regarding the gootechnical study of the site for the proposed new liquid / solid radwaste i
building. A list of attendees is enclosed.
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. JCP4L has proposed upgrading the Oyster Creek Nuclear Generating Station radwaste system.. A new liquid / solid radwaste building designed to withstand j'
seismic ' loading and a new non-seismic designed off gas building will be constructed to house additional radwaste equipment. By letter dated March 6, 1975, JCP4L submitted a geotechnical report that analyzes site seismology and evaluates the liquefaction potential of the material beneath the proposed j
liquid / solid radwaste building, 1he NRC staff stated that based on our review, we conclude that the geotechnical f
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report does not provide enough standard penetration test data taken directly under the proposed site. In addition, the NRC staff stated that based on t
our review of the standard penetration data that were obtained under the proposed structure, we conclude that liquefaction could be a problem in the Upper Cohansey sands during the SSE. Woodward - Clyde representatives stated i
that based on both the undisturbed samples and the standard penetration values, they conclude that the Cohansey sands will not liquefy.
l In addition, some of the more significant NRC concerns discussed were:
1.
The liquefaction of adjacent deposits (loose fill) and the possibility of progressive liquefaction toward the radwaste building.
2.
He evaluation of the previous loading of the clay in the Upper Clay Formation.
3.
D e possibility of groundwater level variations during the life of the plant and the effect on the liquefaction potential.
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De backfill procedures that were used to place fill near borings W2, W5, and W9; and the reason for the extremely loose condition of the fill.
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The possibility of large secondary compression of.the clays which were described as organic deposits.
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H e evaluation of the significant number of cycles used in the
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liquefaction analysis, i
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The settlement criteria and settlement monitoring program.
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. De NRC staff stated that our concerns discussed during the meeting will be transmitted formally by the middle of August.
In addition, the NRC staff a
agreed to document our current position regarding seismic design requirements
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for structures housing radioactive waste management systems.
Walter A. Paulson Operating Reactors Branch #3 Division of Reactor Licensing 4
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ENCLOSURE LIST OF ATTENDEES Nuclear Regulatory Commaission W. A. Paulson i
J. Greeves t
General Public Utilities _
t D. Callahan J. Devine C. R. Montgomery L. Lanese Woodward - Clyde Consultants j
I. S. Oweis H. M. Horn Y. Lacroix Burns & Roe S. W. Chou 4
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UCLE AR REGULNIDRY COf/.'.'.!S0lON
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20Lf4 AUG 2 81975
- n A!EETING SU'efARY DISTRIBUTJO] LIST JERSEY CENTRAL POWER 6 LIGHT COMPANY Paul Rosenberg, Esquire ATTN:
Mr. I. R. Finfrock, Jr.
Daniel Rappoport, Esquire Vice President - Generation 2323 S. Broad Street Madison Avenue at Punch Bowl Road Trenton, New Jersey 08610 Norristown, New Jersey 07960 l
Honorable Joseph W. Ferraro, Jr.
G. F. Trowbridge, Esquire Deputy Attorney General Shaw, Pittman, Potts, Trowbridge 6 Madden State of New Jersey r,,evision of Law - Room 316 Barr Building 910 17th Street, N. W.
.ewark, New Jersey 07102 Washington, D. C.
20006 Burtis W. Horner, Esquire I
' Jersey Central Power & Light Company Stryker, Taas and Dill ATTN: Callahan, Devine, Montgomery, Lanese 55 Madison Avenue GPU Service Corporation
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Morristown, New Jersey 07960 260 Cherry Hill Road Parsippany, New Jersey 07054 George F. Kugler, Jr.
Attorney General State of New Jersey
. _ State House Annex _,,,,,,,,,,,
j Trenton, New Jersey 08625 j
NRC PDll RL AD.s A. Schwencer TR.TDs~~
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Local PDR R. Clar1.
NRR Rdn Tile R. C. DcYoung I. Speis V. Stello ORl!f3 lhlg Filo V. Moore R. Vollmer R. N: ceary Duclet File R. Denise R. Ilour. ton' R. Tc Jc:.co S. Yarga K. R. Coller P. Collins H. D:m aa T. J. Carter D. J. Skovholt R. Purple R. E. Hei nciaan D. Muller D. Zicmann Tn tr.:
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F. SchrocJer G. Lear EP Project Manager RL BCs R. Reid T. Nc'. :.k Project Manager G. Knighton D. Res-0
.D D. Vassallo G. Dici;cr T. 1p}olito W.. Butler J. Youngblood C. Lor.*;
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Licensing Assistant O. Parr W. Regan G. If I r: -
NRC Participants J. Stol:
V. Denn:aya ACRS (16)
K. Kniel
. D. Crin s T. B. Abernathy W. Ca.' : J!1
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.r M. Spiry!cr R. Dalisrd J. Knight S. P.w' ichi L. S!w, g
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Jersey Central Power & Light Company MADif>ON VENUE AT PUNCH BOWL ROAD
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- 201-539 6111 General Puebc Utahtees Corporation August 28, 1975 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement, Region 1 United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 1940o
Dear Mr. O'Reilly:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Status Report for IE Bulletins No'. 75-04 and No.75-04A
Reference:
My letters to you dated May 27, 1975, June 30, 1975 and August 1, 1975.
This reports the status of incomplete activities that were initiated in response to IE Bulletins No. 75-04 and No.75-04A.
1 Since the August 1, 1975 Status Report on the fire detection and suppression system, the following activities have taken place:
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- 1.. The Modification Proposal for the installation of the Fire Protection System at Oyster Creek has been submitted to the Plant Operations Review Committee.
2.
Completed the engineering evaluation of the Fire Protection System for the Cable Spreading, Battery, and 480-volt Switch-2 gear Rooms.
It is anticipated that during the next 30-day period, the following will be accomplished:
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Review and approval of Modification Proposal from the Plant Operations Review Committee.
2.
Formalize an engineering evaluation of needed area structural h
change.
3.
Review vendors recommendation on additional area ventilation h V
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Mr. O'Reilly August. 28, 1975 The status 'of the Shutdown and. Emergency Procedures review is un-changed.
Y truly yours, p,
t Donald A. Ross, Manager Generating Stations-Nuclear 1
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Karl V. Feyfrit. Chief
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Technical Assistance Branch i
Office of Inspection and Enforcement, IE:HQ OYSTER CREEK - SEPARATION OF DC CONTROL CIRCUITS IN BATTERY ROOM (TRACK F14168H1)
REFERENCES:
1.
Region I Inspection Report 50-219/68-08, Detail III.B and IV.B.1 2
Region I Inspection Report 50-219/75-13, petail 4.d 3.
Memor:andum,GreenmantoCapiston, dated' september 12, 1975
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The attached memorandum is forwarded to headquarters for action.
Headquarters is requested to review the licensee's "as built" configuration and to determine the conformity of existing DC circuitry with applicable separation criteria.
Please refer I
any questions on this subject to E. G. Greenman (215-337-1273).
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Eldon J. Brunner, Chief Reactor Operations Branch t.
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Enclosure:
Memorandum, Greenman to Caphton, dated September 12, 1975 cc:
F. Dreher bec:
R. C. Haynes D. L. Caphton E. G. Greenman ROB Files 1
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UN'ITED STATES i
i-ATOMIC ENERGY COMMISSION oencevonArz or acous.4 tony orenavsons nsonoN t e
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hP KING OF PRUSSI A, PENNSYLVANIA 19406.
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SEP 1 g 3975 Tes' D. L. Cephton, a== tar Raaster Inspeeter L., if,.
Reester Operatises Bramah m,.~
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0'ern CREE-RErfEET ROCN DC DISTRIBUTION FAMEIA AND CABLE TR&YS.
b Based upes a verbal regnest from RL, I revisued surrent status based on Inspection Emports 50-219/68-10 and 50-119/75-13. The latter referenes states that "all almetriaal cablas supplied from J
f Bettery Reen DC distributten pe' eels A and B are colleated into a l
single sable tray." Findings as described in Inspection Report 50-219/75-21 are as follouse
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Radeadant 125 voit DC sentrei airamits, serving as boek up.
for the battery and controls osampy a single enimmon tray from b
j the peuer distributism pamals in the bettery room to thespeint where they enter conduits to esatinue ~ '.. c ' to the diseal 2
generater building.
(DC-4 embla 86-68 and DC-1 emble 86-19) these cables are in a ea==an tray and terminate into tray 24.
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Beaundant 125 volt DC sentrol aircuits serving the 4160 volt 1
1 vital baseos (1C and 1D) do not seenpy the same common tray The ic bus feed (Cable 62-88) whiah is located ta Panel A has been placed la separate oseduit outside the common tray, and the 1D bus feed from Pamal 3 (Cabla 62-100) is located taside the tray. Physisal separation provided la this testanee is en the order of 2.5 to 3 feet eseept at the point where cable 62-100 exits the distribution panel adjacent to the common L
tray.
l 3.
Circuitry is demeribed on DC line drawing 302-8 Revision 10, l
Reviewed for as built conditions, June 10, 1970.
I Within the scope of my inspection 1 ebtained no additional findings.
However, ebeervations of the common tray inputs from both distribu-tion panels A and B, indicated that a number of DC embles are present in the ecumon tray.
l Although this area has been====inad during the licensing process for I
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Oyster Creek it is recammanded that these findings be forwarded to the Technical Assistance Branch for review with respect to adequacy i
of separation.
Edward G. Greenman, Reactor Inspector cel D. caphton lt
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