ML19241B077

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Summary of 750430 Meeting in Bethesda,Md Re Pumphouse Settlement for Svc Water Reservoir.Recommended Issuance of Show Cause Order Re Suspension of Reservoir Const
ML19241B077
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 05/01/1975
From: Ferguson R
Office of Nuclear Reactor Regulation
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML19241B068 List:
References
NUDOCS 7907110638
Download: ML19241B077 (3)


Text

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a Mi 1R5 Docket Ros 50-333 and 50-337-

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A. Schwe=cer, Chief, Light Unter Reactoro Ercnch 2-3, DRL SETTLC'ENT OF CU.SS I STEUCTURES AT NORIII ARIA Ul?IIS 1 AND 2 - S110V

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CAUSE ', RECO35"OATION

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On April 30, 1975, a =eeting was held in Ecthesda by representative-of the liRC secf f to diccuss the cettic :nt of the purphouse for the Service Unter T,cservoir. Thic =ecting uns attended by Ikssrs. A. Cardone, S. Chan, R. She. naker, J. Creeves, W. Cr---411, L. Ecratan, J. Ital an, W. Olnstead and R. Ferguscu.

lir. Ecretan inforned 'the other nerbers of the staff of the inforcation he obtained during his visit to the cito on April 29, 1975. The significant V

pointe made ucre as follovst In August 1972, the licensee noticed a 5/8" crack in the "uing vall" 1.

of the p=phouce. Ibis crach vas deter:Anod to be caused by sett1ccent of the picphouse. A procrcn was initiated to monitor the setticaant of the ptcphouce nore clo;cly.

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2.

The pu=phouse has continued to settia and at present one corne.r has cettled note than 6".-

A'. least 3" of additional settic=ent in expected during the lifev6f the plent.

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3.

Since the pipes that connect the pttphouse to the facility have been e

connected the pt=phouse has settled c.t least one inch, P :nfincreased T

stress in the pipes because of this nettlement, is stated.iy the -

7 licennee to be about 2S03 pai..

4.

In DeceEber'1974, the licensee amended the FSAF to increase the expected g

settlenent of the pt=photme fro 0.12 f t to 0.4 ft.

He provided Table 3.8.4-2 thst presented the factors of safcty for the cc-vice unter reservoir dikcs that vere about a factor of t o Ic.ecr than those pre-l viously presented on Table 2.5-4.

No eplanation was of fered for the.

reduced safety factors or for the transfer of the table from a FSAR f

section ccsocicted with ctability of subsurface conditices to a FSAR section associated with structural design.

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t Mr.' Ecratan recorrended a technicci cpecification requiring con!toring of tha crpceted cottlement and en approprit.to action if the c :tittent crecedo a cpecified limit.

Tc11ovin; Fr. Ecratan's precentation, there was a discussion of the 1711 cation of this setticuent. ne significant points cada vere as follovc 1.

ne foundationf a conditions at the pun:phouse do not appear to be consistent with such conditions dcocribed in the application (i.e. PSAE) at the time the construction pernit was issued.

2.

Thcro is not cuf ficient infortmtion in the present cpplication to approve an operating license.

3.

Wo do not know if or when the licensee intends to file a report on this natter under 10 CFR Part 50.55(e).

4.

Three alternatives are availnble to obtain the informations (n) c chov cause order (b) a 10 CFR Part 50.55(c) Report

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(c).a request for additional infor ution '

Subsequent to thin recting I called Mr. Welter Bennett (VEPCO) and asked whether VEPCO planned to subuit any cdditional information on this catter.

He onid VEPCO in preparing a letter report se=arizing ti e 'nfornation p presented at die sito yesterday. ne report will be submitted within two vecks. He vill call ne tomorrow (May 1,1975) to confira the subtittal

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dato and to outline the contents of the report.

I inforced hin that we would like to be advista of the analycis that has been done to deternine whether the foundation conditic citer the chility-of the cervice water reservoir to withstand environnental design bcsia events.

To resolve this natter enpeditiously, I reco rend that consideration be given j

to issuing an order to request the cpplicant to show cause why the construction of the Service Unter Reservoir c.hould not be suspended until licensce's analysic of the safety icplications of this settictent have been evaluated by tne NRC staff.

Cfchd U::d by y

R. L. Ferrucon, Project Ihnster Light Unter Ecactors 3rcach 2-3 Division of Reactor Licensing l

ces:

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307 319

I 3-i cess V. A. ! bore A. Gicchucso E. C. Case D. Ecrtalia J. Cohen W. Cat =111

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