ML20058A660

Forwards Request for Addl Info Re Drywell Corrosion Program, Including Sampling of Shell Surfaces for UT Measurements

ML20058A660
Person / Time
Site:	Oyster Creek
Issue date:	10/16/1990
From:	Dromerick A Office of Nuclear Reactor Regulation
To:	Devine J GENERAL PUBLIC UTILITIES CORP.
References
NUDOCS 9010290053
Download: ML20058A660 (4)

Text

'

October 16, 1990

. Docket No. 50-219 DISTRIBUTION e ;DocketJ11e:7 NRC & L PDRs SNorris PDI-4 File JStolz SVarge Mr. J. D. DeVine, Jr.

ADromerick AD/RI Vice President and Director RHermann OGC i

Technical Functions GBachi ACRS(10)

GPU Nuclear Corporation KMechion EJordan One Upper Pond Road JRichardson Parsippany, New Jersey 07054

SUBJECT:

DRYWELL CORROSION PROGRAM 0YSTER CREEK NUCLEAR GENERATING STATION On September 29, 1990, GPUNuclearCorporation(GPUN)metwiththeNRCstaff to discuss the Oyster Creek Nuclear Generating Station's Drywell Corrosion Program. During the meeting, GPUN requested that the staff provide feedback regarding the Drywell Corrosion Program. As a result of the discussions held during the meeting the staff so far has identified the following) aspects of-GPUN's presentation that call for staff feedback. These are:

1 sampling of shell surfaces for UT measurements, 2) appropriateness of the use of ASME Section III Subsection NC, and 3) the need for detailed review of preliminary results of the stres analysis presented by GPUN. The Enclosure provides details of the required clarification.

If during our ongoing review of your program additional items requiring further clarification are identified we will notify you..

If you have any questions regarding the above, please contact me.

Sincerely, original signed by Alexander W. Dromerick, Senior Project Manager Project Directorate I.4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

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October 16, 1990 Docket No. 50-219 Pr. J. D. DeVine, Jr.

Vice President and Director Technical Functions GPU Nuclear Corporation One Upper Pond Road Parsippany, New Jersey 07054

SUBJECT:

DRYWELL CORROSION PROGRAM - OYSTER CREEK NUCLEAR GENERATING STATION On September 29, 1990, GPU Nuclear Corporation (GPUN) met with the NRC staff to discuss the Oyster Creek Nuclear Generating Station's Drywell Corrosion Program.

During the meeting, GPUN requested that the staff provide feedback regarding the Drywell Corrosion Program.

As a result of the discussions held during the meeting the staff so far has identified the following aspects of GPUN's presentation that call for staff feedback.

These are:

1) sampling of shell surfaces for UT measurements, 2) appropriateness of the use of ASME Section III Subsection NC, and 3) the need for detailed review of preliminary results of the stress analysis presented by GPUN.

The Enclosure provides details of the required clarification.

If during our ongoing review of your program additional items requiring further clarification are identified we will notify you.

1 If you have any questions regarding the above, please contact me.

Sincerely, f

Alexander W. Dromerick, Senior Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page i

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Mr. J. D. DeVine, Jr.

0,v M.cr Creek Nuclear GPU Nuclear Corporation Generating Station 4

CC:

Ernest L. Blake, Jr.

Rc:idant Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C.

20037 Forked River, New Jersey 08731 Commissioner I. H. Jolles, Executive Vice President New Jersey Department of Energy GPU Service Corporation 101 Comerce Street 100 Interpace Parkway Newark, New Jersey 0710P Farsipanny, New Jersey 07054 Kent Tosch, Chief Regional Administrator, Region 1 New Jersey Department of Environmental U.S. Nuclear Regulatory Comission Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 CN 415 Trenton, New Jersey 08625 l

BWR Licensing Manager GPU Nuclear Corporation

. 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager E

Oyster Creek Nuclear Generating Station Mail Stop:

Site Emergency Bldg.

P. O. Box 388 l

Forked River, New Jersey 08731 1

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Mr. E. E. Fitzpatrick Vice President and Director-Oyster Creek Nuclear Generating Station Post Office Box 388

- Forked River, New Jersey 08731

i d

ENCLOSURE REQUESTED CLARIFICATION REGARDING OYSTER CREEK CORROSION OF DRYWELL SHELL DOCKET NO. 50-219 L

There are several aspects of the licensee presentation that call for staff feed back, these are:

i) sampling of shell surfaces for UT measurements, ii) appropriateness of the use of ASME Section 111 Subsection NC, and iii) need for detailed review of preliminary results of the stress analysis presented by the licensee.

1)

Sampling plan for monitoring drywell corrosion: The licensee presented a statistically based-inspection program of the entire shell surface not embedded in concrete.

However, based on the results of observation so far, the licensee presented a correlation between corrosion and presence of moisture for example, in the sand region the plug samples 15A and 11A-H were dry and had corrosion rates equal to zero.

It is not clear to the-staff how the licensee plans to locate secsors for on-line monitoring of drywell corrosion rate at those places where the presence of moisture is likely. The staff needs to review the statistically based sampling plan.

ii) The original design code for the Oyster Creek shell is ASME Section V111. Should the licensee choose to use a more recent code, there will be a burden on the licensee to clearly establish that the material selection, design, fabrication, inspection and surveillance in service are all in accordance with the requirements of the current code which should be the ASME Section III, Subsection NE, and Section XI.

l iii) It is clear that through the corrosion process, the margin for over pressure capacity of the containment has been reduced (see GDCf 50 and 51).

Therefore, the staff judgment as to the adequacy of the drywell shell margin must be based on a detailed review of the stress calculations and the stress allowables.

iv) In your presentation you indicated that there has been leakage from refueling cavity liner,. equipment pool and spent fuel pool. Describe the actions you will.take to prevent leakage from these structures into the drywell gap and-the effect of the leakage on other structures or equipment.

1 v,

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