ML18094B178
| ML18094B178 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/17/1989 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | Miltenberger S Public Service Enterprise Group |
| References | |
| TAC-74140, TAC-74141, NUDOCS 8911290172 | |
| Download: ML18094B178 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 17, 1989 Docke~ Nos. 50-272/311 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric & Gas Company Post Office 8ox 236 Hancocks Bridge, ~ew Jersey 08038
Dear Mr. Miltenberqer:
SUBJECT:
RE:
References:
CONTAINMENT MONITOR CHANNELS (TAC NOS. 74140/74141)
SALEM GENERATING STATION, UNIT NOS. 1 ANO 2
- 1.
Letter from E. A. Liden (PSE&G) to S. A. Varga (NRC) dated October 13. 1983, on Containment Integrated Leak Rate Test.
Salem Unit I.
- 2.
Letter from E. A. Liden (PSE&G) to S. A. Varga (NRC) dated November 8, 1984, on Containment Integrated Leak Rate Test, Salem Unit 1.
In references 1 and 2, PSE&G supplied details concerning containment monitor channels (CMCs) with some justification for keeping some of the CMCs pluaged during containment integrated leak rate testing (CILRT).
The staff's position on this matter is that containment monitor channels should be vented to the containment atmosphere during the CILRT to permit the detection of potential leak oaths in the primary containment liner welds.
However, if the licensee can demonstrate that the channels would maintain their integrity when subjected to the loading conditions of a postulated design basis accident as well as during normal operations, and that the design for the new pressure boundary of the containment would compare favorably with the applicable portion of ASME B&PV Code,Section III, Division 1, Subsection NE requirements for class MC Components; Division 2, Subsection CC requirements for concrete containment; and AISC Specification, the channels need not be vented.
Based on our review of the information in references 1 and 2, we find that there is not sufficient data to demonstrate that the CMC can be qualified as an integral part of the containment liner plate.
In order ~or us to complete our review, you are request to provide the additional information listed in the enclosure.
( 8911290172 891117 PDR ADOCK 05000272 P
PNU
- . We request that. you respond to the above request within 60 days of receipt of this letter.
The reporting and/or record keeping requirements of this letter affect fewer than ten respondents; therefore. OMB clearance is not required under P.L.96-511.
Enclosure:
Request for Additional Information cc w/enclosure:
See next page Sincerely,
~S~ne~
Manager Project Directorate !-2 Divisio~ of Reactor Projects I/II Office of Nuclear Reactor Regulation
- We request that you respond to the above request within 60 days of receipt of this letter. The reporting and/or record keeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Enclosure:
Request for Additional Information cc w/enclosure:
See next page DISTRIBUTION w/enclosure:
Dodeti=iie NRC PDR Local PDR PDI-2 Reading SVarga BBoger WButler M0 1 Brien EJordan OGC MThadani JS tone ACRS (10) t1Linville, RI GBagchi Sincerelyt
/SI James C. Stonet Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
[MILTENBERGER]
PDI-2/PM JStone:mj
\\\\ 1,'\\ /89 PDI-2/D I °'
WButler ~~
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Mr. Steven E. Miltenberger Public Service Electric & Gas Company cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Law Department - Tower 5E 80 Park Place Newark, NJ 07101 Mr. L. K. Miller General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. S. LaBruna Vice President - Nuclear Operations Nuclear Department P.O. Rox 236 Hancocks Bridge, New Jersey 08038 Kathy Halvey Gibson, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, NJ 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, NJ 08625 Dr. Jill Lipoti, Ph.D New Jersey Department of Environmental Protection Division of Environmental Qualit.y Radiation Protection Programs State of New Jersey CN 415 Trenton, NJ 08625 Maryland People's Counsel American Building, 9th Floor 231 East Balt.imore Street Baltimore, Maryland 21202 Salem Nuclear Generating Station Richard B. McGlynn, Connnission Department of Public Utilities State of New Jersey 101 Commerce Street Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Bruce A. Preston, Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Mr. Scott B. Ungerer MGR. - Joint Generation Projects Atlantic Electric Company P.O. Box 1500 1199 Black Horse Pike Pleasantville, NJ 08232 Mr. Jack Urban General Manager, Fue1s Department Delmarva Power & Light Company 800 King Street Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division ATTN:
Chief Engineer 231 E. Baltimore Street Baltimore, MD 21202-3486
REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTAINMENT MONITOR CHANNELS SALEM GENERATING STATION UNITS l & 2 ENCLOSURE
- 1.
Provide supporting analysis and stress calculations for at least one typical monitor channel to show that the containment liner monitor channel system meets the following requirements:
- a.
The materia~ strength and quality of weld attaching the channel to the liner plate should be equal to or better than that of the original liner joints and should meet the applicable requirements of either ASME Boiler and Pressure Vessel Code,Section III, Division 2, Subsections CC-2000, 3000 and 4000 (Code of Concrete Reactor Vessels and Containments, 1983) or whatever comparable code that was used in design and construction.
- b.
Since the monitor channels now become part of the containment wall and are therefore considered a structural element, the strength of the channel box and its welds should be able to resist all load combinations involving the tested loads and the loads of a postulated accident, including seismic loads. The design of the monitor channel should meet the applicable requirements of steel containments; i.e., either ASME Boiler and Pressure Vessel Code,Section III, Division 1, Subsections NE-2000, 3000 and 4000 for Class MC Components (1983) and American Institute of Steel Construction Specification for the Design, Fabrication and Erection of Structural Steel for Buildings (1978), or whatever comparable code that was used in design and construction.
- 2.
Complete documentation of installation records, including leak test procedures and results of the lin~r seam welds and the welds attaching the channel to the liner, should be available.on site. Please summarize and provide examples of available records. If no records or only partial records are available, provide whatever additional information/assurance is available regarding procedures, materials, welds, inspection records, etc.
- 3.
The staff needs a commitment that you will perform a visual inspection of the accessible interior and exterior surfaces of the containment structure and components prior to any Type A test, including a visual inspection of accessible channel plugs, as required by 10 CFR Part 50, A.ppendi x J.