ML18093B243
| ML18093B243 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/20/1988 |
| From: | Nicholls G NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8810270034 | |
| Download: ML18093B243 (2) | |
Text
Jorge H. Berkowitz, Ph.D.
Director State of New Jersey DEPARTMENT OF ENVIRONMENTAL PROTECTION DIVISION OF ENVIRONMENTAL QUALl1Y CN415 Trenton, N.J. 08625-0415 (609) 987-6402 Fax (609) 987-6390 Gerald P. Nicholls, Ph.D., Assistant Director Radiation Protection October 20, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
On October 10, 1988, Public Service Electric and Gas Company (PSE&G) submitted an Emergency License Amendment Request for Salem Unit 2 (Docket No. 50-311). The purpose of this request was to receive regulatory relief from Technical Specification requirements governing extensive steam generator tube inspection following an unsatisfactory steam generator tube surveillance (indicating that an elevated number of steam generator tube defects are present).
PSE&G has stated that the steam generator tube degradation has been determined to exist on the inside diameter of Row 1 tubes in the tangential area of the U-bend. PSE&G has further stated that these results are comparable to steam generator tube failures at various other operating Pressurized Water Reactors.
On October 14, 1988, Mr. J.C. Stone (Licensing Project Manager-Nuclear Regulatory Commission-Region 1), indicated that the NRC has granted this Emergency Technical Specification Change Request. This information was conveyed during a telephone conversation held with Bureau of Nuclear Engineering (BNE) staff members.
The Bureau of Nuclear Engineering (BNE) has reviewed this change request as part of their integrated nuclear power plant surveillance program and pursuant to 50.91 of the Code of Federal Regulations, Title 10 is submitting the following comments:
The steam generator tube sample selection and the inspection frequency of the technical specification is a statistical method of ensuring integrity of steam generator tubes. The requirements set forth in the Technical Specification should be adhered to. In light of the NRC decision to grant the Technical Specification change, the BNE believes that all of the tubes in each steam generator (contained in rows 2 and 3) should be tested to ensure that the phenomenon affecting the number 1 row area tubes is not also affecting adjacent row tubes.
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The BNE requests that the NRC ensure that the utility treats this steam generator tube degradation as a category C-3 failure as stated in the Technical Specification (4.4.6.2). The utility would then be required to perform an accelerated steam generator tube inspection in accordance with Technical Specifications (4.4.6.3.b).
If you should wish to discuss this issue further please contact Pat Patniak or Randy Ebright of my staff at 609-987-2032. Thank you for your time and cooperation in this matter.
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Sincerely,
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Gerald P. Nicholls, Ph.D.
Assistant Director J.C. Stone, Licensing Project Manager, NRC Region 1 F. Combs, Director, State, Local, and Indian Tribes Program, NRR file: sal.sgt page 2