ML18101B003
| ML18101B003 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/12/1995 |
| From: | Olshan L NRC (Affiliation Not Assigned) |
| To: | Eliason L Public Service Enterprise Group |
| References | |
| GL-95-03, GL-95-3, TAC-M92269, TAC-M92270, NUDOCS 9509190239 | |
| Download: ML18101B003 (4) | |
Text
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,Mr. Leon R. Eliason Chief Nuclear Officer & President-Nuclear Business Unit Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
Dear Mr. Eliason:
septem9 12, 1995
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE TO GENERIC LETTER (GL) 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES" (TAC NOS. M92269 AND M92270)
On April 28, 1995, the U.S. Nuclear Regulatory Commission issued Generic Letter (GL) 95-03 "Circumferential Cracking of Steam Generator Tubes" which requested addressees to evaluate recent operating experience related to circumferential cracking, justify continued operation until the next scheduled steam generator tube inspections, and to develop plans for the next steam generator tube inspections. The staff has reviewed the response provided by Public Service Electric and Gas Company for Salem Nuclear Generating Station, Units 1 and 2.
As a result of the review of your response, the staff has identified areas for which additional information and/or clarification is needed.
The enclosure to this letter contains the information needed for the staff to complete its review of your response to GL 95-03.
- Please provide your response by October 2, 1995.
This request is within the original reporting burden for information collection of 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1977.
Docket Nos. 50-272 and 50-311
Enclosure:
As stated cc w/encl:
See DISTRIBUTION Docket File PUBLIC PDI-2 Reading SVarga JStolz next page LOlshan MO' Brien OGC ACRS(4)
JWhite, RGN-I OFFICE PDI-2/LA DI-2/PM Olshan:rb DATE 9/ l /95 9 /11./95 OFFICIAL RECORD COPY DOCUMENT NAME:
SA92269.GEN 1( - 9509190239 950912 I
f DR ADOCK 05000272 t'
PDR Sincerely, original signed by Leonard N. Olshan, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation KKarwoski
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 September 12, 1995 Mr. Leon R. Eliason Chief Nuclear Officer & President-Nuclear Business Unit Public Service Electric a*nd Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
Dear Mr. Eliason:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE TO GENERIC LETTER (GL} 95-03, "CIRCUMFERENTIAL CRACKING OF STEAM GENERATOR TUBES 11 (TAC NOS. M92269 AND M92270}
On April 28, 1995, the U.S. Nuclear Regulatory Commission issued Generic Letter (GL} 95-03 "Circumferential Cracking of Steam Generator Tubes" which requested addressees to evaluate recent operating experience related to circumferential cracking, justify continued operation until the next scheduled steam generator tube inspections, and to develop plans for the next steam generator tube inspections.
The staff has reviewed the response provided by Public Service Electric and Gas Company for Salem Nuclear Generating Station; Units 1 and 2.
As a result of the review of your response, the staff has identified areas for which additional information and/or clarification is needed.
The enclosure to this letter contains the information needed for the
- staff to complete its review of your response to GL 95-0~. Please provide your response by October 2, 1995.
This request is within the original reporting burden for information collection of 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> covered by the Office of Management and Budget clearance number 3150-0011, which expires July 31, 1977.
Docket Nos. 50-272 and 50-311
Enclosure:
As stated cc w/encl:
See next page Sincerely,
-if~t.~
Leonard N. Olshan, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr. L~on R. Eliason ~
'Public Service Electric & Gas Company cc:
Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street NW Washington, DC 20005-3502 Richard Fryling, Jr., Esquire Law Department - Tower SE 80 Park Place Newark, NJ 07101 Mr. John Summers General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. J. Hagan Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Mr. Charles S. Marschall, Senior Resident Inspector Salem Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Maryland Office of People's Counsel 6 St. Paul Street, 21st Floor Suite 2102 Baltimore, Maryland 21202 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne; PA 19087 Mr. S. LaBruna Vice President - Nuclear Engineering Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Nucle~Generating Station, Units 1 and 2 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor 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. Frank X. Thomson, Jr., 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 Ms. P. J. Curham MGR. Joint Generation Department Atlantic Electric Company P. 0. Box 1500 6801 Black Horse Pike Pleasantville, NJ 08232 Carl D. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806
REQUEST FOR ADDITIONAL INFORMATION SALEM NUCLEAR GENERATING STATION. UNITS 1.AND 2 I. For the inspections performed at the expansion transition during 2R8 and IRll, clarify if the percentages cited were the percentages of the total number of tubes in the steam generator or the number of tubes in Zone 4 (e.g., for steam generator 11 i.n IRll, does the 39% imply t~at 3'9% of all the tubes in the steam generator were examined with the examinations concentrated in Zone 4 or does the 39% imply that 39% of the tube in Zone 4 were examined?).
- 2.
It was indicated that 5 tubes have been plugged as a result of circumferential cracking. Please clarify that all tubes with circumferential indications were removed from service. Clarify the outages in which these i~dications were detected.
- 3.
In your response, it was indicated that dented locations (specifically dented support plate locations) are susceptible to circumferential cracking and that augmented rotating pancake.coil examinations have been performed for detecting circumferential cracking at dented tube support plates. Specify the inspections performed during the previous Salem Units 1 and 2 steam generator tube inspection outages.
It was indicated that dents greater than 5.0 volts will be inspected with an Appendix H qualified probe (Cecco 5 or plus point) during the next
- steam generator tube inspections.
Provide the procedures used for sizing the dents. If the procedure is identical to the procedure for the voltage-based repair criteria, a detailed description is not necessary.
Future inspection plans for dented (> 5V) intersections concentrate at the lowest hot-leg tube support plates. A large dent at an upper tube support plate may be more significant in terms of corrosion susceptibility as a result of higher stresses than a small dent at a lower tube support plate even though the temperature is lower at the upper tube support plate.
Given this, discuss the basis for the proposed sample strategy given that cracRing depends on many factors including temperature and stress levels.
The inspection plan for dented locations differs from Units 1 and 2.
Discuss the reason for this difference.
- 4.
Please provide the expansion criteria to be used for all locations susceptible to circumferential cracking.