ML20199H647
| ML20199H647 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/20/1999 |
| From: | Colburn T NRC (Affiliation Not Assigned) |
| To: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-MA4234, NUDOCS 9901250261 | |
| Download: ML20199H647 (4) | |
Text
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.I January 20, 1999 Mr. James W. Langenbach, Vice President and Director - TMl GPU Nuclear, Inc.
P.O. Box 480 Middletown, PA 17057
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING GPU NUCLEAR, INC., TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) NO. 277, 1
ONCE THROUGH STEAM GENERATOR (OTSG) CYCLE 13 (13R) INSERVICE l
INSPECTIONS FOR THE THREE MILE ISLAND NUCLEAR STATION, UNIT 1 i
(TMI-1) (TAC NO. MA4234)
Dear Mr. Langenbach:
The staff has reviewed your November 25,1998, license amendment application regarding TSCR No. 277, for OTSG inservice inspection during 13R for TMI-1. The staff has determined that it will need the additional information identified in the enclosure to complete its I
review. As discussed with and agreed to by your staff, please respond to this request for additional information within 3 weeks of receipt in order for the staff to remain on schedule with its review.
Sincerely,
/s/
[
Timothy G. Colbum, Senior Project Manager 9901250261 990120 Project Directorate 1-2 ADOCK 0500 M 9 l
%DR Division of Reactor Projects - t/11 Office of Nuclear Reador Regulation Docket No. 50-289 t
Enclosure:
Request for AdditionalInformation
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NUCLEAR REGULATORY COMMISSION I
If WASHINGTON, D.C. 20565 4001 0,,,,8 January 20, 1999 Mr. James W. Langenbach, Vice President and Director - TMI GPU Nuclear, Inc.
P.O. Box 480 Middletown, PA 17057
SUBJECT:
REQUEST FOR ADDITIONALINFORMATION REGARDING GPU NUCLEAR, INC., TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) NO. 277, ONCE THROUGH STEAM GENERATOR (OTSG) CYCLE 13 (13R) INSERVICE INSPECTIONS FOR THE THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1) (TAC NO. MA4234)
Dear Mr. Langenbach:
l The staff has reviewed your November 25,1998, license amendment application regarding TSCR No. 277, for OTSG inservice inspection during 13R for TMl-1. The staff has determined that it will need the additional information ider)tified in the enclosure to complete its review. As discussed with and agreed to by your staff, please respond to this request for additional information within 3 weeks of receipt in order for the staff to remain on schedule with its review.
Sincerely, I
l k.
Timothy G. Col rn, Senior Project Manager Project Directorate 12 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation l
Docket No. 50-289
Enclosure:
Request for AdditionalInformation cc w/ encl: See next page i
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J.Langenbach Three Mile Island Nuclear Station, Unit No.1 i
ec:
i Michael Ross l
Director, O&M, TMl Robert B. Borsum GPU Nuclear, Inc.
B&W Nuclear Technologies l
P.O. Box 480 Suite 525 i
l Middletown, PA 17057 1700 Rockville Pike Rockville, MD 20852 i
John C. Fornicola Director, Planning and William Domsife, Acting Director Regulatory Affairs Bureau of Radiation Protection GPU Nuclear, Inc.
Pennsylvania Department of i
100 Interpace Parkway Environmental Resources Parsippany, NJ 07054 P.O. Box 2063 Harrisburg, PA 17120 Jack S. Wetmore Manager, TMl Regulatory Affairs Dr. Judith Johnsrud GPU Nuclear, Inc.
National Energy Committee P.O. Box 480 Sierra Club Middletown, PA 17057 433 Orlando Avenue State College, PA 16803 Emest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge Peter W. Eselgroth, Region I l
2300 N Street, NW.
U.S. Nuclear Regulatory Commission Washington, DC 20037 475 Allendale Road King of Prussia, PA 19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident inspector (TMI-1)
U.S. Nuclear Regulatory Commission l
P.O. Box 219 Middletown, PA 17057 i
Regional Administrator l
Region i U.S. Nuclear Regulatory Commission 475 Allendale Road
(
King of Prussia, PA 19406
REQUEST FOR ADDITIONAL INFORMATION l
THREE MILE ISLAND, UNIT 1 l
TECHNICAL SPECIFICATION CHANGE REQUEST NO. 277 i
CYCLE 13 STEAM GENERATOR 10 IGA INSPECTION ACCEPTANCE CRITERIA l
l By letter dated November 25,1998, GPU Nuclear, Inc., submitted a request to change the l
Technical Specification surveillance requirements for steam generator inservice inspections for Three Mile Island, Unit 1 (TMI-1) cycle 13 refueling (13R) outage examinations which would be l
applicable for one cycle of operation only. Spec'fically, the change requested is associated l
with inspection acceptance criteria for inside diameter intergranular attack (ID IGA) of the l
steam generator tubes. The staff has reviewed the request and determined additional information is necessary to complete the review. The required information is listed below.
1.
The November 25,1998, letter stated the metallurgical and chemical analyses performed on the 12R outage pulled tubes suggest strongly that there was no progression in ID volumetric degradation. The conclusion that ID volumetric degradation is non active l
degradation is a significant aspect of the technical basis supporting this amendment request. Therefore, please submit a summary of the metallurgical and chemical analyses performed, and the results oi the analyses which enabled you to determine that the ID volumetric degradation is not progressing.
l l
2.
Provide a discussion on the inspections planned (rotating pancake coil and bobbin probe) l for the 13R outage as compared to previous outage inspections (specifically, the 11R and l
12R outages). This information is needed to assess the credibility of flow growth rate data as determined from a comparative analysis of the 12R and 11R inspection results. The discussion should focus on the equipment not the inspection scopes, and should be geared towards similarities and differences. Include the following items in addition to other details you determine to be relevant: describe the probes used (for detection, sizing and comparisons to previous outage data); describe how probe wear is evaluated and controlled; describe how calibrations are controlled (e.g., calibration standards); and describe evaluations of data analyst uncertaintiss if performed.
3.
A one-cycle technica! specification change was previously requested and granted for ID IGA degradation for the 12R cycle and outage. Please discuss your reasons, both technical and regulatory, for requesting another one-cycle change for 13R.
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