ML20216B683
| ML20216B683 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/13/1998 |
| From: | Colburn T NRC (Affiliation Not Assigned) |
| To: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-MA1403, NUDOCS 9805180337 | |
| Download: ML20216B683 (6) | |
Text
..
/7y May 13, 1998 Mr. James W. Lang:nb ch, Vice PresidInt
. and Director - TMI-1 GPU Nuclear, Inc.
P.O. Box 480 Middletown, PA 17057
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1) - TECHNICAL i
SPECIFICATION CHANGE REQUEST NO. 270 TO RPV PRESSURE / TEMPERATURE LIMITS - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MA1403)
Dear Mr. Langenbach:
By letter dated March 23,1998, GPU Nuslear Inc. submitted a request (TSCF' No. 270), to amend the pressure and temperature (P-T) limits in the Technical Specifications for TMI-1. In order for the staff to complete its review of your request, please provide the additional information requested in the enclosure to this letter. It is requested that you provide a response within 30 days of receipt of this letter. It is also requested that the information contained in
' questions 1 and 2 be provided to the staff via teleconference (with written followup) as soon as -
convenient for your staff.
Sincereiy, ORIGINAL SIGNED BY Timothy G. Colbum, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
Request for Additional Information cc w/ encl: See next page Distnbution-I Docket File PUBLIC (t f PDI-3 Rdg.
J. Zwolinski C. Thomas T. Clark T. Colbum K. Wichman A. Hiser OGC
/)
ACRS C. Hehl, RI B. Elliot W.~ Smidt M. Evans
~ NAME: G:\\COLBURN\\TMIA1403.RAI To rective a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PDl-3/LA, y LL PDI-3/PM l
PD}8/PD _ lA) l NAME TClark Ck2D TColbum MIw -
@W DATE 05/R/98
- 05//,l98 05/) 998 OFFICIAL RECORD COPY en 4
9005100337 990513
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J.Langenbach Three Mile Island Nuclear Station, Unit No.1 cc:
Michael Ross Robert B. Borsum Director, O&M, TMl B&W Nuclear Technologies GPU Nuclear, Inc.
Suite 525 P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 John C. Fomicola William Domsife, Acting Director Director, Planning and Bureau of Radiation Protection Regulatory Affairs Pennsylvania Department of GPU Nuclear, Inc.
Environmental Resources 100 Interpace Parkway P.O. Box 2063 Parsippany, NJ 07054 Hanisburg, PA 17120 Jack S. Wetmore Dr. Judith Johnsrud Manager, TMI Regulatory Affairs National Energy Committee GPU Nuclear, Inc.
Sierra Club P.O. Box 480 433 Orlando Avenue Middletown, PA 17057 State College, PA 16803 Emest L. Blake, Jr., Esquire Peter W. Eselgroth, Region i Shaw, Pittman, Potts & Trowbridge U.S. Nuclear Regulatory Commission 2300 N Street, NW.
475 Auendale Road Washington, DC 20037 King of Prussia, PA 19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Hanisburg, 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 P.O. Box 21g Middletown, PA 17057
' Regional Administrator Region i U.S. Nuclear Regulatc,ry Commission 475 Allendale Road King of Prussia, PA 19406
REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND flUCLEAR STATION UNIT 1 TSCR No. 270
- 1. Provide the reactor pressure vessel (RPV) wall thickness and RPV inside diameter used in calculation of the submitted P-T curves.
- 2. Is the RPV wall thickness constant within the beltline region? If not, provide details conceming the geometry and location of the region with the varying wall thickness.
- 3. Provide the vessel fluences and location of the fluence values (e.g., wetted surface, clad-base metal interface, etc.) for the various beltline material at 17.7 EFPY used in calculation of the submitted PT curves. Also provide the thickness of the stainless steel cladding (if any) used for attenuation of the fluence through the RPV wall.
- 4. Provide a copy of GPU Nuclear calculation no. C-1101-221-E520-13 Rev. O and FTl calculation no. 32-5001065-01 (References 6 and 7 on page 3-5 of the submittal.
Enclosure
May 13, 1998 bCb Mr. James W. Langenbach, Vice President and Director-TMI-1 GPU Nuclear, Inc.
l P.O. Box 480 l
Middletown, PA 17057
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1)- TECHNICAL SPECIFICATION CHANGE REQUEST NO. 270 TO RPV i
l PRESSURE / TEMPERATURE LIMITS - REQUEST FOR ADDITIONAL i
INFORMATION (TAC NO. MA1403)
Dear Mr. Langenbach:
By letter dated March 23,1998, GPU Nuclear Inc. submitted a request (TSCR No. 270), to amend the pressure and temperature (P-T) limits in the Technical Specifications for TMI-1. In order for the staff to complete its review of your request, please provide the additional information requested in the enclosure to this letter. It is requested that you provide a response within 30 days of receipt of this letter. It is also requested that the information contained in l
questions 1 and 2 be provided to the staff via teleconference (with written followup) as soon as l
convenient for your staff.
Sincerely, l
ORIGINAL SIGNED BY l
Timothy G. Colbum, Senior Project Manager Project Directorate 1-3 l
Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation Docket No. 50-289 i
(
Enclosure:
Request for Additional Information l
cc w/ encl: See next page l
Distribution:
Docket File PUBLIC PDl-3 Rdg.
J. Zwolinski C. Thomas T. Clark T. Colbum K. Wichman A. Hiser OGC ACRS C. Hehl, RI B. Elliot W. Smidt M. Evans j NAME: G:\\COLBURN\\TMIA1403.RAI l To rec;ive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PDi-3/LA,.
ll. PDI-3/PM
[
PD}8/PD _ lN l
NAME TClark 'LW TColbum VJze-
@Kat DATE 05/,298 05//,198 050 998 OFFICIAL RECORD COPY
J.Langenbach Three Mile Island Nuclear Station, Unit No.1 cc:
Michael Ross Robert B. Borsum l
Director, O&M, TMl B&W Nuclear Technologies GPU Nuclear, Inc.
Suite 525 P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 -
l John C. Fomicola William Domsife, Acting Director l
Director, Planning and Bureau of Radiation Protection Regulatory Affairs Pennsylvania Department of GPU Nuclear, Inc.
Environmental Resources 100 Interpace Parkway P.O. Box 2063 l
Parsippany, NJ 07054 Harrisburg, PA 17120 l
Jack S. Wetmore Dr. Judith Johnsrud l
Manager, TMI Regulatory Affairs National Energy Committee GPU Nuclear, Inc.
Sierra Club P.O. Box 480 433 Orlando Avenue l
Middletown, PA 17057 State College, PA 16803 Emest L. Blake, Jr., Esquire Peter W. Eselssoth, Region l Shaw, Pittman, Potts & Trowbridge U.S. Nuclear Regulatory Commission l
l 2300 N Street, NW.
475 Allendale Road i
l Washington, DC 20037 King of Prussia. PA 19406 l
Chairman i
Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 l
Chairman Board of Supervisors l
of Londonderry Township l
R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L Schmidt Senior Resident inspector (TMI-1)
U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Regional Administrator Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION UNIT 1 TSCR NO. 270
- 1. Provide the reactor pressure vessel (RPV) wa'l thickness and RPV inside diameter used in calculation of the submitted P-T curves.
- 2. Is the RPV wall thickness constant within the beltline region? If not, provide details I
concoming the geometry and location of the region with the varying wall thickness.
j
- 3. Provide the vessel fluences and location of the fluence values (e.g., wetted surface, clad-base metal interface, etc.) for the various beltline material at 17.7 EFPY used in calculation of the submitted PT curves. Also provide the thickness of the stainless steel cladding (if any) used for attenuation of the fluence through the RPV wall.
- 4. Provide a copy of GPU Nuclear calculation no. C-1101-221-E520-13 Rev. O and FTl calculation no. 32-5001065-01 (References 6 and 7 on page 3-5 of the submittal.
1 i
Enclosure