ML20236H174
| ML20236H174 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/30/1998 |
| From: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20236H176 | List: |
| References | |
| 1920-98-20326, NUDOCS 9807070112 | |
| Download: ML20236H174 (2) | |
Text
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l GPU Nuclear,Inc.
c
(
Route 441 South NUCLEAR Post Office Box 480 j
l Middletown, PA 17057-0480 1
June 30,1998 Telm 944-7en 1920-98-20326 L
U. S. Nuclear Regulatory Commission Attn: Document Control Desk i
Washington, DC 20555 Gentlemen:
Subject:
Three Mile Island Unit No. I Nuclear Generating Station (TMI-1)
Docket No. 50-219 i
Facility Operating License No. DPR-16 Response to Request for Additional Information - Technical Specification Change Request (TSCR) No. 270 to RPV Pressure / Temperature Limits j
'l
Reference:
NRC letter, to J. W. Langenbach, dated May 13,1998, "Three Mile Island Nuclear Station, Unit No.1 (TMI-1)- Technical Specification Change Request No. 270 to RPV Pressure / Temperature Limits - Request for Additional Information (TAC No. MA1403)"
By letter dated March 23,1998, GPU Nuclear submitted a request (TSCR No. 270), to amend the pressure and temperature (P-T) limits in the Technical Specifications for TMI-1.
Subsequently, on May 13,1998, the NRC staff issued a request for additional information (RAI) in order to complete their review of our request. The RAI also requested that the information contained in questions I and 2 be provided to the staff via teleconferences (with written follow-up). On June 8, 1998 GPU Nuclear provided information requested by questions 1,2 and 3 during our teleconference J
with the staff.
Enclosed is our response to the RAI. Included with the response is a revised Technical Specification page,3-5, with Reference 6 updated to reflect the latest revision number (Revision 1) for the requested GPU Nuclear calculation. This calculation was revised in Revision I to incorporates editorial changes to improve clarity. If you have any questions regarding our response, please contact Yosh Nagai at (973) 316-7974 of our Licensing staff.
- incerely, I
f ames W. Lan n ach j
i Vice President Director, TMI
\\
Enclosure Attachments I/Il -
Cc:
Administrator, Region i Q{
TMINRC Project Manager
,U l
TMI NRC Sr. Resident inspector File 98043 k
'9807070112 980630 P PDR ADOCK 05000219; P
PDRn LbUC6
1920-98-20326 Enclosure t
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION i
THREE MILE ISLAND NUCLEAR STATION UNIT 1, TSCR NO 270 Question 1:
Provide the reactor pressure vessel (RPV) wall thickness and inside diameter (l. D.) used in calculation of the submitted P-T curves.
Response
The RPV dimensions used in the calculation of the submitted P-T curves are:
i l
RPV 1. D. to the cladding is 170.625 inches.
Cladding thickness is 3/16 inches.
Base metal thickness is 8.438 inches.
e Question 2:
Is the RPV nll thickness constant within the beltline region? If not, provide details concerning the geometry and location of the region with the varying wall thickness.
Response
Yes, the RPV wall thickness within the beltline region is constant. Only the forged nozzle belt region of the RPV is thicker, and the lower head assembly is thinner. In the beltline area of the circumferential weldments joining these sub-assemblies with the RPV shell assembly, the wall thickness is the same as the shell assembly.
Question 3:
Provide the vessel fluence 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 l
submitted P-T curves. Also provide the thickness of the stainless steel cladding (if any) used for attenuation of the fluence through the RPV wall.
Response
The fluence values for 17.7 EFPY are contained in the attached GPU Nuclear calculation (they were also provided to the staff during our teleconference). The fluences were calculated on the basis of the peak vessel flux at the inside surface of the RPV base metal with an availability factor of 0.935 for future cycles. These values were then adjusted on the basis of the azimuthal and axial correction factors. The RPV through wall attenuation was calculated using the R.G.1.99 Rev 2 attenuation equation. The GPU Nuclear calculation addresses only two weldments, which are of the same material, and have the highest Reg. Guide 1.99, Rev. 2 chemistry factor and margin term of all of the RPV materials, thus, the calculation addresses only the limiting materials for the TMI-l vessel.
Question 4:
Provide a copy of FIT calculation No. 32-5001065-01 and GPU Nuclear calculation No. C-l 1101-221-E520-13 Rev. 0 (Reference 6 and 7 on page 3-5 of the submittal).
Response
He requested calculations are attached (Attachment I and II). Please note that the attached GPU Nuclear calculation C-1101-221-E520-13 has been revised in Revision I to incorporate editorial changes ta improve clarity. Therefore, a revised Technical Specification page 3-5 is included to update Reference 6 with the correct revision number for the GPU Nuclear calculation.
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