ML20070L771: Difference between revisions
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' MamM aer one upper eoac noao s Wwwaw 55n Parsippany, New Jett.ey 07054 201 316-7000 TELEX 136 482 Writer's Direct Dia! Number: | |||
Nrch 12,1991 C321-91-2058 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20355 centlemen | Nrch 12,1991 C321-91-2058 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20355 centlemen | ||
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Docket No. 50-219 Correction to Technical Specification Change Request No. 194 4-The purpose of this letter is to correct a neutron fluence value given on page 3.3.-5 of the proposed Technical Specification Change Request (TSCR) No. 194 which was submitted on January 11, 1991. The TSCR No. 194 proposed new pressure-temperature limits up to 17 EFPY and a new minimum bolt-up temperature for the vessel closure head stud tensioning. | Docket No. 50-219 Correction to Technical Specification Change Request No. 194 4-The purpose of this letter is to correct a neutron fluence value given on page 3.3.-5 of the proposed Technical Specification Change Request (TSCR) No. 194 which was submitted on January 11, 1991. The TSCR No. 194 proposed new pressure-temperature limits up to 17 EFPY and a new minimum bolt-up temperature for the vessel closure head stud tensioning. | ||
An incorrect value was provided inadvertently in the second paragraph of the page 3.3-5 of the proposed technical specification. The second sentence of the second paragraph should read: | An incorrect value was provided inadvertently in the second paragraph of the page 3.3-5 of the proposed technical specification. The second sentence of the second paragraph should read: | ||
"The results of dosimeter wire cnalyses (Reference 14) indicated that the neutron fluence (E>1.0MeV) at the end of 17 effective full power years of 10 2 | |||
10 A fluence value given in our January 11, 1991 submittal was 2.44 x 10 n/ | operation is 1.25x10 n/cm at the 1/47 (T= vessel wall thickness) location". | ||
10 A fluence value given in our January 11, 1991 submittal was 2.44 x 10 2 | |||
n/cm. The correct value was provided in the attachment (page 3-5, GE Nuclear Energy Report, SASR 90-89) to the January 11, 1991 submittal. | |||
The revised page 3.3-5 of the Oyster Creek Tec:nical Specifications with a correct neutron fluence valum is attached to this letter. | The revised page 3.3-5 of the Oyster Creek Tec:nical Specifications with a correct neutron fluence valum is attached to this letter. | ||
Vyryr truly yours, | Vyryr truly yours, j | ||
h d | |||
JJB/YN/cb cc Adminletrator, Region I Senior NRC Resident Innspector Oyster Creek Proioct Manager GPU Nuclear Corporation is a subsd;ary of General Pubic UtAt es Corporation | { | ||
g J. | |||
J 3arton 9103200234 910312 ADOCK05000,g9 I | |||
Di e or, oyster Creek q | |||
PDR P | |||
JJB/YN/cb cc Adminletrator, Region I Senior NRC Resident Innspector Oyster Creek Proioct Manager | |||
$8/ | |||
GPU Nuclear Corporation is a subsd;ary of General Pubic UtAt es Corporation | |||
-j h O n, | |||
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Latest revision as of 09:25, 16 December 2024
| ML20070L771 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/12/1991 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20070L773 | List: |
| References | |
| C321-91-2058, NUDOCS 9103200234 | |
| Download: ML20070L771 (1) | |
Text
_ _....
5 i
d.
A e
GPU Nuclear Corporation
. ()
' MamM aer one upper eoac noao s Wwwaw 55n Parsippany, New Jett.ey 07054 201 316-7000 TELEX 136 482 Writer's Direct Dia! Number:
Nrch 12,1991 C321-91-2058 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20355 centlemen
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 Correction to Technical Specification Change Request No. 194 4-The purpose of this letter is to correct a neutron fluence value given on page 3.3.-5 of the proposed Technical Specification Change Request (TSCR) No. 194 which was submitted on January 11, 1991. The TSCR No. 194 proposed new pressure-temperature limits up to 17 EFPY and a new minimum bolt-up temperature for the vessel closure head stud tensioning.
An incorrect value was provided inadvertently in the second paragraph of the page 3.3-5 of the proposed technical specification. The second sentence of the second paragraph should read:
"The results of dosimeter wire cnalyses (Reference 14) indicated that the neutron fluence (E>1.0MeV) at the end of 17 effective full power years of 10 2
operation is 1.25x10 n/cm at the 1/47 (T= vessel wall thickness) location".
10 A fluence value given in our January 11, 1991 submittal was 2.44 x 10 2
n/cm. The correct value was provided in the attachment (page 3-5, GE Nuclear Energy Report, SASR 90-89) to the January 11, 1991 submittal.
The revised page 3.3-5 of the Oyster Creek Tec:nical Specifications with a correct neutron fluence valum is attached to this letter.
Vyryr truly yours, j
h d
{
g J.
J 3arton 9103200234 910312 ADOCK05000,g9 I
Di e or, oyster Creek q
PDR P
JJB/YN/cb cc Adminletrator, Region I Senior NRC Resident Innspector Oyster Creek Proioct Manager
$8/
GPU Nuclear Corporation is a subsd;ary of General Pubic UtAt es Corporation
-j h O n,
/[j
^