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{{#Wiki_filter:( ommonw c.ilth 1:th%on ( aimp.in3 | {{#Wiki_filter:( ommonw c.ilth 1:th%on ( aimp.in3 | ||
,I | |||
, liranlwinn!(ecncr;stmg Station I44 811(c C l. llal% M 8 | |||
Tei sis. ss .:so February 15,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Den Washington,DC 20555 Braidwood Station, Units 1 and 2 Facility Operating License No. NPF-72 and NPF-77 NRC Docket No. STN 50-456 and STN 50-451 | ,lirat es elle, if (O 60">X:l') | ||
Tei sis. ss.:so February 15,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Den Washington,DC 20555 Braidwood Station, Units 1 and 2 Facility Operating License No. NPF-72 and NPF-77 NRC Docket No. STN 50-456 and STN 50-451 | |||
==Subject:== | ==Subject:== | ||
Braidwood Station, Unit 1 Cycle 8 and Unit 2 Cycle 7, Core Operating Limits Report The Nuclear Regulatory Commission has recently approved the Braidwood Station Improved Technical Specifications licensing submittal for use. The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for the operating cycles consistent with Generic Letter 88-16 and the Technical Specifications. | Braidwood Station, Unit 1 Cycle 8 and Unit 2 Cycle 7, Core Operating Limits Report The Nuclear Regulatory Commission has recently approved the Braidwood Station Improved Technical Specifications licensing submittal for use. The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for the operating cycles consistent with Generic Letter 88-16 and the Technical Specifications. | ||
The Braidwood cores, which consists of NRC approved fuel designs, were designed to operate within approved fuel design criteria, Technical Specifications and related bases such that: | The Braidwood cores, which consists of NRC approved fuel designs, were designed to operate within approved fuel design criteria, Technical Specifications and related bases such that: | ||
/ | |||
1) core operating characteristics will be equivalent to or less limiting than those previously reviewed and accepted or | |||
/ | |||
limiting postulated UFSAR events which could be affected by the | 2) re-analyses or re-evaluations have been performed demonstrate that the | ||
included values are within allowable limits. | /ld/ | ||
4 9902250022 990215 PDR | limiting postulated UFSAR events which could be affected by the included values are within allowable limits. | ||
A 1'nh om compam | The reload licensing analyses performed utilized NRC approved methodologies. The cycle specific power distribution limits for Unit 1 Cycle 8 and Unit 2 Cycle 7 are presented in the attached COLR. | ||
4 9902250022 990215 PDR ADOCK 05000456 P | |||
PDR A 1'nh om compam | |||
o | o February 15,1999 U.S. Nuclear Regulatory Commission Page 2 of 2 Comed has performed a detail review of the relevant reload licensing documents, the associated bases, and references. Based on that review, a safety evaluation was prepared, as required by 10CFR50.59, which concluded that the included values present no unreviewed safety questions. | ||
If there are any questions regarding this matter please contact this office. | If there are any questions regarding this matter please contact this office. | ||
f Ti othy J. Tulon ice President raidwood Nuclear Generating Station | f Ti othy J. Tulon ice President raidwood Nuclear Generating Station | ||
==Attachment:== | ==Attachment:== | ||
Core Operating Limits Report, Braidwood Unit 1 Cycle 8 and Draidwood Unit 2 Cycle 7 cc: | Core Operating Limits Report, Braidwood Unit 1 Cycle 8 and Draidwood Unit 2 Cycle 7 cc: | ||
Regional Administrator - USNRC, RIII NRC Senior Resident inspector - Byron Station NRC Senior Resident Inspector - Braidwood Station nrcS9006tjt. doc}} | |||
Latest revision as of 23:04, 6 December 2024
| ML20206U894 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/15/1999 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20206U898 | List: |
| References | |
| GL-88-16, NUDOCS 9902250022 | |
| Download: ML20206U894 (2) | |
Text
( ommonw c.ilth 1:th%on ( aimp.in3
,I
, liranlwinn!(ecncr;stmg Station I44 811(c C l. llal% M 8
,lirat es elle, if (O 60">X:l')
Tei sis. ss.:so February 15,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Den Washington,DC 20555 Braidwood Station, Units 1 and 2 Facility Operating License No. NPF-72 and NPF-77 NRC Docket No. STN 50-456 and STN 50-451
Subject:
Braidwood Station, Unit 1 Cycle 8 and Unit 2 Cycle 7, Core Operating Limits Report The Nuclear Regulatory Commission has recently approved the Braidwood Station Improved Technical Specifications licensing submittal for use. The purpose of this letter is to transmit the Core Operating Limits Report (COLR) for the operating cycles consistent with Generic Letter 88-16 and the Technical Specifications.
The Braidwood cores, which consists of NRC approved fuel designs, were designed to operate within approved fuel design criteria, Technical Specifications and related bases such that:
/
1) core operating characteristics will be equivalent to or less limiting than those previously reviewed and accepted or
/
2) re-analyses or re-evaluations have been performed demonstrate that the
/ld/
limiting postulated UFSAR events which could be affected by the included values are within allowable limits.
The reload licensing analyses performed utilized NRC approved methodologies. The cycle specific power distribution limits for Unit 1 Cycle 8 and Unit 2 Cycle 7 are presented in the attached COLR.
4 9902250022 990215 PDR ADOCK 05000456 P
PDR A 1'nh om compam
o February 15,1999 U.S. Nuclear Regulatory Commission Page 2 of 2 Comed has performed a detail review of the relevant reload licensing documents, the associated bases, and references. Based on that review, a safety evaluation was prepared, as required by 10CFR50.59, which concluded that the included values present no unreviewed safety questions.
If there are any questions regarding this matter please contact this office.
f Ti othy J. Tulon ice President raidwood Nuclear Generating Station
Attachment:
Core Operating Limits Report, Braidwood Unit 1 Cycle 8 and Draidwood Unit 2 Cycle 7 cc:
Regional Administrator - USNRC, RIII NRC Senior Resident inspector - Byron Station NRC Senior Resident Inspector - Braidwood Station nrcS9006tjt. doc