ML20247C455
| ML20247C455 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/06/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247C462 | List: |
| References | |
| NLS-89-250, NUDOCS 8909130372 | |
| Download: ML20247C455 (2) | |
Text
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gpat Carolina Power & Light Company SEP 0 61989 i
SERIAL: NLS-89-250 United States Nuclear Regulatory Commission i
ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 6 50-324/ LICENSE NOS. DPR-71 & DPR-62 CORRECTIONS TO RECEN1LY ISSUED LICENSE AMENDMENTS Gentlemen:
Carolina Power & Light Company has reviewed several recently issued license amendments for the Brunswick Steam Electric Plant, Units 1 and 2 and identified several corrections which are required. An explanation of each of the necessary corrections is provided below.
Amendment Nos. J30 and 160:
On May 22, 1989, the NRC issued Amendment Nos. 130 and 160 for Brunswick Unit 1 and Unit 2, respectively. These amendments deleted instrument tag numbers from the Technical Specifications, deleted one-time exceptions which were added as footnotes, and provided other editorial and administrative changes. Technical Specification Table 3.3.4-1 was re-oriented to an upright position and the instrument tag numbers removed. However, the associated Notes page for Table 3.3.4-1 was not properly updated to reflect a previously issued amendment (Amendment Nos. 112 and 139 dated September 24, 1987 for Units 1 and 2, respectively) which revised footnote (f). This footnote was previously changed to requir.. the rod block monitor to be operable when rated thermal power is greater than or equal to 30 percent.
Enclosed are revised Technical Specification pages for both Unit 1 and Unit 2 which correct this error.
Amendment Nos. 132 and 162:
On June 12, 1989, the NRC issued Amendment Nos. 132 and 162 for Brunswick Unit 1 and Unit 2, respectively. These amendments revised Technical Specification Section 3/4.3.2 to include Limiting Conditions for Operation and Surveillance Requirements to ensure the capability of the main stack radiation monitor circuitry to isolate the primary containment purge and vent valves.
Technical Specification Table 3.3.2-2 war. revised to add Item 1 g, " Main Stack Radiation - High" to the table. However, due to a typographical error, both the trip setpoint and the allowable value setpoint for Item 1.c.1, " Main Steam Line Radiation - High' were inadvertently changed to "<" (i.e., less than) rather than the originally designated "s" (i.e., less than or equal to).
Enclosed are revised Technical Specification pages for both Unit 1 and Unit 2 which correct this error.
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- P. O Box 1551
- Raleigg N C 27602 8909130372 890906 N"5"#""*"MMM I
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.Dacur:nt Control Dack NLS-89-250 / Page 2 Amendment Nos. 133 and 163:
On June 13, 1989, the NRC issued Amendment Nos. 133 and 163 for Brunswick Unit 1 and Unit 2, respectively. These amendments revised the index section of the Technical Specifications to be consistent with the titles shown in the text and the pagination of the sections. However, page V of the index section for Unit 2 did not correctly reflect the repagination of Technical Specification Section 3/4.3 due to the issuance of Amendment No. 160 dated May 22, 1989 for Unit 2.
Enclosed is a revised Technical Specification page for Unit 2 which corrects this error.
Amendment Nos. 136 and 166:
On August 4, 1989, the NRC issued Amendment Nos. 136 and 166 for Erunswick Unit 1 and Unit 2, respectively. Thes; amendments revised Technical j
Specification 4.6.1.2 to allow the use of any integrated leak test method j
permitted by 10 CFR 50, Appendix J.
Bases section 3/4.6.1.2 was revised to l
describe the use of either the mass-point method or the Total Time method for performing integrated leak rate tests. However, the Bases pages were not properly updatta to reflect a previously issued amendment (Amendment Nos. 128 and 158 dated April 25, 1989 for Units 1 and 2, respectively) concerning primary containment airlocks.
Enclosed are revised Technical Specification bases pages for both Unit 1 and Unit 2 which correct this error.
The Company regrets any inconvenience these oversights may have caused the Staff. Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.
Yours very truly, l
Leonard I.
flin Manage j
Nuclear Licensing Section j
WRM/wrm
(\\cor\\ correct)
Enclosures l
cc:
Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny l