ML20246D437
| ML20246D437 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/02/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NLS-89-096, NLS-89-96, TAC-60429, TAC-60430, NUDOCS 8905100225 | |
| Download: ML20246D437 (2) | |
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Carolina Power & Light Company l
MM 021989 SERIAL:
NLS-89-096' l
United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 NUREG-0737 ITEM II.F.2 (NRC TAC NOS, 60429 AND 60430)
Gentlemen:
On March 30, 1989, the NRC Project Manager for the Brunswick Steam Electric Plant, Units 1 and 2 requesged information supporting closeout of NUREG-0737, Item II.F.2.
This information is provided herein.
Reference ter Modification On December 10, 1984, Carolina Power & Light Company (CP&L) submitted a response to Generic Letter 84-23 stating that the Company was pursuing an engineering evaluation of potential design modifications to improve reactor vessel water level indication errors. caused by hi h drywell S
temperature. Among the options being considered were reference leg cooling and reference leg vertical drop reduction.
Based'on this evaluation, plans to reduce the length of the reference leg vertical drop in the drywell were submitted to the NRC on December 19, 1985.
The required modifications have been completed and declared operable (i.e., installed, training complete, and procedures implemented) for Unit 1 on March 29, 1989, and for Unit 2 on April 18, 1988.
Mechnnical Indication Eauipment As discussed in our December 10, 1984 submittal, the mechanical indication equipment at BSEP has been replaced with an analog' trip system. Amendment 26 to the Unit 1 Technical Specifications and Amendment 50 to the Unit 2 Technical Specifications, issued March 14, 1980, f,trst reflected replacement of certain digital instrumentation, including vessel water level instrumentation, with analog instrumentation.
Subsequently, Amendment 60 to the Unit 1 Technical Specifications, issued December 12, 1983,. and Amendment 97 to the Unit 2 Technical Specifications, issued June 7, 1984, reflected digital to analog instrumentation changes in the reactor protection system, containment isolation system, reactor core cooling system, and the emergency core cooling system.
j 8905100225 890502 l
gDR ADOCK0500gg4 411 Fayettevme Street
- P. O. Box 1551
- Raleigh, N. C. 27602 h!
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Document Control Desk
'NLS-89-096 / Page 2 Because the analog trip system is currently addressed in the Technical Specifications, and due to lack of NRC guidance on incorporation of additional information, the Company has determined that no additional Technical Specifications changes are necessary and that this issue is closed.
Please refer any questions regarding this submittal to Mr. Stephen D.
Floyd at (919) 546-6901.
Yours very truly, fD 2 Leonard I.
oflin l
Manag:r l
Nuclear Licensing Section l
l BAB/bab
(\\cor\\iif2) l cc:
Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny 1
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