ML20079R644
| ML20079R644 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/20/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079R646 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 LAP-83-236, NUDOCS 8306240145 | |
| Download: ML20079R644 (2) | |
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SERIAL: LAP-83-236 Carolina Power & Light Company JUN t o 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 PLANT MODIFICATION TECHNICAL SPECIFICATION REVISION REQUEST
Dear Mr. Denton:
Carolina Power & Light Company (CP&L) has been advised by the NRC Licensing Project Manager, Mr. S. D. MacKay, that NRR does not e.xpect to be able to issue certain administrative Technical Specification (TS) revisions prior to Brunswick Steam Electric Plar.t Unit No.1 (BSEP-1) startup at the end of this month. Therefore, as recommended by the Brunswick NRR Project Manager, CP&L will start up BSEP-1 using the revised Technical Specifications requested in our letters dated April 28, 1983; January 26, 1983; and December 13, 1982. A copy of each of the effective pages is attached for your information. These revised TS pages, will be inserted in the Technical Specifications Interpretation Manual and referenced in the control room copy of the Technical Specifications.
With the exception of the digital-to-analog instrumentation
- changes, the revisions to the subject TS pages involve changes in the form of snubber listings, drywell sump instrumentation numbers, remote shutdown panel instrumentation numbers, installation of NUREG-0737 modifications, and other administrative type changes, and are at least as conservative as the present l
-Technical Specifications.
In the case of the digital-to-analog instrumentation changes, the new analog instruments have longer calibration l
periods with respect to surveillance requirements due to better instrument characteristics. Approval for this longer calibration period was contained in a NRC Safety Evaluation Report (SER) which suppoeted Amendment No. 26 (dated March 14, 1980) for BSEP-1 which stated that the proposed plant modifications were technically acceptable. The SER also stated that future periodic submittals by CP&L revising instrument designations for those systems which had the digital-to-analog modification completed would be considered j
administrative in nature.
8306240145 830620 PDR ADDCK 05000325 i
P PDR
_.,.n....... _ _. _. _ _
Mr. H. R. Denton Accordingly, CP&L believes that use of these draft revised Technical Specifications until the issuance by the NRC of the revised pages is acceptable from a safety viewpoint. It is CP&L's understanding that both Region II and NRR believe that issuance of these revised TS is not required for BSEP-1 startup and have approved this intended action. If we have not been advised that this understanding is incorrect by June 24, 1983, we will proceed with startup of BSEP-1 on schedule.
Carolina Power & Light Company requests that you expedite the appropriate public notice of these changes and issue them as soon as possible. Should you have any questions in regard to this issue, please feel free to contact our staff.
Yours very truly, U.
to.
n P. W. Howe Vice President Brunswick Nuclear Project JSD/kjr (7067JSD)
Enclosure cc:
Mr. D. O. Myers (NRC-BSEP)
Mr.'J. P. O'Reilly (NRC-RII)
Mr. S. D. MacKay (NRC)
Mr. D. B. Vassallo (NRC) 1