ML20071L062

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Application to Amend Licenses DPR-71 & DPR-62 Tech Specs, Reflecting Change in ECCS Actuation Instrumentation Setpoints & Concomitant Surveillance Requirements.Change Request Involves Single Technical Issue
ML20071L062
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 07/29/1982
From: Howe P
CAROLINA POWER & LIGHT CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML20071L064 List:
References
NUDOCS 8208020318
Download: ML20071L062 (2)


Text

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l Carolina Power & Light Company JUL 29 1982 Office of Nuclear Reactor Regulation ATTN:

Mr. D. B. Vassal'lo, Chief Operating Reactors Branch No. 2 United States Nuclear Regulatory Commission Washington, D.C.

20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 TECHNICAL SPECIFICATION REVISION REQUEST DEGRADED VOLTAGE RELAYS

Dear Mr. Vassallo:

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP) Unit Nos. I and 2.

The revisions reflect a change in emergency core cooling system (ECCS) actuation instrumentation setpoints and concomitant surveillance requirements.

DISCUSSION Following investigation of a June 28, 1982 reactor scram on BSEP Unit No. 1, CP&L determined Degraded Voltage Surveillance Tests on Unit I were not being performed. The NRC was promptly notified of this discovery.

Continuing investigation of the above included a thorough examination of the NRC Safety Evaluation and Staff Position Relative to Emergency Power Systems (EPS) for Operating Reactors (dated June 3, 1977), the installed plant modification ard proposed TS (filed March 6, 1979), and NRC approval of the TS changes (dated June 11, 1980). Results of the investigation determined incorrect relays were referenced in the plant modification and therefore, the incorrect setpoint values were incorporated in TS.

Again, the NRC was promptly notified regarding the investigation results.

Research indicates TS Table 3.3.3-2, Item 5.a. describes Balance-of-Plant (B0P) busses IC, 1D, 2C, and 2D for Device 27.

The correct relay should have been Emergency Busses E-1, E-2, E-3, and E-4, Device 27/59E. The enclosed TS pages correct the aforementioned discrepancies.

069J 8208020318 820729

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ADMINISTRATIVE INFORMATION The enclosed TS revision changes are denoted by a vertical bar in the right-hand margin.

We have evaluated this change request, in accordance with 10CFR170.22, and have determined it involves a single technical issue.

Therefore, a Class III and Class I amendment fee is required for BSEP Unit Nos. 1 and 2, respectively. Our che.ck for $4,400.00 is enclosed as payment of these fees.

Should you have any questions regarding this submittal, please contact our staff.

Yours very truly,

( L)

P. W. Howe Vice President Technical Services i

MSG /1r (311C6T3b)

Enclosures cc: Messrs. J. P. O'Reilly (NRC-RII)

J. A. Van Vliet (NRC)

D. O. Meyers (NRC-BSEP)

P. W. Howe, having been first duly sworn, did depose and say that the information contained herein is true and correct to his own personal knowledge or based upon information and belief.

Y M4&Sst Notary'(Seal) 1"""'88 OCT 041986 1N My commission expires:

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