ML20236Y025

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Forwards Drawings Showing Changes to Design of Alternate Rod Injection Sys to Address NRC 870918 Concerns Discussed in SER Re Compliance W/Atws rule,10CFR50.62
ML20236Y025
Person / Time
Site: Brunswick  
Issue date: 12/04/1987
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NLS-87-262, NUDOCS 8712110036
Download: ML20236Y025 (5)


Text

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CP&L Carolina Power & Light Company DEC 0 4 M47 SERIAL:

NLS-87-262 10CFR50.62 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 ATWS-ARI DRAWINGS Gentlemen:

On September 18, 1987, the NRC issued a Safety Evaluation Report (SER) for the Brunswick Steam Electric Plant ( BSEP), Units 1 and 2 concerning compliance with the ATWS Rule, 10CFR50.62.

In that SER, the NRC concluded that the testabi?ity features of the alternate rod injection (ARI) system while at power is not acceptable.

It also stated that Carolina Power & Light Company (CP&L) should modify the testability portion of the ARI design so that surveillance testing while at power does not prevent the ARI system from responding to an automatic or manual ARI initiation signal.

Carolina Power & Light Company has changed the design of the ARI system to address the NRC concerns discussed in the September 18, 1987 SER.

The ARI system has been redesigned to j

allow testing at power without preventing the system from providing its intended protection while testing is in progress.

The enclosed drawings, which replace Figures 10, 11, and 12 of CP&L's June 18, 1987 submittal, show these changes.

More contacts were added to the test isolation switches to allow isolation of a single circuit, allowing the other to remain available for ARI initiation.

The Company intends to install the proposed ARI system on BSEP-2 during the upcoming outage, which is scheduled to begin on January 2, 1988.

8712110036 871204 PDR ADOCK 05000324 P

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411 reyettevme street

  • P o Box 1551. Rate'99 N C 27602 trrCr:mW:Crr:23rnicmrmm2LM7210 l

Document Control Desk NLS-87-262 / Page 2 Please refer any questions regarding this submittal to Mr. Stephen D.

Floyd at (919) 836-6901.

Yours very truly, S.

Zimmerman Manager Nuclear Licensing Section f

/BAB (\\cor\\)

i Enclosure cc:

Dr. J.

Nelson Grace Mr. W.

H. Ruland q

Mr.

E.

D.

Sylvester j

9 9

ENCLOSURE 1 ALTERNATE ROD INJECTION SYSTEM DRAWINGS i

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