ML20214W957
| ML20214W957 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/03/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20214W911 | List: |
| References | |
| 50-369-87-14, 50-370-87-14, NUDOCS 8706160264 | |
| Download: ML20214W957 (1) | |
Text
o ENCLOSURE 2 NOTICE OF DEVIATION Duke Power Company Docket No. 50-369 McGuire Unit 1 License No. NPF-9 The following deviation was identified during a Nuclear Regulatory Commission (NRC) inspection conducted on April 21 - May 22, 1987.
The McGuire Nuclear Station Final Safety Analysis Report (FSAR), Section 9.5.1.2.1, states that the Fire Protection System is designed to meet the standards developed by the National Fire Protection Association (NFPA) where practicable.
NFPA Standard 12A, "Halon 1301 Fire Extinguishing Systems", Section 1-9.4.6, states that, when manifolded, containers shall be adequately mounted and suitably supported in a rack...".
The McGuire Nuclear Station Fire Protection Review Manual responded to positions presented in Appendix A to Branch Technical Position APCSB 9.5-1.
Position E.4, "Halon Suppression Systems", states that the use of halon fire extinguishing agents should, as a minimum, comply with the requirements of NFPA 12A.
The licensee's response failed to take exception to the Branch Technical Position and stated that approved halon 1301 systems were available for the steam-driven auxiliary feedwater (CA) pumps.
Drawing MCM 1206.07-30, Sheet 3, illustrates the Unit 1 CA halon 1301 system as being rack mounted to provide suitable support.
Contrary to the above, the Unit 1 CA halon 1301 system was not constructed in accordance with applicable design drawings and industry standards as committed to the NRC, in that the manifolded containers were not adequately mounted and suitable supported.
Please provide in writing within 30 days of the date of this Notice a description of corrective actions regarding this deviation, actions taken to avoid further deviations, and the dates when these actions were or will be completed.
FOR THE NUCLEAR REGULATORY COMMISSION 8706160264 870603
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DR ADOCK 0 369 g
g gyg, Luis A. Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this Sep day of May 1987