View source for BSEP-87-1008, Responds to Violations Noted in Insp Repts 50-324/87-23 & 50-325/87-23.Corrective Actions:Standing Instruction for Security Sweep of Protected/Vital Areas to Ensure Personnel Notification of Emergencies & Mods Re Vol Override Function

{{Adams
| number = ML20238C331
| issue date = 09/04/1987
| title = Responds to Violations Noted in Insp Repts 50-324/87-23 & 50-325/87-23.Corrective Actions:Standing Instruction for Security Sweep of Protected/Vital Areas to Ensure Personnel Notification of Emergencies & Mods Re Vol Override Function
| author name = Dietz C
| author affiliation = CAROLINA POWER &amp; LIGHT CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000324, 05000325
| license number = 
| contact person = 
| document report number = BSEP-87-1008, NUDOCS 8709100041
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

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CD&L                                                                                            1 Carolina Power & Light Company u
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Brunswick Steam Electric Plant P. O. Box 10429                                                                                    ,
Southport, NC 28461-0429                                                                                ?
September 4, 1987 FILE:- B09-135100                                                                                       10CFR2.201-SERIAL:   BSEP/87-1008 NRC Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO INFRACTIONS OF NRC REQUIREMENTS Gentlemen:
The Brunswick Steam Electric Plant (BSEP) has received I&E Inspection Report 50-325/87-23 and 50-324/87-23 and finds that it does not contain information of a proprietary nature.
This report identified one item that appeared to be in noncompliance with NRC requirements. Enclosed is Carolina Power & Light Company's response to this violation.
Very truly yours, d'y       m C. R. Dietz, General Manager Brunswick Steam Electric Plant MJP/mcg Enclosure cc:   Dr. J. Nelson Gra.:e J
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G709100041 870904                                                                                                       (I, PDR    ADOCK 05000324 Q-                    PDR
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VIOLATION 10CFR50.54(q) states that a licensee authorized to operate a nuclear power reactor shall follow and maintain in effect emergency plans which meet the standards of 50.47(b) and the requirements of 10CFR50, Appendix E.
The Brunswick Plant Emergency Plan, Revision 22, Section 4.4.2.1 states that the on-site public address system and appropriate alarms will be used to warn / alert and notify on-site personnel of an emergency and necessary protective actions as described in the Plant Emergency Procedures.
Contrary to the above, the Brunswick Plant Emergency Plan was not adequately maintained in effect in that the on site public address unit in the Feedwater Pump Room 1A area was found inaudible and inoperable during a special test of the evacuation siren system on July 15, 1987. Thus, this area of the plant was' isolated from the public address / evacuation siren. Personnel present in the area could not have been informed by the on-site public address system of an emergency and the need for evacuarion or protective action in the event of an emergency.
This is a Severity Level V violation (Supplement VIII).

===RESPONSE===
I. Admission or Denial of the Alleged Violation Carolina Power & Light Company acknowledges that the Brunswick plant Emergency Plan was not adequately maintained in that the on-site public address unit in the Feedwater Pump Room 1A was inoperable ~during a special test of the evacuation siren system on July 15, 1987.
Consequently, this area of the plant was isolated from the public address / evacuation siren which potentially prevented personnel in the pump room from being informed by the on-site public address system of an emergency and the need for evacuation.
II. Reason for the Violation A Work Request / Job Order (WR/J0) was initiated to determine the cause of the 1A Reactor Feed Pump Room PA not working correctly. The investigation determined that the amplifier of the associated PA had failed and' required replacement. It was also determined that this failure had occurred subsequent to previous testing which indicated the PA was correctly working.

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III. Corrective Steps'Which Have Been Taken                                                       ?>      ca -  .
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                                                                                                                 <-     j As noted, a WR/JO was' initiated (July 17, 1987) to' correct L t.e problem.3                        ]
with the PA unit. Maintenance activities relative to this WR/JO                            ,;     t commenced on July 21, 1987, and were completed'on July 23, 1987.       In 6                      '
additiontothecorrectionoftheidentifiedPAproblem,areviewofth4 plant modifications for PA volume overrides was performed to ensure thai.
PA units requiring this feature-(such as the 1A Feedwater Pump Room) had been installed. This review determined that 63 of approximately 180 PA units had been declared fully operable in accordance with plant modifi-cation procedures. Engineering personnel are currently addressing the modifications to ensure timely resolution and full operability of the remaining pas to be modified.
               -Prior to the identification of this PA failure, compensatory actions had                                !
been taken to assure that personnel are evacuated from affected plant areas until the plant modifications are completed. This consists of a
               . standing instruction (still in effect) for security to sweep the                                          ;
protected / vital areas to ensure personnel notification during an                                      j emergency.
IV. Corrective Steps Which Will Be Taken Timely completion of the modifications which install volume override functions will be performed. This will allew necessary maintenance and testing to be-adequately accomplished on (approximately) 180 PA units required to meet the requirements for emergency evacuation.
V. Date When Full Compliance Will Be Achieved Full operability of the PA system override modifications will be achieved as follows:
Unit 1     Unit 2 Accessible PA systems                8/1/88    7/1/88 Inaccessible PA systems              1/31/89   7/1/88 1
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