ML19275A834
| ML19275A834 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/21/1979 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7910190170 | |
| Download: ML19275A834 (3) | |
Text
5 E
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 JOSEPH W. G ALLAGH ER (215) 841-5o03 aLseTmc encoucv on os-antuant September 21, 1979 Re:
Docket Nos.:
50-277 50-278 lE Bulletin 79-18 Mr. Boyce H.
Grier, Director Office of Inspection & Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This letter is in response to IE Bulletin 79-18, forwarded to us on August 7,
1979, concerning audibility problems encountered on evacuation of personnel from high-noise areas.
The " Action to be Taken by Licensees" and our responses are treated sequentially.
Action to be Taken by Licensee 1.
Determine whether current alarm systems and evacuation announcement systems are clearly audible or visible throughout all plant areas with emphasis on high-noise areas.
Determination in high-noise areas must be made with the maximum anticipated noise level.
Resnonse An existing routine testing procedure (RT 2.6.1 Internal Plant Noise Level Test) was performed between August 14 and September 19, 1979 This test measures noise level in the plant reactor buildings, turbine buildings, radwaste building, recombiner building, emergency diesel generator building, cooling tower pump structures, circulating water pump structures, auxiliary pump structures and auxiliary boiler house.
In each of these areas, g,7()
i180 266 7910190
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4 4
Mr. Boyce H.
Grier Page 2 noise level was measured and a determination was made whether or not a PA announcement was audible over the background noise.
This test was performed during plant operation such that the normal background noise was present during most of the test period.
The test covered all areas which are normally accessible during plant operation.
Some inaccessible high radiation areas were not included.
This test identified those areas where the PA was inaudible.
Since the evacuation alarm system operates through the PA system, performance of this test has determined those areas which require corrective action.
2.
Determine what corrective action is necessary to assure that areas identified as inaudible areas in (1) above, will receive adequate audible / visual evacuation signals.
In areas where adequate audible / visual evacuation signals cannot be assured by hardware changes, determine what additional administrative measures are necessary to assure personnel evacuation.
Response
Performance of procedure RT 2.6.1 identified areas which require corrective action.
Corrective actions fall into one of the three following categories: 1) repair of existing PA's, 2) installation of new PA's, and 3) installation of visual means of alerting personnel.
Corrective action is being taken to repair defective PA's.
Procurement and installation of additional PA's will be accomplished as expeditiously as possible.
Electrical Engineering has been assigned the responsibility for designing, procuring, and installing required visual alerting systems.
The estimated completion of necessary repairs and modifications 13 on or before December 5, 1979, contingent upon availability of materials and radiological conditions.
Peach Bottom presently has various administrative and emergency procedures that control pe sonnel activities during plant evacuation.
This includes personnel accountability procedures which would be initiated immediately following a plant evacuation.
This mechanism ould insure rapid identification and notification of an individu21 who did not respond during a plant evacuation.
Personnel working in high radiation areas are normally aided by craft or Health Physics personnel outside the high radiation areas.
This mechanism would insure notification of these individuals working in high radiation areas during local area evacuations.
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4 Mr. Boyce H.
Grier Page 3 The established p rocedu res are adequate to insure personnel safety until the erhancements in the PA system and the evacuation alarm system can be provided.
Very truly yours, hel lt Y cc:
U r.i t e d States Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555 1180 268