ML19242D544
| ML19242D544 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/07/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 7908150398 | |
| Download: ML19242D544 (1) | |
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UNITED S TATES
'j NUCLEAR REGULATORY COMMISSION REGION 111 o, h ", ' "[E 5 '-
799 ROOSEVELT ROAD
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GLEN E LLYN, lLLINOIS 60137 AUG 7 1979 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, EI 532(1 Gentlemen:
The enclosed IE Bulletin No. 79-18 is forwarded to you for action.
A written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
- E $^
James C. Kepp er Director
Enclosure:
IE Bulletin No. 79-18 cc w/ encl:
Mr. G. A. Reed, P ant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Trammell, ORB $RR PDR Local PDR NSIC TIC Sandra A. Bast, Lakeshore Citizens for Safe Energy 631G15 g 9081.50 393
Accessions No: 7908030403
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6 8.'.0 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 7, 1979 IE Bulletin Ro. 79-18 AUDIBILITY PROBLEMS EHCOUNTERED ON EVACUATION OF PERSONNEL YROM HIGH-NOISE AREAS Description of Circumstances:
In January 1979, a number of licensee personnel were engaged in routine activities in the auxiliary building at the Florida Power Corporation, Crystal River Unit 3 nuclear plant. While these individuals were working in the auxiliary building, in a high-noise (fan) area, an unplanned release of radio-active noble gases was detected by building monitors within the auxiliary building at concentrations which caused the licensee to initiate the facility emergency plan auxiliary building evacuation procedure.
The facility Emer-ge.ncy Officer (Shift Supervisor) assessed the monitor readings and initiated an auxiliary building evacuation.
The evacuation announcement, made over the licensee's PA system, was not heard by the personnel working in the high-noise Licensee personnel did evacuate the auxiliary building upon observing area.
tbst other personnel had left, and after calling the control room to inquire if an evacuation had been initiated.
During these occurrences, licensee personnel were not exposed to quantities of radionuclidcs above regulatory guidance. Bovever, the potential existed for inadvertent unnecessary txposure of individuals to radioactive materials.
Subsequent to the NRC follovup inspection of this occurrence, Florida Power Corporation initiated an assessment of this situation and performed an engineering evaluation and identified several plant areas where the annon-ciator system needed audibility improvement. The licensee has installed a new auxiliary building evacuation tone signal and may add vi.sual alarm indi-cators in areas of very high-noise.
Action to be Taken by the Licensees:
For all power reactor facilities with an operating license:
1.
Determine whether current alarm syste=s and evacuation announcement systems are clearly audible or visible throughout all plant areas with e=phasis on high-noise areas. Determination in high noise areas must be made with the maximum anticipated noise level.
631016 receoe04-04
IE Bulletin No. 79-18 August 7, 1979 Page 2 of 2
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2.
Determine what corrective action is necesacry to assure that areas identified as inaudible areas in (1) above, will receive adequate audible /
visual evacuation signals.
In areas where adequate audible /visuni evacua-tion signals cannot be assured by hardwarc changes, determine wbst addi-tional administrative measures are necessary to assure personne) evacuation.
3.
Submit within 45 days of the date of issuance of thia Bulletin, a written report of the findings on item (1), and delineete co=pleted or proposed corrective actions per ite= (2). For operating facilities in a refueling or extended outage, the written report must be submitted within 30 days after plant startup following the outage.
4.
For accessible areas, all corrective actions determined per item (2) must be completed within 120 days of the date of issuance of this Bulletin.
For inaccessible areas, the written report must include a time schedule for co=pletion o' corrective actions in this area.
Reports should be submitted to the Director of the appropriate NRC Ecgional Office and a copy should be forwarded to the NRC Off ce of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C. 20555.
For all power reactor facilities with a construction permit, this Bulletin is for information only and no written response is required.
Approved by GAO, B180223 (R0072); clearance expire 7/31/09 Approval uns given under a blanket clearance specifically for identified generic proble=s.
Enclosure:
List of IE Bulletins Issued in Last 6 Months b31017
.. =-
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 1 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX M0hTHS Bulletin Subject Date Issued Issued To -
No.
79-17 Pipe Cracks in Stagnant 7/26/79 All PWR's with Borated Water Systems at operating license PWR Plants 79-16 Vital Area Access Controls 7/26/79 All Holders of and applicants for Power Reactor Oper. sting Licenses who anticipate loading fuel prior to 1981 79-15 Decp Draft Pu=p 7/11/79 All Power Reactor Deficiencies Licensees with a CP and/or OL 79-14 Seismic Analyses for 6/2/79 All Power Reactor As-Built Safety-Related facilities with an Piping System OL or a CP 79-13 Cracking in Feedvater 6/25/79 All PWRs with an System Piping OL for action. All BWRs with a CP for information.
79-02 Pipe Support B_se Plate 6/21/79 All Power Reactor (Rev. 1)
Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or a CP 79-12 Short Period Scrams at 5/31/79 All GE BWR Facilities BWR Facilities with an OL 79-11 Faulty Overcurrent Trip 5/22/79 All Power Reactor Device in Circuit Breakers Facilities with an for Engineered Safety OL or a CP Systems 79-10 Requalification Training 5/11/79 All Power Reactor Progra= Statistics Facilities with an OL 631018
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 2 of 3 LISTING OF IE "ULLETINS ISSUED IN LAST SIX M0hTES Bulletin Subject Date Issued Issued To No.
79-09 Failures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systems OL or CP 79-08 hvents Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Stress Ana?.ysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with ar OL or CP 79-05C&O6C Nuclear Incident at Three 7/26/79 To all PWR Power Mile Island - Supplement Reactor Facilities with an OL 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and System Mis-ing Designed. tessurized alignments Identified Water Power Reactor During the Three Mile Facilities with an Ireland Incident Operating License 79-06A Review of Operational 4/18/79 All Pressurized Water (Rev 1)
Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident G31G13
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 3 of 3
.tISTING OF IE BULLETINS IESUED IN LAST SIX MONTES Bulletin Subject Date Issued Issued To No.79-05B Nuclear Incident at 5/21/79 All B&W Power K r Three Mile Island Facilities with an OL 79-05A Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 Nuclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP 79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manuf actured by Velan OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reacter Pressure Facilities with an Vessel Welds OL or CP 79-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.79-01A Environmental Qualification 6/6/79 All Power Reactor of Class IE Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves) 691020
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