ML19242D521
| ML19242D521 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/07/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 7908150360 | |
| Download: ML19242D521 (1) | |
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NUCLEAR REGULATORY COMMISSION
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GLEN ELLYN, ILLINOIS 60137 AUG 7 1979 Docket No. 50-461 Docket No. 50-462 Illinois Power Company ATTN:
Mr. W C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 62525 Gentlemen:
The enclosed IE Bulletin No. 79-18 is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, h-James G. Keppler Director
Enclosure:
IE Bulletin No. 79-18 cc w/ encl:
Central Files Director, NRR/DPM Directcr, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General
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Accessions No: 7908030403 SSINS No: 6820 UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENIORCEMENT WASHINGTON, D.C.
20555 August 7, 1979 IE Bulletin No. 79-18 AUDIBILITY PROBLEMS ESCOUhTERID ON EVACUATION OF PERSONNEL FRG.M EIGE-NDISE AREAS Description of Circumstances:
In January 1979, a nur6er of licensee personnel were engaged in routine activities in the auxiliary building at the Florida Power Corporation, Ccfstal 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-gency Officer (Shift Supervisor) assessed the monitor readings and initiated an auxiliary building evacuatior. The evacuation announcement, made over the licensee's PA eystem, was not heard by the personnel working in the high-noise Licensee personnel did evacuate the auxiliary building upon observing area.
tha. other personnel had left, and af ter calling the control room to inquire if an evacuation had been iritiated. During these occurrences, licensee personnel were not exposed to quantities of radionuclides above regulatory guidance. Bovever, the potential existed for inadvertent unnecessary exposure of individuals to radioactive materials.
Subsequent to the NRC follovup inspection of this occurrence, Floride Power Corporation initiated an assessnent of this situation and performed an engineering evaluation and identified several plant areas where the annun-ciator syster needed audibility improvement.
The licensee has installed a new auxiliary building evacuation tone signal and may add visual 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 systene =nd evacuation announcement syste=s are clearly audible or visible :hroughout all plant areas with e=phasis en high-noise creas. Determination in high noise areas r.ust be made with the ma:Imu= anticipated noire level.
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Il Bulletin No. 79-18 August 7, 1979 Page 2 of 2 2.
Determine what corrective action is necessary to assure that areas identified as inaudible r eas in (1) above, will receive adequate audible /
visual evacuation signals.
In areas where adequate audible / visual evacua-tion signals cannot be assured by hardware changes, determine what addi-tional administrative measures are necessary to assure personnel evacuation.
3.
Submit within 45 days of the date of issuance of this Bulletin, a writ ten report of the findings on ite (1), and delineate completed or proposed corrective actions per ite= (2). For operating facilities in a refueling or extended outage, the written report cust be sub=ltted within 30 days after plant startup following the outage.
4.
For accessible areas, all corrective actions determined per ite: (2) must be co=pleted within 120 days of the date of issuance of this Bulletin.
For inaccessible areas, the written report must include a time schedule for completion of corrective actions in this area.
Raports should be rub =1tted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforce =ent, 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, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic proble=s.
Enclosure:
List of IE Bulletins Issued in Last 6 Months f
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IE Sulletin No. 79-18 Enclosure August 7, 1979 Page 1 cf 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To -
No.
79-17 Pipe Cracks in Stagnant 7/26/79 All PWR's with Borated Water Syste=s at operating license PWR Plants 79-16 Vital Area Access Controls 7/26/79 All Holders of and applicants for Power Reactor Operating Licenses who anticipate loading fuel prior to 1981 79-15 Deep 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 Syste=
OL or a CP 79-13 Cracking in Feedwater 6/25/79, All FWRs with an Syste= Piping OL for action. All BWRs with a CP for information.
79-02 Pipe Support Base Plate 6/21/79 All Power Re (Rev. 1)
Designs Using Concrete Facilities with aa Expansion Anchor Bolts OL or a CP 79-12 Short Period Scrs=s at 5/31/79 All CE 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 m
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IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTP.S
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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 Facilitiec with an Related Systens OL or CP 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seiamie Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-05C&O6C Nuclear Incident at Three 7/26/79 To all FWR Power Mile Island - Supplement Reacto: Fecilities with an OL 7 9-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and System Mis-ing Designed Pressurized align =ents identiffed Water Power Reactor During the Three Mlle Facilities with an Island 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 align =ents Identified of Westinghouse Design During the Three Mile with an OL Icland Incident 79-06 Review of Operational 4/11/79 All Pressurited Water Errors and System Mis-Power Reactors with an alignments Identified OL except E&W facilities During the Three Mile Island Incident (p
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IE Bulletin No. 79-18 Enclosure I
August 7, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTFS Bulletin Subject Date Issued Issued To No.79-03E Nuclear Incident at 5/21/79 All B&W Power Reactor 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 vith an Manufactured by Velan OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor 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-OlA 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 Velves)
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