ML19242D506
| ML19242D506 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 08/07/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7908150336 | |
| Download: ML19242D506 (1) | |
Text
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UNITED ST ATES E'
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NUCLE AR REGULATORY COMMISSION
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AUG 7 1979 Docket No. 50-358 Cincinnati Gas and Electric Company ATTN:
Mr. Earl A. Borgmann Vice President Engineering Services and Electric Production 139 East 4th Street Cincinnati, OH 45201 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 {b.
James G. Keppler Director
Enclosure:
IE Bulletin No. 79-18 cc w/ encl:
Mr. J. R. Schott, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Citizens Against a Radioactive Environment Helen W. Evans, State of Ohio 690b1-ascem 7 90815 $
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Accessions No: 7908030403 SSINS No:
6820 UNITED STATES NUCLEAR RECULATORY COMMISSION OFFICE OF INSPECTION AND FNFORCEMENT WASHINGTON, D.C.
20555 August 7, 1979 IE Bulletin No. 79 18 AUDIBILITY PROBLEMS ENCOUNTERED ON EVACUATION OF PERSONNEL FROM BIGH-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 naclear 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 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.
that 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 radionuclides above regulatory guidance. However, the potential existed for inadvertent unnecessary exposure of individuals to radioactive materials.
Subsequent to the NRC followup 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 annun-ciator system needed audibility improvement. The licensee has installed a new Luxiliary 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 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.
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IE 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 areas in (1) above, will receive adequrte audible /
visual evacuation signals.
In areas where adequate audible /via al evacua-tion signals cannot be assured by hardware changes, determine what addi-tional administrative measures are necessary to assure personnel evacuation.
3.
Submi' within 45 days of the das' of issuance of this Bulletin, a written repor: of the findings on item (1), and delineate completed or proposed corr.ctive actions per item (2). For operating facilities in a refueling or.xtended outage, the written report must be submitted within 30 days af.er plant startup following the outage.
4.
For accessible areas, all corrective actions determined per item (2) must e completea 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 of corrective actions in this area.
Reports should be submitted to the Director of the appropriste NRC Regional Office and a copy should be forwarded to the NRC Office 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, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
Enclosure:
List of IE Bulletins Issued in cast 6 Months g30%3
9 IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 1 of 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 Systems 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 System OL or a CP 79-13 Cracking in Feedwater 6/25/79 All FVRs with an System Piping OL for action. All BWRs with a CP for information.
79-02 Pipe Support Base Plate 6/21/79 All Power Reactor (Re i. 1)
Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or a CP 79-12 Short Period Scra=s 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 Program Scatistics Facilities with an OL 630264
r IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 2 of 3 LIS'INO OF IE BULLETINS ISSbiD IN LAST SIX MONTHS Bulletin Subject Date Issued Iosued 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 Events 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 Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-05C606C 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 Pressurized alignments Identified Water Power Reactor During the Three Mile Facilities with an Island Incident Operating Liccuse 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 De sign During the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and Sy. stem Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident (fji)@dd
P IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTES Bulletin Subject Date Issued Issued To No.79-05B 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 with an Manufactured by Velan OL or CP Engineering Corporatior.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 breel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.79-01A Environmental Qualification 6/6/79 All Power Reactor of Class 1E Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronmer'.al Qualification of ASCO Solenoid Valves) 6302G6