ML19249A259
| ML19249A259 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/07/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Johari Moore SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 7908210485 | |
| Download: ML19249A259 (1) | |
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UNITED STATES E
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NUCLEAR REGULATORY COMMISSION
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2 REGION V I
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SUITE 202, WALNUT CREEK PLAZA WALNUT CREE K, CALIFORNI A 91596 August 7, 1979 Docket ilos. 50-361 50-362 Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention:
Mr. J. B. l'oore Vice President Gentlemen:
The enclosed Bulletin 79-18 is forwarded to you for information.
tio written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
/>[ 67k 3c([L R. H. Engelken Director
Enclosure:
IE Bulletin fio. 79-18 cc w/ enclosure:
J. H. Drake 790821oW5
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Accessions flo: 7908030403 SSINS th:
6820 UtlITED STATES tiUCLEAR REGULATORY COMf1ISSION OFFICE OF INSPECTION AND EtiFORCEMENT WASHIflGTON, D.C.
20555 August 7, 1979 IE Bulletin No. 79-18 AUDIBILITY PROBLEMS ENCOUNTERED ON EVACUATION OF PERSONNEL FROM HIGH-N0ISE AREAS Description of Circumstances:
In January 1979, a number of licensee personnel were engaged in routine activities in the auxiliary building
- the Florida Power Corporation, Crystal P,iver 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 vias detected by building monitors within the auxiliary building at concentrations which caused the licensee to iritiate the facility emergency plan auxiliary building evacuation procedure.
The facility Emer-gency Officer (Shift Supervisor) assess id 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 area. Licensee personnel did evacuate the auxiliary building upon observing that other personnel had lef t, and after calling the control room to inquire if an evacuation had been initiatt.i.
During these occurrences, licensee personnel were not exposed to quantities of radionuclides above regulatory guidance.
However, the potential existed for inadvertent unnecessary exposure of individuali 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.nstalled a new auxiliary building evacuatior, 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 systems and evacuation anncuncement 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 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 written report of the findings on item (1), and delineate completed or proposed corrective actions per item (2).
For operating facilities in a refueling or extended outage, the written report must be sutnitted within 30 days after plant startup following the outage.
4.
For accessible areas, all corrective actions determined per itent (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 schedcle for completion of corrective actions in this area.
Rcports should be submitted to the Director of the appropriate flRC Regional Office and a co y should be forwarded to the fiRC Office of Inspection and r
Enforcement, Division of Reactor Operations Inspection, Washington, D.C. 20555.
For all power reactor facilities with a construction perrlit, 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 Last 6 flonths W A '. 0 1 G
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 Pump 7/11/79 All F.4er Reactor Deficiencies Licen:ces 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 PWRs 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 (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 Program Statistics Facilities with an OL 7020.1.7
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 2 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.
79-09 Failures of GE Type AK-2 4/17/79 Ali 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 79-05C&C6C Nuclear Incident at Three 7/26/73 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 License 79-0CA Review of Operational 4/18/79 All Pressurized Water (Rev1)
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 Systen Mis-Power Reactor Facilities alignments Identified of Westinghouse Design Duririg the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and Systen His-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident 7G2018
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 3 of ?
LISTING 0F IE BULLETINS ISSUED IN LAST SIX MONTHS 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 Re6ctor 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 Ueights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velar.
OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities v:ith an Vessel Welds OL or CP 79-03 Longitudinal Welds De#ects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL cr Cr Manufactured by Youngstown Welding and Engineering Co.79-01A Environmental Qualification 6, /79 All Power Reactor of Class 1E Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronr: ental Oualification of A3CO Solenoid Valves)
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