ML19249A261
| ML19249A261 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/07/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 7908210497 | |
| Download: ML19249A261 (1) | |
Text
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UNITED STATES e8,y
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WALNUT CREE K, CALIFORNI A 94596 August 7,1979 Docket flo. 50-344 Portland General Electric Company 121 S. W. Salmon Street Portland, nregon 97204 Attention: Mr. Charles Goodwin Assistant Vice President Gentlemen:
The enclosed Bulletin 79-18 is forwarded to you for action.
A written response is required.
J.f you desire additional information regarding this matter, please contact this office.
Sincerely, Jht(%~, c.L l-R. H. Engelken Director
Enclosure:
IE Bulletin fio. 79-18 cc w/ enclosure:
B. Withers, PGE F. Gaidos, PGE 79082.loqq 76'aD34
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Accessions No: 7908030403 SSIttS fio:
6820 UNITED STATES fiUCLEAR REGULATORY COMt11SSION OFFICE OF INSPECTION AND EfiFORCEMEllT WASHINGT0tl, D.C.
20555 August 7, 1979 IE Bulletin fio. 79-18 AUDIBILITY PROBLEMS ENC 0UtiTERED ON EVACUATION OF PERSONNEL FRGM HIGH-fiOISE AREAS Descripti a 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 nu;1 ear plant. While these individuals were worki.ig 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 th licensee to initiate the facility emergency plan auxiliary bu:' ding 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 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 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 fiRC 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-ciatcr system 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 alarn systems and evacuation announcement systems are clearly audible or visible throughout all plant areas with emphasis on high-noise areas.
Determination in high no' e areas must be made with the maximum anticipated noise level.
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IE Bulletin flo. 79-18 August 7, 1979 Page 2 of 2 2.
Determine what corrective action is necessary i1 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 adminis+~'tive 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 te 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 iuuance of this Bulletin.
For inaccessible areas, the written report r"ust include a time schedule for completion of corrective actions in this area.
Reports should be subritted to the Director of the appropriate f!RC Regional Office and a copy should be forwarded to the fiRC Office of Inspection and Enforcernent, Division of Reactor Operations Inspection, Washington, D.C. 20555 For all power reactor fecilities with a construction pemit, this Bulletin is for information only and no written response is required.
Approved by GAC, B180725 (R0072); clearance expires 7/31/80. Approval was given under a Llanket clearance specifically for identified generic problens.
Enclosure:
LIST OF IE Bulletins Issued in Last 6 Months
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IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 1 of 3 LISTING OF IE BULLETIllS ISSUED IN LAST SIX fiONTHS E'411eti n 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 Powm 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 PWRs with an System Piping OL for action. All BWRs with a CP for information.
79-02 Pipe 'opport Base Plate 6/21/79 All Pm*.r Reactor (Rev. 1) r,1gns Using Concrete Facilities with an txpansion 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 TG203?
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 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 79-05C&O6C Nuclear Incident at Three 7/26/79 To all PWR Power Mile Island - Supplenent 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 79-06A Review of Goerational 4/18/79 All Pressurized Water (Rev1)
Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Gesign During the Three Mile with an O'.
Island Incident 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and System Mis-Power Reactor Facilities alignments Identi34ed 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 Systen Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident "ib2038
IE Bulletin No. 79-18 Enclosure
' August 7, 1979 Page 3 of 3 LISTING OF IE BULLETINS ISSUED IN LAST SIX f40NTHS Bulletin Subject Date Issued Issued To No.79-05B t'uclear 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 flile 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 flant ~actured by Velan OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in P.eactor Pressure Facilities with an Vessel Welds OL or CP 79-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASi1E SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP flanufactured by Youngstown Welding and Engineering Co.79-01A Environnental Oualification 6/6/79 All Pcwer Reactor of Class IE Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronnental Outlification of ASCO Solenoid Valves) 76'4039