ML19249A260
| ML19249A260 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 08/07/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7908210488 | |
| Download: ML19249A260 (1) | |
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UNITED STATES
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WALNUT CREE K, CALIFOHNI A 9459G august 7,1979 Docket flo. 50-133 acific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention:
Mr. Philip A. Crane, Jr.
Assistant Genercl Counsel Gentlemem The enclosed Bulletin 79-18 is forwarded to you for action.
A written response is required.
If you desire additional information regarding this matter, pleae
- ontact this office.
Sincerely,
/87b C R. H. Engelken Director
Enclosure:
IE Bulletin tio. 79-18 cc w/ enclosure:
W. Barr, PG&E W. Raymond, PG&E E. Weeks, PG&E, Humboldt Bay 790821M88 76'4020
Accessions No: 7908030403 SSINS No:
6820 UNITED STATES NUCLEAR REGULATORY C0F. MISSION OFFICE OF INSPECTION AND ENTORCEMENT WASHINGTON, D.C.
20555 August 7, 1979 IE Bulletin No. 79-18 AUDIBILITY PROBLEMS ENCOUNTERED ON EVACUATION OF PERSONNEL FROM 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 Carporation, Crystal River Unit 3 ruclear 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.
- .ie 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, wcs not heard by the personnel working in the high-noise araa.
Licensee personnel did evacuate the auxiliary building upon observing that other personnel had left, and af ter 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 ennecessary 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 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.
Detenaine 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.
WZO21
IF bulletin flo. 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-tien signals cannot be assured by hardware changes, determine wnc 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 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 completion of corrective actions in this area.
Reports should be submitted to the Director of the appropriate i;RC Regional Office and a copy should be forwarded to the flRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C. 20555.
For all power reactor facilities with a construction pemit, 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 fionths 7o2022
IE E-etin No. 79-18 Enclosure Augt
, 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 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 Crackiag in Feedwater 6/25/79 All PWRs with an Sys cem 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 S/31/79 All GE BWR F icilities BWR Facilities with an OL 79-11 Faulty Overcurrent Trip S/22/79 All Power Reactor Device in Circuit Breakers Facilities with an for Engineered Safety OL or a CP Systems 79-10 Requalification Training S/11/79 All Power Reactor Program Statistics Facilities with an OL W3%O23
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 Systens OL or CP 79-08 Events Relevant to CWR 4/14/79 All BWR Power Reactor Reactors lientified 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 7/26/79 To all PWR Power
!!ile Islar,d - Supplenent Reactor racilities with an OL 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and Systen Mis-ing Designed Pressurized alignments Identified Water Power Reactor During the Three Mile 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 Prc:surized 1%ter Errors and Systen Mis-rower Reactor Faci ities l
alignments Identified of Westinghouse Des gn During the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Error; and Systen Mis-Power Reactors with an alignments Identified OL except B&W facilities During the Three Mile Island Incident 764' 024
TE B'ulletin flo. 79-18 Enclosure August 7, 1979 Page 3 of 3 LISTIriG OF IE BULLETIlls ISSUED IN LAST SIX l-10NTHS Bulletin Subject Date Issued Issued To flo.79-05B Nuclear Incident at 5/21/79 All B&W Power Reactor Three tiile Island Facilities with an OL 79-05A
'uclear Incident at 4/5/79 All B&W Power Reactor Three fiile Island Facilities with an OL 79-05 iluclear Incident at 4/2/79 All Power Reactor Three f4ile Island Facilities with an OL and CP 79-Ca Ince rect Ueights for 3/30/79 All Pcwer Reactor Swing Check Valves Facilities with an flanufactured 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 70-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASt1E SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP fianufactured by Youngstown Welding and Engineering Co.79-01A Environnental Qualification 6/6/79 All Power Reactor of Class 1E Equipment Facilities with an (Deficiencies in the Fnvi-OL or CP ronr:catal Oualification of ASCO Solenoid Valves) 76%O2S