ML19249A270
| ML19249A270 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/07/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 7908210518 | |
| Download: ML19249A270 (1) | |
Text
[pe Peog 'o UNITED STATES j,, l v 8
'[g NUCLEAR REGULATORY COMMISSION 7,.ph) l REGION V 1990 N. CALIFORNI A DOULEVARD I;,
%,fs.
g
' \\.1-6" SUITE 202 WALNUT CREEK PLAZA 4e,,*
WALNUT CREEK, CALIFORNI A 94596 August 7,1979 Docket flo. 50-312 Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention:
11r. John J. Mattimoe Assistant General Manager Gentlemen:
The enclosed Bulletin 79-18 is forwarded to you for action.
A written response is required.
If you desire addition'.1 information regarding this nat'cer, please contact this office.
Sincerely,
{
s[
R. H. Engelken Director
Enclosure:
IE Bulletin No. 79-18 cc w/ enclosure:
R. J. Rodr kuez, SMUD L. G. Schwieger, SMUD 790821osl3 7612G8
Accessions No: 7908030403 SSINS No:
6820 UNITED STATES NUCLEAR REGULATORY C0F111SSION OFFICE OF IllSPECTION Arid Ef!FORCEMEllT WASHINGTON, D.C.
20555 August 7, 1979 IE Bulletin No. 79-18 AUDIBILITY PROBLEMS EriCOUNTERED ON EVACUATIF 0F PERSONNEL FROM HIGH-NOISE AREAS Desc iption 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 nuclear plant. While these individuals were working in tae auxiliary building, in a high-noise (fan) area, an unplanned release of radio-active noble gases was detected by building monitors within the auxiliasy building at concentrations which caused the licensee to initiate the fa.:ility emergency plan auxiliary building evacuation procedure.
The facility Emer-gency Officer (Shift Supervisor) assessed the monitor readings and initieted an auxiliary building evacuation. The evacuation announcement, made over the '
licensee's PA system, was not heard by the personnel working ;a'the high-noise area.
Licensee personnel did evacuate the auxiliary building upon observing 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 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.
Detennine whether current alarm systems arid evacuation anrouncement systems are clearly audible or visible throughout all plant areas with emphasis on high-noise areas.
Determination in high noise areas nust be moJe with the maximum anticipated noise level.
761269
IE Bulletin flo. 79-18 August 7, 1979 Page 2 of 2 2.
Determine what corrective actic. 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 submitted within 30 days after plant startup following the outage.
4.
Fw accessible areas, all corrective actions determined per item (2) must be completed witMn 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 subnitted to the Director of the appropriate f1RC Regional Office and a copy should be forwarded to the fiRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C. 20555.
For all power reactor facilities with a construt.' ion permit, this Bulletin is for information only and no written response is re,uired.
Approved by GAU, B180L (R0072); clearance expires //31/80. Approval was given unde:r a blanket clearance specifically for iden ified generic problems.
Enclosure:
LIST OF IE Bulletins Issued in Last 6 l'onths 761270
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 1 of 3 LISTIdG 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 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 ReyL311fication Training 5/11/79 All Power Reactor Program Statistics Facilities with an OL 761271
IE Bulletin No. 79-18 Enclosure August 7, 1979 Page 2 of 3 LISTIfiG CF IE BULLETIlls ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issred 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 79-03 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 19-07 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 itile Island - Supplenent Reactor Facilities 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 (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 System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three !!ile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and Systen flis-Power Reactors with an alignments Identified OL except B&W facilities During the Three !!ile Island Incident 761272
i*
IE Bulletin flo. 79-18 Enclosure August 7, 1979 Page 3 of 3 LISTI!!G 0F IE B'JLLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To tio.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 fluclear Incident at 4/2/79 All Power Reactor ihree 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 flanufactured by Velan 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 Defects 3/12/79 All Power Reactor In AS!!E SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.79-01A Environnental cualification 6/6/79 All Power Reactor of Class 1E Fquipment Facilities with an (Deficiencies in the Envi-OL or CP ronnental Oual'ficatior: of ASCO Solenoid Valves) 761273