ML19263E971
| ML19263E971 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/07/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Herbein J METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7908280115 | |
| Download: ML19263E971 (1) | |
Text
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UNITED STATES g
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Docket Nos. 50-289 50-320 Metropolitan Edison Company ATTN:
Mr. J. G. lferbein Vice President P. O. Box 542 Reading, Pennsylvania 19640 Gentlemen:
The enclosed Bulletin No. 79-18 is forwarded to you for information. No written response is required. If you desire additional iniormation regarding this matter, please contact this. office.
Sincerely, hbb
' l oyce H. Grie Director
Enclosures:
1.
Listing of IE Bulletins Issued in Last 6 Months cc w/encls:
E. G. Wallace, Licensing Manager J. J. Barton, Project Marager 2220 080 R. C. Arnold, Vice President - Generation L. L. Lawyer, Managar - Generation Operations G. P. Miller, Manager - Generating Station - Nuclear J. L. Seelinger, Unit 1 Superintendent W. E. Potts, Unit 1 Superintendent - Technical Support J. B. Logan, Unit 2 Superintendent G. A. Kunder, Unit 2 Superintendent - Technical Support I. R. Finfrock, Jr.
Mr. R. Conrad G. F. Trowbridge, Esquire Miss Mary V. Southard, Chairman, Citizens for a Safe Environment
/
7908280Ib
r ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 79-18 Date:
August 7, 1979 Page 1 of 2 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 activi-ties in the auxiliary building at the Florida Power Corporation, Crystal River Unit 3 nuclear plant.
While these individuals were working in the auxiliary building, in a high-noise (fan) area, an unplanned release of radioactive noble gases was detected by buiIding monitors within the auxiliary building at concentrations which caused the licensee to initiate the facility emergency plan auxiliary building evacuation procedure.
The facility Emergency 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 upor observing that other personnel had left, and after calling the control room to inquire if an evacuation had t'c a 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 annunciator system needed audibility improvement.
The licensee has installed a new auxiliary building evacuation tone signal and may add visual alarm indicators in areas of very high-noise.
Action to be Taken by the Licensees:
For all power reacter 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 ar.as.
Determination in high noise areas must be made with the ma> imum anticipated noise level.
2220 081
F IE Bulletin No. 79-18 Date:
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 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 NRC Regiona' Office cad a copy should be forwarded to the NRC Office of Ins,ection 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 cnly 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 problena.
2220 082
a IE Bulletin No. 79-18 Date:
August 7, 1979 Page 1 of 4 ENCLOSURE 2 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin Subject Date Issued Issued To No.78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 79-01A Environmental Qualification 6/6/79 All Power Reactor
.of Class 1E Equipment Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves) 79-02 Pipe Support Base Plate 6/21/79 All Power Reactor (Rev 1)
Design Using Concrete Facilities with an OL Expansion Anchor Bolts or CP 79-03 Longitudinal Weld Defects 3/12/79 All Power Reactor in ASME SA-312 Type Facilities with 304 Stainless Steel Pipe an OL or CP Spools Manufactured by Youngstown Welding and Engineering Company 79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 79-0S Nuclear In-ident at 4/1/79 All Babcock and Three Mile island Wilcox Power Reactor Facilities with an OL, Except Three Mile Island 1 and 2 (For Action),
and All Other Power Reactor Facilities With an OL or CP (For Information) 2220 083
IE Belletii. No. 79-18 Date:
August 7, 1979 Page 2 of 4 LIST OF IE BULLETINS ISSUED IN LAST SIX MONTils (CONTINUED)
Bulletin S.bject Date Issued Issued To No.79-05A Nuclear Incident at 4/5/79 Same as 79-05 Three Mile Island -
Supplement 79-05B Nuclear Incident at 5/21/79 Same as 79-05 Three Mile Island -
Supplement 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System Mis-Power Reactor Facil-alignments Identified ities with an OL Except During the Three Mile B6W Facilities (For Incident Action), All Other Power Reactor Facil-ities with an OL or CP (For Information)79-06A Same Title as 79-06 4/14/79 All Westinghouse Designed Pressurized Power Reactor facil-ities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information)79-06A Same Title as 79-06 4/18/79 All Westinghouse (Revision 1)
Designed Pressurized Pcwer Reactor Facil-ities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information) 2220 084
IE Bulletin No. 79-18 Date:
August 7, 1979 Page 3 of 4 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued To No.79-06B Same Title as 79-06 4/14/79 All Combustion Engineering Designed Pressurized Power Reactor Facilities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information) 79-05C&O6C Nuclear Incident at 7/26/79 All PWR Power Three Mile Island -
Reactor Facilities Supplement with an OL 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-08 Events Relevant to A/14/79 All BWR Power Boiling Water Power Reactor Facilitics Reactors Identified with an OL (For During Three Mile Action), All Other Island Incident Power Reactor Facil-ities with an OL or CP (For Information) 79-09 Failures of GE Type 4/17/79 All Power Reactor AK-2 Type Circuit Facilities with an Breaker in Safety OL or CP Related Systems 79-10 Requalification Training 5/11/79 All Power Reactor Program Statistics Facilities with an OL 2220 085
IE Bulletin No. 79-18 Date:
August 7, 1C79 Page 4 of 4 LISTING 0F IE BULLETINS ISSUED IN LAST SIX MONTHS (CONTINUED)
Bulletin Subject Date Issued Issued To No.
79-11 Faulty Overcurrent Trip 5/22/79 All Power Reactor Device in Circuit Breakers Facilities with an for Engineered Safety OL or CP Systems 79-12 Short Period Scrams at 5/31/79 All GE BWR Facilities BWR Facilities with an OL 79-13 Cracking in Feedwater 6/25/79 All PWRs with an System Piping OL (for Action),
All Other Power Reactor Facilities with an OL or CP (For Information) 79-14 Seismic Analysis for 7/2/79 All Power Reactor As-Built Safety Related Facilities with an Piping Systems OL or CP 79-15 Deep Draft Pump Defi-7/11/79 All Power Reactor ciencies Facilities with an OL or CP 79-16 Vital Area Access Con-7/30/79 All Holders of and trols Applicants for Reactor Operating Licenses 79-17 Pipe Cracks in Stagnant 7/26/79 All PWR Power Reactor Borated Water Systems Facilities with an OL at PWR 'lants 2220 086