ML16341B201
| ML16341B201 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| 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 7908210493 | |
| Download: ML16341B201 (12) | |
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NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 August 7, 1979 Docket Nos.
50-275 50-323
, Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention:
Nr. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
The enclosed Bulletin 79-18 is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, R.
H. Engelken Director
Enclosure:
IE Bulletin No.. 79-18 cc w/enclosure:
J. Worthington, PG&E W. Raymond, PG&E R.
- Ramsay, PG&E, Diablo Canyon
Accessions No: 7908030403 SSINS No:
6820 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTIOf1 AND ENFORCEt1ENT WASHINGTON, D.C. '0555 August 7, 1979 IE Bulletin No. 79-18 AUDIBILITY PROBLEMS ENCOUNTERED ON EVACUATION OF PERSONNEL FROtl HIGH-NOISE AREAS Des cription 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.
1lhile 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.
The facility Emer-gency Officer (Shi ft Supervisor) assessed the moni tor readings and initiated'n 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 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.
Determine 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'reas must be made with the maximum anticipated noise level.
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 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 HRC Regional Office and a copy should be forwarded to the NRC Office of Inspection 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 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 llonths
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)L 1,
IE Bulletin No. 79-18 August 7.
1979 Bulletin Subject No.
Enclosure Page 1 of 3 LISTING OF. IE BULLETINS ISSUED IN LAST SIX MONTHS Date Issued Issued To 79-17 Pipe Cracks in Stagnant Borated Mater Systems at PMR Plants 7/26/79 All PMR's with operating license 79-15 C
Deep Draft Pump Deficiencies 7/11/79 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 All Power Reactor Licensees with a CP and/or OL 79-14 79-13 79-02 (Rev.
1) 79-12 79-11 79-10 Seismic Analyses for.
As-Bui1t Safety-Rel ated Piping System Cracking in Feedwater System Piping Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts Short Period Scrams at BMR Facilities Faulty Overcurrent Trip Device in Circuit Breakers for Engineered Safety Systems Requal ification Training Program Stati sties 6/2/79 6/25/79 6/21/79 5/31/79 5/22/79 5/11/79 All Power Reactor facilities with an OL or a CP All PMRs with an OL for action. All BMRs with a CP for information.
All Power Reactor Facilities with an OLor a CP All GE BMR Facilities with an OL All Power Reactor Facilities with an OL or a CP All Pointer Reactor Facilities with an OL
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IE Bulletin No. 79-18 August 7, 1979 Enclosure Page 2 of 3 LISTING OF IF. BULLFTINS ISSUED IN LAST SIX MONTHS Bulletin No.
Subject Date Issued Issued To 79-09 Failures of GE Type AK-2 4/17/79 Circuit Breaker in Safety Related Systems All Power Reactor Facilities with an OL or CP 79-08 79-07 Events Relevant to BHR Reactors Identified During Three Mile Island Incident Seismic Stress Analysis of'afety-Related Piping 4/14/79 4/14/79 All BHR Power Reactor Facil ities with an OL All Power Reactor Facilities with an OL or CP 79-05C&06C Nuclear Incident at Three 7/26/79 Mile Island - Supplement To all PWR Power Reactor Facilities
'ith an OL 79-06B 79-06A (Rev 1)79-06A 79-06 Review of Operational Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Nis-alignments Identified During the Three Mile Island Incident Review of Operational Errors and System Nis-alignments Identified During the Three Mile Island Incident Revi ew of Operational Errors and System Nis-alignments Identified During the Three Mile Island Incident
'4/14/79 4/18/79 4/14/79 4/11/79 All Combustion Engineer-ing Designed Pressurized Hater Power Reactor Facilities with an Operating License All Pressurized Hater Power Reactor Facilities of Westinghouse Design with an OL All Pressurized Hater
.Power Reactor Facilities of Westinghouse Design with an OL All Pressurized Hater Power Reactors with an OL except B&H facilities
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IE'Bulletin No. 79-18 August 7, 1979 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Enclosure Page 3 of 3 Bulletin Subject fto.
Date Issued Issued To 79-05B 79-05A 79-05 79-04 78-12B Nuclear Incident at Three Mile Island
, Nuclear Incident at Three Mile Island Nuclear Incident at Three Nile Island Incorrect Weights for Swing Check Valves Manufactured by Velan Engineering Corporation Atypical Weld Material in Reactor Pressure Vessel Welds 5/21/79 4/5/79 4/2/79 3/30/79 3/19/79 All B&W Power Reactor Facilities with an OL All B&W Power Reactor Facilities with an OL All Power Reactor Facilities with an OL and CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP 79-03 79-01A Longitudinal Welds Defects 3/12/79 In ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Co.
Environmental gual ificati on 6/6/79 of Class 1E Equipment (Deficiencies in the Envi-ronmental gualification of ASCO Solenoid Valves)
All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP
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