ML18116A396
| ML18116A396 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 08/07/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7908220655 | |
| Download: ML18116A396 (7) | |
Text
e UNITED STATES NUCLEAR REGULATORY COMMISSlc,pf REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 In Reply Refer To:
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Virginia Electric and Power Company Attn:
W. L, Proffitt Senior Vice President, Power P. 0, Eox 26666 Richmond, Virginia 23261 Gentlemen:
AUG 7 1979 The enclosed Bulletin 79-18 is forwarded to you for action.
A written response is required. If you desire additional information regarding this matter, please contact this office.
Sincerely,
-~z.. James P, O'Reilly-Director
Enclosures:
- 1.
- 2.
Listing of' IE Bulletins Issued in Last Six Months 790522005!;
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e Virginia Electric and Power Company cc w/encl:
W.R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W. L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883
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j__Qll;essions f~INS No:
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UNITED STATES t~'
NUCLEAR REGULATORY COMMISSI OFFICE OF INSPECTION AND ENFO MENT WASHINGTON, D.C.
20555 August 7, 1979 No: 7908030403 6820 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 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 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 (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 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 thii 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 6lar11 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 areas must be aade with the aaximum anticipated noise level.
I I,.
e 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 can.not be assured by hardware changes, determine what addi-tional administrative measures are nec~ssary to assure personnel evacuation.
- 3. Submit within 45 days of the date of i*suance 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 eztended outage, the written report aust 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 aust include a time schedule for completion of corrective actions in this area.
Reports should be submitted to* the Director of the appropriate NRC 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 peI'llit, this Bulletin is for information only and no written response is required.
Approved by GAO, BI80225 (R0072); clearance ezpites 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
e IE Bulletin No. 79~18 August 7, 1979 Bulletin llo.
79-17 79-16 79-15 79-14 79-13 79-02 (B.ev. 1) 79-12 79-11 79-10 LISTING-OF IE BULLETI~cJ/
ISSUED IN LAST SIX MON... y Subject Date IHued Pipe Cracks in Stagnant 7/26/79 Borated Water Systems at PWR Plants Vital Area Access Control*
7/26/79 Deep Draft Pump 7/11/79 Deficiencies Seismic Analyses for 6/2/79 As-Built Safety-Related Piping System Cracking 1n Feedwater 6/25/79.
System Piping Pipe Support Base Plate -
- -6/21/79 Designs Using Concrete Expansion Anchor Bolts Short Period Scrams at S/31/79 BWR Facilities Faulty OYercurrent Trip 5/22/79 Device 1n Circuit Breakers for Engineered Safety Systems llequalification Training 5/11/79 Program Stati*tics Enclosure Page 1 of 3 Issued To All PWR.'* vith operating license All Bolder* of and applicants for Power Reactor Operating Licenses vho anticipate loading fuel prior to 1981 All Power Reactor Licensees with a CP and/or OL All Power Reactor facilities 111th an OL or a CP All PWR.s with an OL for action. All BWlls with a CP for inforaation.
All Power Reactor Pacilities with an OL or a CP All GE IWll Facilities vith an OL All Power Reactor Facilities with an OL or 11 CP All Power Reactor Pacilitiea with an OL-
e IE Bulletin No. 79-18 August 7, 1979 Bulletin Ho.
79-09 79-08 79-07 79-05C&06C 79-06B 79-06A (llev 1)79-06A 79-06 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date Issued Failures of GE Type AK-2 4/17/79 Circuit Break.er 1n Safety I.elated Systems Evento Relevant to BlJR 4/14/79 Reactors Identified During Three Mile Island Incident Seismic Stress Analysis
- 4/14/79 of Safety-Related.Piping Nuclear Incident at Three 7/26/79 Mi.le Island - Supplement 1.eview of Operational 4/14/7-9
- Errors and System Mis-alignments Identified
- During the Three Mile ___ _
laland Incident Review of Operational 4/18/79
- Errors and System Mis-alignments Identified During the Three Mile Island Incident Review of Operational 4/14/79 Errors and System Mis-alignments Identified During the Three Mile Island Incident '
Review of Operational 4/11/79 Error* and Sy*tem Mia-alignments Identified During the Three Mile Island Incident Enclosure Page 2 of 3 Issued To All Power Reactor Facilities With an OL or CP All B'WR Power Reactor Facilities With an OL All Power Reactor Facilities w:lth an OL or CP To all PWR Power Reactor Facilities with an OL All Combustion Engineer-ing Designed Pressurized Water Power Reactor Facilitieo With an
-*Operating License
- 7 All PreeEJUrized Water Power Reactor Facilities of Westinghouse Design with an OL All Preasurized Water Power Reactor Facilities of Westinghouse Design with an OL All Pre*surized Water Power Reactor* with an OL except l&W facilities
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IE Bulletin No. 79-18 August 7, 1979 Bulletin Ro.
79-0SB 79-0SA 79-05 79-04 78-12B 79-03 79-0lA LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Subject Date !Hued Nuclear Incident at S/21/79 Three Mile Island Nuclear Incident at 4/5/79 Three Mile Ialand Nuclear Incident at 4/2/79 Three Mile Ialand Incorrect Weights for 3/30/79 Swing Check Valves*
Manufactured by Velan Engineering Corporation Atypical Weld Material 3/19/79 in Reactor Preasure Vessel Welds Longitudinal Welds Defect*
3/12/79 In ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Co.
Enviromaental Qualification 6/6/79 of Class lE Equipment (Deficiencies in the Envi-ronmental Qualification of ASCO Solenoid Valves)
Encloaure Page 3 of 3 Ia1Jued To All l.&W Power Reactor F~cilitiea vith on OL All B&W Power Reactor P'acilitiea with an OL All Power Reactor Facilities with an OL and CP All Power Reactor Facilities with an OL or CP All Power l.eactor facilities v!th an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Pacilitiem v.l.th an OL or CP