Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers

Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers

ML031200384
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	04/29/1992
Revision:	0
From:	Rossi C E Office of Nuclear Reactor Regulation
To:
References
IN-92-032, NUDOCS 9204230088
Download: ML031200384 (3)

UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555April 29, 1992NRC INFORMATION NOTICE 92-32: PROBLEMS IDENTIFIED WITH EMERGENCY VENTILATIONSYSTEMS FOR NEAR-SITE (WITHIN 10 MILES)EMERGENCY OPERATIONS FACILITIES AND TECHNICALSUPPORT CENTERS

Addressees

All holders of operating licenses or construction permits for nuclear powerreactors.

Purpose

The U.S. Nuclear Regulatory Commission (ARC) is issuing this information noticeto alert addressees to potential problems resulting from inadequate maintenanceand testing of Emergency Operations Facility (EOF) and Technical Support Center(TSC) emergency ventilation systems. These problems could result in a situa-tion after an accident in which the EOF or TSC would not provide the level ofprotection to emergency workers that was intended. It is expected that recipi-ents will review the information for applicability to their facilities andconsider actions, as appropriate, to avoid similar problems. However, sugges-tions contained in this information notice are not NRC requirements; therefore,no specific action or written response is required.

Description of Circumstances

Through routine inspection activities, the NRC has identified concerns with theoperational readiness of EOF and TSC emergency ventilation systems. Thefollowing are three examples of recent inspection results:1. Brunswick, February 1991. While observing a requested startup of theemergency ventilation system for the EOF, the inspector noted that thesystem was in poor material condition. The inspector also noto thelicensee had not implemented procedures for operating, maintaining, orfunctional testing of the-system. (Inspection Report 50-325,3I91-03).2. Vogtle, May 1991. During a demonstration of the EOF ventilatiQk system,the system failed to provide a positive pressure in the EOF in the emer-gency mode. After initial repair efforts, the system again fai d toinitiate the emergency mode when required. The licensee had nether amaintenance program nor test and operating procedures for the system.(Inspection Reports 50-424,425/91-04 and 50-424,425/91-08).9204230088 iIDR .t E L qI-o32. '1oq29

iIN 92-32April 29, 1992 . Crystal River, May 1991. During an annual exercise, the TSC ventilationsystem failed to maintain facility habitability after approximately2 hours of operation. The facility was originally designed for 29 personsassuming a heat load of 450 btulhr per person. A heat load assumption of640 btu/hr per person for an approximate 70 persons occupancy level wouldhave been more applicable. The licensee had neither operating proceduresnor a maintenance and testing program for the ventilation system.(Inspection Report 50-302/91-08).DiscussionThe NRC requires licensees and applicants to provide emergency facilities andequipment in support of operating nuclear power plants in the followingregulations:1. 10 CFR 50.47, "Emergency Plans," Section (b)(8)2. 10 CFR Part 50, Appendix E, Section IV.E, "Emergency Facilities andEquipment"Guidance for implementing the requirements contained in the regulations isprovided in NUREG-0737, Supplement 1, "Clarification of TMI Action PlanRequirements." This NUREG document was transmitted to licensees viaGeneric Letter 82-33, "Supplement 1 to NUREG-0737 -Requirements for EmergencyResponse Capability," dated December 17, 1982. It provides general design andperformance criteria for EOF and TSC ventilation systems. The NRC has notspecifically identified maintenance and test criteria for these ventilationsystems, but instead has provided a degree of flexibility within whichlicensees can exercise management prerogative in their maintenance programs.Other documents that provide guidance on maintenance and test programs forventilation systems, which many licensees have used as a basis for maintenanceand test programs, are:I. Regulatory Guide 1.52, "Design, Test, and Maintenance Criteria forPost-Accident Engineered-Safety-Feature Atmosphere Cleanup System AirFiltration and Adsorption Units of Light-Water-Cooled Nuclear PowerPlants"2. Regulatory Guide 1.140, "Design, Test, and Maintenance Criteria for NormalVentilation Exhaust System Air Filtration and Adsorption Units ofLight-Water Cooled Nuclear Power Plants"3. American Society of Mechanicdl Engineers (ASME) Standard N510, "Testing ofNuclear Air Treatment Systems"If dose assessment, communications, or decisionmaking capability is lost orimpaired because the EOF and/or TSC become uninhabitable and are evacuated, theability of the licensee's emergency response staff could be severely impaired,thus jeopardizing protection of the health and safety of the public.0 =8119 I El I" I 0io4' 0IN 92-32April 29,. 1992 This information notice requiresyou have any questions about theof the technical contacts listedReactor Regulation (NRR) projectno specific action or written response. Ifinformation in this notice, please contact onebelow or the appropriate Office of Nuclearmanager.C!,;g f i S k1'1"Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts:Glen W. Salyers, RII(404) 331-5604Daniel M. 6arss, NRR(301) 504-2922

Attachment:

List of Recently Issued NRC Information NoticesAttact.1wnt;I §-32IN 92'2April 29. 1992Page 1 of ILUST OF MECEKTLT ISSUEDhiC INFORMATION NOtICESInformation Date ofNotice No. subject IisiitCe issued to52-31 Electrical Connection 04127/92 A11 holders Of OLS Or CPsproblem In Joneson for nuclear power reactors.tokogawa Corooratlon.S-80 Programale mdi-cating Controllers92-30 Falsification c' Plant 04/22/92 111 holders of OLS Or CPSRecords for ruclear power reactorsand all licensed operatorsand senior operators.92-21 Spern Fuel Pool Re- 04/22n2 All holders of Ots or CPSSump. I activity Calculations for nuclesr power reactors.92.29 Potential Breater Ni.- 04/17/92 All holders of OLs or cPScoordination Caused by for nuclear power reactors.Instantaneous TripCircuitry92-28 Inadeguate Fire SuPores- 04/08/92 All toloers of OLs or CPssion Systes Testing for nuclear power reactors.92-27 The-rwlly Induced Acceler- 04/03/92 All holders of Ota Or CPSatdd Aging and Failure of for nuclear power reactors.ITEC/GOLO A.C. Aelays UVdin Safety-Belated ApPlic.Ations92-26 Pressure Locking of motor- 04/02/92 All holders of OLS or CPsOperated Flelible Wedge fe- nuclear power reactors.Cate Valves92-25 Potential Neatness in 03/3/ 92 All holders of 0LS Or CPsLicensee P-ocedures fo, A for ruClear Power ractors.Loss of the BetuelingCavity WaterOL Operating LIcenstCr

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