ML20003G042
| ML20003G042 | |
| Person / Time | |
|---|---|
| Issue date: | 03/26/1981 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8104280120 | |
| Download: ML20003G042 (2) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
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REGION 111 e
8 799 ROOSEVELT ROAD E
GLEN ELLYN, ILLINOIS 60137 o
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MAR 2 61981 0
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7 Illinois Department of 2
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Nuclear Safety 2
ATTN:
Mr. Gary N. Wright
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%gg 1035 Outer Park Drive IS Springfield, IL 62704 9
Centlemen:
The enclosed IE Information Notice No. 81-09 titled " Degradation of Residual Heat Removal (RHR) System" was sent to the licensees listed below on March 26, 1981:
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
LaSalle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light and Power Company Duane Arnold (50-331) 8104280 M
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Illinois Department of Nuclear Safety Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
Sincerely, a lta/D r.
D6 rot y r oll, Chief Word Processing and Document Control Section
Enclosure:
IE Information Notice No. 81-09 cc w/ enc 1:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit h3C 20b AE0D Resident Inspectors, RIII J. G. Keppler, RIII Acting Division Directors, RIII P. R. Wohld, RIII PDR Local PDR NSIC TIC
b SSINS No.:
6835 Accession No.:
p 8011040280 IN 81-09 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 26, 1981 IE Information Notice No. 81-09:
DEGRADATION OF RESIDUAL HEAT REMOVAL (RHR)
SYSTEM Description of Circumstances:
Recent, repeated expressions of serious concern have been mac'e regarding loss of shutdown coolin0 capability (IEB 80-12 and IN 80-20).
Nevertheless, an additional instance has occurred in which proper attention was not given to assure reliability of the shutdown cooling function.
On March 5,1981 during a shutdown at Beaver Vciley, residual heat removal (RHR) flow was severely degraded while the water level was near the hot leg midpoint.
During the 54 minutes needed to vent both RHR pumps and add approxi-mately 600 gallons of water to the primary system, primary coolant temperature increased from 102 F to 168 F.
The event occurred when water was slowly lost from the reference leg of a temporary (tygon tubing) differential pressure system installed to measure water level in the primary system.
There were no required surveillance procedures to check proper operation of the water level instrument.
Consequently, the reference leg water loss was not detected until the actual primary system water level decreased to about 6" below tt.a indicated level, sufficiently low to allow air entrainment in the RHR suction line, which air-bound both RHR pumps.
Loss of shutdown cooling capability is a potentially significant contributor to the total risk associated with nuclear power (Reactor Safety Study, WASH - 1400, pg. 135.) It is expected that licensees will review the circumstances of this event and take appropriate actions to assure shutdown cooling system operability.
This notification, in conjunction with IEB 80-12 and IN 80-20, is intended to convey the seriousness of NRC concern with failures to maintain adequate decay heat removal provisions.
No written response to this information notice is required.
If you require additional information with regard to this subject, please contact the appropriate NRC Regional Office
Attachment:
Recently issued IE Information Notices
Attachment IN 81-09 p
March 26, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 81-08 Repetitive Failures of 3/20/81 All power reactor Limitorque Operator SNB-4 facilities with an Motor-to-Shaft Key OL or CP 81-07 Potential Problem with 3/16/81 All power reactor Water-Soluble Purge Dam facilities with an Materials Uste During OL or CP Inert Gas Weloing 81-06 Failure of ITE Model 3/11/81 All power reactor K-600 Circuit Breaker facilities with an OL or CP 81-05 Degraded DC System at 3/13/81 All power reactor Palisades facilities with an OL or CP 81-04 Cracking in Main Steam 2/27/81 All power reactor Lines facilities with an OL 81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in OL Accordance with 10 CFR 50.72 81-02 Transportation of 1/23/81 All Radiography Radiography Devices licensees i
81-01 Possible Failures of 1/16/81 All power reactor General Electric Type facilities with an HFA Relays OL or CP.
80-45 Potential Failure of 12/17/80 All PWR facilities BWR Backup Manual Scram with an OL or CP Capability 80-44 Actuation of ECCS in the 12/16/80 All PWR facilities Recirculation Mode While with an OL or CP in Hot Shutdown OL = Operating Licenses CP = Construction Permits
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