ML19331C858
| ML19331C858 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/18/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| GL-80-55, NUDOCS 8008190632 | |
| Download: ML19331C858 (1) | |
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UNITED STATES LPDR NUCLEAR REGULATORY COMMISSION O '*
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June 18, 1980
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Dockst No. 50-298 Nebraska Public Power District ATTN:
J. M. P11 ant, Director Licensing & Quality Assurance P. O. Box 499 Columbus, Nebraska 68601 Gentlemen:
Enclosed is IE Sulletin No. 80-15 which requires action by you with regard to your power reactor facility and/or fuel facility with an operating license.
In order to assist the NRC in evaluating the value/ impact of each Bulletin on licensees, it would be helpful if you would provide an estimate of the manpower expended in conduct of the review and preparation of the report (s) required by the Bulletin. Please estimate separately the manpower associated with corrective actions necessary following identification of problems through the Bulletin.
Should you have any questions regarding this Bulletin or the actions required by you, please contact W. E. Vetter of my staff.
Sincerely,
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/g,Karl V. Se rit
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Director
Enclosures:
1.
List of Recently Issued IE 3ulletins l
l cc:
L. C. Lessor, Superintendent l
Cooper Nuclear Station Post Office Box 98 Brownville, Nebraska 68321 1
.8008190 43y
UNITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accessions No.:
0FFICE OF INSPECTION AND ENFORCEMENT 8005050072 WASHINGTON, D.C.
20555 IE Bulletin No. 80-15 Date:
June 18, 1980 Page 1 of 2 POSSIBLE LOSS OF EMERGENCY NOTIFICATION SYSTEM (ENS) WITH LOSS OF 0FFSITE POWER In the past year, there have been two occurrences where a loss of off-site power has resulted in a loss of communications between a power eactor facility and the NRC Operations Center via the Emergency Notification System (ENS).
The most recent occurrence was at Indian Point Unit 2 on June 3, 1980.
The earlier event occurred at the Davis Besse facility dn October 15, 1979 and resulted in the issuance of IE Circular 80-09.
The installation of the ENS requires a station packabe which operates on 110 VAC.
In some cases, the station package is located at the local telephone company which supplies the required power for normal operation and emergency power for operation during abnormal occurrences, but in many cases, the package is located at the site and is served by on-site power.
In some cases where the station package is served by on-site power, the station package has not been backed up by emergency power.
NRC data indicates that the station packages for each facility are powered in the manner described in the two enclosures.
Actions to be taken by all licensees:
1.
Within 10 days of the date of this Bulletin, verify by direct inspection, in conjunction with the appropriate telephone company representative, that the ENS at your facility is powered in the manner described in the two enclosures.
2.
Those facilities which have station packages requiring on-sice power, but which are not connected to a safeguards instrumentation bus which is backed up by batteries and an inverter or equally reliable power supply, shall make necessary modifications and provide such a connection.
3.
All facilities are to develop and conduct a test, within 60 days of the issuance of this Bulletin, to verify that all extensions of the ENS located at your facility (ies) would remain fully operable from the facility (ies) to the NRC Operations Center in the event of a loss of offsite power to your facility (ies).
This is not intended to mean that an actual loss of offsite power be executed.
Date: June 18, 1980 Page 2 of 2 4.
If it is determined that a station package requiring on-site power i
is t connected to a safeguards instrumentation bus backed up by aut. tic transfer to batteries and an inverter or an equally reliable power supply, notify the NRC Operations Center via the ENS within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after such determination.
l 5.
Prepare and issue an administrative procedure or directive which requires notification to the NRC Operations Center by commercial telephone or relayed message within one hour of the time that one or more extensions of the ENS located at your facility (ies) is subsequently found to be inoperable for any reason.
6.
Provide a written report, within 75 days of the issuance of,this Bulletin, j
describing the result of the reviews required by items 1 and 2 above, the results of the testing required by item 3 and the procedures required by item 5.
This information is requested under the provisions of 10 CFR 50.54(f).
Accordingly, you are requested to provide within the time periods specified in item 6 above, written statements of the above information, signed under oath or affirmation.
j Reports shall be submitted to the Director of the appropriate NRC Regional Office and a copy forwarded to the Director, NRC Office of Inspection and Enforcement, Washington, D.C.
20555.
Approved by GAO, B180225 (R0072): clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
Enclosures:
1.
Facilities With " Hotline" Powered By Local Telephone Company 2.
Facilities With " Hotline" Using On-Site Power l
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+ -,,, - -, -,, ~., - -,
Facilities With " Hotline" Powered By Local Telephone Company Region I B&W Leechburg/ Apollo Beaver Valley 1 Calvert Cliffs 1 & 2 Fitzpatrick Ginna Indian Point 2 Indian Point 3 Millstone 1 & 2 NFS-West Valley Nine Mlle Point 1 Three fiile Island 1 & 2 TI-Attleboro Westinghouse Cheswick Region II Hatch I & 2 NFS-E rwin Region III l
Cook 1 & 2 Dresden 1, 2 & 3 Duane Arnold Kerr McGee Cresent La Crosse Monticello f
Palisades Point Beach I & 2 Quad Cities 1&2 Region V Exxon Richland General Atomics LaJolla Rockwell Canoga Park San Onofre Troj an Enclosure I
Facilities With " Hotline" Using On-Site Power Region I Haddam Neck Maine Yankee Oyster Creek Peach Bottom 2 & 3 Pilgrim 1 Salem 1 & 2 UNC-Montville UNC-Wood River Junction Vermont Yankee Yankee Rowe Region II B&W LRC-Lynchburg B&W Navy-Lynchburg Browns Ferry 1, 2 & 3 Brunswick 1 & 2 Crystal River Farley 1 North Anna 1 & 2 Oconee 1, 2 & 3 Robinson 2 Sequoyah 1 St. Lucie 1 Surry 1 & 2 Turkey Point 3 & 4 Region III Big Rock Point Davis-Besse Kewaunee Prairie Island 1 & 2 Zion 1 & 2 Region IV Arkansas Nuclear One, 1&2 Cooper Fort Calhoun Fort St. Vrain Region V Diablo Canyon Rancho Seco
IE Bulletin No. 80-15 June 18, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-08 Examination of Containment 4/7/80 All power reactors with a Liner Penetration Welds Construction Permit and/or Operating License (OL) 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits (cps) 80-10 ('
Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Pctential for Operating License (OL)
Unmonitored, Uncontrolled or Construction Permit R? lease to Environment (CP) 80-11 Masonry Wall Design 5/8/80 All power reactor facilities with an Operating License (OL),
except Trojan and holders of a Construction Permit (CP) 80-12 Decay Heat Removal System 5/9/80 Each PWR with an Operability Operating License (OL) 80-13 Cracking In Core Spray 5/12/80 All BWR's with an Operating License (0L) 80-14 Degradation of Scram 6/12/80 All BWR's with an Discharge Volume Operating License (OL)
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