NRC Generic Letter 1980-55
| ML031350404 | |
| Person / Time | |
|---|---|
| Issue date: | 06/18/1980 |
| From: | Grier B NRC Region 1 |
| To: | |
| References | |
| BL-80-015 GL-80-055, NUDOCS 8007020710 | |
| Download: ML031350404 (6) | |
- RG& UNITED STATES a 9A *°- CLEAR REGULATORY
COMMISSION-REGION I 631 PARK AVENUE KING Of PRUSSIA, PENNSYLVANIA
19406 June 18, 1980 Docket Nos. 50-03 50-247 Consolidated Edison Company of New York, Inc.ATTN: Mr. W. J. Cahill, Jr.Vice President 4 Irving Place New York, New York 10003 Gentlemen:
The enclosed IE Bulletin No. 80-15, "Possible Loss of Emergency Notification System (ENS) With Loss of Off-Site Power," is forwarded to you for action. A written response is required.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.If you desire additional information regarding this matter, please contact this office.Sincerely, 4A.rkv grce H. Grier Director Enclosures:
1. IE Bulletin No. 80-15 2. List of Recently Issued IE Bulletins
CONTACT
- Dr. C. 0. Gallina (215-337-5350)
cc w/encls: L. 0. Brooks, Project Manager, IP Nuclear W. Monti, Manager -Nuclear Power Generation Department M. Shatkouski, Plant Manager J. M. Makepeace, Director, Technical Engineering W. 0. Hamlin, Assistant to Resident Manager J. 0. Block, Esquire, Executive Vice President
-. Administration Joyce P. Davis, Esquire 8 0070 2 09 (&
UNITED STATES SSINS No.: 6820 NUCLEAR REGULATORY
COMMISSION
Accessions No.: OFFICE OF INSPECTION
AND ENFORCEMENT
8005050072 WASHINGTON, D.C. 20555 June 18, 1980 IE Bulletin No. 80-15 POSSIBLE LOSS OF EMERGENCY
NOTIFICATION
SYSTEM (ENS) WITH LOSS OF OFFSITE 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 reactor 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 on October 15, 1979 and resulted in the issuance of IE Circular 80-09.The installation of the ENS requires a station package 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 indicate that the station packages are powered in the manner described in the enclosures.
Actions to be taken by all licensees:
1. Within 10 days of the date of this Bulletin determine by direct inspection, in conjunction with the appropriate telephone company representative, the manner in which the ENS at your facility is powered.2. Those facilities which have station packages requiring on-site 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 ties) would remain fully operable from the facility(ies)
to the NtC Operations Center in the event of a loss of offsite power to your facilityties).
This is not intended to mean that an actual loss of offsite power be executed.
IE Bulletin No. 80-15 June 18, 1980 4. If it is determined that a station package requiring on-site power is not connected to a safeguards instrumentation bus backed up by automatic 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.
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, 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.
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 ENS Powered By Local Telephone Company 2. Facilities With ENS Powered Using On-Site Power Facilities With ENS 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 Mile Point 1 Three Mile Island 1 & 2 TI-Attleboro Westinghouse Cheswick Region II Hatch 1 & 2 NFS-Erwin Region III Cook 1 & 2 Dresden 1, 2 & 3 Duane Arnold Kerr McGee Cresent La Crosse Monticello Palisades Point Beach 1 & 2 Quad Cities 1 & 2 Region V Exxon Richland General Atomics LaJolla Rockwell Canoga Park San Onofre Trojan Enclosure
1 Facilities With ENS Powered 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 Enclosure
2 IE Bulletin No. 80-15 June 18, 1980 Enclosure
2 RECENTLY ISSUED IE BULLETINS Bulletin No.Subject Degradation of Scram Discharge Volume Capability Date Issued 6/12/80 Issued To All BWR's with an OL 80-14 80-13 80-12 80-11 80-10 Cracking In Core Spray Spargers ,-Decay Heat Removal System Operability Masonry Wall Design Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment Hydramotor Actuator Deficiencies Examination of Containment Liner Penetration Welds 5/12/80 5/9/80 5/8/80 5/6/80 4/17/80 a 4/7/80 Each PWR with an OL All power reactor facilities with an OL, except Trojan All power reactor facilities with an OL or CP All power reactor operating facilities and holders of power reactor construction permits All power reactors with a CP and/or OL no later than April 7, 1980 All OL BWR's with an 80-09 80-08 80-07 79-03A 80-06 80-05 BWR Jet Pump Assembly Failure Longitudinal Weld Defects In ASME SA-312 Type 304 Stainless Steel Pipe Engineered Safety Feature (E SF) Reset Controls Vacuum Condition Resulting In Damage To Chemical Volume Control System (CVCS) Holdup Tanks 4/4/80 4/4/80 3/13/80 3/10/80 All GE BWR-3 and BWR-4 facilities with an OL All power reactor facilities with an OL or CP All power reactor facilities with an OL All PWR power reactor facilities holding OLs' and to those with a CP