ML16340B058
| ML16340B058 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/18/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8007030017 | |
| Download: ML16340B058 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 June 18, 1980 Docket Nos.
50-275, 50-323 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention:
Hr. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
Enclosed is IE Bulletin No. 80-15 which requires action by you with regard to your power reactor facility(ies) and/or fuel facility(ies) 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 this office.
Sincerely, R.
H. Engelken Director
Enclosures:
l.
List of Recently Issued IE Bulletins cc w/enclosures:
E.
B. Langley, Jr.,
- Ramsay, PG&E, Diablo Canyon GOOVO 8 9 Olg
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UNITED STATES SSINS Ho.:
6820 NUCLEAR REGULATORY COMt1ISS ION Accessions Ho.:
OFFICE OF INSPECTION AHD EHFORCEt<EHT 8005050072 WASHINGTON, D.C.
20555 June 18, 1980 IE Bulletin No. 80-15 POSSIBLE LOSS OF B1ERGENCY NOTIFICATION SYSTBI (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 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 EHS at your facility is powered in the manner described in the two enclosures.
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 EHS located at your facility(ies) w'ould 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.
IE Bulletin No. 80-15 June 18, 1980 Page 2 of 2 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 wi,thin 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, Mashington, 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 Mith "Hotline" Using On-Site Power
Facilities With "Hotline" Powered By Local Telephone Company Region I B8W Leechburg/Apollo Beaver Valley 1
Calvert Cliffs 1 5 2 Fitzpatrick Ginna Indian Point 2 Indian Point 3
Millstone 1 5 2 NFS-West Valley Nine Mile Point 1
Three Mile Island 1
8 2
TI-Attleboro Westinghouse Cheswick Region II Hatch~i 2 NFS-Erwin Region III Cook 1
8 2
Dresden 1,
2
& 3 Duane Arnold Kerr McGee Cresent La Crosse Monticello Palisades Point Beach 1
8 2
squad Cities 1 5 2 Region V
Exxon Richland General Atomics LaJolla Rockwell Canoga Park San Onofre Trojan
'nclosure 1
Facilities With "Hotline" Using On-Site Power Region I Haddam Neck Maine Yankee Oyster Creek Peach Bottom 2 8
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
8 2
Turkey Point 3
& 4 Region III Big Rock Point Davis-Besse Kewaunee Prairie Island 1
8 2
Zion 18 2
Region IV Arkansas Nuclear One, 1
8 2
Cooper Fort Calhoun Fort St. Vrain Region V
Diablo Canyon Rancho Seco Enclosure 2
I
IE Bulletin No. 80-15 June 18, 1980 RECENTLY ISSUED IE BULLETINS Enclosure Bulletin No.
Subject Date Issued Issued To 80-14 80-13 80-12 Degradation of Scram Discharge Volume Capability Cracking In Core Spray'pargers 6/12/80 5/12/80 Decay Heat Removal System 5/9/80 Operability All BWR's with an OL All BWR's with an OL Each PWR with an OL 80-11 80-10 80-09 masonry Mall Design Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment Hydramotor Actuator Deficiencies 5/8/80 5/6/80 4/17/80 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 80-08 Examination of Containment 4/7/80 Liner Penetration Welds All power reactors with a
CP and/or OL no later than April 7, 1980 80-07 BWR Jet Pump Assembly Failure 4/4/80 All GE BWR-3 and BWR-4 facilities with an OL 79-03A 80-06 80-05 Longitudinal Weld Defects 4/4/80 In ASt1E SA-312 Type 304 Stainless Steel Pipe Engineered Safety Feature 3/13/80 (ESF)
Reset Controls Vacuum Condi tion Resul ting 3/10/80 In Damage To Chemical Volume Control System (CVCS) Holdup Tanks 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
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