ML20049H243
| ML20049H243 | |
| Person / Time | |
|---|---|
| Site: | 05000000 |
| Issue date: | 02/26/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| IEIN-82-01, IEIN-82-1, NUDOCS 8202040105 | |
| Download: ML20049H243 (3) | |
Text
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SSINS No.: 6835 Accession No.:
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IN 82-01, Rev. 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 February 26, 1982 IE INFORMATION NOTICE NO. 82-01, REV. 1: AUXILIARY FEEDWATER PUMP LOCK 0UT RESULTING FROM WESTINGHOUSE W-2 SWITCH CIRCUIT MODIFICATION Due to a reproduction problem, Figure 3 of IE Information Notice No. 82-01 was incomplete as issued to some power reactor facilities holding an operating license or construction permit. A reissue of Figure 3 is attached. Table 1 is also revised to further clarify the circuit diagrams.
No specific action or response is required at this time.
If you have any questions regarding this matter, please contact the Regional Administrator of the appropriate NRC Regional Office.
Attachments:
1.
Figure 3 and Table 1
~2.
Recently issu,ed IE Information Notices 4
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d IN 82-01, Rev. 1 February 26, 1982 RECENTLY ISSUED IE INFORMATION NOTICES
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Information Date of Notice No.
Subject Issue
~ Issued to 80-32 Clarification of Certain 02/26/82 All facility, Rev. -
Recuirements for Exlusive-materials and Use Shipements of Radio-Part 50 licensees active Materials 82-02 Westinghouse NBFD Relay 01/27/82 All power reactor Failures in Reactor facilities holding Protection Systems at an OL or CP Certain Nuclear Power Plants 82-01 Auxiliary Feedwater Pump 01/22/82 All power reactor Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuit Modification 81-39 EPA Crosscheck Program -
12/23/81 All power reactor Low Level Radiciodine in facilities holding Water Test Pregram an OL or CP 81-38 Potentially Significant 12/16/81 All power reactor Equipment Failures Resulting facilities holding from Contamination of Air-an OL or CP Operated Systems 81-37 Unnecessary Radiation 12/15/81 All power reactor Exposure to the Public and facilities holding Workers During Events byproduct material Involving Thickness and licenses Level Measuring Devices 81-36 Replacement Diaphragms for 12/3/81 All power reactor Robertshaw Valve (Model facilities holding No. VC-210) an OL or CP 81-35 Check Valve Failures 12/2/81 All power reactor 4
facilities holding an OL or CP s
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NOTE: TRIPPING BREAKER WITH AUTO-START SIGNAL PRESENT WILL OP i
AND N. AND OPEN CONTACT E. THE SNEAK PAT CONTACTS CTO O
a WILL PERSIST IN KEEPING (Y) COIL ENERGlZED THEREBY PREVENTING CONTACTS 1 AND1 FROM CHANGING STATUS TO ENERGlZE THE b
a UNLATCHING (X) COIL AND RECLOSE THE BREAKER ON DEMAND.
Figure 3 Sneak Path in Control Switch " Neutral" Position with Auto Start Signal hesent lABLE 1 Legend for Figures 1-3 CS Control Switch, Spring Return to Neutral X Closing Coil (contacts are closed position designated; g in switch C = closed; Y Anti-Pump Coil T = tripped; O = neutral; etc.)
LS Y Y Limit Switch / Breaker charging ii, i:I ANTI-PUMP COIL CONTACTS Spring Status (a = contact closed when 52 52 spring charged, b contact a, b Breaker Auxiliary Contacts closed when spring (a = contact closed when Breaker closed, discharged) b = contact closed when Breaker opened)
Snaak Power Path AS Safeguards Contacts (closed for Auto-Start)
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