ML18136A346
| ML18136A346 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 12/19/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-25, NUDOCS 8001030712 | |
| Download: ML18136A346 (6) | |
Text
i e
VIRGINIA ELECTIHC.A.ND POWER COMP.A.NY RIOHMOND,VIRGINIA 23261 December 19, 1979 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 A~lanta, Georgia 30303
Subject:
IE Bulletin 79-25 Failures of Westinghouse BFD Serial No.
PO/RMT:baw Docket Relays in Safety-Related Systems
Dear Mr. O'Reilly:
This is in response to.IE Bulletin No. 79-25, "Failures of Westinghouse BFD Relays in Safety-Related Systems".
Our responses for North Anna Power Station Unit Nos. 1 and 2 and Surry Power Station Unit Nos. 1 and 2 are attached.
Attachment Very truly yours,
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C. M. Stallings Vice President-Power Supply and Production Operations cc:
Director, Office of Inspection and Enforcement Division of Reactor Operation Inspection U. S. Nuclear Regulatory Commission Washington, D. C.
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e Attachment page 1 North Anna Power Station Response to IE Bulletin 79-25 Failures of Westinghouse BFD Relays in Safety-Related Systems
- 1.
Determine whether or not the following Westinghouse BFD/NBFD relays are used or planned for use in safety-related systems at your facilities:
- a.
Type BFD, style 46E7352 or 766A235, coil style 503C428G21
- b.
Type BFD, style 5069A95, coil style 1259C71G19
- c.
Type BFD, style 5072A49, coil style 1271C50G01
Response
An investigation was conducted at the North Arina Power Station to determine whether or not relays of the type listed in the bulletin are used or were planned for use in safety-related systems.
It was determined that relays of that type are not currently in use or planned for use in any safety-related systems.
Based on this determination, responses to items 2 and 3 of the bulletin are not required *
- ~
e Surry Power Station Response to IE Bulletin 79-25 Failures of Westinghouse BFD Relays in Safety-Related Systems Attachment page 2
- 1.
Determine whether or not the following Westinghouse BFD/NBFD relays are used or planned for use in safety-related systems.at your facilities:
- a.
Type BFD, style 46E7352 or 766A235, coil style 503C428G21
- b.
Type BFD, style 5069A95, Coil style 1259C71Gl9
- c.
Type BFD, style 5072A49, coil style l271C50G0I
Response
A review has been performed to determine if any of the Westinghouse BFD type relays noted in Item 1 of IE Bulletin 79-25 are in use or planned for use in safety-related systems.
Surry currently utilizes the Item lB relays in all Engineered Safeguards Systems for Logic Trains.
A limited number of the Item lC units are also in use in these systems.
- 2.
If such relays are used or planned for use, identify the safety-related systems involved, specific function of relays and provide in written form your plans for a test and/or replacement program which will assure design performance of affected relays.
Response
'l'he relays involved and the specific function of each relay are listed in Table I of this attachment.
A program is being generated whereby all the relays identified in Table 1 will be replaced with Item le units.
Following replacement of all relays in a given system, existing performance tests will be accomplished to verify logic and relay operability.
Since the program will involve replacing safety-related components, the effort will be handle~ through the Design Change Program.
- 3.
The but
- a.
- b.
- c.
- d.
program to assure performance of affected relays shall include, not be limited to, the following:
Establishment and a<:lherence to a periodic testing and/or replacement schedule to assure operability of applicable relays.
The basis for the test interval of 3A. above including the data base upon which the initial test schedule is established.
Development of *approved procedures to be utilized by qualified personnel for the testing and/or replacement of applicable relays.
Relay failures found during program testing are to be documented in final report and reported at the time of finding in accordance with license requirements.
---~
e
~achment page 3
Response
- a.
Unless otherwise directed, the establishment of a periodic testing program to ensure relay operability will not be done.
'!he safety-related systems involved are currently subject to monthly logic testing during which the relays are cycled.
Consequently, mal-functioning units will be discovered and appropriate corrective action taken.
The replacement of all affected relays in Unit 2 safety-related systems will be accomplished prior to returning the unit to service after the current outage and those in Unit 1 during the upcoming Steam Generator Replacement Project outage.
- b.
The basis for the test interval noted in item 3a above is docu-mented in the Surry Power Station Technical Specifications.
- c.
The relays will be replaced in accordance with an existing approved maintenance procedure (EMP-C-RT-24).
However, prior to performing the work, the procedure will be modified to include testing of the new relays for armature overtravel and undertravel.
This testing will meet.the requirements and recommendations of Westinghouse Technical Bulletin HSD-TB-79-05.
- d.
During the course of the replacement program, defective relays will be recorded and reported in accordance with reporting re-quirements. At the end of the program for each unit, a report will be generated and forwarded with the results of all testing
- TABLE 1 RELAY NUMBER FUNCTION NUMBER BFD-665 IRBXA INTR. RANGE BLOCK 1
BFD-665 IRBXA INTR. RANGE BLOCK 1
BFD-485 FC COOLANT FLOW 1
BFD-485 FC COOLANT FLOW 1
BFD-485 AST 1 TURBINE AUTO STOP 1
BFD-485 27-1-XA UNDER VOLTAGE 1
BFD-485 SVl TURBINE STOP VALVE l
BFD-22 RTl REACTOR TRIP 6
BFD-485 FC COOLANT FLOW
- 2 BFD-485 AST 2 TURBINE AUTO STOP 1
BFD-485 27-2-XA UNDERVOLTAGE 1
BFD-485 SV2-XA TURBINE STOP VALVE 1
BFD-225 RT REACTOR TRIP 6
BFD-665 SRB SOURCE RANGE BLOCK 2
BFD-665 PRB POWER RANGE BLOCK 2
BFD-485 PS PERMISSIVE PS 2
BFD-485 PlO PERMISSIVE PlO 2
BFD-485 FC COOLANT FLOW 2
BFD-485 AST 3 TURBINE AUTO STOP 1
BFD-485 27-3-X4 UNDERVOLTAGE 1
BFD-485 SV3-XA TURBINE STOP VALVE 1
BFD-245 AFP 1,2,3 AUX. FEED PUMP START 3
BFD-245 TXXA TURBINE TRIP 1
BFD-665 AFP-YA AUX. FEED POMP START 1
BFD-485 P7-YAXA PERMISSIVE PT 1
BFD-665 33XA HOT LEG STOP VALVE 6
BFD-335 33YA HOT LEG STOP VALVE 9
BFD-485 SV4 TURBINE STOP VALVE 2
BFD-225 RT2 REACTOR TRIP 2
BFD-845 SI SAFETY INJECTION 1
BFD-445 PRB PERMISSIVE & BLOCK SIGNAL 1
BFD-845 LTA MAIN STEAM ISOLATION 1
BFD-225 SIR HIGH CONT. PRESSURE 1
BFD-845 Sil SAFE.TY INJECTION 1
BFD-845 S12 SAFETY INJECTION 1
BFD-845 Sl3 SAFETY INJECTION 1
BFD-485 S14 SAFETY INJECTION 1
BFD-485 Sl5 SAFETY INJECTION 1
BFD-485
- S16 SAFETY INJECTION 1
BFD-485 CII SFGDS. ACTUATION (SAFETY INJECTION) 1 BFD-445 RT-A REACTOR TRIP 1
BFD-225 FIY FEEDWATER ISOLATION 1
BFD-225 F2Y FEEDWATER ISOLATION 1
BFD-225 F3Y FEEDWATER ISOLATION 1
BFD-845 SL1 STEAM LINE ISOLATION 1
BFD-845 SL2 STEAM LINE ISOLATION 1
Bm,:_485 63XI HI S'IM LINE DIFF. PRESS.
1 BFD-445 63X2 HI S1M LINE DIFF. PRESS.
1 BFD-445 63X3 HI S'IM LINE DIFF. PRESS.
1 BFD-225 74-A STEAM LINE ISOLATION 1
BFD-225 74-A STEAM LINE ISOLATION 1
.. ~.
e TABLE I (CONT'D.)
RELAY NUMBER FUNCTION NUMBER BFD-225 FIR-A FEEDWATER ISOLATION 1
BFD-445 FIX-A FEEDWATER ISOLATION 1
BFD-225 F2R-A FEEDWATER ISOLATION 1
BFD-445 F2-XA FEEDWATER ISOLATION 1
BFD-225 F3R-2 FEEDWATER ISOLATION 1
BFD-445 F3-XA FEED FLOW 1
B.FD-445 SDX5-A STEAM DUMP 1
BFD-485 SDX6-A STEAM DUMP 1
EFD-485 5DX7-A STEAM DUMP 1
BFD-845 SlA-AY SAFETY INJECTION 1
BFD-445 3/4 CLS-lA CONSQ. LIMIT.
1 BFD-445
- 3 CLS-lAM +
3CL -
lAMX CONSQ. LIMIT.
2 B~225 CR-CLS lAl THRU CA-CLS 1A14 CONSQ. LIMIT.
14 BFD-445 3/4 CLS-2A (x 2) 3 CLS-lAM-X (Two 3 CL-lAMY CONSQ. LIMIT.
3 Trains)
BFD-845 CR-CLS-2Al THRU CR-CLS-2A4 CONSQ. LIMIT.
4 BFD-665 CR-CLS-2A5 CONSQ. LIMIT.
1 BFD-485 CR-CLS-2A7 CONSQ. LIMIT:
2 CR-CLS-2A6 CONSQ. LIBIT.
TOTAL 147 X 2 (2 Units) 294
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