ML19291C105
| ML19291C105 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, Zion |
| Issue date: | 12/20/1979 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-20, IEB-79-25, NUDOCS 8001220115 | |
| Download: ML19291C105 (3) | |
Text
Commonwealth Edison b'
One First National Plaza. Chicago. Illinois Address Reply to: Post Office Box 767 Chicago. Illinois 60690 December 20, 1979 IEe 17 E
E Mr. James G.
Keppler, Director Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Dresden Station Units 1, 2,
and.:
Quad Cities Station Units 1 and 2; Zion Station Units 1 and 2 Response to IE Bulletin 79-25 NRC Docket Nos. 50-10/237/249, 50-254/265 and 50-295/304 Reference (a) :
J.
G.
Keppler letter to C.
Reed dated November 2, 1979
Dear Mr. Keppler:
In response to your request for information regarding the use of Westinghouse BF D relays in safety-related systems (Reference (a)), on the subject units, Commonwealth Edison submits the enclosed response.
As indicated, with the limited exceptions described for our Zion Station, the discrepant components are not now nor will be used at our operating plants.
The use of those components at our facilities now in construction is currently being evaluated and the results of that review will be submitted to your office in accordance with the schedule defined in Reference (a).
If you have any further questions in this regard, please direct them to this office.
Very truly yours, k.
foK D.
Louis Peoples a
Director of Nuclear Licensing Enclosure 1791 010 cc:
U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operation Inspection
(
b,', m E I 5 v%.l 80 12f(*I
3 Enclosure Response to IE Bulletin 79-25 NRC Docket Nos. 50-10/237/249, 50-254/265, 50-295/304 Dresden Units 1, 2, and 3
- 9 The subject bulletin has been reviewed at the station.
No West-2' 7 inghouse Type BFD Relays of the styles given in IElBulletin 79-25
-- are used or planned for use in safety-related systems.
Therefore,
[ no further action is deemed necessary.
Quad Cities Ur.its 1 and 2 The subject bulletin has been reviewed at the station.
No West-inghouse Type BFD Relays of the styles given in IE Pulletin 79-25 are used cr planned for use in safety related systems.
Therefore, no further action is deemed necessary.
Zion Units 1 and 2 The subject bulletin has been reviewed at the station, and the following response is provided:
Item 1:
All BFD relays in the safety related systems at Zion Stction were checked.
Five relays that had style numbers designated in the bulletin were found installed in these systems.
Twenty additional relays with the designated style numbers were found in stores.
The relays in the storeroom that are subject to sticking in the energized position have been removed and will be disposed of.
The relays that have an overtravel problem will be tested as outlined in the Westinghouse Technical Bulletin NSD-TB-79-05.
Item 2:
Identify the safety-related systems involved, specific function of relays and plans for replacement.
This relay is installed in 1CB-32 Train A of safeguards.
SIX 4-A style 766A235Gll:
This relay is used for Safety Injection ractuation in Train A of Unit I safeguards.
This relay is normally de-energized.
-This relay is installed in 1CB-33 Train B of safeguards.
L.T.A.-B style 766A235Gll:
This relay is used for Safe ty Infection on low temperature average of reactor coolant in conjunction with high steam line flow.
This relay is normally de-energized also.
1791 011
This relay is installed in 1CB-30 Train A reactor protection.
P10-YA style 5072A49G14:
This relay is used for source and intermediate range blocks and is de-energized above 10 per cent reactor power.
This relay has another relay PT10,%A in parallel with it that performs the same functions and is nog of the style 2
identified in the bulletin.
p L
g This relay is installed in ICB-30 Train A of reactor protection.
t P7-2YA st"'e 766A235G14:
This relay is used for annunciator and computer u,ots only.
This relay also has another relay in parallel with it performing the same functions and is not of the style identified in the bulletin.
Both relays are de-energized above ten per cent reactor power.
This relay is installed in 2CB-33 Train B safeguards.
SIR-B style 766A235G08: this relay is used for auto safety injection block.
The control room has an annunciator light to, indicate when this relay is energized.
This relay is normally de-enercized.
Item 3:
All relays of the type described in the bulletin as having the potential for sticking will be replaced and those found in stores have been removed from stock.
All relays of the type described in the bulletin as having a potential over travel problem will be tested as outlined in the Westinghouse Technical Bulletin NSD-TB-79-05.
Each of the five relays discussed in Item 2 above which are now installed in the plant will be replaced with components not subject to the limitations described in the bulle tin.
In the case of relay P10-YA(style 5072A49G14), this component will be replaced with a new relay that has been tested for over travel, before the startup of Zion Unit 1.
The other four relays currently installed are not energized, at rated power so they are not subject to the temperature induced sticking problem described in the bulletin.
However, in the case of relay P7-2YA (style 766A235G14) which is energized up to 10% power, the relay is subject to monthly surveillance under existing technical specification requirements.
This testing is judged adequate during the period prior to replacement.
In as much as the use of the potentially discrepant relays described in the bulletin is limited to the five cases described, and each of those relays will be replaced shortly, it is judged that no further corrective action is required; i.e. periodic testing and/or replacement beyond that specifically delineated
. herein is unnecessary.
1791 012'