ML20198J580
| ML20198J580 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle, 05000000 |
| Issue date: | 05/30/1986 |
| From: | Wojnarowski J COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 1724K, IEB-86-001, IEB-86-1, NUDOCS 8606030156 | |
| Download: ML20198J580 (3) | |
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O) One First National Plaza. Chicago. Ilhnois 8
Commonwealth Edison
( C "J Address Riply to. Post Office Box 767 T
Q Chicago, Illinois 60690 May 30, 1986 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Dresden Station Units 2 and 3 Quad cities Station Units 1 and 2 LaSalle County Station Units 1 and 2 Response to I.E.Bulletin 86-01 NRC Docket Nos. 50-237/249, 50-254/265 and 50-373/374
Reference:
I.E. Bulletin 86 J.M. Taylor letter to All GE BWR Facilities with OL and CP dated May 23, 1986.
Dear Mr. Keppler:
Conunonwealth Edison has reviewed the minimum flow bypass valve logic for the RHR/LPCI pumps at Dresden, Quad Cities and LaSalle with respect to the concerns identified in the referenced I.E. Bulletin. Our review has determined that the logic problem which could potentially result in closure of all RHR/LPCI minimum flow bypass valves due to a single failure does exist at Dresden Units 2 and 3 and Quad cities Units 1 and 2 (all BWR 3's).
The logic problem does not exist at LaSalle (BWR 5).
The following paragraphs describe the short term actions we've initiated at Dresden and Quad Cities to address this concern.
It should be noted that both Dresden units were in cold shutdown when the Bulletin was issued. The LPCI system was not required to be operable for either unit per the Technical Specifications. Dresden Unit 3 is projected to startup in early July, 1986. Dresden Unit 2 is expected to return to service the week of June 2, 1986. Both Quad Cities units were operating at the time the Bulletin was issued.
QUAD CITIES SHORT TERM ACTIONS Upon confirming that this condition existed, the immediate action taken was to instruct the operating shifts of the problem and provide a Procedure to recognize and mitigate the problem as required by the Bulletin.
Training was provided to the shifts as they came on duty. The training identified the potential problem and provided for operator actions to be 8606030156 860530 gll PDR ADOCK 05000237.
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l Mr. J. G. Keppler May 30, 1986 l
taken to recognize and mitigate a loss of minimum flow path for the RHR pumps. Upon automatic initiation of RHR pumps, the operator action should be to:
(1) Immediately verify a pump flow path is availabe via the minimum flow valves or the injection valves (2) If no flow path exists, manually open the minimum flow valves (3) If the minimum flow valves will not open or do not stay open, stop the RHR pumps and place the control switches in the PULL-TO-LOCK position. The pump should be monitored and restored to operation when a flow path is established.
A temporary change to Procedure QOA 1000-4, LPCI AUTOMATIC INITIATION, was made adding a precaution which summarized these actions.
The training and procedure change were initiated on May 23, 1986, the date of receipt of the Bulletin.
Upon reviewing the Station response with the corporate office and Dresden Station, the Station decided to amend its short term response.
j Instead of stopping the RHR pumps upon loss of. mil flow paths, the
" Containment Cooling Permissive" and the " Cont. CLG 2/3 Level and ECCS Initiation Bypass" keylock switches will be used to allow opening the 1001-34 and 36 valves to establish a flow path to the torus. Should a flowpath via the minimum flow valves or the vessel injection valves be established, the keylock switches shall be returned to their normal po:lLlon and the 1001-34 and 36 valves closed. A temporary procedure will be written stating these actions, and will be maintained until a long term solution is completed.- The operating shifts will also be trained on the revised operator actions.
DRESDEN SHORT TERM ACTIONS Upon identification of the problem, a memorandum was issued to all Shift Engineers, Station Control Room Engineers, and Shift Foremen explaining the potential problem. In addition to the memorandum, operating order 35-86, operational Guidelines to Provide Adequate LPCI Minimum Flow, has been issued. The operating order instructs licensed operators to verify the that LPCI minimum flow valves MO-2(3)-1501-13A and 13B are open if there is no flow through either LPCI loop injection lines upon receipt of a LPCI system initiation signal.
If any minimum flow valve is found failed closed with the pumps dead headed, the operators are instructed to consider providing alternate minimum flow through the appropriate LPCI test line by opening valves MO-2(3)-1501-20A(b) and 38A(B). This would require the operator to override the LPCI. loop select logic that interlocks these valves closed by placing the containment spray keylock switches 316 and 317 to the manual position. Flow could then be throttled to approximately 1000 gpm until LPCI injection occurs or the minimum flow valves open.
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L Mr. J. G. Keppler May 30, 1986 Training will be conducted for all licensed reactor operators and senior reactor operators assigned on shift. All licensed operators assigned to the shift during startup of Unit 2 following the current short maintenance outage will receive training prior to startup. All other licensed operating
' personnel will receive training prior to returning to operating duties.
rm=mnwealth Edison feels the above described actions sufficiently address this concern on an interim basis. We are currently investigating potential modifications to provide a permanent resolution. We will provide a supplemental response describing our long term resolution as required by Action Item.4 of the Bulletin.
This response fulfills Action Items 1, 2 and 3 of IRB 86-01 for Dresden Units 2 and 3 and Quad Cities Units 1 and 2.
Since the logic problem does not exist at LaSalle Station, no further action or response is required regarding LaSalle Units 1 and 2.
Please address any questions that you or your staff may have concerning our response to this office.
One signed original is being sent directly to the USNRC Document Control Desk in Washington, D.C. for reproduction and distribution as requested in the Bulletin.
Respectfully,
(
J. R.
jnarowski Nuclear Licensing Administrator in cc: US NRC Document Control Des l
Washington, D.C.
20555 l
Region III Inspectors - D, QC, LSCS l
SUSCRIBRD AND to r
this day befo g /11A of IyI
, 1986 il Notary Piiblic
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