ML20235W415
| ML20235W415 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/09/1987 |
| From: | Burdick T, Isaksen P, Jensen N, Reidinger T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235W414 | List: |
| References | |
| 50-456-OL-87-02, 50-456-OL-87-2, 50-457-OL-87-02, 50-457-OL-87-2, NUDOCS 8710160213 | |
| Download: ML20235W415 (3) | |
Text
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L U.S. NUCLEAR REGULATORY COMMISSION l
l' REGION III Report No. 50-456/0L-87-02 i
l Docket Nos. 50-456; 50-457 License No. NPF-70 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL' 60690 Facility Name:
Braidwood
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Examination Administered At: Braidwood Examination Conducted: Week of September 14, 1987
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7 Examiners:
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/d!I N. Jensen, EGG Date P
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Date Ttinna(s Burdick, Chief
/6/9/O LL Approved By:
Operator Licensing Section Date' Examination Summary Examination administered on the Week of September 14, 1987 Report No. 50-456/
.i OL-87-02)
Results:
Eight licensed Senior Reactor Operator (SR0) and four Reactor Operators (RO) were administered only the operating examinations. All operators passed the examination.
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REPORT DETAILS-q
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Examiners-t a
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. T..D.' Reidinger, Chief Examiner, NRC PJ Isaksen, EGG:
N..Jensen, EGG-E 2.
Exit Meeting On: September 18,1987.the Chief Examiner met with members of the plant-
-staff to discuss. generic findings made during the course of the-examinations,.the following personnel attended the exit meeting.
' Attendees T. Tongue, RIII, SRI T. Reidinger, RIII, Chief Examiner
'P. Isaksen,. EGG' B. Picker, EGG.
G, Vanderheyden, Training Supervisor, Braidwood
~ K. Gerling, PTC Training Supervisor, PWR D. Seph,-PTC-Training. Staff Simulator E, Fitzpatrick, Plant-Manager, Braidwood D. O'Brien, Assistant Plant Superintendent, Operations Summary of NRC-Comments The Chief Examiner presented the following facility strengths. The
' candidates were well versed in the Unit's mechanical differences as well as the administrative differences between the two units. The candidates R
. were strong in their overall plant knowledge as demonstrated in the walk through portion of'the operating examinations. The candidates exhibited-good familiarity with their emergency and abnormal procedures.
Several generic deficiencies were identified by the examiners.
. The technical dialogue by the operating crew exhibited during the majority of the simulator examinations tended to be of generalities with lack of regard to content and scope of directions or comments issued by either of the crew members. The SR0: Ordering the R0 to increase charging to the primary would state "Give me big time charging,": Ordering the R0 to close "C" S/G MSIV, " Hit the "C" S/G MSIV,":
asking 80P for limits on containment pressure, B0P answering " Pretty High".
While the orders or directions issued did not result in the crew misdiagnosing any casualties or effect proper recovery actions the non specific technical nature of the dialogue could possibly lend itself to be misinterpreted and misdirect " uninformed" crew members to incorrect procedures or actions in the control room.
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TheNRCexaminersnotedaoperationaldifferenceintheBrai$do'dabnormal l
3 procedures, Excessive Primary Plant Leakage (PRI-1) and Control Abom Inaccessibility (PRI-5)jnregardstoemergencyboration.
Procedurally an operator cannot emergency borate the: primary from the remote shut down 1
panel with the (PRI-5):'procetre becaus'e there is !no ctep requiring ths i
start of the boric acid trarpf,er pump for )the emygency boration.
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Also during simuistor examina-tions the NRC team,vbWd an irregularity BFR H-1 (Heat Sink) in tdgards to Step 5 with anLactive 10 pstp,in /-
containment, there is no, direction in clearing the containment.c,dal in' order to restart feekater to the S/G's, (resetting the feedwu.p 'Isoletion signal).
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Subsequent phone calls With the utility reveal they are investigating 4
problems noted and will implement corrective actions to the procedures.
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