ML14174A994

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Exam Rept 50-261/OL-90-01 on 900709-13.Exam Results:All Applicants Passed Exams
ML14174A994
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 08/28/1990
From: Munro J, Curtis Rapp
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML14174A993 List:
References
50-261-OL-90-01, 50-261-OL-90-1, NUDOCS 9009140195
Download: ML14174A994 (6)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA STREET, N.W.

ATLANTA, GEORGIA 30323 ENCLOSURE 1 EXAMINATION REPORT NO.: OL-90-01 Facility Licensee:

Carolina Power and Light Company H. B. Robinson Steam Electric Plant P.O. Box 790 Hartsville, SC 29550 Facility Docket No.:

50-261 Facility License No.:

DPR-23 Examinations were administered at H. B. Robinson near Hartsville, SC.

Chief Examiner:

app e t Approved by:

t jE 14 Uhn F. Munro, -S--ction-Chief 7 Date Migned Operator Licensing Section 1 Operations Branch Division of Reactor Safety

SUMMARY

Examinations administered on July 9-13, 1990.

Written and operating examinations were administered to 5 SRO applicants.

A written re-examination was administered to 1 SRO applicant.

Simulator re examinations were administered to 2 SRO applicants and 1 RO applicant.

All applicants passed these examinations.

9009140195 900829 PDR ADOCK 05000261 V

PNU

REPORT DETAILS

1. Facility Employees Contacted
  • S. A. Billings, Technical Aide - Regualtory Compliance
  • R. L. Barnett, Outages and Modifications Manager
  • C. R. Dietz, RNPD Manager
  • J. D. Kloosterman, Regulatory Compliance Director
  • C. A. Bethea, Training Manager
  • R. E. Morgan, Plant General Manager
  • R. Shane, Operator Training Senior Specialist
  • A. Sanders, Simulator Manager
  • R. A. Steele, Operations Coordinator
  • S. Allen, License Training Manager
  • J. B. Allen, Operator Training Senior Specialist
  • T. R. Byron, Operator Training Senior Specialist
  • Attended Exit Meeting
2. Examiners

.K Rapp, Region II T. Guilfoil, Sonalysts I. Kingsley, Sonalysts B. Maier, Region I (Observer)

D. Lane, Sonalysts (Observer)

    • L. W. Garner, Senior Resident Inspector
    • K. Jury, Resident Inspector
  • Chief Examiner
  • Attended Exit Meeting Only
3. Pre-Examination Review On June 25-26, 1990, representatives of the facility reviewed the written examination at the Region II office.

This review was conducted to improve examination technical accuracy and ensure all test items were correct and concise prior to administration.

4. Post-Examination Review Following examination administration, a copy of the written examination was left with facility representatives for review. The facility submitted three comments for NRC review.
5. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. The following items were discussed at the exit meeting.

2

1) AOP-001, Rod Control System Malfunction, does not include direction for recovery of dropped shutdown bank control rods.
2) No direction is present for the amount of power reduction or how to conduct the power reduction following a failure of turbine runback.
3) AOP-14, Loss of CCW, cautions against operating two CCW pumps as required by the EOPs.
4) Vent cap for seal injection filter is corroded and no hose exists to route venting to floor drain.
5) Operators were observed acknowledging alarms without informing other operators during simulator examinations.
6) FRP-H.1 was not entered even though all AFW flow was going to an unisolable faulted steam generator and providing no primary heat removal. The Critical Safety Function for loss of heat sink states 300 gpm to any steam generator as the entry condition. This criteria fails to consider an unisolated faulted steam generator and delays initiation of feed and bleed when required for core cooling.
7) Foldout 'C' SI Reinitiation Criteria improperly required the operators to transistion to EPP-17, SGTR with Loss of Primary Coolant. This delayed identification and isolation of the ruptured steam generator when no loss of primary coolant existed. Also, Foldout 'C' superceeds Path 2 which has the opeators check for indications of a loss of primary coolant at discrete points in Path 2.

The cooperation given to the examiners was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

UNITED STATES C'

NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA STREET, N.W.

ATLANTA, GEORGIA 30323 ENCLOSURE 1 EXAMINATION REPORT NO.: OL-90-o1 Facility Licensee:

Carolina Power and Light Company H. B. Robinson Steam Electric Plant P.O. Box 790 Hartsville, SC 29550 Facility Docket No.:

50-261 Facility License No.:

DPR-23 Examinations were administered at H. B. Robinson near Hartsville, SC.

Chief Examiner:

C~rf Rapp ate Signed Approved by:,

ath6fin F. Munro, Section Chief Date Signed Operator Licensing Section 1 Operations Branch Division of Reactor Safety

SUMMARY

Examinations administered on July 9-13, 1990.

Written and operating examinations were administered to 5 SRO applicants.

A written re-examination was administered to 1 SRO applicant.

Simulator re examinations were administered to 2 SRO applicants and 1 RO applicant.

All applicants passed these examinations.

REPORT DETAILS

1. Facility Employees Contacted
  • S. A. Billings, Technical Aide - Regualtory Compliance
  • R. L. Barnett, Outages and Modifications Manager
  • C. R. Dietz, RNPD Manager
  • J D. Kloosterman, Regulatory Compliance Director
  • C. A. Bethea, Training Manager
  • R. E. Morgan, Plant General Manager
  • R. Shane, Operator Training Senior Specialist
  • A. Sanders, Simulator Manager
  • R. A. Steele, Operations Coordinator
  • S. Allen, License Training Manager
  • J. B. Allen, Operator Training Senior Specialist
  • T. R. Byron, Operator Training Senior Specialist
  • Attended Exit Meeting
2. Examiners
  • C. Rapp, Region II T. Guilfoil, Sonalysts I. Kingsley, Sonalysts B. Maier, Region I (Observer)

D. Lane, Sonalysts (Observer)

    • L. W. Garner, Senior ResidentInspector
    • K. Jury, Resident Inspector
  • Chief Examiner
  • Attended Exit Meeting Only
3. Pre-Examination Review On June 25-26, 1990, representatives of the facility reviewed the written examination at the Region II office. This review was conducted to improve examination technical accuracy and ensure all test items were correct and concise prior to administration.
4. Post-Examination Review Following examination administration, a copy of the written examination was left with facility representatives for review.

The facility submitted three comments for NRC review.

5. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. The following items were discussed at the exit meeting.

2

1) AOP-001, Rod Control System Malfunction, does not include direction for recovery of dropped shutdown bank control rods.
2) No direction is present for the amount of power reduction or how to conduct the power reduction following a failure of turbine runback.
3) A0P-14, Loss of CCW, cautions against operating two CCW pumps as required by the EOPs.
4) Vent cap for seal injection filter is corroded and no hose exists to route ventina to floor drain.
5) Operators were observed acknowledging alarms without informing other operators during simulator examinations.
6) FRP-H.1 was not entered even though all AFW flow was going to an unisolable faulted steam generator and providing no primary heat removal.

The Critical Safety Function for loss of heat sink states 300 gpm to any steam generator as the entry condition. This criteria fails to consider an unisolated faulted steam generator and delays initiation of feed and bleed when required for core cooling.

7) Foldout 'C' SI Reinitiation Criteria improperly required the operators to transistion to EPP-17, SGTR with Loss of Primary Coolant. This delayed identification and isolation of the ruptured steam generator when no loss of primary coolant existed. Also, Foldout 'C' superceeds Path 2 which has the opeators check for indications of a loss of primary coolant at discrete points in Path 2.

The cooperation given to the examiners was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

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