IR 05000400/1992018
| ML18010A791 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/17/1992 |
| From: | Crlenjak R, King L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18010A790 | List: |
| References | |
| 50-400-92-18, NUDOCS 9209250236 | |
| Download: ML18010A791 (7) | |
Text
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Aeport No.:
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 50-400/92-18 Licensee:
Car'olina Power and Light Company P.O.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400
Facility Name:
Shearon Harris License No.:
NPF-63 Inspection Conducted:
August 31 - September 4,
1992 Inspector: ~
L. King, Reactor Insp or Date Signed Approved by':
. Cr1enjak, e
Operational Programs Section Division of Reactor Safety Da e i ned SUMMARY Scope:
This was a special announced Emergency Operating Procedure followup inspection.
Its purpose was to verify that corrective actions for previous findings in the area of -emergency and abnormal operating procedures were adequate.
Results:
The overall assessment concluded that the licensee response to the Inspector Followup Items identified in inspection report 50-400/90-11 addressed all of the concerns and that the Emergency Operating Procedures were adequate to mitigate the spectrum of accidents addressed in the Emergency Response Guidelines.
9209'250236 920921 PDR ADOCK 05000400
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J
- E
- J
- C
- H.
- S
- S
- V
- J
- C
- M.
NRC
- J N.
Bradley, Manager Operations Support
- Operations Brooks, Operations Procedure Coordinator
- Operations Collins, Manager of Operations Gibson, Manager of Programs and Procedures Hamby, Project Specialist
- Regulatory Compliance Hinnant, Plant General Manager McCoy, Shift Technical Advisor NcGrew, Shift Technical Advisor Moyer, Manager of Project Assessment Olexi k, Manager
- Regulatory Compliance Wallace, Senior Specialist
- Regulatory Compliance Resident Inspectors Tedrow, Senior Resident Inspector Shannon, Resident Inspector
~
~
- Attended exit interview on September 4,
1992.
2.
Actions on Previous Inspection Findings (92701)
a.
b.
C.
(Closed) IFI 400/90-11-01:
This item addressed Procedure Generation Package inadequacies.
The requirements for writing and maintaining the Emergency Operating Procedures were incorporated into a
new administrative procedure, OMM-021, Maintenance of Emergency Operating Procedures.
ONN-021 superseded the Procedure Generation Package and controls OMN-005, Emergency Operating Procedures Writer's Guide, and OMM-020 Emergency Operating Procedure Verification and Validation Program.
(Closed)
IFI 400/90-11-02:
This item addressed inadequate Step Deviation Document justifications.
~ The inadequate Step Deviation Document justifications were revised with the new issue of the Emergency Operating Procedures.
ONN-021 stated that any deviations from the Emergency Response Guidelines would be justified.
(Closed)
IFI 400/90-11-03; This item addressed technical and human
'factors discrepancies.
The licensee addressed all of the comments in Appendix B.
The inspector reviewed all of the responses and found them acceptable.
(Closed)
IFI 400/90-11-04:
This item addressed Writer's Guide discrepancie The new issue of the Writer's Guide, Revision 7, incorporated most
- of the comments in Appendix C of inspection report 400/90-11 and where the comments were not incorporated, the inspector found the responses acceptable.
e.
(Closed)
IFI 400/90-11-05:
This item addressed Emergency Operating Procedure nomenclature inaccuracies.
The nomenclature inaccuracies were incorporated in most cases and where they were not, the inspector found the justification for not changing them to be adequate.
New procedure OMM-020, Emergency Operating Procedure Verification and Validation Program, step 5.2.2. 1 stated that local actions were to be validated to the same extent as -any other Emergency Operating Procedure action,
. However, this was a
new procedure and had not been fully implemented.
The procedure did not require validation except for major'revisions or every two years.
This item was closed based on the licensee identifying all local actions that have to be d and commiting to do them during the next validation.
validate
'.
Exit Interview f.
(Closed)
IFI 400/90-11-06:
This item addressed inadequate Verification and Validation of locally-performed actions.
The inspection scope and findings were summarized on September 4,
1992, with those persons indicated in paragraph 1.
The NRC described the areas inspected and discussed in detail the inspection findings listed below.
No proprietary material is contained in this report.
. No dissenting
- comments were received from the licensee.
Item Number Status Descri tion Para ra h
IFI 400/90-11-01 Closed Procedure Generation Package inadequacy, paragraph
IFI 400/90-11-02 Closed
,,
Inadequate Step Deviation Document justifications, paragraph
IFI 400/90-11-03 Closed IFI 400/90-11-04 Closed IFI 400/90-11-05 Closed IFI 400/90-11-06 Closed Technical and human factors -discrepancies, paragraph
Writer's Guide discrepancies, paragraph
Emergency Operating Procedure nomenclature inaccuracies, paragraph
Inadequate Verification and Validation of locally performed actions, paragraph
'
Qi EOP-PATH-1 EOP-PATH-2 EOP-EPP-001 EOP-EPP-002 EOP-EPP-003 EOP-EPP-004 EOP-EPP-005 EOP-EPP-006 EOP-EPP-007 EOP-EPP-008 EOP-EPP-009
'EOP-EPP-012'OP-EPP-013 EOP-EPP-014 EOP-EPP-015 EOP-EPP-017 EOP-EPP-018 EOP-EPP-020 EOP-EPP-021 EOP-EPP-022 EOP-FRP-C.
EOP-FRP-C.2 EOP-FRP-H.
EOP-FRP-H.2 EOP-FRP-H.3 EOP-FRP-H.4 EOP-FRP-I. 2 EOP-FRP-J.2 EOP-FRP-P.
EOP-FRP-S.1 EOP-CSFST AOP-001 AOP-002 AOP-003 AOP-004 AOP-005 AOP-008 AOP-009 AOP-010 AOP-012 REV 6/1 REV 5/1 REV
REV 4 REV 4 REV 4 REV 5 REV 4 REV 4 REV 4 REV 4 REY 4 REV 4 REV 4 REV 4 REV 4 REV 4 REV 4 REV 4 REV 5 REV 4 REV 4 REV 5 REV 4 REV 4 REV 4 REV 4
REV 4 REV 4 REV 4 REV 3 REV 5 REV
REV 4 REV 6 REV 6 REV 6 REV
REV 6 REV 5 Appendix A PROCEDURES REVIEWED Path-1 Path-2 Loss of All AC Power to 1A-SA and 1B-SB Busses Loss of All AC Power Recovery Without SI Required Loss of All AC Power Recovery With SI Required Reactor Trip Response Natural Circulation Cooldown Natural Circulation Cooldown With Steam Void in Vessel (With RVLIS)
Natural Circulation Cooldown With Steam Void in Vessel (Without RVLIS)
SI Termination Post-LOCA Cooldown and Depressurization Loss of Emergency Coolant Recirculation LOCA Outside Containment Faulted Steam Generator Isolation Uncontrolled Depressurization of all Steam
.
Generators Post-SGTR Cooldown Using Backfill Post-SGTR Cooldown Using Blowdown SGTR with Loss of Reactor Coolant:
Subcooled Recovery SGTR with Loss of Reactor Coolant:
Saturated Recovery SGTR without Pressurizer Pressure Control Response to Inadequate Core Cooling Response to Degraded Core Cooling Response to Loss of Secondary Heat Sink Response to Steam Generator Overpressure Response to Steam Generator High Level Response to Loss of Normal Steam Release Capability Response to Low Pressurizer Level Response.to Containment Flooding Response to Imminent Pressurized Thermal Shock Response to Nuclear Power Generation/ATWS Critical Safety Function Status Trees Malfunction of Rod Control and Indication Systems Emergency Boration Malfunction of Reactor Make-up Control Shutdown in Case of Fire or Control Room Inaccessibility
,
Radiation Monitoring System Accidental Release of Liquid Waste Accidental Release of Waste Gas Feedwater Malfunctions Partial Loss of Condenser Vacuum
Appendix A
AOP-014 AOP-017 AOP-018 AOP-019 AOP-020 AOP-021 AOP-022 AOP-024 AOP-025 AOP-026 AOP-028 AOP-029 AOP-030 AOP-031 AOP-032 AOP-034 AOP-035 AOP-036 AP-301 EOP-USER'S OMM 006 OMH-020 OMM-021 REV 6 REV 5 REV
REV 4 REV
REV 5 REV 5 REV 5 REV 6 REV 4 REV 6 REV 6 REV 4 REV 4 REV 4 REV 4 REV 3 REV 0 REV I/I GUIDE REV
REV
REV 0 REV 0 Loss of Component Cooling Water Loss of Instrument Air Reactor Coolant Pump Abnormal Conditions Malfunction of RCS Pressure Control Loss of RCS Inventory or Residual Heat Removal While Shutdown Seismic Disturbances Loss of Service Water Loss of Uninterruptible Power Supply Loss of One Emergency AC. (6.9KV) or One Emergency DC (125V)
Bus Loss of Essential Services Chilled Water System Low Voltage Operation Low Frequency Operation Metal Impact Monitoring System Trouble Loss of. Refueling Cavity Integrity High RCS Activity Axial Flux Difference Hain Transformer Trouble Safe Shutdown Following a Major Fire Adverse Weather Operations EOP User's Guide EOP Writer's Guide Emergency Operating Procedure Verification and Validation Program Maintenance of Emergency Operating Procedures