ML031890924
| ML031890924 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/01/2003 |
| From: | Christopher Cahill NRC/RGN-I/DRS/EB |
| To: | Neil Perry NRC/RGN-I/DRP/PB7 |
| References | |
| FOIA/PA-2003-0358 IR-03-003 | |
| Download: ML031890924 (8) | |
See also: IR 05000334/2003003
Text
July 1, 2003
MEMORANDUM TO:
Neil Perry, Acting Chief
Projects Branch 7
Division of Reactor Projects
THRU:
James C. Linville, Chief
/RA/
Electrical Branch
Division of Reactor Safety
FROM:
Christopher G. Cahill, Electrical Branch
/RA/
Division of Reactor Safety
SUBJECT:
FEEDER FOR BEAVER VALLEY INSPECTION REPORT
50-334/03-003 and 50-412/03-003
During the week of June 16 - 20, 2003, two inspectors from the Division of Reactor Safety and
a contractor performed the biennial inspection of permanent plant modifications and the
evaluation of changes, tests and experiments. The inspection was performed in accordance
with inspection procedure 71111, Attachment 17 and Attachment 02.
The inspection was conducted by the following personnel:
Chris Cahill
Senior Reactor Inspector, Electrical Branch, Lead Inspector
Reactor Inspector, Systems Branch
Ray Cooney
Contractor
Cover Letter Input
No input.
Summary of Findings Input
No findings of significance were identified.
Attached is the feeder for inspection report 50-334/03-003 & 50-412/03-003.
cc w/attachments:
W. Lanning, DRS
R. Crlenjak, DRS
D. Kern, DRP
P. Maccaglia, DRP
DRS File
2
DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML031890924.wpd
After declaring this document An Official Agency Record it will not be released to the Public.
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
OFFICE
RI/DRS
RI/DRS
NAME
CCahill
JLinville
DATE
06/27/03
06/27/03
OFFICIAL RECORD COPY
Report Details
1.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
1R02
Evaluations of Changes, Tests, or Experiments (IP 71111.02)
a.
Inspection Scope
The inspectors reviewed eight selected safety evaluations associated with initiating
event, mitigating, and barrier integrity cornerstones to verify that changes to the facility
or procedures as described in the UFSAR were reviewed and documented in
accordance with 10 CFR 50.59, and that the safety issues pertinent to the changes were
properly resolved or adequately addressed. These safety evaluations were selected
based on the safety significance of the changes and the risk to structures, systems and
components.
The inspectors also reviewed seventeen screen-out evaluations for changes, tests and
experiments for which the licensee determined that safety evaluations were not
required. This review was performed to verify that the licensees threshold for
performing safety evaluations was consistent with 10 CFR 50.59.
In addition, the inspectors reviewed the administrative procedure that was used to
control the screening, preparation, and issuance of the safety evaluations to ensure that
the procedure adequately covered the requirements of 10 CFR 50.59.
The listing of the safety evaluations and screen-out evaluations reviewed is provided in
Attachment 1.
a.
Findings
No findings of significance were identified.
1R05
Fire Protection (IP 7111.05)
1.
Post-fire Safe Shutdown Manual actions
a.
Inspection Scope
The inspectors reviewed evaluation 50.59-01-003, for BVPS Unit 2. The evaluation
reviewed an update to the Fire Protection Safe Shutdown Report to document spurious
signal analysis for ventilation system components. The inspectors utilized the guidance
provide in IP 71111.05, enclosure 2, to evaluate the acceptability of the new manual
actions. Factors, such as timing, access to the equipment, diagnostic instrumentation
and the availability of procedures, were considered in the inspectors review. The team
also reviewed condition report (CR) 02-00921 that identified problems with the
application of manual actions.
2
b.
Findings
The team identified an unresolved item concerning the acceptability of the licensees
use of manual actions to remotely operate equipment or defeat spurious actuations
necessary for achieving and maintaining hot shutdown. This is unresolved pending
completion of the licensees validation of fire protection time critical manual actions.
USFAR section 9.5A.1.2.1.2.8, states "If manual actions are required these actions must
be performed by onsite personnel within the necessary time interval without adversely
affecting safe shutdown."
The inspectors utilized IP 71111.05, enclosure 2, Inspection Criteria for Fire Protection
Manual Actions to evaluate the application of manual actions as described in USFAR
section 9.5A.1.2.1.2.8. The IP provides guidance for the assessment of manual actions
including diagnostic instrumentation, environmental considerations, staffing,
communications, special tools, training, accessibility, procedures, verification and
validation. In particular, the verification and validation guidance states Determine
whether the manual actions have been verified and validated by plant walkdowns using
current procedures. Ensure that the licensee has adequately evaluated the capability of
operators to perform the manual actions in the time available before the plant will be
placed in an unrecoverable condition.
The inspector reviewed CR 02-00921, which identified that the BVPS Unit 2, Fire
Protection Safe Shutdown Report and associated safe shutdown procedures did not
clearly identify critical actions which must be accomplished within prescribed time
frames. The inspectors concluded that an assessment of the manual actions could not
be completed until the licensee had analyzed and validated the critical fire protection
safe shutdown manual actions which must be accomplished within prescribed frames.
This issue has been entered into the licensees corrective action program as corrective
action (CA) 13, to CR 02-00921. This issue will remain unresolved pending the
licensees validation of fire protection time critical manual actions. (URI 50-412/03-003-
01)
1R17
Permanent Plant Modifications (IP 71111.17)
a.
Inspection Scope
The inspectors reviewed nine selected risk-significant plant modification packages to
verify that: (1) the design bases, licensing bases, and performance capability of risk
significant Structures, Systems or Components (SSC) had not been degraded through
modifications; and, (2) modifications performed during increased risk configurations did
not place the plant in an unsafe condition. The modification packages were selected
from among the design changes that were completed within the past two years.
The selected plant modifications were distributed among initiating event, mitigating, and
barrier integrity cornerstones. For these selected modifications, the inspectors reviewed
the design inputs, assumptions, and design calculations, such as instrument set-point,
instrument uncertainty, and electrical loading calculations, to determine design
3
adequacy. The inspectors also reviewed field change notices that were issued during
the installation to confirm that the problems associated with the installation were
adequately resolved. In addition, the inspectors also reviewed the post-modification
testing, functional testing, and instrument calibration records to determine readiness for
operations. Finally, the inspectors reviewed the affected procedures, drawings, design
basis documents, and UFSAR sections to verify that the affected documents were
appropriately updated.
The listing of the reviewed modifications is provided in Attachment 1.
b.
Findings
No findings of significance were identified.
4.
OTHER ACTIVITIES
4OA2 Identification and Resolution of Problems (IP 71152)
a.
Inspection Scope
The inspectors reviewed CRs associated with 10 CFR 50.59 issues and plant
modification issues to ensure that the licensee was identifying, evaluating, and
correcting problems associated with these areas and that the corrective actions for the
issues were appropriate. The inspectors also reviewed two self-assessments related to
10 CFR 50.59 and plant modification activities at Beaver Valley.
The listing of the condition reports and self assessments reviewed is provided in
Attachment 1.
b.
Findings
No findings of significance were identified.
4OA5 Meetings, including Exit
The inspectors presented the inspection results to Mr. L. W. Pearce, Site Vice
President, and other members of licensee management at the conclusion of the
inspection on June 20, 2003. The licensee acknowledged the inspection findings
presented.
4
SUPPLEMENTAL INFORMATION
Key Points of Contact
Licensee
G. Cacciani
50.59 Program Manager
C. Mancuso
Engineering Change Program Owner
M. Manolerar
Design Engineering
D. Mickinac
Regulatory Affairs
L. Pearce
Site Vice President
G. Ritz
Engineering Assessment Board Chairman
F. Oberlitner
Design Engineering
NRC
D. Kern, Senior Resident Inspector, Beaver Valley
a.
Items Opened, Closed, and Discussed
Opened
50-412/03-03-01
URI Validation and Verification of Manual Actions not Complete
(Section 1R05)
b.
List of Acronyms Used
automatic recirculation valves
Beaver Valley Power Station
CFR
Code of Federal Regulations
CR
condition reports
engineering change package
First Energy Nuclear Operating Company
high head safety injection
IP
inspection procedure
non-cited violations
problem identification and resolution
Regulatory Guide
safety evaluation
structures, systems or components
service water system
to be determined
TS
Technical Specifications
Updated Final Safety Analysis Report
5
Attachment 1
Documents Reviewed
Modifications
ECP 02-0040 Determine Minimum Number of Tensioned Reactor Head Studs to Commence
Reactor Fill and Vent
ECP 02-0077 Removing Blocking Diodes from Rod Control Circuits
ECP 02-0183 Install Feedwater Isolation Valve to Support Power Up-rate
ECP 02-0063 Replacement of the No. 4 Vital Bus Inverter
ECP 02-0253 Replace 6 inch Service Water Piping with 4 inch Piping
ECP 02-0514 Modify Fire Damper
ECP 02-0731 Change the Fuses in the Control System Power Cabinet
TER 1355
Update Unit 2 Fire Protection Safe Shutdown Report to Document
Spurious Signal Analysis for Ventilation System
10 CFR 50.59 Safety Evaluations00-019
Installation of Mechanical Clamp on BVPS-2 Atmospheric Steam Dump
00-081
Revise UFSAR Section 8.4
00-113
Engineering Safety Feature Response Times01-003
Update Unit 2 Fire Protection Safe Shutdown Report to Document Spurious
Signal Analysis for Ventilation System
01-2854
Install Automatic Recirculation Control Valves (ARV) at Discharge of
HHSI/Charging Pump 2CHS*P21C
02-2417
Replace Service Water System 6 inch Supply and Return Headers to Control
Room Chillers.
03-0294
Unit 1 Feedwater Isolation Valve Installation
03-0655
Turbine Missile Analysis
10 CFR 50.59 Screening Evaluations
02-2590
Replacement of Service Water System 6 inch Supply and Return Headers to
Control Room Chillers
02-3127
Inverter No. 4 Replacement
02-3318
Replace Voltage Regulator
02-3521
Connection of Newly Installed Service Water Lines from the Control Room
02-3679
Install 3/4 inch Branch Line on 2-SWS-006-164-3 for ECP 02-0253
02-3946
Install 3/4 inch Branch Line on 2-SWS-006-163-3 for ECP 02-0253
03-1327
Transformer Tap Changes
03-1335
Vital Bus Inverter Voltmeter
03-1427
Battery Equalizing Charge
03-1436
EDG Monthly Test
03-1581
Main Generator Loss of Field Relay Setting Change
03-1605
Possible Circuit Anomoly EDG 1-2 During Sequence Test
03-1793
Return to Service 4KV Emergency Bus 1DF
03-1870
7300 Power Supply Change
6
03-2145
Safeguards Train A Miscelenaeous
03-2145
Oil Filter Pressure Switch GO Test
03-0294
Unit 1 Feedwater Isolation Valve Installation
Self-Assessments
Nuclear Quality Assessment: 10 CFR 50.59 Evaluations, dated February 28,2003
Engineering Assessment Board, Product No. ECP 02-0214
Corrective Action Reports
01-3399, 01-4509, 01-0758, 02-7268, 02-09517, 02-2996, 02-7927, 02-7928, 02-6733, 03-5404
Procedures
DE-DG-005, Engineering Assessment Board, Revision 0
1/2-ADM-1902, Fire Brigade, Revision 0
1/2-ADM-2007, Operational Acceptance of Engineering Change Packages, Revision 4
2OM-56B.3.B.3, Fire Prevention and Control, Pre-Fire Strategies, Revision 14
NOP-CC-2001, Design Verification, Revision 1
NOP-CC-2002, Design Input, Revision 1
NOP-LP-4003, Evaluation of Changes, Tests and Experiments, Revision 0
Miscellaneous
BVPS-2 Fire Safe Shutdown Report
Unit 2 Drill Report 2OM-56C, Post-Fire Alternate Shutdown from Outside of the Control Room
NUREG-1057, Supplement No. 5, Safety Evaluation Report Related to the Operation of Beaver
Valley Power Station Unit 2