ML20245J558
| ML20245J558 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/26/1989 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20245J560 | List: |
| References | |
| NUDOCS 8907030092 | |
| Download: ML20245J558 (8) | |
See also: IR 05000339/1989200
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. NUCLEAR REGULATORY COMMISSION
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. WASH WGTON, D. C. 20555
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' June 26, 1989
Docket Hos. 50-338
and 50-339
Mr. W. R. Cartwright'
Vice President-Nuclear
Virginia Electric anc Power Company
5000 Dominion Boulevard
Glen. Allen, Virginia .23060
Dear Mr. Cartwright:.
SUBJECT:
NORTH ANNA POWER STATION, UNIT 2 - SAFETY SYSTEM OUTAGE
>
' MODIFICATION INSPECTION (DESIGN) - 50-339/89-200
This letter conveys the results and conclusions of the design portion of the
safety system outage modification inspection (SSOM1) of the North Anna Power
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Station Unit 2 conducted by. the NRC's Office of Nuclear Reactor Regulation.
- The . inspection teani consisted of NRC personnel and consultants. The inspection
was conducted primarily at your engineering offices in Richmond, Virginia
during the periods February 13-17 and February 27 - March 3,1989 and was
augmented with a 1-day site visit.
The purpose of the design portion of the 550MI was to examine, on a. sampling
basis, the detailed design and engineering that were required to support
modifications implemented during the outage.
In addition to the design portion
of the SSOMI, %is office has also conducted an inspection of installation and
test activities for Unit I during its outage. A separate report will be
published detailing that phase of the SSOMI.
.The report is organized to present the findings in three formats.
Section 1.3'
provides an overview of the team's activities and summarizes major findings by
discipline. Sections 2 and 3 summarize the effectiveness of your design' effort
in terms of weaknesses and strengths, respectively. The items of concern
identified by the team during the inspection have been classified as finoings
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and are referenced throughout the report ano presented in detail in Appendix C.
Ey separate correspondence' dated March 17, 1989 you were advised of four
11ndings characterized as " safety-significant matters" which needed to be
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addressed in an expeditious s.anner. Your response of March 31, 1969 resulted
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in a Region 11 confirmatory inspection during the week of April 3,1989.
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Also your letters of April 13, 1989 and April 28, 1989 provided supplemental
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information with regard to your actions and comitments for these four
findings. A current status of these four " safety-significant matters" is
provided in the enclosed Executive Summary.
Of particular concern to the team were findings related to improperly si:ed
motor operated valve actuators and improper isolation between a nontlass IE
instrument that was powered from a Class IE bus. The motor-operated valve
PFbt
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Mr. W. R. Cartwright
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June 26, 1989
actuator issue has resulted.in the resetting of torque switches as well as the
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need for new torque switch spring packs for certain valves in the service water
system. The improper isolation has resulted in the replacement of the associated
fuses with' ones qualified as Class IE.
Additionally, VEPC0 needs to assess the
-pervasiveness of improper isolation of nonClass' 1E components powered from
. Class 1E buses at the North Anna facility.
NRR is planning to reinspect the findings addressed herein. Once your response
to this inspection report is received a schedule will be established.
Some of
the identified items may be potential enforcement findings. Any enforcement
actions will be identified by Region II in separate correspondence.
A safeguards finding is being transmitted to you under separate cover.
~
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will
be placed in the NRC' Public Document Room.
- You are requested to respond to this office within 60 days regarding the
,
unresolved items in Appendix C and weaknesses in Section 2 identified in the .
2
'
enclosed inspection report. Should you have any questions concerning this
inspection, please contact the NRR Project Manager, Leon Engle or Ron Parkhill of
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the NRC staff. Messrs. Engle and Parkhill can be reached at (301) 492-1484 and
(301)492-0963, respectively.
Sincerely ,
Steven A. Varga, Director
Division of Reactor Projects - 1/II
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Office of Nuclear Reactor Regulation
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Enclosures:
'1.
Executiye Summary
2.
Inspection Report
50-339/89-E00
cc w/ enclosures:
See next page
[ COVER LTR NA]
- SEE PREVIOUS CONCURRENCE
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______:. ______________:_____.._______:.____ ..__..__:-_______..... :-______.....__:...______....
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'~DATE -:06/ /89
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Mr. W. R. Cartwright
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actuator issue has resulted in the resetting of torque switches a well as the
need for new torque switch spring packs for certain valves in t e service water
system. The improper isolation has resulted in the replaceme
of the associated
fuses with ones qualified as Class 1E. Additionally, VEPC0 eeds to assess the
pervasiveness of improper isolation of nonClass 1E compon ts powered from
Class 1E buses at the North Anna facility.
NRR is planning to reinspect the findings addressed
rein. Once your response
to this inspection report is received a schedule wi
be established.
Some of
the identified items may be potential enforcement indings. Any enforcement
actions will be identified by Region II in separ te correspondence.
A safeguards finding is being transmitted to ou under separate cover.
In accordance with 10 CFR 2.790(a), a cop of this letter and the enclosure will
be placed in the NRC Public Docurrent Ro i.
You are requested to respond to this office within 60 days regarding the
unresolved items in Appendix C and eaknesses in Section 2 identified in the
enclosed inspection report.
Shou d you have any questions concerning this
inspection, please contact NRR
oject Manager, Leon Engle or Ron Parkhill of
l
the NRC staff. Messrs. Engle nd Parkhill can be reached at (301) 492-1484 and
(301) 492 0963, respectively
Sincerely,
Steven A. Varga, Director
Division of Reactor Projects - I/II
Office of Nuclear Reactor Regulation
,
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Enc'osures:
l
1.
Execut e Summary
2.
Inspe tion Report 50-339/89-200
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cc:
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next page
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SEE PREVIOUS C 4CURRENCE
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- RSIB ARIS:hRR
- RSIB:DRIS:NRR :RSIB:DRIS:NRR :D:DRIS:NRR
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__-_-_:.____.__________:_____.....____:_______.._____:....__________.____________...______.___
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DATE
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- 06/ /89
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Regional Administrators:
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Inspection . Team
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June 26, 1989
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Mr. W. R. Cartwright
Virginia Electric and Power Company
Surry Power Station
cc:
Michael W. Maupin, Esq.
Attorney General
Hunton and Williams
. Supreme Court Building
Post Office Box.1535
101 North 8th Street
~
Richnend, Virginia 23212
Richmond, Virginia 23219
Mr. Michael Kansler, Manager
,.
-Surry Power Station
'
Post Office Box 315
1100 Circle 75 Parkway
'
Surry, Virginia 23883
Atlanta, Georgia 30339
-
Resident inspector
,
Surry Power Station
U.S. Nuclear Regulatory Comission
. Post Of fice Box 166, Route 1
Surry, Virginia _23883
Mr. Sherlock Holnes, Chairman
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Board of Supervisors of Surry County
Surry County Courthouse
Surry, Virginia 23683
,
Mr. W. T. Lough.
Virginia Corporation Comission
Division of Energy Regulation
Post Office Box 1197
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Richmond, Virginia. 23209
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Regional Administrator,. Region 11
U.S. Nuclear Regulatory Commission
101 Marietta Street N.W., Suite 2900
Atlanta, Georgia 30323
C. N. G. Buttery, M.D., M.P.H.
Department of Health
109 Governor Street
4
Richmond, Virginia 23219
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EXECUTIVE SUMARY
INSPECTION REPORT 50-339/89-200
NORTH ANNA POWER STATION - Unit 2
The NRC conducted the-design portion of a safety system outage modification
inspection (SSOMI) for North Anna Unit 2 during the weeks of February 13 and
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February 27, 1989.
The inspection was conducted at the Virginia Electric and
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Power Company (VEPCO) corporate offices in Richmond, Virginia, where the
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associated exit meeting was held on March 3, 1989.
The purpose of this design
SSOMI was to review planned plant changes and ascertain if the as-modified
plant remained in accordance with its licensing basis. The inspection focused
on an in-depth review of sampled modifications for the disciplines of instru-
mentation and controls, mechanical systems, electrical power, mechanical
components and civil / structural. Sungnarized below are the more significant
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findings.
In a letter from Mr. G. C. Lainas to Mr. W. R. Cartwright dated March 17, 1989,
the NRC identified four findings characterized as safety significant and
requested VEPCO to respond within 15 days. VEPC0 responded in a letter dated
March 31, 1989 and Region 11 performed an inspection the week of April 3,1989
to evaluate the response. This inspection will be sumarized in a future
inspection report covering an assessment of the corrective actions to the
findings in this report.
In letters dated April 13, 1989 and April 29, 1989,
VEPCO provided supplemental information for the. safety significant findings. A
brief sumary of these issues is provided below addressing the commitments and
actions required.
(1) VEPCO-designed and procured service water valve operators were identified
to be undersized based on the worst-case differential pressure. VEPC0
reanalyzed the sizing criteria and concluded that two spray array valves
had to have their torque switch settings readjusted and the bypass spray
valves had to have their torque switch spring packs replaced.
Until the
spring packs can be replaced, VEPCO committed to implementing administra-
tive controls when operating in Modes 1 through 4 to ensure proper system
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response under design-basis accidents. Also, VEPCO had been requested
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with the NRR project manager)g on April 7, 1989 and during a discussionto p
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(at the Region 11 exit meetin
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problems were not pervasive at North Anna by reviewing the design basis of
other VEPCO designed and procured safety-related motor-operated valves
(MOVs).
VEPCO's response of April 28, 1989 indicated that their review of
E0Vs replaced or modified confirned that the associated design pressure
and torque requirements were adequate (See Appendix C Fincing IC-1).
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(2) The inspection team identified unjustified assumptions and omissions in
setpoint calculations.
VEPC0 was requested to sample 10 setpoint calcula-
tions to verify that these identified errors had no adverse impcct on the
safety system setting limits and report any reductions in safety margin.
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Additionally, VEPCO was requested to issue guidance for performing setpoint
calculations.
VEPCO's letter dated March 31, 1989 committed to these
aforementioned requests.
In a letter dated April 28, 1989. VEPC0 stated
that the calculational review was complete and where safety limits were
established'the margin of safety was confirmed (See Appendix C Finding IC-2).
(3) The inspection team identified improper isolation between nonclass 1E
pressure transmitters for the service water system and a Class IE vital
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power source.
Consideration of VEPCO's March 31, 1989 response in addi-
tion to discussions within the NRC and review of VEPCO's response dated
April 28, 1989 has resulted in the following comitments and issues (See
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Appendix C Finding IC-3):
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(a) VEPCO comitted to replace the subject isolation devices with Class
IE fuses prior to restart.
(b) .VEPCO comitted to review all modifications installed during this
outage for.similar isolation errors and make the appropriate changes
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prior to restart.
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(c) VEPCO comitted to review all modifications implemented after April
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1987 by Novenber 1,1989 and the NRC understands that any associated
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change would be made prior to the end of the next refueling outage.
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Procedure changes and personnel training would be completed by
September 15, 1989, to preclude future occurrence of similar isolation
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issues.
(d) The NRC staff disagrees with VEPCO's position for modifications
rior to April 1987. The staff position is that all similar
made.p'ations of improper isolation at the North Anna facility need
applit
to be identified 6nd corrected prior to the end of the next refueling
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outage. VEPCO has verbally requested a meeting with the staff to
discuss this ratter.
(4) The inspection team noted that the design change packages did not specify
the testing required to demonstrate functionality of the system and
affected components following the change. Additionally, in regard to the
anticipated transient without scram (ATWS) modification, the team found
that one periodic test procedure (i.e., two tests) was being performed
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before the installation of the modification. As a consequence VEPC0 was
requested to explicitly identify the functional test requirements in the
design change packages and engineering work requests to be installed thi,s
outage, to ensure th6t all necessary testing would be perfonned (See
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Appendix C Finding 10-8).
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The following is a brief sumary of other significant items addressed in the
' enclosed inspection report.
(1) A potentially vital system did r.ot have two protective barriers as required
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by.10 CFR 73.55.
(See finding MS-1 which was tr6nsmitted under separate
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coverletter.)
(2)
A change was made to a pipe support baseplate to enlarge the holes,)
without proper design justification.
(See Appendix C finding MC-1.
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(3) A quality' control inspection report had an inadequate design evaluation
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and inadequate' safety evaluation in that riaither recognized the_inappro-
priateness of losing one battery channel due to interaction with
non-seismic hardware.
(See Appendix C Finding EP-2.)
(4) VEPC0 did not comply with its comitment in regard to a previous violation
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concerning the omission of leakage current effects in instrument loop
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securacy calculations.
(See Appendix C Finding IC-7.)
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