ML20236V672
| ML20236V672 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1987 |
| From: | Richardson S NRC OFFICE OF SPECIAL PROJECTS |
| To: | White S TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8712040466 | |
| Download: ML20236V672 (11) | |
See also: IR 05000327/1987060
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NOV 3 01987
Docket Nos. 50-327, 50-328
Tennessee. Valley Authority
ATTN: Mr. S. A. White.
Manager of Nuclear Power
.SN 38A Lookout Place.
1101 Market Street
Chattanooga, TN 37402-2801
Gentlemen:
SUBJECT:
ENFORCEMENT CONFERENCE SUMMARY
(NRC INSPECTION REPORT NOS. 50-327/87-60AND50-328/87-60)
This letter refers to the Enforcement Conference held at our request on .
October 22, 1987.
This meeting concerned activities authorized for your.
Sequoyah facility. ' The issues discussed at this conference related to TVA's
apparent' failure to meet the requirements of 10 CFR 50.59 such that a required
license amendment was not sought in support of the cavitating venturi instal-
lation associated with all . four motor driven auxiliary feedwater pumps.
A
summary, a list of attendees, and a copy of your handout are enclosed.
It is our opinion that this neeting was beneficial and has provided a better
understanding of the inspection findings, the enforcement issues, and the
status of your' corrective actions.
We are continuing our review of these
issues to determine the appropriate enforcement action.
In accordance with Section 2.790 of' the NRC's " Rules of Practice," Part 2
Title 10 Code of Federal Regulations, a copy of this letter and its enclosures
will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, please contact us.
Sincerely.
!
Original signed by S. Richardson
Steven D. Richardson, Acting Director
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TVA Projects Division
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Office of Special Projects
Enclosures:
1.- Enforcement Conference Summary
2.
List of Attendees
.
1
3.
Handout
cc w/encls:
(See page 2)
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NOV 3 01987
Tennessee Valley Authority
2
cc w/encis:
H. L. Abercrombie, Site Director
Sequoyah Nuclear Plant
J. A. Kirkebo, Director,
Nuclear Engineering
R. L. Gridley, Director
Nuclear Safety and Licensing
M. R. Harding,- Site Licensing
Manager
TVA Representative, Bethesda
Office
bec w/encis:
S. Ebneter, OSP
G. Zech, OSP
B. Liaw, OSP
K. Barr, OSP/TVA
W. Little, OSP/TVA
G. Jenkins, OSP/RII
F. McCoy, OSP/RII
>
R. Carroll, OSP/RII
J. Brady, OSP/RII
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J. Liberman, DOE
J. Rutberg, OGC
NRC Resident Inspector
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Document Control Desk
State of Tennessee
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ENCLOSURE 1
MEETING SUMMARY
On October 22, 1987, an Enforcement Conference was held between representatives
of Tennessee Valley Authority (TVA) and the Office of Special Projects - NRC,
at NRC's request, at the Sequoyah site. The purpose of this conference was to
discuss TVA's apparent failure to meet the requirements of 10 CFR 50.59 such
that a required license amendment was not sought in support of the cavitating
venturi installation associa,ted with all four motor driven auxiliary feedwater
pumps.
I
NRC opened the conference with a brief summary of events since the
Septembei 24, 1987 management meeting which was held between NRC and TVA to
discuss concerns over operability problems related to the Hydrogen Analyzers,
Essential Raw Cooling Water (ERCW) skid valves, ERCW screen wash and strainer
backwash systems, Containment Spray (CS) system, and the motor driven Auxiliary
Feed Water ( AFW) pumps. It was explained that subsequent to the September 24,
,
1987 meeting, NRC review determined that: (1) a TVA plant specific analysis of
'
the inappropriate CS orifice installation was necessary, and (2) the AFW pump
cavitating venturi issue warranted treatment as a potential escalated enforce-
ment issue. Accordingly, it was the later determination which prompted the
need for the Enforcement Conference. The specifics, as addressed below, were
then presented to the licensee:
(1)
In 1984, TVA implemented ECN L 5842 to replace the Unit I and Unit 2
motor driven AFW pumps' pressure control
valves with cavitating
venturis.
Justification for this modification was documented in an
unreviewed safety question determination dated April 25, 1983.
In
accordance with 10 CFR 50.59 this modification was not allowed since it
resulted in increased system flow resistance which required a change to
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the test acceptance value specified in Technical Specification (TS)
'
4.7.1.2.
(2) Related Post Modification Testing indicated that AFW pump 2A-A could not
deliver 440 gpm with the increased system flow resistance. TVA accepted'
this degraded flow condition as documented in an unreviewed safety ques-
tion determination dated November 1,1984.
This reduction in flow con-
stituted a change in the margin of safety as defined in the basis of
TS 4.7.1.2.a.1 and, therefore, constituted an unreviewed safety question
as defined by 10 CFR 50.59.
Following the modifications, both of the units were returned to power operation
(Unit 1 in April 1984 and Unit 2 in December 1984) without ever changing the TS
or receiving prior Commission approval. Additionally, it was expressed to TVA
that had it not been for NRC intervention, it appears that the above problems
would not have been adequately resolved prior to restart.
TVA acknowledged that TS changes should have been made in support of the
modification and subsequent degraded condition of AFW pump 2A-A.
The root
cause was identified as personnel judgement error caused by insufficient
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Enclosure 1
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guidance and compounded by a complex design issue (e.g. , TS minimum pump
recirculation, flow D/P is derived / interpolated, not the actual system limit as
is the case with most TSs). It was further indicated that because the 440 gpm
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flow rate was based.on a Westinghouse generic analysis, TVA felt that their
plant specific analysis supporting 400 gpm met the intent of the TS basis.
!
Presented. corrective actions on this specific problem included: (1) a commit-
ment to revise TSs within 60 days after Mode 3 testing, and (2)- the AFW Pump
2A-A venturi and impeller were replaced during this outage.
TVA then discussed those actions which have been implemented since plant
shutdown in August 1985, to assure similar type problems haven't recurred.
These actions include:
(1)' program enhancements such as TS training for
engineering design personnel and independent reviews of the engineering safety
evaluation by licensing personnel prior to the performance of related work, as
well as a licensing review of the work plan after the work is complete to
assure no changes, test- deficiencies, etc. have occurred; (2) a review of TS
related equipment, associated TS surveillance requirements, and surveillance
instructions during .the TS surveillance instruction review program; and (3) a
review of ' work plans associated with TS amendments since 1985.
This last
review indicated that all but two work plans initially recognized the need for
a TS. change; however, the independent licensing. review did identify such a
need.- The licensee felt this was conclusive proof that the program enhance-
ments have worked, and the problem has been adequately corrected.
NRC asked whether the enhanced process had been audited by TVA and inquired as
to what actions have been or will be taken to assure similar pre-1985 problems
don't exist. In response to the first question, TVA indicated that an audit of
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the process would be conducted by Quality Assurance and Engineering Assurance.
With respect to the existence of similar pre-1985 problems, TVA requested some
time to look into related Nuclear Performance Plan (NPP) reviews and committed
~to provide the NRC with an answer.
1
In regard to NRC's concern that the AFW pump cavitating venturi problems would
not have been resolved prior to restart without NRC intervention, TVA presented
the following: (1) a TS change was submitted in August 1986 to delete the pump
recirculation flow D/P value and reference the associated surveillance instruc-
tion in its place (This change request was rejected by NRC in December 1986.),
and -(2) TVA had always intended to return the AFW pump 2A-A flow rate to
440 gpm.
They had replaced the pumps cavitating venturi, and once they were
aware that NRC had concerns, they replaced the pump's impeller.
The conference was brought to a close with the understanding that NRC would
review the results of the QA and EA audits, and that TVA would respond to NRC
on actions to assure similar pre-1985 problems don't exist. NRC reminded TVA
once again that this problem is under evaluation for potential enforcement
action.
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ENCLOSURE 2'
MEETING ATTENDEES
,
U. S. Nuclear Regulatory Commir,sion
- J. G. Keppler, Director, Office of Special Projects (OSP)
S. D. Ebneter, Director, TVA Projects Division (TDVAPD), OSP
G. G. Zech, Assistant Director for Inspection Programs, TVAPD, OSP
K. P. Barr, Deputy Assistant. Director for Inspection Programs, TVAPD, OSP
W. S. Little,' Technical Assistant, TVAPD, OSP
F. R. McCoy, Section. Chief, Sequoayh
R. E. Carroll, Jr. , Project Engineer, Sequoeyh
K. M. Jenison, Senior Resident Inspector, Sequoyah
.
W. K. Poertner, Resident Inspector, Sequoyah
Tennessee Valley Authority
. S. A. White, Manager ~, Office of Nuclear Power (ONP)
C. H.' Fox, Deputy Manager, ONP
R. L. Gridley, Director, Division of Nuclear Licensing
H. L. Abercrombie, Site Director, Sequoyah Nuclear Plant
J. LaPoint, Assistant Site Director
L. M. Nobles, Plant Manager
P. R. Wallace, Assistant to Site Director
M. R. Harding, Engineer Group Manager
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R. H. Buchholz, Sequoyah Site Representative
L'. E. Martin, Manager, Site Quality
J. Hosmer, Division of Nuclear Engineering
M. Burzynski, Manager, Regulatory Licensing
J. Bynum, Assistant Manager, ONP
R. M. Mooney, Supervisor, Systems Engineering
R. H. Scheide, Licensing Engineer
G. B. Kirk, Manager, Compliance Licensing
H. R. Rogers, Plant Operations Review Staff
M. Cooper, Site Licensing
J. Mcdonald, Manager, Watts Bar Licensing
R. Levi, Office of General Council
M. J. Ray, Deputy Director, Division of Nuclear Licensing
T. E. Bostrom, Manager, Project Engineering
R. Rogers, Project Manager,.Bechtel
B. Charlson, Advisor, ONP
R. A. Loar, Regulatory Licensing
A. M. Qualls, Assistant to Plant Manager
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J. B. Brady, Information Manager
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ENCLOSURE 3
TVA HANDOUT
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