ML20210Q991
| ML20210Q991 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/27/1997 |
| From: | Richards S NRC (Affiliation Not Assigned) |
| To: | Reid D VERMONT YANKEE NUCLEAR POWER CORP. |
| Shared Package | |
| ML20210Q998 | List: |
| References | |
| 50-271-97-201, NUDOCS 9709020242 | |
| Download: ML20210Q991 (8) | |
See also: IR 05000271/1997201
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UNITED STATES
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NUCLEAR REEULATCRY COMMISSION
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WASHINGTON, D.C. 30e66 0001
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August 27, 1997
Mr. Donald A. Reid
Vice President, Operations
Vermont Yankee Nuclear Power Corporation
Ferry Road
Brattleboro, VT 05301
SUBJECT:
VERMONT YANKEE DESIGN INSPECTION (NRC INSPECTION REPORT
NO. 50-271/97 20l)
Dear Mr. Reid:
From May 5 through Jt.nc 13,1997, the staff of the U.S. Nuclear Regulatory Commission (NRC),
Office of Nuclear Reactor Regulation (NRR), Special Inspection Branch, performed a design
inspection of the low pressure coolant injection (LPCI) and residual heat removal service water
,
(RHRSW) systems at the Vermont Yankee Nuclear Power Station (VY). The purpose of the
inspection was to evaluate the capability of the selected systems to perform the safety functions
required by their design bases, as well as the adherence of the systems to their respective design
and licensing bases, and the consistency of the as built configuration and system operations with
the final safety analysis report (FSAR). The team discussed significant findings of the inspection
,
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with your staff during the team exit meeting on June 13,1997, and during the public exit meeting
on July 1,1997.-
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As discussed in the enclosed report, the team concluded that the LPCI and RHRSW systems were
capable of performing their intended safety functions. Overall, the design engineers of the Yankee
Atomic Electric Company, who provided engineering services to VY, had excellent knowledge
'
and capabilities. Nonetheless, the team identified concerns in the following areas.
First, the team identified several operability issues which required prompt corra.ctive actions by
your staff. For example, the team found that the non safety-related pressure regulator could result
in loss of service water to the diesel generators. Also, the team questioned the operability of your
RHR pumps with minimum pump flow considerably less than what the pump vendor
recommended for continued operation. Additionally, the team raised concuns regarding the
operability of the RHR pumps while in the torus cooling mode and the operability of the RHR
heat exchangers on the basis ofimproperly performed tests. Your initial corrective actions to
address these issues were acceptable.
Secondly, the team had concerns with your past resolution to several engineering issues such as
operation of the unit with the torus temperature above the analyzed region and various
discrepsncies in the plant's Technical Specifications. In particular, we were concerned with your
long term resolution to operation ofyour RHR pump with less than recommended minimum
pump flow during a design basis event.
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Donald A. Reid
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Based on the understanding of your current design bases efforts, the team concluded that it was
unlikely that you would have uncovered some of the issues identified in this report. Based on the
conversation at the exit meeting, we understand that your staff will be re-examining your design
bases program. Region I intends to review this issue when they inspect the findings in this report.
Please provide a schedule, within 60 days, detailing your plans to complete the corrective actions
required to resolve the open items listed in Appendix A to the enclosed report. This schedule will
,
enable the NRC staff to plan for the reinspection and closcout of these items.
In addition, as with ali NRC inspections, we expect that your staff will evaluate the applicability of
the results and specific findings of this inspection to other systems and components throu~ghout
the plant.
In accordance with Title 10, Section 2.790(a) of the Code ofFedera/ Regulations, a copy of this
letter and the enclosure will be placed in the NRC's Public Document Room. Any enforcement
action resulting from this inspection will be handled by NRC Region I sia separate
correspondence.
Should you have any questions concerning the enclosed inspection report, p. case contact the
project manager, Mr. Kahtan Jabbour at (301) 415-1496, or the inspection team leader, Mr.
James A. Isom, at (301) 415-1109.
Sincerely,
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- SpecialInspection Branch
Division ofInspection and Support Programs
Office ofNuclear Reactor Regulation
Docket No.: 50-271
Enclosure: Inspection Report 50-271/97-201
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lMr. Donald A, Reid
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Based on the understanding of your current design bases efforts, the team concluded that it was
. unlikely that you would have uncovered some of the issues identified in this report. Based on the -
. conversation at the exit meeting, we understand that your staff will be re-examining your design
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. bases program; Region I intends to review this issue when they inspect the findings in this repon,
I
Please provide a schedule, within 60 days, detailing your plans to complete the corrective actions
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required to resolve the open items listed in Appendix A to the enclosed report. This schedule will
'
enable the NRC staff to plan for the reinspection and closcout of these items.
l
In addition, as with all NRC inspections, we expect that your staff will evaluate the applicability of
the results and specific findings of this inspection to other systems and components throughout
,
the plant,
.
In accordance with Title 10, Section 2,790(a) of the Code offedera/ Regulations, a copy of this
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letter and the enclosure will be placed in the NRC's Public Documer* Room. Any enforcement
action resulting from this inspection will be handled by NRC Region i via separate
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correspondence,
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Should you have any questions concerning the enclosed inspection report, please contact the
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project manager, Mr. Kahtan Jabbour at (301) 415-14%, or the inspection team leader, Mr.
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James A. Isom, at (301) 415-1109,
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Sincerely,
1
ORIGINAL SIGNED BY Donald P. Norkin
Stuart A. Richards, Chief
Special Inspection Branch
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Division ofInspection and Support Programs
Office of Nuclear Reactor Regulation
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_ Docket No.: 50-271
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Enclosure: Inspection Report 50-271/97-201
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required to resolve the open items listed in Appendix A to the enclosed report. This schedule will
enable the NRC staff to plan for the reinspection and closcout of these items.
In addition, as with all NRC inspections, we expect that your staff will evaluate the applicability of
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the results and specific findings of this inspection to other systems and cornponents throughout
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the plant.
In accordance with Title 10, Section 2.790(a) of the Code offedera? Regulations, a copy of this
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letter and the enclosure will be placed in the NRC's Public Documfnt Room. Any enforcement
action resulting from this inspection will be handled by NRC Re on I via separate
correspondence.
Should you have any questions concerning the enclosed inspection repon, please contact the
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project manager, Mr. Kahtan Jabbour at (301) 415 1496, or the inspection team leader, Mr.
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Stuart A. Richards, Chief
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Please provide a schedule, within 60 days, detailing your plans to complete the corrective actions
required to resolve the open items listed in Appendix A to the enclosed report. This schedule will
enable the NRC staff to plan for the reinspection and closcout of these items.
In addition, as with all NRC inspections, we expect that your staff will evaluate the applicability of
the results and specific findings of this inspection to other systems and components throughout
the plant.
'
In accordance with Title 10, Section 2.790(a) of the Code ofFcdcralRsgulations, a copy of this
letter and the enclosure will be placed in the NRC's Public Document Room. Any enforcement
action n esulting from this inspection will be handled by NRC Region I via separate
correspondence.
'
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Should you have any questions concerning the enclosed inspection report, please contact the
project manager, Mr. Kahtan Jabbour at (301) 415-1496, or th'e inspection team ler. der, Mr.
James A. Isom, at (301) 415-1109.
/
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Sincerely,
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,Stuart A. Richards, Chief
/ SpecialInspection Branch
/
Division ofInspection and Support Programs
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Office of Nuclear Reactor Regulation
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Docket No.: 50-271
Enclosure: Inspection Report 5 271/97-201
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DOCUMENT NAME: G:\\VY97201. FIN
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Vermont Yankee Nuclear Power
Vermont Yankee Nuclear Power Station
Corporation
.cc:
Resident Inspector'
Regional Administrator, Region'I -
Vermont Yankee Nuclear Power Station
U. S. Nuclear Regulatory Commission
U.S. Nuclear Rcgulatory Conunission
475 AllendaleRoad
P.O. Box 176
King of Prussia, PA 19406
Vernon, VT 05354
Mr. David R. Lewis
Chief, Safety Unit
Shaw Pittman, Potts & Trowbridge
Office of the Attorney General
2300 N Street, N.W.
One Ashburton Place,19th Floor
Washington, DC 20037-1128
Boston,MA 02108
Mr. Richard P. Sedano, Commissioner
Vermont Department of Public Service
Mr. Peter LaPorte, Director
120 State Street,3rd Floor
ATTN: James Muckerheide
Montpelier, VT 05602
Massachusetts Emergency Management
Agency
Public Service Board
400 Worcester Rd.
State of Vermont
P.O. Box 1496
120 State Street
Framingham, MA 01701-0317
Montpelier, VT 05602
Mr. Raymond N. McCandless
Chairman, Board of Selectmen
Vermont Division of Occupational
Town of Vernon
and Radiological Health
P.O. Box i16
Administration Building
Vernon, VT 05354-0116
Montpelier, VT 05602
Mr. Richard E. McCullough
Mr. J. J. Duffy
Operating Experience Coordinator
Licensing Engineer
Vermont Yankee Nuclear Power Station
Vermont Yankee Nuclear Power
P.O. Box 157
Corporation
Governor Hunt Road
580 Main Street
Vernon,VT 05354
Bolton, MA 01740-1398
G. Dana Bisbee, Esq.
Mr. Robert J. Wanczyk
Deputy Attorney General
Director of Safety and Regulatory
33 Capitol Street
Affairs
Concord, NH 03301-6937
Vermont Yankee Nuclear Power Corp.
Ferry Road
Brattleboro, VT 05301.
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Mr. Ross B. Barkhurst, President
Ms. Deborah B. Katz
- Vermont Yankee N; clear Power Corporation
Box 83
Ferry Road
Shellburne Falls, MA 01370
~
Brattleboro, VT 05301
Mr Jonathan M. Block, Esq.
Mr. Gregory A. Maret, Plant Manager
Main Street
Vermont Yankee Nuclear Power Station
P.O. Box 566
P.O. Box 157
Putney, VT 05346-056f,
Governor Hunt Road
Vernon,' VT. 05354
Mr. Donald A. Reid
Senior Vice President, Operations
Vermont Yankee Nuclear Power Corporation
Ferry Road
Brattleboro, VT 05301
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Distribution:
- Docket Files 50-271/97-201--
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PSIB R/F
BWSheron, NRR
FPGillespie, NRR
SARichards, NRR
DPNorkin, NRR
= TOMartin, OEDO
CERossi, AEOD
JWRoe, NRR
REaton, NRR
KJabbour, NRR
CBoyle, NRR
WCook, SRI
.
Regional Administrators
Regional Division Directors
Inspection Team
PUBLIC
ACRS (3)
OGC (3).
IS Distribution
SPSB,NRR
PRAB,RES
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