ML19063B488
| ML19063B488 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/04/2019 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Emily Larson Entergy Operations |
| Gaddy V | |
| References | |
| IR 2019002 | |
| Download: ML19063B488 (7) | |
See also: IR 05000416/2019002
Text
March 4, 2019
Mr. Eric Larson, Site Vice President
Entergy Operations, Inc.
Grand Gulf Nuclear Station
P.O. Box 756
Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC TRIENNIAL
HEAT SINK PERFORMANCE INSPECTION (05000416/2019002) AND
REQUEST FOR INFORMATION
Dear Mr. Larson:
On June 17, 2019, the Nuclear Regulatory Commission (NRC) will begin the onsite portion of
the triennial heat sink performance inspection at your Grand Gulf Nuclear Station. This
inspection will be performed in accordance with NRC baseline inspection procedure
(IP) 71111.07 by one inspector from the NRCs Region IV office for one week.
In order to minimize the impact that the inspection has on the site and to ensure a productive
inspection, we have enclosed a request for documents needed for the inspection. The
documents have been divided into three groups.
The first group lists information necessary for our initial inspection scoping activities.
This information should be available to the lead inspector no later than May 6, 2019.
By May 9, 2019, the inspector will communicate the initial selected set of approximately
2-3 risk-significant heat exchangers.
The second group of documents requested includes those items needed to support our
in-office preparation activities. This set of documents, including the calculations
associated with the selected heat exchangers, should be available no later than June 3,
2019. This information should be separated for each selected component, especially if
provided electronically (e.g., folder with component name that includes calculations,
condition reports, maintenance history, etc.). During the in-office preparation activities,
the inspector may identify additional information needed to support the inspection.
The last group includes the additional information above as well as plant specific
reference material. This information should be available onsite to the inspector on
June 17, 2019. It is also requested that corrective action documents and/or questions
developed during the inspection be provided to the inspector as the documents are
generated.
It is important that these documents be as complete as possible, in order to minimize the
number of documents requested during the preparation week or during the onsite inspection.
E. Larson
2
All requested documents are to be for the time period from the onsite inspection period back to
the last triennial heat sink performance inspection. If nothing addressing a request was done in
that time period, then the request applies to the last applicable document in the previous time
period.
We have discussed the schedule for this inspection activity with your staff and understand that
our regulatory contact for this inspection will be Mr. R. Meister of your licensing organization. If
there are any questions about this inspection or the material requested, please contact the lead
inspector, Wayne Sifre, by telephone at 817-200-1193 or by e-mail at Wayne.Sifre@nrc.gov.
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget, control
number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget control
number.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter
and its enclosure will be available electronically for public inspection in the NRC Public
Document Room or from the Publicly Available Records (PARS) component of NRC's
document system (ADAMS). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-416
License No. NPF-29
Enclosure: Request for Information
Triennial Heat Sink Performance Inspection
cc: w/ encl: Electronic Distribution
Enclosure
Request for Information
Triennial Heat Sink Performance Inspection
Grand Gulf Nuclear Station
Inspection Report: 05000416/2019002
Inspection Dates:
June 17 - 21, 2019
Inspection Procedure:
IP 71111.07, Triennial Heat Sink Performance
Lead Inspector:
Wayne C. Sifre, Senior Reactor Inspector
I.
Information Requested by May 6, 2019:
1. List of the Generic Letter (GL) 89-13, Service Water System Problems Affecting Safety-
Related Equipment, heat exchangers in order of risk significance
2. Copy of heat exchanger performance trending data tracked for each GL 89-13 heat
exchanger
3. List of corrective action program documents (with a short description) associated with
GL 89-13 heat exchangers, heat sinks, silting, corrosion, fouling, or heat exchanger
testing, for the previous 2 years or since the last heat sink performance inspection
4. Copy of any self-assessment done on any of GL 89-13 heat exchangers done since last
heat sink performance inspection
5. System health report(s) and maintenance rule system notebooks for all the GL 89-13
heat exchangers
6. Copy of your responses for GL 89-13
II.
Information Requested by June 3, 2019:
1. For the specific heat exchangers selected:
a. Copies of the two most recent completed tests confirming thermal performance for
those heat exchangers which are performance tested;
b. Copy of system description and design basis document for the heat exchangers (as
applicable);
c. Copy of any operability determinations or other documentation of degradation
associated with the heat exchangers or the systems that support the operation for
the selected heat exchangers;
2
d. Copy of the Updated Final Safety Analysis Report (UFSAR) sections applicable for
each heat exchanger; and
e. Provide a list of calculations with a description which currently apply to each heat
exchanger.
2. A schedule of all inspections, cleanings, maintenance, or testing of any plant heat
exchanger to be done during the onsite portion of the inspection
3. Copies of procedures developed to implement the recommendations of GL 89-13,
(e.g., the GL 89-13 Heat Exchanger Program description)
4. Pages from the UFSAR for the GL 89-13 Heat Exchanger Program
5. Maximum GL 89-13 heat exchanger inlet temperatures that still allow full licensed power
operation of the nuclear reactor. Please provide the documents that state these limits
(e.g., UFSAR or Technical Requirements Manual (TRM)) and the operating procedures
that ensure these limits are not exceeded.
III.
Information Requested by June 17, 2019:
1. For the specific heat exchangers selected:
a. Provide the Design Basis Documents and Updated Final Safety Analysis Report
pages for the selected heat exchangers;
b. Copy of the design specification and heat exchanger data sheets for each heat
exchanger;
c. Copy of the vendor manuals including component drawings for each heat exchanger;
d. Copy of the calculation which establishes the limiting (maximum) design basis heat
load which is required to be removed by each of these heat exchangers;
e. Copy of the calculation which correlates surveillance testing results from these heat
exchangers with design basis heat removal capability (e.g., basis for surveillance test
acceptance criteria);
f.
Copy of the calculations or documents which evaluate the potential for water
hammer or excessive tube vibration in the heat exchanger or associated piping;
g. List of engineering-related Operator Workarounds/Temporary Modifications for these
heat exchangers since the last triennial heat sink performance inspection;
h. Copy of the evaluations of data for the two most recent completed tests confirming
the thermal performance of each heat exchanger;
i.
Documentation and procedures that identify the types, accuracy, and location of any
3
special instrumentation used for the two most recently completed thermal
performance tests for the heat exchangers (e.g., high accuracy ultrasonic flow
instruments or temperature instruments). Include calibration records for the
instruments used during these tests;
j.
Copies of those documents that describe the methods taken to control water
chemistry in the heat exchangers;
k. Copies of the documents that verify the structural integrity of the heat exchanger,
e.g., eddy current summary sheets, ultrasonic testing results, and visual inspection
results;
l.
The cleaning and inspection maintenance schedule for each heat exchanger for the
next 5 years;
m. Copy of the document describing the inspection results for the last two cleaning and
inspection activities completed on each heat exchanger;
n. Copy of the document which identifies the current number of tubes in service for
each heat exchanger and the supporting calculation which establishes the maximum
number of tubes which can be plugged in each heat exchanger;
o. Copy of the document establishing the repair criteria (plugging limit) for degraded
tubes which are identified in each heat exchanger; and
p. Information regarding any alarms which monitor on-line performance.
2. For the ultimate heat sink (UHS):
a. Maintenance or inspection of inaccessible below-water portions of the UHS system
including results of underwater diving inspections and assessments of sediment
intrusion and/or removal of sediment; and
b. Documentation of inspections to verify no structural damage to intake structures that
would indicate loss of structural integrity and/or capacity.
3. For the safety-related residual heat removal (RHR) service water and diesel generator
cooling water systems (DGCWS):
a. Copies of the pipe testing and/or inspection program procedures and the latest
completed surveillances and tests verifying structural integrity of the piping;
b. History during the last 3 years of any through wall pipe leak on the system and the
disposition documentation; and
c. Copies of the procedures to monitor, assess, and disposition active through wall pipe
leaks, including structural evaluations and/or planned corrective actions.
4
If the information requested above will not be available, please contact Wayne Sifre as soon as
possible.
Inspector Contact Information:
Wayne C. Sifre
Senior Reactor Inspector
817-200-1193
Wayne.Sifre@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne C. Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4511
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002
By: WCS Yes No
Publicly Available Sensitive
OFFICE
DRS:SRI/EB1
DRS:C/EB1
NAME
WSifre
VGaddy
SIGNATURE
/RA/
/RA/
DATE
03/04/2019
03/04/2019