ML17055D801
| ML17055D801 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/21/1988 |
| From: | Florek D, Lange D, Lumb T, Sisco C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055D800 | List: |
| References | |
| 50-410-88-04, 50-410-88-4, IEIN-86-110, NUDOCS 8805030103 | |
| Download: ML17055D801 (12) | |
See also: IR 05000410/1988004
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report
No.
50-410/88-04
Docket No.
50-410
License
No.
Licensee:
Nia ara
Mohawk Power Cor oration
301 Plainfield Road
S racuse
13212
Facility Name:
Nine Mile Point Nuclear Station
Unit 2
Inspection At:
Scriba
Inspectors
Inspection
Conducted:
Februar
2 -26, 1988
F
ek, Senior Operations
Engineer,
ate
T.
umb,
Seni r Operations
Engineer,
C. Sisco,
Operation
Engineer,
9 /z.~lrs
date
0 (kg
date
Approved by:
D.
Lange,
Ch f,
ection
Operations
Branch,.
date
Ins ection
Summar
Ins ection
on Februar
24-28
1988
Re ort No.
~/
Areas
Ins ected:
Routine,
unannounced
inspection
by region-based
inspectors
of the overall
power ascension
test
program including test procedure
review and test results evaluation of Test Condition
3 and
5 tests,
neutron
flux oscillation observations
and
QA interfaces.
Results:
No violations were identified.
The licensee
satisfied the startup
test program requirement'for testing in Test Condition
3 and 5.
Note: for acronyms
not defined, refer to NUREG-0544,
"Handbook of Acronyms and
Initialisms."
3305030203
330420
PDr.'DOCK 0S0004~0
DETAILS
1.0
Persons
Contacted
Nia ara
Mohawk Power
Cor oration
~R. Abbott, Station Superintendent
"G. Carlisle,
STOMA Engineer
C.
Beckham,
Manager
gA Operations
- J. Conway,
Power Ascension
Manager
- P. MacEwan, Site Representative,
NYSEG
R. Pasternak,
Manager Nuclear Consulting Services
- T. Perkins,
Generla
Superintendent
- A. Pinter,
Licensing Engineer
R. Seifried, Assista'nt Superintendent
Training
D. Straka,
Supervisor
Ops Training Unit
1
L. Mott, Site Licensing Engineer
K. Zollitsh, Training Superintendent
New York State
P.
Eddy, Site Representative
NRC Personnel
W. Cook, Senior Resident
Inspector
"Denotes
those
present at the exit meeting
on November 6,
1987.
The inspector also contacted
other
members of the licensee's
Operations,
Technical,
Test
and
gA staffs.
2.0
Power Ascension
Test
Pro
ram
PATP
2. 1
References
Revision 2, August 1978, "Initial Test
Program for Water cooled Nuclear
Power Plant."
"Administrative Controls
and guality Assurance
for Operations
Phase
of Nuclear Power Plants."
Nine Mile Point Unit 2 (NMP-2) Technical Specifications,
July 2,
1987.
Nine Mile Point Unit 2 Final Safety Analysis Report
(FSAR)
Chapter
14, "Initial Test Program."
Nine Mile Point Unit 2 Safety Evaluation Report.
Nine Mile Point
2 AP-1.4, Startup Test
Phase,
Revision 5.
f
A,
2.2
Overal
1
Power Ascension
Test
Pr o ram
The inspector held discussions
with the power ascension
manager
design
and analysis '(STD&A) engineer
and other
members of the
PATP staff to assess
the status
of testing,
the test results evaluation
process
and the preparation
and approval
of test procedures.
In addition,
the inspector
attended
two daily
power ascension
management
meetings.
2.3
Power Ascension
Test Procedure
Review
~Sco
e
Procedure
N2-SUT-27-6 "Generator
Load Reject" Final Draft dated
February
1988 was reviewed for the attributes identified in
Inspection
Report
No. 50-410/86-38,
Section 4.3.
Discussion
The procedure
reviewed
was technically acceptable.
Final facility
approval of the procedure
is required.
~Findin
s
No unacceptable
conditions were identified.
2.4
Power Ascension
Test Results
Evaluation
~Sco
e
The power ascension
results listed in Attachment
A were evaluated
'for the attributes identified in Inspection
Report
No. 50-,410/86-64,
Section
2. 1.
Findin
s and Conclusion
All test results
evaluated
were determined to satisfy the test
criteria or where deficiencies
existed the licensee
processed
test
exceptions.
The licensee's
resolution of test exceptions
was
determined
to be acceptable.
The licensee
is following the
established
administrative
requirements
for the startup test program.
No violations were identified.
3.0
A Interface with the
PATP
The inspector
reviewed
QA Surveillance
Reports
88-10044
and 88-10047.
The inspector verified that the survei llances
were performed in
accordance
with applicable
QA procedures
and the commitments
made in the
surveillance
plan for the power ascension
test program.
\\r.
The inspector also observed
an on-shift gA engineer
preparing to perform
a surveillance of TC-6 steady
state testing activites.
A check list was
being utilized by the
gA engineer
to perform his surveillance
activities.
In addition, during the evaluation of power ascension
test
results,
the inspector verified that the results
had
been
reviewed
by gA.
No violations were identified.
4.0
Neutron Flux Noise Observations
During prior testing the licensee
had observed that when operating at
100%
core flow and
50% power, osci llations in APRM power and total core flow
exist.
These oscillations
are also quite evident
when operating
near
100% power
100% core flow.
The oscillations
were observed
by the
inspector to be nominally
10% on reactor flux with some higher peaks
and nominally
3% on total core flow with the plant operating at
100%
power.
The inspector inquired of the licensee activities to understand
the
reason for the osci llations and the analysis
to indicate that the facility
can operate with this condition.
The
NRC had issued
IE Information Notice
86-110
"Anomalous Behavior of Recirculation
Loop Flow in Jet
Pump
Plants"
on December
31,
1986.
The facility has
been obtaining data to try
to better understand
what is occurring.
Individual loop flows are
oscillating, with no change
in flow control valve position.
Current
reasons
theorize bi-stable flow regimes in the jet pump riser piping
relocating riser flows and thus changing overall
system resistance.
Each
individual loop has its own characteristics
response
with the flow regimes
sometimes
in phase.
and
sometimes
out of phase.
A loop may be in one
regime for periods
up to
a minute or as little as
a few seconds.
This
change
in total core flow is causing
a change
in neutron flux as
seen
by
the traces
in all the
APRNs (A-F) showing the
same flux shape
response.
The facility has utilized GE to analyze
and observe
plant response.
BWR-5 product lines generally experience oscillation in neutron flux but
the response
at
NMP-2 is amplified by the recirculation
system
response.
GE has
responded
that the current plant oscillations did not result in
a
safety concern
and the plant can operate
as long as
NRC licensed
thermal
power limitations are not exceeded.
Fuel design considers
30% peak to
peak osci llations.
(Draft copy of GE response
was reviewed
by inspector).
The facility long term solution is to obtain
more data
and determine
a
course of action.
The facility is in contact
and
has results of an
overseas
plant that experienced
similar oscillations
and is aware of the
actions taken to mitigate the observed actions.
The licensee
has not yet
finalized their long range
plans in this regard.
5.
Exit Interview
At the conclusion of the inspection
on February
26,
1988
an exit meeting
was held with licensee
personnel
(identified in Section
1.0) to discuss
the inspection
scope,
findings and observations
as detailed in this
report.
At no time during the inspection
was written inspection findings
provided to the licensee
by the inspector.
Based
on the
NRC Region I
review of this report and discussions
held with licensee
representatives
during the inspection, it was determined that this report does
not
contain information subject to
10 CFR 2.790 restrictions.
ATTACHMENT A
TEST CONDITION 3 TESTING
Tests
Results
Reviewed
N2-SOT-1-3 Chemical
and 'Radiochemical
N2-SUT-02-3 Radiation
Measurements
N2-SUT-16-3 Selected
Process
Temperatures
and Water Level Measurement
N2-SUT-22-3 Pressure
Regulator Test
N2-SUT-23-3 Feedwater
System
N2-SUT-30-3 Reactor
Recirc System
N2-SUT-33-3 Drywell Piping Vibration
N2-SOT-35-3 Recirculation
Flow Calibration
N2-SUT-74-3 Off Gas
System
N2-SUT-79-3 Reactor Internal Vibration Measurement
N2-PP-3 Test Plateau
3 Procedure
TEST CONDITION 5 TESTING
N2-SUT-1-5 Chemi ca 1
and
Radi ochemi ca 1
N2-SUT-12-5
APRM Cal ibration
N2-SUT-16-5 Selected
Process
Temperatures
and Water Level Measurements
N2-SOT-19-5 Core Performance
N2-SUT-22-5 Pressure
Regulator
N2-SUT-23-5 Feedwater
System
N2-SUT-24-5 Turbine Valve Surveillance
N2-SUT-30-5 Reactor Recirculation
System
N2-SUT-.33-5 Drywell Piping Vibration
N2-SUT-77-5
BOP Piping Vibration
h