IR 05000316/1981017
| ML17319A985 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/14/1981 |
| From: | Hopkins J, Jackiw I, Swanson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17319A984 | List: |
| References | |
| 50-316-81-17, NUDOCS 8107270115 | |
| Download: ML17319A985 (6) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-316/81-17 Docket No. 50-316 License No. DPR-74 Licensee:
American Electric Power Service Corporation Indiana 8 Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:
D.
C.
Cook Nuclear Plant, Unit, 2 Inspection At:
D.
C.
Cook Site, Bridgman, MI Inspection Conducted:
May 18, 19 and June 23-25, 1981 Inspectors:
une 23-25, 1981)
. R.
son (May 8,
1981)
ra P/
. N. Jackiw (May 18 and 19, 1981)
Approved By:
. N. Jackiw, Acting Chief Test Program Section Ins ection Summar Ins ection on Ma
19 and June 23-25 1981 Re ort No. 50-316 81-17)
Areas Ins ected:
Routine, announced inspection of initial criticality ARO (all rods out)
CB (boron concentration), control rod worths, core power dis-tribution limits, isothermal temperature coefficient, incore/excore cali-bration, core thermal power evaluation, target axial flux difference, control rod scram times, and shutdown margin determination.
The inspection involved 35 inspector-hours onsite by three NRC inspectors including zero inspector-hours onsite during off-shifts.
Results:
No items of noncompliance or deviation were identified.
8107870115 810714 PDR ADOCK 050003i6 i
PDR',
DETAILS 1.
Persons Contacted E. A. Smarrella, Technical Superintendent C. Ross, Nuclear Engineer Supervisor A. Blind, Performance Engineering Supervisor J.
C. Ho, Nuclear Engineer R. Hennen, Nuclear Engineer 2.
Verification of Conduct of Startu Ph sics Testin The inspector reviewed the startup physics testing and verified that the licensee conducted the following:
a ~
b.
c ~
d.
e.f.
g.
h.
Control Rod Scram Timing Core Power Distribution Limits lncore/Excore Calibration Core Thermal Power Evaluation Determination of Shutdown Margin Isothermal Temperature Coefficient Power Coefficient of Reactivity Measurement Control Rod Worth Measurement Target Axi.al Flux Difference Calculation 3.
Observation of Startu Testin The inspector observed the tests listed below and verified that the refueling outage startup testing was conducted in accordance with technically adequate procedures and that the facility was being operated within license limits.
The following tests were observed:
12THP6040 Per
.050
"Isothermal Temperature Coefficient Measurement" 12THP6040 Per
.057
"Initial Criticality, All Rods Out Boron Concen-tration Nuclear Heating Level" 12THP6040 Per
.051
"Differential Boron, Individual Rod Bank Worth and Boron Endpoint Measurement" 12THP6040 Per
.023
",Incore Flux Mapping System Operating Instructions" No items of noncompliance or deviations were identified.
4.
Control Rod Scram Times The inspector reviewed procedure 12 THP 4030 STP.
387, Revision 4,
"Rod Drop Measurements" and noted that all control rod scram times met the Technical Specification requirement,'of less than or equal to 2.2 seconds from the loss of stationary gripper coil voltage to dashpot entry.
No items of noncompliance or deviations were identifie Shutdown Mar in Determination C
The inspector reviewed information relating to Cycle 3 shutdown margin determination as described in Appendix B, "Shutdown Margin Verification", of procedure 12 THP 6040 PER.
059, Revision 5, "Zero Power and Power Ascension Tests."
The inspector noted that the calculated shutdown margin, with the most reactive rod stuck out of the core, met the Technical Specification requirement of at least 1.6$ for 'both the beginning of core life and the end of core life conditions.
No items of noncompliance or deviations were identified.
Initial Criticalit ARO C
The inspector reviewed procedure 12 THP 6040 PER.
057, Revision 5,
"Initial Criticality, All Rods Out Boron Concentration Nuclear Heating Level" for Cycle 3.
The measured initial criticality ARO C
of 1926 ppm met the acceptance criterion of 1916 + 75 ppm.
No items of noncompliance or deviations were identified.
Control Rod Worth Measurements The inspector reviewed information relating to Cycle 3 determi'nation of control rod worths as described
=-in procedures 12 THP 6040 PER.
051, Revision 5, "Differential Boron, Individual Rod Bank Worth and Boron Endpoint Measurements,"
and 12 THP 6040 PER.
060, Revision 3, "Differ-ential Boron, Overlap Rod Bank Worth and Boron Endpoint Measurement."
The rod worth measurements met the acceptance criteria in that the individual control bank rod worths A, B, C, and D,were within 15'/ of design and the summation of control bank rod worths A, B, C, and D
were within 10/ of the design value from WCAP-9828,
"The Nuclear Design and Core Management of the D.
C.
Cook Unit 2 Nuclear Power Plant Cycle 3."
No items of noncompliance or deviations were identified.
Tar et Axial Flux Difference The inspector reviewed the information relating to the Cycle 3 determination of target axial flux difference as described in pro-cedure 12 THP 4030 STP.
372, Revision 4, "Target Flux Difference Update."
The inspector noted that the current target value was supplied to the control room operators and correctly input to the P-250 computer.
The inspector, further noted that. the target flux difference was updated at least once per 31 effective full power days in accordance with Technical Specifi'cation requirements.
No items of n'oncompliance or deviations were identifie ~ ~
~
9.
Core Power Distribution Limits
~
~
The inspector examined select ed computer printouts from May and June 1981 for Cycle 3.
The inspector determined that hot channel factors, quadrant tilts, and axial flux difference measurements satisfied Technical Specification requirements.
No items of noncompliance or deviations were identified.
10.
Isothermal Tem erature Coefficient (ITC)
The inspector reviewed information relating to Cycle 3 determination of isothermal temperature coefficient, as described in procedure
THP 6040 PER.
050, Revision 3, "Isothermal Temperature Coefficient Measurement."
The measured ITC of 1.596 pcm/
F met the acceptance criterion of +0.43 + 3 pcm/o F.
The inspector noted, that as a
precaution to ensure a negative moderator temperature coefficient at 70% power and above, a graph limiting the maximum boron concentration versus reactor power level was issued.
No items of noncompliance or deviation were identified.
ll.
Core Thermal Power Evaluation The inspector reviewed information relating to the 100'/ thermal power measurement of June 2, 1981.
Procedure 12 THP 6040 PER.
020, Revision 2, was used and the inspector determined that the procedure was technically adequate.
No items of noncompliance or deviations were identified.
12.
Incore-Zxcore Detector Calibration
"The inspector reviewed procedure 12 THP 4030 STP.
362, Revision 5,
"Incore-Excore Detector Calibration" for Cycle 3 and verified that control rod insertion did not exceed the insertion limits, the 100'/
excore detector currents were correctly determined, and the axial flux difference was maintained as required by Technical Specifications.
No items of noncompliance or deviations were identified.
13.
Exit Interview The inspector summarized the purpose, scope, and findings of the inspection in a telephone call to Mr. D. Shaller on July 2, 1981.
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