IR 05000261/1986008
| ML14175B372 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/18/1986 |
| From: | Jape F, Long A, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B371 | List: |
| References | |
| 50-261-86-08, 50-261-86-8, NUDOCS 8605070057 | |
| Download: ML14175B372 (5) | |
Text
G-,tREGU 1 UNITED STATES
-
nw0 NUCLEAR REGULATORY COMMISSION
REGION II
o 101 MARIETTA STREET, SATLANTA, GEORGIA 30323 Report No.: 50-261/86-08 Licensee:
Carolina Power and Light Company P. 0. Box 1551 Raleigh, NC 27602 Docket No.:
50-261 License No.:
DPR-23 Facility Name: H. B. Robinson Inspection nducted: March 16-21, 1986 Inspector:. \\, _/ Mathis Date Signed Rong Date Signed Accompanying Personnel: F. Jape, Section Chief, TPS Approved by:
(2-sC -/
______
F. Jape, Section h ief, TPS Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection involved 98 inspector-hours on site in the areas of start-up after refueling, low power physics testing and follow-up to inspector identified item Results:
No violations or deviations were identifie PDR ADOCK 05000261 PDR
REPORT DETAILS 1. Persons Contacted Licensee Employees
- R. E. Morgan, General Manager
- A. R. Wallace, Manager - Technical Support
- J. M. Curley, Director - Regulatory Compliance
- F. L. Lowery, Manager -
Operating
- H. J. Young, Director, QA/QC
- A. M. McCauley, Principal Engineer
- J. C. Sturdavant, Technical Regulatory Compliance
- G. Nonma, Sr. Specialist - Regulatory Compliance T. Cleary, Reactor Engineer R. Chambers, Reactor Engineer Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security office members, and office personne Other Organization I. Z. Stone, Exxon Nuclear Fuels NRC Resident Inspectors
- H. E. P. Krug, SRI
- R. M. Latta, RI
- Attended exit interview 2. Exit Interview The inspection scope and findings were summarized on March 21, 1986, with those persons indicated in paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio. Unresolved Items Unresolved items were not identified during the inspectio. Precritical Test (72700)
The inspectors witnessed precritical test EST-048 (Revision 3), Control Rod Drop Tes All 45 control rods were drop-time tested at an average reactor coolant system temperature between 540 and 545 degrees F. System pressure was maintained between 2235 to 2245 psig, with all reactor coolant pumps runnin The recorded drop times to dashpot entry ranged from 1.25 to 1.46 seconds. The requirements of Technical Specifications 3.10.4 and 4.1 (table 4.1-3, item 1) were satisfie. Initial Criticality and Zero Power Physics Testing (72700)
The post-refueling initial criticality and Zero Power Physics Testing (ZPPP)
were conducted in accordance with EST-050 (Revision 3),
Refueling Startup Procedure a. Initial Criticality Initial criticality for cycle 11 was achieved in a well-controlled fashion. The all-rods-out (ARO) critical boron concentration was 1249 ppmB, which was in acceptable agreement with the predicted ARO concentration of 1269 ppmB. Adequate overlap between source-range and intermediate-range nuclear instruments was demonstrated, followed by a determination of sensible heat to set the upper power limit for zero power physics testin b. Reactimeter The reactimeter is a special-purpose digital computer for making real-time measurements of core reactivity by analysis of temporal variations in flux leve In addition to an analog flux signal from one of the power-range nuclear instruments, digital input of delayed neutron group constants appropriate to the control rod configuration in use is also require Proper calibration of the reactimeter was demonstrated by comparing the reactimeter solutions with reactivity values obtained by measuring the reactor period with a stop watch and finding the corresponding reactivity from a curve of the independently calculated reactivity-period (in-hour) relationshi In the demonstration, a series of two increasingly positive transients were followed by a series of three increasingly negative transient The accepted measurements did agree with the reactimeter indications plus or minus 10 percent of the measurement as required by procedur In most cases the measurements were within plus or minus 5 percen c. Isothermal Temperature Coefficient (61708)
The isothermal temperature coefficient was performed in accordance with Appendix C to EST-050. The inspectors reviewed the measurement of the Isothermal Temperature Coefficient (ITC) in the ARO configuration. The test method was to have a temperature signal drive one axis of an X-Y recorder and a reactivity signal drive the other axi The slope of
the trace obtained by increasing or decreasing temperature is the IT The Moderator Temperature Coefficient (MTC)
in the ARO position was negative. The requirements of TSs were satisfie Control Rod Worth Measurement (61710)
Starting from the ARO configuration the reactivity worths of control banks D and C were measured in sequence. D bank had a measured worth of 645 pcm and for C bank the measured worth was 1801 pc The predicted worth were 665 and 1702 pcm, respectivel Since the measured values were within 10 percent of prediction, the results were acceptabl Primary System Leakage (61727)
The inspectors reviewed procedure OST-051, Reactor Coolant System Leakage Evaluation, Revision 6. This procedure was used to evaluate RCS leakage and to satisfy TS 4.1.1, Table 4.1-3, item 9. TSs required that the total unidentified primary system leakage rate does not exceed one gpm. The procedure recommends, but does not require, that data for OST-051 be obtained over a period of at least an hour. The procedure reviewed by the inspectors had been performed in 30 minute The apparent cause for the shortened test was changing plant condition The total unidentified RCS leakage rate over the period was.7927 gp In the areas inspected, no violations or deviations were identifie.
Followup of Inspector Identified Item (92701)
(Closed) 261/83-37-01, Establish the basis for the PRT Level Correction Term in OST-051. A measured curve of PRT Level vs. gallons was developed which agreed well with the constant ter To provide additional accuracy in leakage calculations, the curve of PRT level vs. gallons was incorporated into the plant curve book as curve 8.23 OST-51 was then revised to use the actual tank curves instead of an average value to calculated volume changes in the PR (Closed)
261/85-02-01, The licensee was to make inverse multiplication measurements during approach to criticality using integral counts obtained by using a scaler-timer with each source range channe Appendix A of procedure EST-050 was revised to use scaler-timer data with a minimum counting time selected to assure about 1000 counts per observatio The inspectors verified that this was implemented during the approach to criticalit The inspectors verified that EST-050 was performed prior to refuelin.(Closed)
261/85-02-02, The licensee had agreed to implement a chi-square detector reliability test prior to the 1986 refuelin EST-001 was developed and approved by the licensee to perform the chi-square test prior
to fuel handling, new core initial criticality, and lowering the vessel water leve The inspectors verified that EST-001 was implemented prior to the 1986 refueling outag (Closed)
261/85-02-03, The licensee revised EST-050 to incorporate a 10 percent acceptance criteria for agreement between observed doubling time and reactimete (Closed)
261/85-02-04, The licensee revised EST-050 to give the test engineer flexibility to change the recorder scaling and to assure that good resolution of MTC data will be obtained by maximizing span on the X-Y recorde (Closed) 261/85-02-05, The licensee revised the procedure EST-050 to include all the pertinent information as required to close this item out.