IR 05000395/1982028
| ML20051C481 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/14/1982 |
| From: | Burnett P, Jape F, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20051B608 | List: |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 50-395-82-28, GL-81-07, GL-81-7, NUDOCS 8205140539 | |
| Download: ML20051C481 (7) | |
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UNITED STATES 8~
3, NUCLEAR REGULATORY COMMISSION
E REGION ll
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 e
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Report No. 50-395/82-28 Licensee:
South Carolina Electric and Gas Company P. O. Box 764 Columbia, South Carolina 29218 Facility Name:
Summer Docket No. 50-395 License No. CPPR-94 Inspection at Summer site near Jenkinsville, South Carolina Inspectors: _- ;E gg
_4//-72,
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P.
. Burnett Date Signed b
YtstW N-IN-22 t
H. L. Whitener (In office 3/30-3/31)
~ Date Signed
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Approved by:
[44/L Y
Y F. Jipe, Section Chief
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Yate Signed Engineering Inspection Brfrfich [
Division of Engineering and Technical Programs SUMMARY Inspection on March 22-26, 1982 Areas Inspected This routine, announced inspection involved forty inspector-hours onsite. The areas addressed were outstanding items from previous inspections, startup test procedure review, and conformance to NUREG-0612.
Results No violations or deviations were identified.
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8205140539 820419
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PDR ADOCK 05000395
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- 0. S. Bradham, Station Manager
- W. A. Williams, Jr., General Manager, Nuclear Operations
- B. G. Croley, Assistant Manager,-Technical Support S. J. Smith, Assistant Manager, Maintenance
- G. Putt, Supervisor, Mechanical Maintenance S. F. Fipps, Station Reactor Engineer
- S. S. Howze, Licensing Engineer Other Organizations L. A. Wooldridge, Westinghouse NRC Resident Inspector J. L. Skolds, Senior Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 26, 1982, with those persons indicated 'n paragraph I above. The licensee acknowledged that the availability of surveillance test procedures (paragraph 6) might be a constraint on fuel loading.
The inspector followup items, regarding cranet and rigging were discussed. The question of whether painting a weld made it unaccessible was raised and not resolved.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Outstanding Items From Previous Inspections (Closed) Inspector Followup Item (50-395/81-30-01):
Testing program precautions and limitations transmitted to operators.
The inspector reviewed ZPT-0, " Technical Specification Surveillance and Periodic Data Acquisition During Low Power Physics Testing," and found that precautions specific to the low power testing had been included. All licensed personnel will receive training on the zero power and power-operations tests and
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attendent. precautions and limitations as part of the requalification training programs. This training is scheduled to begin on March 29, 1982 and to be completed on May 3,1982.
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(Closed) Open Item (50-395/81-30-03): Comments on draft fuel load procedure CST-3.
The inspector reviewed the approved version of CST-3, which was issued on March 10, 1982.
The final four of the five comments are adequately addressed in the approved procedure. The first comment on the posting requirements of 10 CFR 20 is addressed in administrative procedure AP-711, " Control and Posting of Radiation Control Zones," issued on June 17, 1981.
(Closed) Open Item (50-395/81-30-04):
Chi-square test of nuclear instru-ments.
The inspector reviewed the approved copy of CST-3 and confirmed that the statistical tests are required at appropriate times throughout the procedure and the methodology adequately described in Attachment V to the procedure.
Based upon-discussions with licensee personnel the required number of counts per observation was reduced from 1000 to 200.
A similar change has been formally proposed for ZPT-1 " Initial Criticality" Revision 0, which was issued on September 10, 1981.
(Closed) Open Item (50-395/81-30-06): Determination of differential boron worth. Steps have been added to procedure ZPT-G, issued on March 9,1982 to collate the results of boron end point and con;rol-rod worth measurements from other zero power tests and to obtain the differential boron worth from the shape of the best-fit line of a plot of integral reactivity versus boron concentration.
(Closed)
Open Item (50-395/81-30-08):
Procedure for generating rod-withdrewel limit curves to avoid operating with a positive moderator coefficient.
The licensee has demonstrated by reference to WCAP-9685, section 5.4 and table A.4, and WCAP-9854, Figure 3.1, that a positive moderate coefficient is not predicted for the all-rods-out (most limiting)
configuration.
(Closed) Inspector Followup Item (50-395/81-30-07): Recorder scale factors for temperature and reactivity were not specified in the temperature coefficient test procedures.
The licensee has formally proposed and submitted changes to the af fected procedures, ZPT-3.1, ZPT-3.2, and ZPT-3.3.
These changes provide the recommended scaling factors for the reactivity and temperature recorders to be used.
(Closed) Inspector Followup Item (50-391/81-30-09):
Limit use of the reactivity computer to the dynamically calibrated range. The approved and issued version of ZPT-0, applicable to the entire zero power test program, limits the use of the reactivity computer to the dynamically calibrated rang,.
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(C.losed) Open Item (50-395/82-05-01):
Statistical tests of source range monitors.' A source-range statistical-reliability test has been written for those cold and hot shutdown tests requiring control rod manipulation..This test has been made a part of each of the following procedures: ' CST-6
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(issued 3/10/82),. CST-7 (issued 3/10/12), 'HST-9 (issued 3/8/82), and HST-10 (issued 3/8/82).
In addition,- changes to test procedures issued prior to identification of this issue have been -formally submitted.
These test
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procedures include CST-5, HST-3, HST-8, and HST-11.
6.
Test Procedure Review
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The following power operations tests (POTS) were reviewed:
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POT-5,
" Pseudo Rod Ejection at Power," Revision 0, issued 9/10/81, i
POT-6.1,
" Power Coefficient Determination 30*J Power," Revision 0,
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issued 1/7/82,
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POT-6.2,
" Power Coefficient Determination at 50*4 Power," Revision 0,.
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i ssued 1/7 '*?,
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POT-8,
" Static Rod Drop and Rod Below Bank Position Measurements, Rod D-10, " Revision' 0, issued 10/21/81,.
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POT-9,
" Rod ' Drop Test, Rods D-4 and 0-12," Revision 0, issued 3/3/82,
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POT-12,
"Incore/Excore Detector Calibration, " Revision 0, issued
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10/30/81,and
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POT-17,
"NIS Overlap Verification, Data Acquisition, Power Range l
Calibration and Setpoint Adjustments, " Revision 0,-
issued -
9/10/81.
i Following discussion of the above tests with licensee and Westinghouse i
personnel snly one cancern remained unresolved.
That was related to the l
acceptance criteria for POT-8.
The inspector discussed the issue by l
telephone on April 1,1982 with a member of the core performance branch (NRR) and was assured that the acceptance criteria were adequate.
I The test procadures reviewed during this and previous inspections (82-05 and 81-30) address as prerequisites or use as data gathering procedures a number i
of surveillance test procedures (STPs).
Many of the STPs have not been issued.
The inspector identified fi f ty-seven such procedures that are necessary for mode C and initial fuel loading and are in some stage of preparation, but yet to be issued. At the exit interview the inspector
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voiced the opinion that lack of STPs might delay fuel loading.
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7.
The inspector reviewed the licensee's response to generic letter 81-07 and NUREG-0612 on the control of heavy loads and the following pertinent-licensee procedures.
Operator'and Rigger Training Program Manual,
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MMP-165.007, " Maintenance of Reactor Building Polar Crane and Fuel Handling Building Cranes,"
MMP-165.8, "Use and Control of Rigging Equipment," Revision 1, issued.
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7/17/79,
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MMP-165.006, " Pre-Operational Tests and Inspections of Misce 'aneous -
Hoists / Cranes," Revision 3, issued 12/29/81,
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MMP-500.005,
" Reactor Vessel Head Removal and Installation,"
Revision 0, issued 1/28/82, and
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MMP-500.006,
" Reactor Vessel Internals-Removal / Installation,"
Revision 0, issued 1/29/82.
The training manual included material.taken directly from the following standards, regulations and publications:
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ANSI B30.2-1976, " Overhead and Gantry Cranes,"
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ANSI B30.9-1971, " Slings,"
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ANSI B30.10-1975, " Hooks,"
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ANSI B30.11-1973, " Monorail Systems.and Underhung Cranes,"
ANSI B30.16-1973, " Overhead Hoists,"
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NUREG 0612, " Control of Heavy Loads...," and OSHA Standards 1910.79.
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Taken collectively and presented by an experienced instructor, currently provided by a contractor organization, this material is - adequate for training crane operators, riggers, signalmen and maintenance personnel for work in a nuclear power plant environment. Althouah
.ane and rigging operations are the responsibility of the maintenar v.
department, most operations shift supervisors have also undergone this uuning. This was done so the shift supervisors could better consult with maintenance personnel on lifts that could affect plant safet.
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For the most part procedures and practices affecting - crane training, operation, and maintenance reflect a strong commitment to and 'implementatio'n of - the requirements of NUREG-0612.
The requirements are not fully implemented-in three areas:
(1) Safe load paths are indicated in the licensee's response to generic letter'81-07 and are covered in.the training manual. They have yet to be incorporated into the appropriate procedures. -This issue. will be tracked as inspector followup item (50-395/82-28-01): Safe load paths to be added to crane operating procedures.
(2)- The procedures for -lifting the vessel head (MMP-500.005) and internals (MMP-500.006) do not require inspection of the special lifting devices in accordance with ANSI N14.6-1978 as required by NUREG-0612.
Implementation of non-destructive examination (NDE) procedures for special-lifting devices will be tracked as inspector followup item 50-395/82-28-02.
(3)
In procedure MMP-500.005 the load of the head plus lifting rig has not been specified for load monitoring purposes. This will be tracked as inspector followup ~ item 50-395/82-28-03.
It is expected that these procedural corrections and implementations will be accomplished prior to fuel loading.
The inspector also inspected the storage tagging, inspection and control of slings and shackles issued from 'the tool room. An excellent program appeared to be in full effect.
In the exit interview discussion of the NDE requirements' for special lif ting rigs the licensee suggested that painted welds be treated as in accessible. The inspector will seek.further guidance on this issue.
8.
Integrated Leak Rate Test Report The inspector reviewed the licensee's report on containment integrated leak
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rate (ILRT) test results which was submitted to the NRC in March 1981.
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Problems identified in the report are consistent with the conditions j
observed by the inspector while witnessing a portion of the ILRT. An independent calculation of the measured leak rate (LAM) and supplemental i
test composite leak rate (LC) was in reasonable agreement with the reported values of LAM = 0.055 wt. "s per day and LC = 0.168 wt. *; per day. 'These values are well within the allowable leak rate limits specified in the Technical Specification and Appendix J to 10 CFR 50.
During this review, two areas were identified where more information is needed to cnmplete the test evaluations. These are as follows:
a.
Flow meter calibration:
The report is not clear as to any correction factors which may be involved in determining the imposed leak rate.
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Add-on Leakage:
The report is not specific as to what add-on leakage was identified and the upper confidence limit plus add-on leakage value.
The above items will be tracked for followup inspection as (IFI 50-395/82-28-04).