IR 05000219/1987035
| ML20236W196 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/30/1987 |
| From: | Joe Golla, Hunter J, Murphy K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236W180 | List: |
| References | |
| 50-219-87-35, NUDOCS 8712070324 | |
| Download: ML20236W196 (9) | |
Text
_
_ _ _ _ _ _ _ _ _ _
.
.
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-219/87-35 Docket flo. 50-219 License No. DRP-16 Licensee: GPU Nuclear Corporation
'P.O. Box 388 Forked River, NJ 08731 Facility Name: Oyster Creek Nuclear Generating Station Inspection At:
Forked River, NJ Inspection Conducted: October 19-27, 1987 Inspectors:
fedge
//- 5 0 - 8 7 geph M Golla, Reacttir Engineer
'
date
1
//
o John G'AMfiter, Rpict,6r @(gineer
/date
'
Approved by:
-
,
//
K. G. VefiHY,Act f
/dat/e /
ProgramsSection/gChief,SpecialTest
, EB, DRS Inspection Summary:
Routine unannounced inspection of test witnessing and preliminary results evaluation of containment integrated leak rate test (CILRT).
Results: No violations or deviations were identified.
l 8712070324 871201 PDR ADOCK 05000219 G
PDR L--_-__-_-
-
._
s a
_. _ - _.
_
_.
-
-
_ _ _ _
_ _.
_. _
_
__
. _ _ _ _ _ _ _ _ _ - - _.
_ - _ - _ _ _
-
>
!
l DETAILS 1.
Persons Contacted Licensee
- J. Barton, Deputy Director DCNGS
- G. Busch, Licensing Engineer
- J. DeBlasio, Manager Plant Engineering (Mechanical)
- J. Kowalski, OC Licensing Manager P. Manning, QC Supervisor J. Martin, Computer Analyst J Molnar, Plant Engineer D. Notigan, Core Engineer J. Rogers, Licensing Engineer M. Ruth, OPS QA
- E.
Scheyder, MCF j
- J. Sullivan Jr., Plant Operations Director
,
- P. Thompson, QA Auditor i
R. Weltman Plant Materiel i
s USNRC
- W. Bateman. Senior Resident Inspector i
- J. Wechselberger, Resident Inspector
- Eenotes those present at exit meeting held on October 27, 1987.
]
>
2.
Licensee Actions On Previous Inspection Findings
'
(Closed) Unresolved Item (50-219/86-35-011:
Utilization of the Mass Point Method (MPM) of ANSI /ANS-56.8-1981 for
determining containment leak rate from reduced test data. This calcula-j tional method is not sanctioned by 10 CFR 50 Appendix J.
The licensee has utilized this method for the current and previous CILRT.
The inspector informed the licensee at the entrance meeting of the requirement in
!
Appendix J to utilize those methods endorsed by ANSI 45.4-1972, i.e., the
?
total time method or point to point method. The licensee stated that they will submit to NRR an exemption request for the test.
The licensee also stated that since this test is being conducted approximately six months prior to the end of its surveillance interval and that other ut.i: ties have been granted by NRR an exemption which permitted the use of the Mass Point Method, they were justified in proceeding with the current CILRT using the MPM.
If on the other hand the exemption request is not approved
.
..
.
_ _ - _ _
- -_
.
.
by NRR the licensee will (before the end of the CILRT surveillance inter-val) compute the containment leak rate from the October 1987, test data-using the total time method.
Based on the above, this item is adminis-tratively closed.
However, the licensee's actions to request an exception from computing.the leak rate using total time method will be tracked under a new unresolved item No. (50-219/87-35-01).
-
3.
Containment Integrated Leak Rate Testing 3.1' General During the period October 25 through October 27, 1987, a periodic __
_
CILRT was performad at Oyster Creek Nuclear Generating Station, as required by 10 CTR 50, Appendix J.
The test was conducted with the Containment Isolation Valves (CIV's) and Containment Pressure Boundaries (CPB's) in an "As-left" condition.
The test is performed in accordance with station' procedure 666.5.007
" Primary Containment Integrated Leak Rate Test," Revision 10.
The inspector reviewed the test procedure and witnessed preparations and'
various portions of the "As-Left" CILRT.
The purpose of this inspection was to ascertain that the CILRT was conducted in compliance with the requirements and commitments
. referenced in the following sections, and that the test results met
.the acceptance criteria specified in the station procedures and Appendix J, 10 CFR 50.
The procedures were reviewed for their technical adequacy to perform the intended activities.
3.2 References Oyster Creek Nuclear Generation Station Technical
Specifications Section 4.5.
10 CFR; Part 50, Appendix J, Primary Reactor Containment
Leakage Testing for Water Cooled Power Reactors.
Final Safety Analysis Report (FSAR).
- ANSI /ANS 56.8-1981, Containment Systems Leakage Testing
Requirements.
- USNRC I&E Information Notice No. 85-71; Containment Integrated Leak Rate Tests.
3.3 Documents Reviewed 666.5.007, Primary Containment Integrated leak Rate Test,
Revision 10.
I-
.
.
_
_ _ _ _ _ _
-_
___
. _ _ - _ _
_ _ _ _ _ _
>
t.
.
f'
f
'
.
!
665.5.020, Integrated Local Leak Rate Summary,-Revision No.
S'.
~
Calibration Data for CILRT instrumentation by volumetrics.
- Quality Assurance Monitoring reports on CILRT and CILRT
. preparations (various).
3.4 Administrative Control of CILRT and Procedure Review The inspectors reviewed procedural sign-offs, the CILRT log, and the main control room daily log to verify that:
Test directors were designated and their responsibilities were
clearly defined.
The procedures were adequately detailed to assure satisfactory
performance.
Test prerequisites were met.
- All systems required to maintain the plant in a safe condition
were operable and in their normal mode.
All required plant parameters were being recorded on at least
an hourly basis.
The inspector noted one deficiency in the test prerequisites section of 666.5.007.
Prerequisite No. 4.8 on page 13.0 indicates that a one point calibration check be performed on a samn'e of the installed Resistence Temperature Detectors (RTDs) and dewcells. The inspector brought to the attention of the licensee that the ANSI Standard 56.8-1981 being utilized for test guidance stipulates that a one or more point calibration check be performed for each sensor utilizing a standard which is traceable to the National Bureau of Standards (NBS).
The licensee made appropriate documentation to change the wording in the next revision of 666.5.007 to comply with the ANSI standard.
It is noted that the licensee did conduct in-situ calibra-tion checks on all installed sensors before the inspettor brought to the attention of the licensee the deficiency in the procedure.
The inspector had no further questions.
3.5 Containment Inspection and Test Boundary Verification
!
The inspector conducted a visual inspection of the accessible in-
,
terior and exterior portions of the drywell and torus. The inspector I
verified the positions of a sample of RTDs and dewcells in both the
"
drywell and torus.
Additionally the inspector witnessed the perfor-mance of I&C technicians inside the drywell and torus who were
!
t
.___-___-.__w
_ _ _ _
- _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ - _ - - _ -
-
.
.
performing the one point in-situ calibration checks of the test
instruments discussed earlier. The technicians were competent in performing the assigned tasks.
No obvious containment structural deterioration or deficiencies were observed by the inspectcr.
During the conduct of the test the inspector made repetitive 'eactor building walktroughs to inspect for the existence of artificia'
boundaries and boundaries showing evidence of leakage.
The ins,'ector utilized an ultra sound measuring device (Ultraprobe 2000 by U.E.
Systems Inc.) to assist him in leak searching. No penetration leakage was found either visually or with the use of the ultraprobe.
The inspector also reviewed system configurations for the CILRT.
This review was conducted to ensure that containment isolation valves were exposed to test differential pressure. A sample of system and valve positions were verified for consistency with the test procedure by observing control room valve position indicators.
All systems and valves inspected were found to be in an effective test configuration.
No unacceptable conditions were identified.
3.6 Test Witnessing The inspector witnessed portions of the following test activities:
(1) Containment Atmospheric Stabilization (2) 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT Data Acquisition (3) 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Instrument Verification.
These activities were witnessed to verify that the CILRT was conducted in accordance with the test procedure and within the regulatory requirements of 10 CFR 50, Appendix J.
Additionally, several parameters were monitored by the inspector during the course of the CILRT and are listed as follows:
reactor vessel water level, CRD flow, and torus water level.
The objective was to monitor the inventory of water in the reactor coolant system for prompt identification of leaks and to chase leak sources.
No meaningful changes in RCS inventory were observed.
3.7 Test Instrumentation The inspector reviewed the calibration records of the CILRT instrumentation to ascertain that the instruments had been calibrated within the 6 month period prior to the test, as per the industry standard ANSI /ANS-56.8-1981.
The calibrations were traceable to the National Bureau of Standards.
The inspector also verified that the instrument system satisfied the specifications
..,
/
.
i given in the instrument selection guide of ANSI /ANS-56.8-1981. The l
inspector observed the operation of the automatic data collection
,
system during the conduct of the test.
No unacceptable conditions were identified.
3.8 Chronology of Events October 16, 1987 Operations beginning valve lineups for the CILRT.
October 17, 1987 Completed QC. Inspection of.Drywell Exterior.
October 19, 1987 Completed QC Inspection of Torus interior, Torus
,
exterior and drywell interior..
October 23, 1987 Volume fractions have been entered into the
'
CILRT software, testing of software is completed.
Entered calibration data for RTD's mass flowmeter, and pressure sensors into CILRT Code.
October 24, 1987 Entered calibration data for dewcells into CILRT l
Code. Operations continuing valve / system lineups for test.
l 1800 Advanced CILRT Code to " Standby for Start of I
Test."
1900 Verified communications are established between the volumetrics equipment and the plant computer system.
October 25, 1987 0125 Completed review of procedure, all sign-offs, valve lineups complete.
0213 Began drywell pressurization.
1000 Reached Test Pressure.
1015 Isolated pressure source from drywell and
,
vented off air hose from manifold.
'
1038 Drywell Pressure at 22.4 psig.
1045 Advanced CILRT Compute Code to
" Stabilization".
1445 Temperature stabilization criteria has been satisfied.
1503 Official Start of CILRT.
.
,
___._.m__
_______
__
_ - _ -
,
7
,
i
l 1803 Three hours into the test.
Leak rate is l
within acceptance criteria and is continuing to I
come down.
October ~26, 1987 1515 Twe.nty-four Hour CILRT complete.
Test results meet acceptance criteria.
1547 Advanced computer to verification mode.
1600 Start Time of'4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> verification test.
,
2000 C6mpleted verification test with'
)
satisfactory results.
j i
2124 Began Containment Depressurization.
j j
3.9 Temperature Stabilization
]
The containment atmosphere must meet the following criteria per
)
station procedure 66'.5.007:
]
i
"The primary containment will have reached temperature stabilization
when the test pressure is reached and the latest rate of change of
)
the weighted average contained air temperature averaged over the l
last hour does not deviate by more than 0.5 F per hour from the average rate of change of the weighted average contained air temperature averaged over the last four hours."
J The inspector independently calculated the stabilization criteria from the test data.
The result is as follows:
(1) Average rate of change of the weighted average contained air temperature averaged over the last.four hours = 0.052 F/HR.
i (2) Latest rate of change of the weighted average contained air temperature averaged over the last hour = 0.031 F/HR.
(3) The deviation between the two averages is i
.(0.052 - 0.031) F/HR = 0.021 F/HR.
l This meets the criteria for temperature stabilization.
3.10 CILRT Results
!
The LILRT Leak Rate was computed by the licensee using the Mass Point Method (MPM) endorsed by ANSI /ANS-56.8-1981.
The acceptance criteria for the test is as follows:
(1) Ltm < 0.75 Lt at 95's upper confidence limit (UCL) for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reduced pressure test.
'
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
, -
.-
-
_.. - - - - - _ - - - - - - - _ _. - _ _. - - - _ _ - _
(2) The' calculated leakage rate for the last 8 haurs of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test less than 0.75 Lt.
(The 95% UCL may be disregarded for the final 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> criteria.)
Criteria No. 2 was imposed by the licensee to gain further-i confidence in the test results using the MPM..The addition of I
criterion No. 2 will show a change in the leak rate trend toward the end of the test. The inspector independently calculated the leak rate utilizing an NRC CILRT computer program and the licensees averaged test data.
A comparison of results for the~24 hour CILRT J
is given below.
The inspector also calculated the leak rate using
!
the total time method. The units are containment atmosphere weight percent per day.
Mass Point Results Are As Follows:
-
!
24 HR Test Last 8 HRS Licensee NRC Licensee NRC Measured (Ltm) 0.2040 0.20397 0.17539 0.17540 l
Ltm + UCL 0.2077 0.20773
-
-
Acceptable 0.6011 0.6011 0.6011 0.6011 Total Time Results Are As Follows:
24 HR Test Last 8 HRS Licensee NRC Licensee NRC i
Measured (Ltm)
-
0.22497
-
0.23712 i
Ltm + UCL
-
0.40493
-
-
l Acceptable 0.6011 0.6011 0.6011 0.6011 The licensee and NRC mass point computations show close agreement. These j
preliminary results indicate a successful CILRT.
Note that corrections i
for improvements to containment isolation boundaries (Type B&C Leakages)
must be added onto the above results to determine the "As-Found" value of the Leak Rate. A final test evaluation is pending NRC review of the licensee's summary technical report. The twenty-four hour CILRT was followed by a successful four hour superimposed leakage verification test.
4.0 QA/QC Coverage The inspector discussed coverage of the CILRT with representatives from both QA and QC.
It was determined that QC performed the containment inspection of accessible portions of the interior and exterior of the primary containment required by 10 CFR 50, Appendix J.
It was also determined that OPS-QA would provide surveillance of the test.
This was
.
-
_ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ -
__
__
_
-_-_- __
-
_ _ _.
_ _.- - - -. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
. '
..
. ',
observed by the inspector. The inspector reviewed OPS-QA documentation concerning CILRT coverage.
Included were several " Quality Assurance Monitoring Reports." These reports were well constructed.
No unaccept-able conditions were identified.
5.0 Followup of Licensee Commitment For Preventive Maintenance The licensee during inspection 50-219/86-35, committed to initiate a Preventive Maintenane (PM) Program for Containment Isolation Valves (CIVs) and to perform a study of past Local Leak Rate Test (LLRT) results to determine if a pattern of recurrent " Leakers" existed.
The licensee performed the study of containment isolation valve LLRT results from the 9R (1982),10R (1984) and 11R (1986) outages and identified twenty-six valves as recurrent local " leakers".
Seventeen of the twenty-six " leakers" are soft seated valves. The licensee has developed a PM schedule for seat replacements of the valves.
The licensee is currently investigating possible actions to be taken to prevent continued hard seated valve LLRT failures.
The licensee's Technical Functions group is in contact with outside contractors and other plants and is actively pursuing resolution of this problem.
The effectiveness of the licensee's actions in this regard will be assessed in a future inspection.
6.0 Exit Meeting Licensee management was informed of the purpose and scope of the inspection at the entrance interview.
The findings of the inspection were periodically discussed and were summarized at the exit meeting on October 27, 1987.
Attendees at the exit meeting are listed in section 1.0 of this report.
At no time during the inspection was written material provided to the licensee by the inspectors.