IR 05000219/1978034
| ML19281A156 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/15/1978 |
| From: | Reyes L, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19281A153 | List: |
| References | |
| 50-219-78-34, NUDOCS 7903070110 | |
| Download: ML19281A156 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-219/78-34 Docket No. 50-219 License No. DPR-16 Priority --
Category C Licensee:
Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 Facility Name:
Oyster Creek Nuclear Generating Station Inspection at:
Forked River, New Jersey Inspection conduc d: Nr em r 20-22, 28-29, 1978
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Inspectors: / uis A. Rey
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/ Reactor Ins ector
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11/15 [W Jo n F. Streeter, Chief Nuclear Support Section 1 NJhnF.Cc %
aAs/77 Approved by:
S treeter, Chief Nuclear Support Section 1 Inspection Sur:marv:
Inspection on November 20-22. and November 28-29, 1978. (Report No. 50-219/
78-34).
Areas Inspected: Routine, unannounced inspection by regional based inspec-tors of the containment integrated leak rate test.
The inspection involved 31 inspector-hours on site by two NRC regional inspectors.
Results:
No items of noncompliance or deviations were identified.
7903076 / lo
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1.
Persons Contacted The below technical and supervisory personnel were contacted:
- J.
Carroll, Station Superintendent
- K.
Fickeissen, Technical Engineer
- D.
Ross, Manager, Nuclear Generation
- J.
Sullivan, Chief Engineer A.
Rone, Technical Supervisor M. Budaj, Engineer J. Perreault, Senior Engineer, Exxon Nuclear Company, Inc.
C. Dreike, Project Engineer, Volumetrics The inspector also talked with and interviewed several members of the technical and engineering staff s.
- denotes those present at the exit int erview.
2.
Previous Inscection Item Uodcte (Closed) Unresolved item (219/78-24-01): A formal submittal of the exemption request was submitted to NRR prior to performance of the CILRT.
(Closed) Unresolved item (219/78-24-02):
(1)
The calculated leak rate was corrected for instrument error by correcting the raw data with the information ob tained from a three point calibration performed on the temperature and dewpoint sensors.
(2)
The procedure was revised to agree with the NRC position concerning the acceptance criteria for the CILRT.
(3) All the referenced data sheets and attachments were incor-porated in the procedure.
(4)
The procedure was revised to include upper and lower limits for the calibrated leak.
(5)
The procedure was revised to calculate Lt conservatively by using gauge units.
(6) The procedure was revised to leave the drywell pressure switches exposed to the containment atmosphere during the CILR.
(7)
The procedure was revised to include provisions for the calculation of leak rate adjusted to reactor vessel and sump water level changes during the CILRT.
(8)
The procedure was revised to include guidance f or actions in the event of leakage during the CILRT that exceeds accept-ance crit e ria.
(9)
The procedure was revised to include the mass point tech-nique as the data analysis method.
(10)
The procedure was revised to state chac the absolute method will be utilized for reporting purposes.
(Closed) Unresolved item (219/78-24-07):
(1)
The final instrument calibration certifications were reviewed by the inspector and found to be traceable to NES and within acceptable values.
(2) Atmospheric data was logged by control room operators during the CILRT and can be retrieved from control room records if necessary.
(3) A one-pcint calibration check was performed on the installed RTDs and dewcells and the CILRT procedure was revised to include a checkout of the Volumetrics instrumentation used.
(4) Valve lineups were revised to reflect the requirements of Section III. A. l(d) of Appendix J.
No items of noncompliance or deviations were identified.
3.
Containment Integrated Leak Rate Test (CILRT)
a.
First Attemot The CILRT was first attempted during the period November 20-23, 1978.
During that a ttempt, the torus to reactor building dif-ferential pressure switches, DPS-66A and DPS-66B, were found to have ruptured diaphrams.
Af ter closing the instrenent root valves f or these switches, the leakage a ttributable to the ruptured diaphrams was calculated to be approximately 0.578 weight percent / day.
Without depressurizing the containment, the licensee also perf ormed repairs to the exhaust vent system, isolated the isolation condenser noncondensable vent line iso-lation valves, and corrected a valve lineup error in the trans-versing incore probe purge system before the second CILRT attempt was comnenced and an acceptable leak rate was measared.
The first attempt was considered a failed tes b.
Second Attemot Following completion of the above mentioned corrective actions and with the containment remaining pressurized, a second CILRT attempt was started on November 23, 1978.
The inspector inde-pendently evaluated leak rate data to verify the licensee's calculation of the leak rate.
There was acceptable agreement between the inspector's and licensee's leak rate calculations as indicated in the following su= mary (units are in weight percent per day):
Measurement Licensee Insoector Leakage rate measured (Ltm) during 0.4265 0.4243 CILRT Ltm at 95% confidence level 0.4298 0.4279 Len at 95% confidence level adjust- 0.4806 0.4781 ed to reflect panalties (ref er to Paragraphs 6 and 7) due to isolation condenser vent valve leakage and water level changes Appendix J Acceptance Criterion at 95% confidence level = 0.75 Lt
= 0.567 As indicated above, the adjusted Ltm at the 95% confidence level was less than the maximum allowable by 10 CFR Part 50, Appendix J.
No items of noncompliance or deviations were identif ied.
4.
Sucolemental Test Af ter the satisfactory completion of the 24-hour test on November 24, 1978, a known leakage of 0.1948 weight percent / day was induced.
The inspector independently evaluated leak rate data to verify the licensee's calculation of the supplemental leak rate.
There was acceptable agreement between the inspector's and licensee's leak rate calculations as indicated in the f ollowing summary (units are in weight percent per day):
Measurement Licensee Inspector Measured leakage (Lc) rate during 0.5708 0.5688 supplemental test Lc 0 95% confidence level 0.5803 0.5833 Induced leakage rate (Lo) = 0.1948 Appendix J Acceptance Criterion:
Lo+Ltm-0. 25Lt < Lc < Lo+Ltm+0. 25Lt 0.1948+0. 4243-0.1890 < 0. 5688 < 0.194 8+0. 4243+0.1890 0.4301 < 0. 5688 < 0.8081
As indicated above, the supplemental test results satisfied the requirements of 10 CFR Part 50, Appendix J.
No items cf noncompliance or deviations were identified.
5.
Future Test Schedule Since the first CILRT cttempt failed to meet the acceptance criteria, the test schedule applicable to subsequent Type A tests will be reviewed and approved by the NRC in accordance with Section III.6(a)
of Appendix J.
6.
Volume Change Corrections The licensee calculated an additional leakage due to changes in the reactor vessel and sump levels of.0463 weight percent / day.
The leak rate was added to the unadjusted measured leak rate.
No items of noncompliance or deviations were identified.
7.
Isolation Condenser Vent Line Isolation Valves During the performance of the CILRT the isolation condenser nonconden-sable vent line isolation valves were isolated downstream of the valves due to excessive leakage.
The local leak rate measured before repairs were made was 0.0045 weight percent / day.
This leak rate was added to the unadjusted measured leak rate.
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No items of noncompliance or deviations were identified.
8.
Instrumentation The inspector reviewed the calibration data associated with perf orming the CILRT. A multipoint calibration of all instrumentation was per-formed.
Correction values were generated based on the dif ference between measurements of resistance from a NBS verified resistance box and actual resistance measured.
All corrections were placed as an array or equation into the CILRT computer.
The f ollowing instrumentation was used in the CILRT.
Type Qua ntity Serial Number RTDs
4957 Flowmeter
VMC 505 Pressure Gauge
1069 Temperature Transducer
1776 Dewcells
4957 No items of noncompliance or deviations were identifie.
Procedure The inspector reviewed the test procedure for technical adequacy and conformance with regulatory requirements.
The inspector noted that the current revision of the procedure did not include instru-ment weighting factors used in the computer program.
The licensee stated that the values for the weighting factors would be incor-porated in the procedure.
In addition, since changes to the com-puter program could change the results of a CILRT, the licensee agreed to develop appropriate administrative controls to assure computer program changes are properly reviewed.
This is an un-resolved item (219/78-34-01) pending revision of the test pro-cedure.
No items of noncompliance or deviatiors were identified.
10.
Unresolved Items Unresolved items are matters about which more information is re-quired in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
An unresolved item dis-closed during the inspection is discussed in Paragraph 9.
11.
Exit In te rview An exit interview was conducted at the conclusion of the inspection with the licensee representatives denoted in Paragraph 1.
The total leak rate af ter all corrections were included was determined by the licensee to be 0.481 weight percent / day.
The second CILRT attempt confirmed that the containment leak rate was acceptable.