IR 05000272/1983018
| ML20024A823 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/09/1983 |
| From: | Bettenhausen L, Pullani S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20024A819 | List: |
| References | |
| 50-272-83-18, 50-311-83-17, NUDOCS 8307010012 | |
| Download: ML20024A823 (9) | |
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50272-830205 U. S. NUCLEAR REGULATORY COMMISSION
REGION I
50-272/83-18 Report No. 50-311/83-17 50-272 Docket No. 50-311 DPR-70 License No. DPR-75 Priority
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Category C
Licensee: Public Service Electric and Gas Company P. O. Box 236 Hancock's Bridge, New Jersey 08038
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Facility Name: Salem Nuclear Generating Station, Units 1 and 2 Inspection At: Hancock's Bridge, New Jersey Inspection Conducted:
May 17-24, 1983 Inspectors:
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S. V. Pullani, Reactor Engineer date Approved by:
N 16 e
/62 L. H. Betflenhausen, Chief, Test Program date Section, Engineering Programs Branch Inspection Summary:
Inspection on May 17-24, 1983 (Combined Report No. 50-272/83-18 and 50-311/83-17)
Areas Inspected:
Routine, unannounced inspection of followup of previous inspection findings; procedure review, test witnessing, and results evaluation of Local Leak Rate Testing (LLRT) and Integrated Leak Rate Testing (ILRT); and tours of the facility. All areas covered both units except that the witnessing and results evaluation of ILRT covered Unit 2 only.
The inspection involved 62 inspector hours onsite (23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> for Unit 1 and 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> for Unit 2) and 8 inspector hours in office (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> each for Unit 1 and 2) by one region-based inspector.
Results:
No violations or deviations were identified.
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DETAILS 1.
Persons Contacted 1.1 Public Service Electric and Gas (PSE&G)
- R. Brant, Nuclear Plant Services Engineer R. Crapo, Nuclear Engineer J. Driscoll, Assistant General Manager--Salem Operations F. Meyer, Manager -- Nuclear Site Maintenance
- J. Zupko, General Manager -- Salem Operations 1. 2 PSE&G Research Corporation (Energy Lab)
G. Druffne, Test Engineer B. Hicks, Materials Test Engineer 1. 3 Stone & Webster (S&W)
R. Parry, Test Consultant A. Vanderwoude, Test Consultant 1.4 Nuclear Regulatory Commission (NRC)
- L. Norrholm, Senior Resident Inspector R. Summers, Resident Inspector The inspector also interviewed other licensee employees during the course of inspection.
- denotes those present at the exit interview on May 24, 1983.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (50-272/82-23-05) Additional Valves to be Included in LLRT Program The licensee, in the latest, revision (Revision 15) of the Units 1 and 2 LLRT procedure (M16E, Containment Isolation Type B and C Tests), included approximately 50 additional valves in the LLRT program.
The licensee tested these additional valves during the 1982 fall outage for Unit 1 and-the 1983 winter outage for Unit 2.
Technical Specification Table 3.6-1 remains to be revised to include these additional valves.
The item remains open pending such revision and its review by NRC for conformance with 10 CFR 50, Appendix J.
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3.
Local Leak Rate Testing 3.1 References 10 CFR 50, Appendix J. Primary Reactor Coritainment Leakage
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Testing for Water Cooled Power Reactors Salem Unit 1 Technical Specifications, Section 3/4.6.4, Primary
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Containment-
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Salem Unit 2 Technical Specifications, Section 3/4.6.4, Primary Containment Updated Final Safety Analysis Report (FSAR), Revision 0, Section
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6.2, Containment. Systems
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ANSI /ANS 56.8-1981, Containment System Leakage Testing Require-
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ments 3.2 Documents Reviewed Test Procedure M16E, Containment Isolation Type B and C Tests,
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Revision 15 Summary Technical Report for the first periodic Type A test
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performed during August 1979, for Unit 1
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Summary Technical Report for the preoperational Type A test performed during December.1978, for Unit 2 Leakage Summary Sheets for Type B and C tests performed since
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above Type A tests for Units 1 and 2'
l Selected Type B and C detailed test results
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Selected Piping and Instrumentation Diagrams (P& ids)
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Licensee Event Report 83-010/03L, Containment Systems - Contain-
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ment Type B and-C Leak Rate Out-of-Specification, Unit 1 3.3 -Scope of Review The inspector reviewed the above documents to ascertain that the licensee's LLRT program was conducted in compliance with the regula-tory. requirements and licensee commitments referenced in Section 3.1.
3.4 Test Witnessino On May 19, l'983, the inspector witnessed portions of a Type B test for electrical' penetration 2-19.
The test was being conducted in accordance with approved procedure M16E, Containment Isolation Type B
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and C Tests, Revision 15.
The test volume was pressurized to 47 psig with nitrogen.
The' leakage as read on a volumetric flow indicator was 0 sccm.
The test result met both the licensee's administrative-limit (0 sccm) and TS limit of 0.6La (129, 750 sccm) for the total of Type B and C leakages.
The inspector observed the performance of the test to ascertain that prerequisites were met,2 proper precautions were taken, measuring and test ' equipment was properly calibrated, test was. conducted in accord-
.ance with the procedure, test crew actions were correct and timely-and the required data were recorded.
The inspector did not identify any unacceptable conditions.
.3.5 Test Results Evaluation The inspector reviewed the summary results and selected samples of detailed results of Type B and C tests performed since previous Type A tests of both units to verify conformance with requirements of 10
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CFR 50 Appendix J and Technical Specifications.
The results of Type B and C tests performed during various refueling outages were as follows:
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Outage Date Sum of Type B & C Results Unit 1:
September - November 1980 11,791 sccm October 1982 - January 1983 27,461 sccm*
Unit 2:
January - April 1983 6,792 sccm January - May 1983 18,705 sccm*
(preliminary results)
- includes leakages of 50 additional valves in the LLRT program (see Section 2 of this report).
The above results met the acceptance criterion of 129, 750 sccm (0.6 La). The' inspector did not identify a_ny unacceptable conditions.
3.6 Repairs and Adjustments to Containment Boundary l
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lhe inspector discussed with the licensee the relation' ship between
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the improvements made to the containment boundary as a result of
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repairs and adjustments (ras) and Type A test' failures.
If ras, as a j
result of the Type B and C testing program or other reasons, are made
prior to the Type-A test the difference between AS FOUND and AS LEFT l
Type B-and C results!of the affected leakage paths should be added to i
the Type A test results to arrive at the AS FOUND Type A test l
results.
A periodic Type A-test should be called "a failure" if the AS'FOUND Type A test results exceed 0.75 La for a test conducted at
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Pa, the peak accident pressure.
For periodic Type-A tests conducted
at reduced test pressure Pt, the equivalent limit is 0.75 Lt.
.The licensee stated that the AS FOUND and AS LEFT results would be reported to the NRC, but did not agree with the NRC position that the difference should be added to the Type A test results.
This is an
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unresolved item (50-311/83-17-01).
3.7 Reportability j
The licensee inquired about the NRC position on the reportability of Type B and C tests which are found to have unacceptable leak rates at I
a time when containment integrity is not required such as during a refueling outage.
The inspector explained the-NRC position that
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thirty day written reports should be submitted whenever unacceptable
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Type B and C test results are detected and containment isolation is not required.
If there are more than one such related events, the intent of the above position could be satisfied by reporting the first event within 30 days, and the remaining events in a single comprehensive event report following completion of all Type B and C
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tests, in lieu of a separate event report for each event.
However, prompt reporting with written follow-up must be made for those Type B and C tests which are found to have unacceptable leak
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rates at a time when containment-integrity is or'would have been
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i required as described in the Technical Specifications.
Regulatory Guide 1.16 gives additional guidance on the reportability of opera-
tion with unacceptable Type B and C test results and abnormal degrada-tion discovered in primary containment.
l 3.8 Review of Licensee Event Report The-inspector reviewed Licensee Event Report 83-010/03L, Containment i.
Systems -- Containment Type B'and C Leak Rate Out-of-Specification, Unit 1, March 7, 1983.
The event as reported was that the results of
Type C tests performed during a refueling outage for threeLcontain-
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-ment isolation valves exceeded the maximum range of the leak rate
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. test equipment (20,000 sccm) and therefore could have exceeded l
Technical Specification limit of 0.6 La for combined-Type B and C
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results.
However, redundant barriers and therefore the containment integrity were maintained.
The valves were subsequently repaired and
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retested satisfactorily.
The inspector found'that the licensee's analysis of the event and corrective actions were acceptable.
'4.
I'ntegrated Leak' Rate Testing On May 20 through 23, 1983, a periodic ILRT was performed for Unit 2.
The test was performed in accordance with approved procedure M9-ILP-CT-1,
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Reactor Containment Building Integrated-Leak Rate Test (Type A Test),
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. Revision 1.
The inspector reviewed the procedure and related documents,
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and witnessed preparations and various portions of the test.
Details and inspection. findings are described below.
4.1 Procedure Review The inspector reviewed the ILRT procedure for technical adequacy and compliance with the regulatory requirements and the licensee commit-ments referenced in Section 3.1.
The inspector did not identify any unacceptable conditions.
4.2 Computer Program Review The inspector reviewed portions of the program on a sampling basis to ascertain that the mathematical formulae used in the program are in accordance with applicable industry standards.
The inspector noted that the program used formulae for the Mass Point Analysis techniques described in ANSI /ANS-56.8-1981 except that a more conservative formula was used for the 95th percentile of Student's t distribution (t.95) for calculation of Upper Confidence Limit (UCL) of the contain-ment leakage rate; this was acceptable.
4.3 Test Instrument System The inspector reviewed the calibration records for the instrument system to ascertain that the accuracy requirements were met and the calibration was traceable to the National Bureau of Standards. The inspector also verified that the instrument system satisfied the Instrument Selection Guide (ISG) of ANSI /ANS-56.8-1981.
The inspec-tor also observed the operation of the instrument system and the automatic data processing system during conduct of the test.
The inspector did not identify any unacceptable conditions.
4.4 Venting of Containment Liner Weld Channels
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During a previous inspection, the inspector had discussed with the licensee the need for venting of the containment liner weld channels to expose the liner welds to the test pressure during an ILRT.
The licensee had at that time acknowledged this need and agreed to vent the channels (see combined Inspection Report 50-272/83-04 and 50-311/83-03, Paragraph 4.3).
Subsequently, the licensee found that the channels in the lower parts of the containment are always vented to the containment atmosphere with their plugs removed, but that the channels in the upper parts of the containment have plugs in place and are impractical to be vented due to their inaccessible location.
The licensee stated further that the channels are designed as safety related, Seismic 1 classification and for full Loss of Coolant Accident (LOCA) pressure and therefore could be treated as the containment boundary.
The inspector stated and the licensee agreed that such an evaluation and its supporting documentation need be reviewed and approved by NRR:NRC.
The final determination of valid-ity of the current ILRT for Unit 2 would be subject to such NRR l
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approval. The licensee elected to proceed with the test with channels not vented and to get the NRR approval later on.
The licensee understood that, if NRR would not approve, the ILRT should be redone with channels vented or, as an equivalent suggested by the licensee as an interim measure, a Type B test of the channels be performed and the test results added to the current ILRT results.
This is an Unresolved Item pending the above actions by the licensee and review by NRC (50-311/83-17-02).
4.5 Containment Inspection and Test Boundary Verification The inspector conducted several tours independently and with licensee personnel both before and during ILRT.
During these tours, the containment was inspected for existence of artificial boundaries.
Valve lineups were verified on a sampling basis to be in accordance with the test procedure.
The test boundaries were surveyed for evidence of leakage.
The inspector observed that two pressurized bottles were found inside the containment during the final inspection and were promptly removed by the licensee.
4.6 ILRT Chronology May 20, 1983 1645 hrs.
Completed final containment
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inspection.
2320 hrs.
Started pressurization of the -
containment.
May 21, 1983 1538 hrs.
Containment at test pressure (63.3 psia); stopped pressuriza-tion.
During and subsequent to pressurization, leak surveys were performed.
No major leaks were observed.
Some leaks were observ-ed to the secondary side of steam generators 22 and 23 (probably through the manhole gaskets).
For investigation of the above leaks, the secondary sides of these steam generators were kept at 30 psig during part of the testing period.
Minor leaks were also observed through Fire Protection and Service Air penetrations and a few valve packings.
1915 hrs.
Containment temperature stabiliza-tion criteria met.
May 22, 1983 0913 hrs.
Start of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT data.
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May 23, 1983 0913 hrs.
End of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT data.
1150 hrs.
Started Verification Test.
1300 hrs.
The Verification Test criteria met; end of Verification Test.
1316 hrs.
Started depressurization of the containment.
4.7 Preliminary ILRT Results Evaluation The licensee evaluated the preliminary ILRT results for the 24-hour period starting 0913 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.473965e-4 months <br /> on May 22, 1983 and ending 0913 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.473965e-4 months <br /> on May 23, 1983.
The calculated leakage at 95% UCL was 0.054 weight percent per day.
The test acceptance criterion is 0.075 weight precent per day.
The inspector stated that the following corrections should be applied to the above calculated leakage value before it is reported to the NRC:
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(a) Corrections for changes, if any, in containment free air volume during the test.
(b) Corrections for systems not in proper lineup or not vented or drained.
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(c) Corrections for keeping the secondary side of the steam genera-l tors 22 and 23 at 30 psig during part of the testing period.
The licensee agreed to make the above corrections before the results are reported in the Summary Technical Report.
This is an Inspector Followup Item (50-311/83-17-03).
The inspector also made it clear to the licensee that the validity of the current ILRT would be subject to satisfactory resolution of the liner weld channel issue explained in Section 4.4 of this report.
5.
Unresolved Items Unresolved items are matters about which more information is required to i
ascertain whether they are acceptable, or whether they are violations or deviations.
Paragraphs 3.6 and 4.4 contain unresolved items.
6.
Plant Tours The inspector made several tours of the plant, including Containment, Turbine Building, Primary Auxiliary Building, and Control Room.
During these tours, the inspector observed operations and activities in progress, general condition of the safety related equipment, component tagging, and system operations to support ILRT.
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7.
Exit Interview
.The inspector met with licensee management representatives (see Section 1 for attendees) on May 24, 1983.
The inspector summarized the scope and
. findings of the inspections at that time.
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