IR 05000029/1980017
| ML19345D896 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/21/1980 |
| From: | Caphton D, Rekito W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345D894 | List: |
| References | |
| 50-029-80-17, 50-29-80-17, NUDOCS 8012220006 | |
| Download: ML19345D896 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-29/80-17 Docket No.
50-29 License No. DPR-3 Priority Category C
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Licensee:
Yankee Atomic Electric Company
25 Research Drive Westborough, Massachusetts 01581
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Facility Name:
Yankee Nuclear Power Station (Yankee Rowe)
Inspection at:
Rowe, Massachusetts Inspection conducted:
September.22-24, 1980 Inspectors:
/O!/8 O
W. A. Rekito,' Reactor Inspector date signed
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({N g/ (jg date signed
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Approved by:
'[ < 1 < M
h 0. L. Caphto6, Chief, Nuclear Support date' signed Section No. 1, RO&NS Branch Inspection Summary:
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Inspection on September 22-24, 1980 (Report No. 50-29/80-17)
Areas Inspected:
Routine, unannounced inspection of the Containment Integrated I
Leak Rate Test (CILRT) and licensee action on previous inspection findings.
The inspection involved 15 inspector-hours onsite by one region based NRC inspector.
l Results:
No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- H. Autio, Plant Superintendent E. Bingham, Operations QAD Coordinator
- L. French, Engineering Assistant
- T. Henderson, Reactor Engineer
'D. Long, Shift Technical Advisor
- J. Staub, Technical Assistant to Plant Superintendent
- N. St. Laurent, Assistant Plant Superintendent
- E. Tarnuzzer, YAEC - OPS - Westboro
- B. Warner, Shift Technical Advisor NRC Personnel T. Foley, Resident Reactor Inspector
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (29/77-11-03): Technical Adequacy of the Containment Integrated Leak Rate Test Procedure. The inspector reviewed and verified that Revision 6 of Procedure No. OP-4701 vented the reactor coolant system during the CILRT. The referenced procedure was used to conduct a CILRT on September 22-24, 1980. This item is resolved.
(Closed) Unresolved Item (29/80-13-02):
Piping System Venting Requirements for the CILRT. The inspector verified that Revision 6 of Procedure No.
OP-4701 provided vent paths outside the four test boundaries, containment isolation valves (CIVs), previously identified. The inspector also checked other CILRT procedure valve line-ups and determined that systems were adequately vented to assure CIVs would be subjected to test differential pressure. This item is resolved.
(Closed) Unresoved Item (29/80-13-01): Adequacy of the CILRT Procedure Acceptance Criteria. Revision 6 of Procedure No. OP-4701 specified an i
Acceptance Criteria which included a leakage rate correction factor for:
(1) containment free volume changes, and (2) addition of local leak rate test results for CIVs of systems in operation during the test. The inspector determined that these changes were appropriate and acceptable.
This item is resolved.
(Closed) Unresolved Item (29/80-13-03): Type C Local Leak Rate Test l
(LLRT) of Main Coolant Pressure Sensing Line CIV. The licensee revised Attachment EE of Procedure No. OP-4702, Revision 7 to perform a Type C i
l LLRT of manual isolation valve PR-V-610. The procedure change was reviewed l
by the PORC during Review Meeting No. 80-45 and the test was conducted on September 11, 1980. After review of the revised procedure and test results, the inspector determined that this test met applicable requirements.
This item is closed.
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i 3.
Containment Integrated Leak Rate Test (CILRT)
a.
General On September 22-24, 1980, Yankee Rowe performed a CILRT as required by 10 CFR 50, Appendix J and TS 4.6.1.2.
The test was conducted at a pressure (P ) of 16 psig in accordance with procedure OP-4701, t
Revision 6, " Vapor Container Type A Leakage Test." The inspector reviewed the test procedure, witnessed various portions of the test, verified qualifications of test personnel, and independently verified calculations of the test results.
Details of the test are discussed below.
b.
Procedure Review The inspector reviewed Revision 6 of procedure OP-4701, " Vapor Container Type A Leakage Test," for technical adequacy and compliance with 10 CFR 50, Appendix J. ANSI 45.4, and Yankee Rowe Technical Specifications.
The inspector determined that applicable previous inspection findings for test Acceptance Criteria and system venting requirements were resolved 'and other procedure changes, since NRC review of Revision 4, were acceptable.
Details of review for previous inspection findings are included in Paragraph 2 of this report.
During the valve lineup review the inspector identified two contain-ment isolation valves (CIVs), TV-202 and TV-206 in the main coolant sample and drain lines, which were not subjected to the test differ-ential pressure as required by Appendix J.
The licensee corrected this problem by initiating a temporary procedure change and opening valves SA-MOV-511, VD-MOV-510 and VD-MOV-509.
No items of noncompliance were identified.
c.
Instrumentation The inspector reviewed the calibration records for resistance temper-ature detectors (20), dewpoint temperature detectors (4), and the precision pressure detector. Their calibration prior to the CILRT met applicable accuracy requirements and were traceable to the National Bureau of Standards. The inspector verified that the instrument calibration errors were properly incorporated into the computer program for leak rate calculations.
No items of noncompliance were identifie.
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d.
Tours The inspector accompanied licensee personnel on inspection tours during the CILRT.
During these tours, test boundaries were surveyed for evid_ence of leakage and on a sampling basis, selected valves were verified to be in the correct positions.
These selected valves included vent paths outside the test boundary.
No items of noncompliance were identified.
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Chronology September 21 1716 Vapor Containment pretest inspection completed
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September 22 1045 Commenced pressurizing the Vapor
. Containment 1245 Vapor Containment High Pressure Isolation Trip @ 4.6 psig 1320 Vapor Containment entry and inspec-tion @ 5 psig completed satisfactory 1915 Pressurization complete at 17 psig.
Commenced temperature stabilization.
Commenced leakage surveys and test
boundary inspections.
September 23 0025 Temperature Stabilization completed.
Noted apparent scattered data resulting from periodic mass calculations.
0650 Corrected malfunction of precision pressure detector causing fluctuating readings.
Leakage surveys and leak rate calcula-
tion continue.
September 24 0730 Completed leak rate test with calculated leakage of 0.0351 wt % per day at the 95% upper confidence level.
0741 Commenced " Pump Back" verification test.
1130 Completed verification test.
The inspector identified no items of noncompliance.
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Results Preliminary calculations indicate that the leak rate at the 95%
upper confidence level is 0.0351 weight percent per day.
The test acceptance criteria is 0.07861 weight percent per day.
The inspector noted that the leak rate of 0.0351 is not corrected for changes in containment free volume or addition of local leak rate test results for systems in operation during the test.
These systems include Component Cooling, Service Water, VC Heating, and Valve Stem Leakoff.
The inspector independently calculated several mass values and the leak rate, using raw data from the test to verify the accuracy of the licensee's leak rate calculations.
No items of noncompliance were identified.
4.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on September 24, 1980.
The inspector summarized the scope and findings of the inspection at that time.
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