IR 05000369/1979029
| ML19260A978 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 10/18/1979 |
| From: | Burnett P, Andrea Johnson, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260A948 | List: |
| References | |
| 50-369-79-29, NUDOCS 7912060215 | |
| Download: ML19260A978 (5) | |
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION c,
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.;e REGION 11
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o 101 MARIETTA ST., N.W., SUITE 3100 f'
ATLANTA, GEORGIA 30303
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Report No. 50-369/79-29 Licensee: Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name: McGuire Docket No. 50-369 License No.
CPPR-83 Inspection at McGuire Site Inspected by:
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Date Signed
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P.4. Bd'rnViit, Acting 'Section Chief, Date Signed RONS Branch SUMMARY Inspection on August 16-23, 1979.
Areas Inspected This routine, annnneed inspection involved 175 inspector-hours onsite in the area of containment integrated leak rate testing which included inspection of the test procedure, instrument calibrations, data processing, valve alignment a_d problems encountered during the test.
Results In the area inspected, one apparent item of noncompliance was found (Infraction-Failure to follow valve alignment procedure paragraph 6).
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DETAILS 1.
Persons Contacted Licensee Employees
- M. Sample, Projects and Licenseing
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- L. keaver, Performance Engineer
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- M. Pacetti, Test Engineer, Performance R. Pacetti, Engineer, Corporate Office H. Pham, Test Coordinator
- R.
Trepasso, Shift Test Coordinator G. Galbreath, Shift Test Coordinator A. Kientz, Shift Test Coordinator B. Johant2n, Standby Shift Test Coordinator
- M. Watts, Engineering Services (I&C)
- Attended exit interview 2.
Exit Interview The inspection scope and findings were reviewed with licensee repre-sentatives as indicated in paragraph I during the inspection on August 23, 1979, and by subsequent telephone communications on August 30, 1979. The licensee indicated to the inspector during the August 30, 1979 telephone communication that in addition to the vent valve found closed by the in-spector (See paragraph 6) an additional vent valve NC 103 on penetration M216 was found closed by the plant operation personnel. The licensee agreed to add the leakage determined by local testing penetration M216 and M355 to the upper 95% confidence limit of the type A test along with other identified add-on leakage prior to determining the acceptability of the test.
The licensee and inspector discussed the problem of the personnel air lock seals deflating when instrument air is removed and the licensee stated that this concern is being turned over to the licensee design group for resolution.
3.
Licensee Action on Previous Inspection Findings Not inspected.
s 4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Containment Integrated Leak Rate Test The inspectors witnessed the performance of the primary containment int -
grated leak rate test (CILRT) to determine that the test was conducted in
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i-2-accordance with the requirements of 10 CFR 50, Appendix J, ANSI N45.4, FSAR Section 6, and preoperational test procedure TP/1/A/1200/06.
Selected sampling cf the licensee's activities which were inspected included:
(1)
review of TP/1/A/1200/06 to verify that the test procedure was properly approved and conformed to regulatory requirements (Detailed review of valve alignments and NRC positions were discussed with the licensee during a previous inspection and documented in IE Report No. 50-369/78-30); (2)
observation of test performance to determine test prerequisites were com-pleted, special equipment was installed and calibrated and that appropriate data was recorded and analyzed and (3) preliminary evaluation of leakage rate test results to verify that leak rate limits were met Pertinent aspects of the test are discussed in the following subparagraphs, a.
General Observations The inspector witnessed and/or reviewed portions of the test prepar-ation, containment pressurization, temperature stabilization, leak chasing, and data processing in the period August 16-23, 1979. The following items were noted:
(1) The test was conducted in accordance with an approved procedure maintained at the test control center.
Changes to the procedure were documented.
(2) A sampling of test prerequisites were reviewed and found to be complete.
Personnel airlocks were tested using a temporary procedure and are identified for retest at a later date. This matter will be followed at a later inspection to verify retest aid to review possible generic issues (369/79-29-03).
(3) A sampling of plant systems required to maintain test control were reviewed and found to be in service as required.
(4) A sampling of penetration valve alignments were observed and several discrepancies identified. This matter is discussed in paragraph 6.
(5) A sampling of special test fastrumentation was reviewed and found to be installed and calibrated.
Irstrument checks were performed prior to the test.
(6) Data required for the performance of the containment leak rate calculation were recorded a: 15 minute intervals.
Data were assembled and retained for final analysis and evaluation.
(7) Problems encountered during the test were described in the test event log.
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Evaluation Final analysis of the leak rate data will be perfo ied by the licensee and will be reported in the test report to the Office of Nuclear Reactor Regulation (NRR). The inspector's preliminary review indi-cates that the leakage rate achieved was less than 0.75 Lam. Add-on leakage for isolated leakage paths will be included in the final evaluation of containment leak rate.
6.
Test Sequence and Identified Problems
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The licensee conducted a structural integrity test and then depressurized the containment to 13.5 psig for a period of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to permit outgasing.
The containment was then pressurized
+.o 14.8 psig for the type A test at 7:36 p.m.
on August 16.
At 8:40 a.m.
on August 17, licensee personnel were sent into containment to relocate RTD's 38-47 in the upper condenser, away from the defroster. The inspectors noted that there was no ice in the ice condenser; therefore, the licensee recalculated the volume fraction of each compartment and associated fraction for each RTD. At 00:35 a.m.
on August 18, 1979 the temperature stabilization was completed and the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test began. At approximately 11:15 p.m.
on August 18, while verifying valve alignments the inspectors found that containment penetrations M386 and M359 were not properly isolated and vented.
The licensee then isolated and ve1ted the instrument air lines through these penetrations. The licen-see elected to enter containment at 4:40 p.m.
on J.ugust 19 to check instru-ment airline fittings from the door seals back to the seal air accumulator since the inner door seal air is fed from these penetrations and leakage would cause the door seals to deflate. During this containment entry RTD-4 rignal was repaired. At 5:00 a.m.
on August 20, test pressure was reached and ct 7:00 a.m.
the inner door seals of the upper personnel air lock deflated causing a pressure loss. The licensee elected to use outer door as the pressure boundary and continued the test, after coripleting the 4-hour stabilization period at 3:50 p.m. on August 20.
At 11:^9 p.m. on August 20, the inner seal of the inner door of the lower emet,ency air lock deflated and licensee personnel vented this hatch every 30 micutes until 7:00 a.m. on August 21.
Due to this venting the licensee restarted the test at 7:00 a.m.
on August 21, us.ng the outer door of the emergency hatch as the pressure boundary.
The 24-hour test was completed at 9:40 a.m. on August 22, and then the supplemental leak rate verification test was initiated. The verification test was completed at 9:46 p.m. on August 22.
During the inspection (random sample) of penetration valve alignments inside containment, after containment depressurization, the inspector found that vent valve KC331 on penetration M355 was closed and signed off open when required to be open as per procedure TP/1/A/1200/06.
This is an apparent item of noncompliance for failure to follow procedure (79-29-01).
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Test Method and Results The licensee used a normalized absolute mass technique to determine the containment leakage.
Primary varibles of temperature, pressure and dew-point were input into the computer at 15 minute intervals for upper con-tainment, lower containment and ice condenser volumes.
Total containment leakage was obtained from the summation of these compartment leakages.
The inspector's independent calculations of leak rate and upper (95%) con-fidence limit agreed with the licensee's values of 0.11 and 0.115 percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> obtained by the computer. The composite leakage measured after imposing a 0.2% per day leakage on the 0.11 measured leak rate was within the acceptance limits of 0.25 La.
The inspectors concluded that the containment meets the required type A leak rates limits. However, the final leak rate must include all identi-
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fied add-on leakage. This matter will be reviewed upon submittal of the leak rate test report to the NRC (369/79-29-02).
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