IR 05000321/1986013

Insp Repts 50-321/86-13 & 50-366/86-13 on 860418-23.No Violation or Deviation Noted.Major Areas Inspected: Containment Integrated Leak Rate Testing & Test Procedure

ML20198K089
Person / Time
Site:	Hatch
Issue date:	05/16/1986
From:	Jape F, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20198K082	List: IR 05000321/1986013 ML20198K076
References
50-321-86-13, 50-366-86-13, NUDOCS 8606030332
Download: ML20198K089 (7)

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pA 8tfGo, UNITED STATES

/ 'o NUCLEAR REGULATORY COMMISSION

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[' , e REGsoN 81 g j 101 MARIETTA STREET.N.W.

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• * ATLANTA, GEORGIA 30323

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Report Nos.: 50-321/86-13 and 50-366/86-13 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-321 and 50-36f License Nos.: DPR-57 and NPF-5

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Facility Name: Hatch I and 2 l Inspection Conducted: April 18 - 23, 1986 Inspector: I, /J) uP 6' /5~ d H.'L. Whitener Date Sigiie'd Approved by:

F. Jape, Section Chief M

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E h/NN Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, announced inspection involved * witnessing the eontainment ,

integrated leak rate testing and reviewing the test procedur Results: No violations or deviations were identifie ;

8606030332 860521 PDR- ADOCK 00000321 a PDR

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l REPORT DETAILS

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- Persons Contacted Licensee Employees

• T. Greene, Deputy General Manager, Plant Hatch J. C. McWhorter, Engineer, Southern Company

• A. Huber, Senior Plant Engineer S. Curtis, Shift Supervisor, Operations

• J. M. Bray, Quality Assurance, FR Other Organizations Bechtel M. Burges, Engineering Specialist B. Patel, Engineering Specialist A. Salley,-Engineering Specialist Volumetrics D. Peyran, Instrument Specialist NRC Resident Inspectors P. Holmes - Ray, SRI G. Nejfelt, RI

• Attended exit interview Exit Interview The inspection scope and findings were summarized on April 23, 1986, with those persons indicated in paragraph 1 above. The inspector described the

areas inspected and discussed in detail the inspection finding No i

dissenting comments were received from the licensee.

f The following items were identified during this inspection: Inspector Followup Item (IFI) 321/86-13-01: Review the licensee's leak l rate test report and determine the pass / fail status of the as-found

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containment leak rate, paragraph 5.d.(1),

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IFI 321/86-13-02: Verify that air / water testing of certain valves is

acceptable to the NRC staff, paragraph 5.d.(2).

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IFI 321/86-13-03 and 366/86-13-01: Review the licensees re-evaluation of the local leak rate test program and any corrective actions if required, paragraph 5.d.(3).

The licensee did not identify as proprietary any of the materials provided i

to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Containment Integrated Leak Rate Test - Unit 1 (70313, 70307, 70323)

The inspector reviewed and witnessed test activities to determine that the primary containment integrated leak rate test was performed in accordance with the requirements of Appendix J to 10 CFR 50, ANSI N45.4, test procedure 42SP-TET-003-15. " Primary Reactor Containment Integrated Leakage Rate Test" and the criteria of BN-TOP-1, Revision 1 for a short duration tes Selected sampling of the licensee's activities which were inspected included: (1) review of the test procedures to verify that the procedures were properly approved and conformed with the regulatory requirements; (2) observation of test performance to determine that test prerequisites were completed, special equipment was installed, instrumentation was calibrated and appropriate data were recorded; and (3) preliminary evaluation of leakage rate test results to verify that leak rate limits were me Pertinent aspects are discussed in the following paragraph General Observations The inspector witnessed and reviewed portions of the test preparation, temperature stabilization and data processing during the period of April 18-23, 198 (1) The test was conducted in accordance with an approved procedur Procedure changes and test discrepancies were properly documented in the procedur (2) Test prerequisites selected for review were found to be completed.

(3) Selected plant systems required to maintain test control were

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found to be operational.

(4) Special test instrumentation was reviewed and found to be l installed and c-librate . - - .

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(5) Data required for the performance of the containment leak rate calculations were recorded at 15-minute interval (6) Problems encountered during the test were described in the test event log.

I (7) Containment temperature surveys were performed for both forced flow and no forced flow condition (8) Temperature, pressure, humidity, and flow data were recorded at

15-minute intervals. Data were assembled and retained for final evaluation and analysis by the licensee. A final ILRT report will be submitted to the Office of Nuclear Reactor Regulation, Test Performance - Unit 1 (70313)

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(1) Method The licensee has developed data analysis capability for Total Time analysis in accordance with the requirements of BN-TOP-1, Revision 1, for a short duration test and Mass Point-Linear Regression analysis in accordance with the recommendations of ANSI /ANS N56.8-1981 for a 24-hour test. The Appendix J acceptance limit of 0.75 La was met for the 95% UCL for both the Total Time

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and Mass Point analysis technique A supplemental test was performed in accordance with the specifications of Appendix C to ANSI N45.4 - 1972 and BN-TOP-1, Revision 1 - November 197 '

(2) Test Description The absolute method as defined in ANSI N45.4-1972 was used in

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determining the containment leakage rate. Values bounding the l test conditions were as follows:

Containment Volume 260,000 cubic feet i Accident Pressure (Pa) 59 Psig Maximum Allowable Leakage La 1.2 wt.% per Day l System conditions for performance of the integrated leak rate test l were as follows:

i (a) Reactor Vessel Water level between 53 and 60 inches

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vented to the containment l

l (b) RHR System One loop operating in shutdown l

cooling mode

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(c) Containment Fans Secured

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(d) Instrumentation Instruments which are exposed to containment pressure post accident were exposed to test pressure (e) Pressurized Gas Source-Isolated and vented to atmosphere Containment pressurization was initiated at 5:07 a.m. and terminated at 1:04 p.m. on April 18, 1986, with the containment air pressure at 59.5 psig. Temperature stabilization criteria were met at 5:15 p.m. and time zero for the integrated leak rate test was declared. An eight hour test was concluded at 1:15 April 1 A supplemental test was performed from 2:30 a.m. to 6:30 a.m. on April 19, 198 c. Test Results - Unit 1 (1) Type A Test - The Technical Specification allowable leakage (La)

for Hatch 1 is 1.2 wt.% of the containment volume at accident pressure (Pa) per day. The acceptable test leak rate limit of 0.75 La is therefore 0.9 wt % per day. The calculated leakage rate and 95% UCL for the Total Time and Mass Point Analysis are shown below for the eight hour test period of 5:15 p.m. April 18 to 1:15 a.m. April 19, 1986:

Mass Point Total Time

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Leak Rate 0.413 wt.%/ day 0.437 wt.%/ day UCL 0.424 wt.%/ day 0.607 wt.%/ day These values are below the acceptance limit of 0.9 wt.%/ day and are in agreement with the values calculated by the inspecto (2) Supplemental Test - A four hour supplemental test was performed in accordance with Appendix C of ANSI N45.4-1972 and the BN-TOP-1, Revision 1 criteria. The measured composite leak rate was within the upper and lower acceptance limit specified by the equation Lam + Lo - 0.25La <Lc < Lam + Lo + 0.25La for both the Mass Point

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and Total Time analysis as indicated below:

Mass Point 1.31 wt.% <1.57 wt.%/<1.91 wt.%

Total Time 1.33 wt.% <1.58 wt.% <1.93 wt.%

These values meet the requirements of Appendix The inspector concluded that the containment leakage is within the limits specified in the federal regulat9on . = - - _ .-

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5 Other Inspection Areas (1) As-Found Leak Rate - In this outage, the licensee implemented a program to measure the local leakage of each Type C valve before any repairs or adjustments would result in the loss of the as-found leakage rate. However, due to a scheduling error, five valves had preventative maintenance performed before the leak rate measurement. The licensee stated that an evaluation of the affect on the as-found data will be included in the leakage test repor The licensee's evaluation of leakage data to determine the as-found containment leakage was identified for follow up inspection as:

IFI 321/86-13-01: Review the licensee's leak rate test report and determine the pass / fail status of the as-found containment leak rat The as-found leak rate will not impact on plant startup since the local as-left leakage rate has been reduced to about 25% of the allowable 0.6 La limit and the Type A test has demonstrated containment integrity.

i (2) Air / Water Testing Feedwater check valves are normally Type C tested by draining the line and pressurizing the valve with air since a water seal on these valves cannot be assured post accident. The licensee is testing certain valves including the feedwater check valves by applying the air pressure to a water filled volum Section 5.2.5.1 of the Hatch FSAR permits testing in this manner, however, it could not be determined at this time if this method had been approved by the NRC or if this section of the FSAR has been revised. This matter was identified for further review as:

IFI 321/86-13-02: Verify that air / water testing of certain valves is acceptable to the NRC staf (3) Reverse Testing Appendix J to 10 CFR 50, paragraph III.C requires that the test pressure for Type C tests be applied in the same direction as the accident pressure unless it is as conservative to test in the

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reverse direction. Review of certain Type C tests showed that test pressure for HPCI turbine steam exhaust to the torus is applied between the isolation valves which are located in the

reactor buildin Pressure on the in-board stop check valve is applied in the reverse direction. This is not a conservative test since the stem packing and bonnet gasket for this valve are on the i torus side and are not in the test boundary.

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When a valve cannot be properly tested, due to plant design, the issue is considered an unresolved item. However, based on licensee management's commitment to re-evaluate the local leak rate test program for both Unit I and Unit 2 to identify any tests that are non-conservative and to resolve any identified problems before startup after the next refueling outage, the inspector has identified this issue for followup inspection as:

IFI 321/86-13-03 and IFI 366/86-13-01: Review the licensee's reevaluation of the local leak rate test program and any 1

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corrective actions if require No violations or deviations were identified in the above review.