IR 05000282/1980016
| ML20002B477 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/30/1980 |
| From: | Boone J, Heishman R, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20002B475 | List: |
| References | |
| 50-282-80-16, NUDOCS 8012110645 | |
| Download: ML20002B477 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-282/80-16 Docket No. 50-282 License No. DPR-42 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name:
Prairie Island Nuclear Generating Plant Unit 1 Inspection At: Red Wing, MN 55066 Inspection Conducted: October 8-9, 1980 Mw Inspector:
J. F. Streeter N /30/80 hky Accompanying Personnel:
J. M. Boone l o /3c/3,c,
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Approved By:
. F. Heishman, Chief
/I3Mb Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on October 8-9, 1980 (Report No. 50-282/80-16)
Areas Inspected:
Routine announced inspection of containment integrated leak rate test. The inspe'. tion involved 21 inspector-hours on site by one NRC inspector including six inspector-hours on site during offshifts.
Results: No items of noncompliance or deviations were identified.
8012110645
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DETAILS 1.
Persons Contacted D. Haugland, Test Director E. Watzl, Plant Superintendent, Plant Engineering and Radiation Protection The inspector also talked with and interviewed several other members of the operations, radiation protection and engineering groups.
2.
Licensee Action on Previous Inspection Findings During the test, the inspector confirmed the availability of continuous containment pressure indication in the control room and the installation of special containment smoke detectors.
This indication and equipment were provided to assure prompt detection of a fire inside containment during the leak rate test and reflect experience gained during the Unit 1 leak rate test in 1977.
3.
Containment Integrated Leak Rate Test a.
Procedure Review The inspector reviewed Revision 4 (approved October 1, 1980) of Section 5 of the procedure SP-1071(5) (2071(5), " Procedure for the Containment Vessel Integrated Leakage Rate Test", and deter-mined that the procedure was technically adequate and consistent with regulatory requirements. The inspector stated that the figure of merit for the instrumentation system during a reduced pressure test should be 4.25 Lt rather than 6.25 La as stated in Item F of Appendix C.
The licensee stated he would change the procedure prior to using it for the Unit 2 test sn 1981. The inspector determined that the figure of merit did not exceed
.25 Lt during the present Unit 1 test.
No items of noncompliance or deviationr were identified.
b.
Instrumentation The inspector reviewed the calibration data associated with instrumentation used in performing the test. A multipoint calibration of all instrumentation was performed and correction factors were entered into the computer program. All calibrations were traceable to NBS standards.
No items of noncompliance or deviations were identified.
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c.
Witness of Test The inspector witnessed portions of the Type A and verification tests and verified that:
(1) Appropriate revision of procedure was in use by test personnel.
(2) Test prerequisites were met.
(3) Test crew size and crew qualifications were commensurate with the needs of the test.
(4) Procedure changes were properly approved.
ho items of noncompliance or deviations were identified.
d.
Direct Observation of Valve Lineups During the test, the inspector visually verified the positions of the valves or flanges listed below:
Valve or Flange Position System SA-17-1 Shut Service Air Supply (line vented)
Blind Flange Installed Service Air Supply CV-31740 Shut Instrument Air Supply (Line vented)
NG-1-1 Shut Nitrogen to No. 11 and (Line vented)
12 Accumulators HC-5-3 Shut Hydrogen Control Vent to Shield Building HC-5-4 Open Hydrogen Control Vent to Shield Building Blind Flange Installed Steam Heating The positions of all valves and flanges were in agreement with the procedure and attached tags.
l No items of noncompliance or deviations were identified.
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Blowdown The inspector verified that the licensee had evaluated containment air activity following commencement of the verification te:t and l
depressurization to assure blowdown was within Technical Specifica-
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tion release limits. All containment air was exhausted to the auxiliary building and then filtered prior to being released (monitored) from the plant.
l No items of noncompliance or deviations were identified.
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f.
Data Evaluation The test (at reduced pressure of as24 psig) sequence from comple-tion of pressurization to completion of the verification test was as follows:
Activity Duration Stabilization 4-1/3 hours Type A 10-1/3 hours Verification
hours The inspector independently monitored and evaluated leakage rate data to verify the licensee's calculations. There was acceptable agreement between the inspector's and licensee's calculations as indicated in the following summary (units are in weight percent per day):
Measurement Licensee Inspector Leak rate meaaured during Type A test (Ltm)
0.0435 0.0426 Leak rate measured during Type A test at upper 95%
confidence level 0.0806 0.0797 Leak rate measured during verification test (Induced leak rate was 0.0490)
0.0839 0.1091 The above measured values are based upon a containment free volume of 1,340,000 cubic feet. The highest measured leak rate at the upper 95% confidence lesel was 0.0435 which is much less than the 10 CFR Part 50, Appendix J, acceptance criterion of 0.1157.
The highest and lowest values for the verification test were 0.0839 and 0.1091 which fall within the 10 CFR Part 50, Appendix J, accep-tance band of.0531 to.?302 (based on inspector's Ltm).
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No items of nonccmpliance. or deviations.ere identified.
g.
Containment Volume The inspector noted several different values referenced for containment net free volume as follows:
Source Value
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l FSAR, Section 5.2-1 1,32u,000 cubic feet-4-
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Report of Unit 1 Reactor Containment Building Integrated Leak Rate Test July,1973, Page 2 1,364,000 cubic feet Report of Unit 1 Reactor Containment Building Integrated Leak Rate Test July, 1973,Page 65 1,356,711 cubic feet
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Licensee 1,340,000 cubic feet The licensee stated that the value (1,340,000) he was using was based upon the 1,356,711 value minus 1% for floumeter error. The inspector calculated the leakage rate assuming 1,370,278 (1,356,711 plus 1% for flowmeter error) and the results were as follows:
Measurement Value Leak rate measured during Type A test (Ltm)
0.0492 Leak rate measured during Type A test at upper 95%
confidence level 0.0894 Leak rate measured during verification test (Induced was 0.0480)
0.1097 Although the calculations (measurements) based upon the increased volumes were slightly larger, all values were well within the acceptance criteria. The ir.spector had no further questions regarding this matter.
h.
Criteria for Reduced Duration Test The licensee satisfied all of the criteria listed in IE Inspection Report 50-263/79-18, Paragraph 7.
4.
Appendix J Exemption Requests The inspector reviewed the licensee's letters to the NRC dated August 9, l
1976, and May 30, 1980. Region III will review this area further when NRR dispositions the licensee's exemption requests.
5.
Exit Interview Because the inspection was concluded after working hours on October 9, 1980, the inspector summarized the purpose and the scope of the inspection and the findings in a telephone call to Mr. E. Watzl on October 10, 1980.
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