IR 05000266/1981020
| ML20038A934 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/12/1981 |
| From: | Hague R, Jackiw I, Robinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20038A930 | List: |
| References | |
| 50-266-81-20, NUDOCS 8111240468 | |
| Download: ML20038A934 (4) | |
Text
, -.
,
e U.S. NUCLEAR REGULATORY-COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/81-20
' Docket No. 50-266 License No. DPR-24 Licensee: Wisconsin Electric Power Company 231 West Michigan
.
Milwaukee, WI 53202 Facility Name:
Point Beach Unit 1 Inspection At: Two Creeks, Wisconsin Inspection C ducted: October 11-14 and 28, 1981
$.
sMA Inspectors:
L.
ooinson IO - 11- % I
\\ ^'
@Qg Y. UNh
.N ackiw (October 11 and 12)
\\
d _s N
b R. L.
ague io _gi-E i M/[-c%wt Approved By:
I. N. Jackiw, Acting Chief
/0
'2
/
Test Program Section Inspection Summary Inspection on October 11-14 and 28, 1981 (Report No. 50-266/81-20)
Areas Inspected: Routine, announced inspection of the containment integrated leak rate test.
The inspection involved'a total of 22 inspector-hours onsite
by three NRC inspectors including 0 inspector-hours during off-shift.
Results: No items of noncompliance or deviations were identified.
,
L t
i l
.
'
u11124042 811112'
.. -
--- -..,.. _.
_ _
. - _.. _.,,,, - - _. -.. _. _.
-.
...., _.. _.
.
.
.
DETAILS 1.
Persons Contacted
- G. A. Reed, Manager, Nuclear Operations
- R. E. Link, Superintendent, Quality and Regulatory
- J. G. Schweitzer, Inservice Inspector Engineer
- W. B. Fromm, Nuclear Plant Engineer
- F. A. Zeman, Office Supervisor
- C. W. Rowley, Quadrex Corporation CILRT Consultant
- W. G. Guldemond, USNRC Senior Resident Inspector
- R. L. Hague, USNRC Resident Inspector
- Denotes those present during exit interview.
2.
Point Beach Unit 1 Containment Integrated Leak Rate Test a.
Procedure Review The inspector reviewed the licensee's procedure for the contain-ment integrated leak rate test and verified that the procedure was technically adequate and consistent with regulatory require-ments.
b.
Instrumentation The inspector reviewed the calibration data associated with performing the CILRT. All the instruments used in the CILRT had been calibrated as required. The instrument calibration coeffici-ents, RTD weighting factors, and volume weighting factors were placed into the ILRT Computer Program as required.
The following instrumentation was used in the CILRT:
TYPE Quantity RTD's
Flowmeter
Pressure Gauge
Dewcells
c.
Witness of Test The inspector witnessed portions of the CILRT on October 13-14, 1981, and noted that:
Appropriate revisions of the procedure were in use by test personnel.
l-2-i
.
.
.
Test prerequisites were met.
Proper plant systems were in service.
Also, during witnessing of the Supplemental Test, the inspector observed that six hours into the test the licensee induced a temperature transient in the containment by switching the con-tainment fans. This maneuver caused the temperature equili-brium in the containment to be altered.
Once the temperature had stabilized, the licensee proceeded with the supplemental test.
d.
Valve Lineups The inspector verified that the valve lineups were cc iducted and documented in accordance with an approved test procedure.
In addition, the resident inspector verified, by direct observation, proper valve lineups in accessible areas.
e.
Blowdown and Containment Inspection The resident inspector verified, that blowdown was within technical specification radioactivity release limits, analysis and calculations were completed before the release started, and that required environmental monitoring equipment was functional before the release began. The resident inspector also conducted an independent post CILRT containment inspection for equipment degradation after blowdown and did not identify any degradation.
f.
CILRT Data Evaluation The eight hour reduced pressure CILRT was started on October 13, 1981. The inspectors independently monitored and evaluated leak rate data to verify the licensee's calculation of the leak rate. There was acceptable agreement between the inspector's and licensee's leak rate calculations as indicated in the follow-ing summary (units are in weight percent per day):
Measurement Licensee Inspector Leakage rate measured (LTM)
0.0293 0.0315 during CILRT LTM at 95% confidence level 0.0680 0.0856 Appendix J Acceptance Criteria at 95% confidence level = 0.75 Lt = 0.75 (.283%/ day) = 0.212%/ day. As indicated above, the adjusted Ltm at the 95% confidence level was less than the maximum allowable by 10 CFR Part 50, Appendix J.
-3-
,
.-
g.
Supplemental Test Data Evaluation After the satisfactory completion of the eight hour test on October 14, 1981, a known leakage of 2.922 SCFM or 0.1366 weight percent per day was induced. The inspectors independently moni-tored and evaluated leak rate data to verify the licensee's calculation of the supplemental leak rate. There was acceptable agreement between the inspector's and the licensee's leak rate calculations as indicated in the following summary (units are in weight percent per day):
Measureraent Licensee Inspector Measured leakage (Lc) rate 0.1964 0.2034 during supplemental test Induced leakage rate (Lo) =
2.922 scfm (0.1366%/ day)
Appendix J Acceptance Criteria:
Lo + Ltm - 0.25 Lt Lc Lo + Ltm + 0.25 Lt.
As indicated above, the supplemental test results satisfied the requirements of 10 CFR Part 50, Appendix J.
No items of noncompliance or deviations were identified.
3.
Exit Interview The inspectors met with licensee representatives (denoted in Para-graph 1) on October 14, 1981. The inspectors summarized the purpose, scope, and preliminary findings of the inspection. During a telephone discussion on October 28, 1981, the licensee provided the inspector with the final leak rate calculation data.
-4-