IR 05000282/1989014
| ML20246K393 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/04/1989 |
| From: | Maura F, Phillips M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20246K377 | List: |
| References | |
| 50-282-89-14, 50-306-89-15, NUDOCS 8905180048 | |
| Download: ML20246K393 (19) | |
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U.S.-NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-282/89014(DRS); 50-306/89015(DRS)
Docket Nos. 50-282; 50-306 Licenses No. DPR-42; DPR-60 Licensee:
Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name:
Prairie Island Nuclear Generating Station, Units 1 and 2 Inspection At: Welch, MN 55089 (Red Wing)
Inspection Conducted: April 17-21, and 27, 1989 Inspector:
F Ira 5'/f/ff Date
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Approved By:
M. P. Phillips, Chief
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Operational Programs Section 2 Da'te j
Inspection Summary lospection on_ April 17-21._and 27, 1989 (Reports No. 50-282/89014(DRS):
50-306/89015(DRS))
Areas Inspected:
Routine, announced inspection by a Region based inspector of licensee action on previous inspection findings, containment integrated leak rate test (CILRT) procedure; CILRT performance witnessing; CILRT results reviews; and local leak rate test program.
NRC modules utilized during this inspection incieded 61720, 70307. 70313, 70323, and 92702 Results: Three violations were.dentified in two of the five areas inspected:
one viola'. ion of 10 CFR 50, Appendix J, failure to perform local leak rete testing of airlock prior to repair or adjustments so that the actual as found containment leakage rates could be determined; and two violations of 10 CFR 50, Appendix B, Criterions VI and XIV lack of drawing control and incorrect status of containment isolation valve position. The last two violations had no safety significance and were corrected promptly by the licensee, therefore, no Notice of Violation is being issued. One open item was identified relating to the test pressure maintained at the containment penetration during the Type B and C tests.
Improvements were noted in the performance of CILRT and LLRT programs when compared to 1988.
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PDR ADOCK 05000282 G
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DETAILS
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Persons Contacted
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Northern: States Power Company
- R. Fraser, Lead Production Engineer
- C. Gjermo, Production Engineer (Type B and C tests)
J. Langan, Consultant
- D. Mendele, General Superintendent, Plant-Engineering and Rad Protection J.-Schuelke, Production Engineer (Type A test)
M. Wadley, Shift Manager
- E. Watzl, Plant Manager USNRC J. Hard, Senior Resident Inspector T. O'Connor, Resident Inspector W.'Norris, RES
- Denotes persons attending the exit meeting of April 21, 1989.
The -inspector also contacted other licensee personnel including members of the operations and technical support staff.
2.
Licensee Action on Previous Inspection Findings a.
(Closed) Violation (282/88016-01)
'(1) Failure to require as found and as left data for instrument calibration used for local leak rate testing (LLRT). The inspector reviewed Purchase Order No. P00932MQ issued to the Homer R. Dulin Company for calibration of the Brooks flowmeter used for LLRT, and the calibration sheets received following the. calibrations.
Both documents complied with the corrective action stated by the licensee in their letter (C. E. Larson to G. C. Wright) dated December 21, 1988.
This item is considered closed.
(2) Failure to have and use a leakage rate calculation procedure-or computer program (total time method) which included the 95%
upper confidence level.
Shortly after completion of the CILRT the NRC approved the licensee's exemption request to allow the use of the mass point method for which the licensee had the capability to calculate the 95% UCL. This item is considered closed.
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l (3) Failure to ensure valve HC-1-2 was in the correct position for the CILRT. The inspector reviewed Appendix E to SP 2071, Part 4, and determined that the independent verification-checklist has been revised as stated by the licensee in their letter (C. E. Larson to G. C. Wright) dated December 21, 1988.
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This item is considered closed.
. Closed) Violation (282/88016-02; 306/88016-01)
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b.
Failure to perform Type B tests on electrical penetrations since 1983.
The inspector. verified that a procedure (SP 2073-34) to.
perform Type B tests en the electrical penetrations were prepared,
. approved, and used as stated in the letter (C. 'E.
Larson to G. C. Wright) dated December 21, 1988.
This item is, considered closed.
c.
(Closed) Violation (282/88016-03)
Failure to perform required Type B test on Unit 1 personnel airlock on May 26, 1988. By letter (G. C. Wright to C. E. Larsen) dated January 10, 1989, this violation was withdrawn as it had already been issued in Inspection Reports No. 50_-282/88019; 50-306/88019.
However, the inspector reviewed Procedure SP 1132, Revision 11, and SP 2132, Revision 12 and' determined changes were made to prevent-recurrence of the events as noted in the licensees letter (C. E. Larson' to G..C. Wright) dated December 21, 1988.
-This item is considered closed.
d.
(0 pen) Violation (282/88016-04: 306/88016-02)
Failure to Type C test containment spray penetrations 29A and 29B (valves MV-32105 and M P32103, respectively). The licensee is still conducting the analysis to be submitted to NRR as part of their-exemption request.
The submittal is planned for August 1, 1989.
e.
(Closed) Violation (282/88016-05)
Failure to conduct local leak rate tests on penetrations repaired prior to the CILRT at the same pressure as the Type A test (Pt)
is performed. The inspector reviewed local leak rate testing procedure SP 2072, Revision 2 and the flowmeter calibrations and determined that the corrective actions stated in the licensee's letter (C. E. Larson to G. C. Wright) dated December 21, 1988 had been carried out. This item is considered closed.
f.
(Closed) Unresolved Item (282/88016-06)
Failure to perform a local leak rate test (LLRT) prior to adding a packing ring to each of the four airlock shaft seals during an outage for which a Type A test was scheduled. The inspector reviewed the sequence in which the licensee's actions took place
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and has determined-that failure to perform an airlock LLRT at the start of the refueling outage prevented the determination of the f
actual improvement in. leakage rate prior to the performance of the Type A test._ The use of'the March 1988 "as left" airlock LLRT for the "as found" condition of the airlock in August 1988 is not an -
accepted practice in light of_the fact that during that period of time the airlock was opened at least 10 times, and experience at other sites has shown leakage rate deterioration even in cases where the airlock doors have-not been cycled.
10 CFR Part 50, Appendix J, Paragraph III. A.3.(a) states, in part, that all Type A tests shall
' be t.onducted in accordance with the provisions of the American National Standard N45.4-1972, Leakage Rate Testing of Containment Structures'for Nuclear Reactors, March 16,'1972. ANSI N45.4-1972, Paragraph 4.2 states, in part, that for retesting, an initial record
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proof test shall be conducted at time periods and pressures established by the responsible organization, before any-preparatory repairs are made. To correct past licensee misunderstandings, the NRC issued IE Information Notice 85-71, the NRC restated the requirement to determine the "as found" condition of the containment building during the performance of a Type A test, but allows the performance.of Type B and C tests,.and of repairs to penetrations, prior to the performance of the Type A test provided tests are conducted before and after any repairs or adjustments so that the improvement in leak rate can be added to the Type A test results.
After. shutting down in August 1988, a ring of packing was added to each of the four maintenance airlock shafts seals on September 15, 1988, and the local leak rate and Type A tests were subsequently performed. No tests were performed after the unit shutdown and before the repairs were done to determine _the amount of leakage rate improvement prior to the Type A test. This is a violation (282/89014-01) of 10_CFR 50, Appendix J, Paragraph III.A.3.(a).
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3.
Containment Integrated Leak Rate Test Procedure Review a.
Procedure Review The inspector reviewed the latest revision of Procedure SP 2071,
" Containment Integrated Leak Rate Test" relative to the requirements of 10 CFR Part 50, Appendix J, ANSI N45.5-1972, and the Technical Specifications. All the inspector's comments were satisfactorily resolved.
b.
Clarifications of Appendix J Requirements The following clarifications, previously given to the licensee, were reviewed during the course of the inspection.
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(1). The Type A test length must be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or longer to use the mass point method of data reduction.
If tests of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are planned, the Bechtel Topical Report, BN-TOP-1, must.
be followed in its entirety except for.any Section which conflicts with Appendix J or Technical Specification requirements.
For either methodology, the, acceptance criteria-is that the measured leakage at the 95% upper confidence limit-must be less than 75% of the maximum allowable leak rate for the pressure at which the test was performed.
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(2). Penetrations which are required to be. Type C tested,.as described in the FSAR and SER, must be vented inside and outside the containment during the CILRT.
All vented penetrations must be drained of water inside the containment and between the penetration valves to ensure exposure of the containment isolation valves to containment air test pressure.
The degree of draining of vented penetration outside of'
containment is controlled by the requirement that the valves l
be subjected to the post-accident differential pressure, or proof that the system was built to stringent quality assurance standards comparable to those required for a seismic system.
(3) Whenever penetration configurations during a CILRT deviate from the ideal, the results of the LLRTs for such penetrations must be added as a penalty to the CILRT results at the 95% confidence level. This penetration leakage penalty is determined using the " minimum pathway leakage" methodology. This methodology.
is defined as the minimum leakage value that can be quantified through a penetration leakage path (e.g., the smallest' leakage
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through two valves in series). This assumes no single ~ active l
failure of redundant leakage barriers. Additionally, any increase in containment sump, fuel pool, reactor water, or suppression pool level during the course of the CILRT must be taken as a penalty to the CILRT results.
If penalties exist, they must be added (subtraction is never permitted)
to the upper confidence level of the CILRT results.
No violations or deviations were identified.
4.
Containment Integrated Leak Rate Test Witnessing a.
The inspector reviewed the calibration data and determined all the instruments used in the CILRT had been properly calibrated and that the correct weighting factors had been placed in the computer program as required. The following instrumentation was used throughout the the test:
Type Quantity RTDs
Humidity
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Pressure gauges
'2 Clowmeter
b.
Temperature Survey
'The inspector witnesse'd the temperature / humidity survey. performed with all ventilation fans off~on April 18, 1989.
Several readings were taken the subvolume to be represented by each sensor, with the exception of those in the upper dome area. 'The readings showed very small, if.any, temperature gradient throughout each subvolume. The-inspector has no concerns regarding the performance of a Type A test.
with all fans off and the sensors as positioned.for this test.
c.
Witness of Test-The inspector witnessed portions of the CILRT on April 20, 1989, and noted that test prerequisites were met and that the appropriate revision to the surveillance procedure was followed by test personnel.
Valve 1ineup for the following systems were verified correct'except as noted,'to insure that no fluid could enter the containment atmosphere and that proper venting and draining was provided.
Penetration P-2, Pressurizer Relieve Tank Nitrogen Supply P-11',; Letdown Line P-19, Service Air Supply P-20, Instrument Air Supply P-25A, Containment Air Purge Suoply P-26, Sump A Discharge P-31, Nitrogen to No, 21 and 22 Accumulator P-42A, Hydrogen Control Vent to Shield Building P-42E, Steam Heating Condensate Return P-45, Reactor Water Makeup to PRT P-50, Hydrogen Control Vent to Shield Building P-50, Hydrogen Control Instrument Air to Containment P-54, Steam Heating Supply P-55, Demineralized Water to Hose Connections In addition, all accumulators inside containment were verified to be depressurized and that all gas bottles had been removed l
from containment.
During the inspector's.walkdown, valve MV-32245 (Penetration No. 26)
was found in the closed position. According to the valve lineup the valve was to be open in order to provide a vent path thru valve 2WL-36-7. A review of the CILRT procedure valve lineup
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and valve verification sheets showed the operators had signed ~
- on 4/20/89 indicating ~the valve was open. The investigation
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(1) Vent valve 2WL-36-7 was physically upstream of valve MV-32245, therefore, the incorrect positioning of MV-32245 had no effect on the CILRT.
(2) The CILRT procedure drawing and the controlled copy of P&ID NF-39248 in the control room were incorrect.
Both showed valve 2WL-36-7 downstream of valve MV-32245.
(3) The operators had used the control room Waste Disposal Containment Isolation valve position display panel to verify the valve position. The windows for valves MV-32244 and MV-32245 had been switched giving the erroneous indication that MV-32245 was open when in fact the valve was closed.
The Unit I containment isolation valve position display windows were correct.
(4) A review of the station Optimal Recovery Procedure, IE-0,
" Reactor Trip on Safety Injection," Step 5 calls for the operators to verify that the containment isolation lights are lit. As a result, the swapping of the two windows would have had no effect during an accident, since the required action was to look for the windows to be lit (isolation had taken place)
regardless of the specific valve window position.
As corrective action the licensee will update the CILRT procedure and the control copies of P&ID NF-39248. A Drawing Revision Request, DRR No. PI-89-066 was submitted on 4/21/89. The. isolation panel display windows were correctly repositioned. The lack of drawing control and the incorrect position of the valve display panel windows are considered violations of 10 CFR Part 50, Appendix B, Criterion VI and Criterion XIV, respectively. However, since prompt corrective action was taken and both issues had no safety significance, no Notice of Violation is being issued per Section V.A of Appendix C to 10 CFR Part 2.
5.
Test Results Evaluation a.
CILRT Data Evaluation
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A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT was performed during April 20-21, 1989, at 38 psia l
following satisfactory completion of the required temperature stabilization period. Data was collected every five minutes.
The l
inspector independently monitored and evaluated leak rate data using mass point time formulas to verify the licensee's calculations of
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the leak rate and instrument performance.
There was good agreement between the inspector's and licensee's results as indicated by the-following summary (units are in weight percent per day).
r Measurement Licensee (5 min 1 data)
Inspector (10 min data)
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Leak rate measured 0.027 0.027 during CILRT (Ltm)
Lam at upper 95%
0.027 0.028 confidence level Appendix J acceptance criteria at'95% UCL: < 0.75 La or < 0.133-At the completion of the CILRT and the supplemental test, the changes in sump and reactor vessel water levels were calculated.
No correction to the calculated Ltm at the 95% UCL, for volume L
change, was required.
b.
Supplemental Test Data Evaluation After the satisfactory completion of the CILRT a known leakage rate (based on the inspector's independent readings and calculations) of 4.98 scfm, equivalent to 0.212 weight percent per day was induced.
' Data was collected and analyzed by the licensee and inspector every 5 minutes. The inspector independently monitored and evaluated leak rate data to verify the licensee's results. After four hours,:the supplemental test was terminated with satisfactory results as indicated by the following summary (units are in weight percent per day).
The results were stable within the acceptable criteria.
Measurement Licensee Inspector
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Measured leakage rate, 0.249 0.249 Lc, during supplemental test Induced leakage rate, Lo 0.212 0.212 Lc-(Lo + Ltm)
0.010 0.010 Appendix J acceptance criteria: -0.044 5 [Lc-(Lo + Ltm)] $ + 0.044 c.
CILRT Valve Lineup Penalties Due to valve configurations which deviated from the ideal penetration valve lineup requirements for the CILRT, the results of local leak rate tests for such penetrations must be added er a penalty to Ltm at the 95% UCL. The following penalties must be adied using the minimum pathway leakage method:
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Local Leak Rate Test Value j-Penetration (Units are in SCCM)
Primary System Vent Header
13A No. 21 RCP Seal Water Supply
13B No. 22 RCP Seal Water Supply
29A Internal Containment Spray
29B Internal Containment Spray
30A Containment Sump (B) Suction Line 3900 30B Containment Sump (B) Suction Line
TOTAL Type C Leakage Penalty 4050 After taking these local penalties into account, the upper confidence value for containment leakage is equal 0.031 weight percent per day, well within the acceptable value of < 0.133 weight percent per day, d.
As-Found Condition of CILRT The as-found condition is the condition of the containment at the beginning of the outage prior to any repairs or adjustments to the containment boundary. The inspector reviewed the licensee's summary of the containment penetration local leak rate tests (Type B and C)
performed prior to the CILRT in order to determine the amount of leakage rate improvement due to repairs and adjustments.
Based on the results reviewed, it was dete' mined that the amount of leakage r
improvement prior to the CILRT was negligible and amounted to 0.000 wt%/ day.
No violations or deviations were identified.
6.
Review of Local Leak Rate Testing (Type B and C) Program a.
Procedure The inspector reviewed surveillance procedure SP 2072, Retision 2,
" Local Leak Rate Test of Containment Penetrations," relative to the requirements of 10 CFR 50, Appendix J, and the Technical Specifications. The inspector's comments were satisfactorily resolved.
b.
Type B and C Test Pressure The inspector reviewed the licensee's procedure and test practices and the local leak rate tester (LLRT) used to pressurize the penetration and measure its leakage rate.
The penetration test pressure is monitored at the LLRT. According to the licensee, the
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longest length of 3/8" poly tubing used to connect the test equipment to the penetration is 100 ft. The inspector determined that the licensee has no method to ensure the test pressure is maintained at or about Pa (or Pt for measurements on repaired
penetrations required to calculate the as-found Type A test results)
as the penetration leakage rate increases. A review of the Type B and C test results showed the largest leakage measurement being 3900 sccm for which the pressure drop would be < 1 psi.
Since significant leakage could be expected to occur during future local leak rate tests the licensee was requested to modify its procedures and practices to ensure the required pressure is maintained at the.
penetration. This is an Open Item (282/89014-02; 306/89015-01(DRS))
pending review by the inspector of the licensee's corrective action.
No violations or deviations were identified.
7.
Open Items Open items are L. otters which have been discussed with the licensee, which will be reviewed further by the inspector and which involve some action on the part of the NRC or licensee or both. An open item disclosed during the inspection is discussed in Paragraph 6.b.
8.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) on April 21, 1989. The inspector summarized the scope and findings of the inspection. The licensee acknowledged the statements made by the inspector.
The inspector also discussed the likely informational content of the inspection report with regards to documents or processes reviewed by the inspector during the inspection.
The licensee did not identify any such documents / processes as proprietary.
A telephone call was held on April 27, 1989, with Mr. E. Watzi to further discuss the inspection findings.
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