IR 05000280/1981019
| ML18139B477 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/16/1981 |
| From: | Brooks E, Burnett P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139B476 | List: |
| References | |
| 50-280-81-19, 50-281-81-20, NUDOCS 8108110103 | |
| Download: ML18139B477 (5) | |
Text
e UNITED STATES e
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 JUL t 71981 Report Nos. 50-280/81-19 and 50-281/81-20 Licensee:
Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name:
Surry 1 and 2 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Inspection at Surry site near Williamsburg, VA Inspector:~~
E. H. Brooks Approved by: '"'fL "L._ {A J ~
~ t:/if; P. T. Burnett, Acting Sec~on C~ef Engineering Inspection Branch Division of Engineering and Technical Inspection SUMMARY Inspection on June 22-27, 1981 Areas Inspected 7-/&, -SI Date Signed 7-16- ?I Date Signed This routine, unannounced inspection involved 44 inspector-hours onsite in the areas of containment integrated leakage rate testin Results Within the scope of this inspection, no violations or deviations were identified.
-s1os110103 810717 -
PDR ADOCK 05000280 Q
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REPORT DETAILS Persons Contacted Licensee Employees
- J. Wilson, Plant Manager
- D. Christian, Superintendent Technical Services R. Blount, Test Director M. Kansler, Associate Engineer Other Organizations Stone and Webster R. Parry H. Kun ke 1 NRC Resident Inspector D. Burke M. Davis
- Attended exit interview Exit Interview The inspection scope and findings were summarized on June 27, 1981 with those persons indicated in paragraph 1 abov.
Licensee Action on Previous Inspection Findings Unresolved item (281/80-39-01): The ILRT report for Unit 2 does not contain as-found and as-left leakage results for type Band C tests performed since the last type A test. Also certain minor inaccuracies on page 3-9 of the report require correction. The ILRT report did not contain enough informa-tion relative to leakage rates and leak locations to determine if the two
. failed attempts to perform a Type A test were a result of leakage in new systems or represent a failed ILR The licensee stated that this information would be assembled, evaluated and incorporated into the ILRT report and submitted to the Commission by August 15, 198 Unresolved item (281/80-39-02):
The local leak rate test program is incom-plet Procedures PT-16.3A and PT-16.3B specify certain flanges and valves to be tested only prior to Type A (ILRT) tests (i.e. at greater than 3 year i nterna 1 s).
Appendix J re qui res that l oca 1 leakage rate testing be per-formed *at each refueling outage (not to exceed 24 months).
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The licensee stated that the local leak rate test program will be re-eval-uated and the results of the re-evaluation will be submitted to the Commis-sion by August 15, 198.
Unresolved Items Unresolved items ware not identified during this inspectio.
Containment Integrated Leakage Rate Testing (CILRT)
The following procedures relating to leakage rate testing were provided by the licensee and were reviewed by the inspector:
l-PT-1 l-PT-1 l-PT-16.3A l-PT-16.3B 1-PT-1 l-PT-1 Containment Leakage Monitoring System Containment Penetration Local Leakage Fuel Transfer Flange Local Leakage Containment Isolation Valve Leakage (Prior to Type A Test)
Containment Isolation Valve Leakage (At Periodic Intervals)
Reactor Containment Building Integrated Leak Rate Test (Type A at 59.7 PSIA)
The licensee was advised that procedure l-PT-16.3B and 1-PT-16.4 are still the subject of unresolved item 281/80-39-02 (refer to section 5., above).
The licensee confirmed that all isolation valves listed in these procedures have been locally leak tested prior to initiation of the Type A test on Unit During the period from June 22-27, the inspector conducted the following reviews and inspections: Inspected installation of compressors and preparations for containment pressurizatio, Confirmed removal of all pressure sources from the containmen Confirmed that the reactor coolant system was adequately vented to the containment prior to start of the tes Reviewed containment integrated leakage rate test (type A) instrument calibration records and verified that all instruments have been cali-brated within the last 6 months to standards traceable to the National Bureau of Standards (NBS).
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3 Reviewed plant systems lineups in preparation for the CILRT to confirm compliance with Appendix Jin regard to venting and draining require-ment Reviewed valve lineup checklists for proper valve positioning and sign-of Containment pressurization was initiated at 1837 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.989785e-4 months <br /> on June 25 and a pressure of 61.483 psia was achieved at 0543 hours0.00628 days <br />0.151 hours <br />8.978175e-4 weeks <br />2.066115e-4 months <br /> on June 26 at which time the compressors were stopped and i so 1 ated from the containmen Whi 1 e attempting to achieve containment stabilization, a survey crew discovered two recirculation spray isolation valves located outside containment in the open po.sition with power to the valve operator in the 11on 11 positio The valve lineup checklist indicated that the 2 valves had been closed with power 11off 11 as re qui red for the CI LR As a result, the reci rcul at ion spray system outside containment was subjected to containment test pressure, and a small leak was found to exist in the recirculation spray pump flang The situation was identified to the inspector, and the cause of improper valve positioning resulted from failure of procedure control, i.e., the valves had been closed tn preparation for the CILRT, but reopened by other personnel while performing a different procedur *
The licensee advised the inspector that the appropriate procedures would be revised to emphasize that no valve manipulations are permitted without approval during the CILR It was agreed to continue the CILRT with the recirculation spray system pressurized since this arrangement is considered to be more conservative from a leak test standpoin After achieving containment stabilization at 60.7 psia the CILRT was initi-ated at 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> on 6-26-81 and continued for a period of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> During the test several aberrations were observed in the computer printout of the test result The source of the aberrations was determined to be caused by fluctuations in several resistance temperature detectors (RTD 1s)
due to electrical arcing across a cold solder joint at the RTD power supply bus. After repair of the soldered joint; it was concluded that the contain-ment atmosphere had not become unstabilized and the CILRT was continue Based on the absolute test method, mass-point analysis, the leakage rates and acceptance criteria are as follows:
Calculated Leakage Rate Upper 95% Confidence Level Maximum Allowable Leakage Rate 75% of Maximum Allowable Leakage Rate 0.032%/day 0.035%/day 0.1%/day 0.075%/day
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The acceptance criteria for the CILRT requires that the upper bound of the leakage rate calculated at 95% confidence level pl us any re qui red local leakage rate additions shall be less than 75% of maximum allowable leakage rat Local leakage measured by type 11 8 11 and type 11 (1 1 testing prior to the type A test was 4.6 SCFH or 0.0015%/day. Accordingly, 0.035%/day +0.0015%/day does not exceed 0.075% day and is therefore acceptabl The results of the CILRT including the adjustments for local leakage rate testing will be submitted in a test report to the Commission.