IR 05000281/1980001
| ML18139A215 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/18/1980 |
| From: | Brooks E, Moon B, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139A214 | List: |
| References | |
| 50-281-80-01, 50-281-80-1, NUDOCS 8005120280 | |
| Download: ML18139A215 (4) | |
Text
--*-- --------
t. ;.
i:
'
I
I*
- I ;
\\
e e
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
Report No. 50-281/80-01 101 MARIETTA ST.* N.W.* SUITE 3100 ATLANTA, GEORGIA 30303 Lic~nsee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility: Surry Nuclear Plant
/
Docket No. 50-281 License No. DPR-37 Inspection at Surry Site near Williamsburg, Virginia Inspectors: *<d L:: u)~ JL)
.
E. H. Brooks. l dj,d;-}n~
B. T. Moon
SUMMARY Inspection on February 19-22 and* 26-28, 1980 Areas Inspected i l'
This r~utine, Jnnounce, inspection involved 90 inspector-hours areas of containment integrated leakage rate testin Results nate Signed 3/1eleo Date ~igned on site in the Of the areas.inspected, *no items of noncompliance or.d~viat°ions were identifie ~--~~-----* ---~-~----
.
--
-~~~------------ *-
/
~..... ___.... _.. ~.. **-- *---*~-...,-....-._~ ----**-*---4-
-* *-****,. --* *-. --***-*-*.,- __.., **-*--
,-*
e e
DETAILS Persons Contacted Licensee Employees
- J. Wilson, Operations Superintendent
- R. Blount, Test Coordinator M *.. Kansler, Associate Engineer Other Organizations Stone and Webster B. Kuechler R. Parry C. Morrell R. Bernier H. Kunnel S. Frank NRC Resident Inspector D. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on February 28, 1980, with those persons indicated in paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items
. F -,.
Unresolved items were not identified during this inspectio.
Containment Integrated Leakage Rate Testing During the period of February 19-22, the inspectors conducted the following reviews and inspections: Reviewed Periodic Test No. 16.3 - Containment Leakage Rate Test (Type A at 45 psig) Revised 2-6-8 Inspected installation of compressors and preparations for containment" pressuriza~io *
--~--=-~-~~~--=-==--=---=**=-=-=--=--=-=-=--~--=--~-~--=-~--=--~--~--=--,--,~,-,---,---,--,-,--:c-c--c----::--~~-
--~-
- ..
.... **
/
e e-2-Confirmed removal of all pressure sources from the containmen Confirmed that the reactor coolant system was adequately vented-to the containment atmosphere prior to the start ~f the tes Reviewed containment integrated leakage rate test (Type A) instrument calibration records and verified that the instruments are in calibration according to the available certification which are traceable to the National Bureau of Standards (NBS).
The infiltrument calibrations reviewed were:
Instrument Quartz Manometers (Calibrated by Mensor)
Air Flow Meter (Calibrated by Singer)
Thermoelectric Dew-
.Point Hygrometer (Calibrated by NBS)
Containment Tem RTD Sensors (Calibrated by Rosemont)
Containment Dewpoint Sensors (Calibrated by Rosemont)
Identification S/N 414 S/N 416 S/N 1280 S/N 587 l-AL2300TC General Eastern Instruments, Models 1200APS, S/N 92472, PRT S/N 13975 LM 200-1 LM 200-2 LM 200-3 LM 200-7 LM 200-16 LM 200-18
- No. 6 No. 7 No. 8 No. 9 No. 10 Calibration Date 12/18/79 12/18/79 12/18/79 12/18/79 1/8/80 9/6/79 2/8/80 2/8/80 2/8/80 2/9/80 2/10/80 2/10/80 2/11/80
- 2/11/80 2/11/80 2/11/80-2/11/80 The inspector* also verified that the data-,.acquisition of RTD inputs
f
'
was accomplished by an analog-to-digital conversion which has about 13 bit resolution and is capable of measuring to an accuracy of better than 0.1° Initiation of the containment integrated leakage rate test was delayed due to additional maintenance required during reinstallation of the equipment hatch cover and emergency air lock doors. Containment test pressure (45 psig) was reached on February.27 and the _containment atmol;lphere was permitted to stabilize at approximately 46 to 47 psig for a minimum of 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> The inspectors reviewed documentation of valve alignment and verification by the licensee's quality assurance personne Calculation of containment leakage rate using the mass -*
point analysis and total time analysis commenced at about 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />
/.
e-3-on February 2 The acceptance criteria established by the licensee is stated as the leakage rate upper confidence limit (UCL) plus local leakage measurements (type Band C) shall be less than 0.75 La or 0.075% per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> The local leakage measurements to be added were stated by the licensee to be 0.01236% per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> As the leakage rate test progressed, it became necessary for the licensee to dispatch survey crews to search for and identify leaks and to isolate or adjust components to reduce the measured leakage rat The following valve isolations or adjustments were made:
Tightened valve packing - MOV-CS-201A MOV-.CS-201B MOV-RS-256A Closed valves - 1-CV-1 2-cv-20 2.;..CV-26 Results of the above actions did not reduce containment calculated leakage to a level sufficient to meet the acceptance criteria. Therefore, at 0400 on February 28, it was determined to terminate the test and depressurize the containmen The licensee concluded that additional local testing and corrective action would be required prior to repeating the containment integrated leakage rate tes '
,r