ML20140B386
| ML20140B386 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 09/09/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-81-93, NUDOCS 8109140166 | |
| Download: ML20140B386 (6) | |
Text
SNUPPS Stenderdized Nuclear Unit Power Plant System s choke cherry Road Nicholas A. Petrick Rockville, Maryland 2005o Executive Director (301)8694010 September 9,1981 SLNRC 81-93 FILE: 0541 SUBJ: Containment Leakage Testing Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket Nos.: STN 50-482, STN 50-483, and STN 50-486
Dear Mr. Denton:
In discussions with Dr. Gordon Edison, NRC P:oject Manager for the SNUPPS applications, it was determined that the Containment Systems Branch required additional information in order to complete their review of the SNUPPS FSAR.
The enclosure to this letter provides the requested information and will be included in the next revision to the SNUPPS FSAR.
I Very truly yours,
-kM \\c{
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Nicholas A. Petrick l
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Enclosures:
FSAR pp 6.2.6-2, -2a,
-3,
-4, and -4a cc:
J._K. Bryan, UE
@ SEP 111981
- d l 7
\\y vs, m.incomen G. L. Koester, KGE
'd D. T. McPhee, KCPL W. A. Hansen, NRC/ Cal Id h'
/A T. E. Vandel, NRC/WC D. F. Schnell, UE FG
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8109140166 810909 l
PDR ADOCK 05000482 l
A PDR
I, SNUPPS E
position by the normal method with no accompanying adjustment.
Normal and accident positions for each isolation valve are shown on F'gure 6.2.4-1.
I Systems which are isolated following a LOCA must be properly 1, or vented to reflect their worst potential isolated, drair that the Type.A test results accurately reflect J
status to assur, the most restrictive LOCA conditions.
h Portions of the fluid systems that are part of the reactor coolant f
pressure boundary and are open indirectly to the containment therefore, an atmosphere due to th e accident conditions and are, extension of the boundary of the containment are opened or vented to the containment atmosphere prior to and during the test.
Figure 6.2.4-1 contains the applicable GDC or othe;- defined criteria for the isolation valve arrangements provided.
Portions of the closed systems inside the containment that pene-trate the containment and might rupture as a result of a LOCA are All vented systems are vented to the containment atmosphere.
drained of water or other fluids to the extent necessary to assure the exposure of the system containment isolation valves to the containment air test pressure and to assure that they will be Systems subjected to the post-accident differential pressure.
that are required to maintain the plant in a safe condition r
such as the essential service water lines to the during the test, are operable in their normal mode and containment air coolers, However, the containment isolation valves need not be vented.
are tested in accordance with Type C test requirements.
Systems that are normally filled with water and operating under s the ECCS lines and containment post-accident conditions, r The containment isolation spray system lines, are nc
..e d.
oe closed if the associated subsystem valves in these systems willNormally a water seal will be present inside is not operating.
Should the inner isolation valve during the long-term period.
operational leakage exist outside the containment and the isola-the containment sump water level (Elevation tion valves leak, will ensure that the water in the piping system will 2003'-10")
provide a water seal on the outside containment isolation valves These water which are located at Elevations 2002'-0" and ~1993'.
seals will ensure that containment air will not leak into the test connections are provided to allow l
- Also, auxiliary building.Theca penetrations are identified in Section leakage testing.
6.2.6.3 and Figure 6.2.4-1.
The steam generator tubes and shell and the associated piping systems passing through the containment liner are considered to Therefore, the secondary be an extension of the containment.
side of the steam generator and connecting systems are not vented After the containment stabiliza-to the containment atmosphere.
the secondary side of the steam tion period of the Type A test, l
generators will be vented outside of the containment to ensure I
the most conservative test configuration.
The systems Rev. 7 9/81 6.2.6-2 L
m-
SNUPPS associated with the secondary side of the steam generator are identified in Figure 6.2.4-1.
Pressurized gas and water systems arc vented downstream of the outside isolation valve for the system and vented outside of the containment.
This ia done to preclude inleakage into the contain-ment and to expose the outside isolation valve to a conservatively low back pressure to obtain l'eakage characteristics.
The reactor coolant drain tank, pressurizer relief tank, and accumulator tanks are vented to the containment atmosphere.
This i
Rev. 6 6,2.6-2a 8/81
SNUPPS is done to protect the tanks from the external pressure of the test and to preclude leakage to or from the tanks which would detract from the accuracy of the test results.
During preoperational testing, a structural integrity test (SIT) is performed in conjunction with the first ILRT.
The SIT is a pressure test conducted to verify that the containment structural response due to the induced load is consistent with the predicted behavior.
Section 3.8.1.7 describes the SIT deflection measure-ments and concrete crack inspections.
Following the preoperational SIT, an ILRT is performed.
6.2.6.1.2 ILRT Test Method The ILRT will be conducted in accordance with ANS N45.4.
The test procedure used during the Type A tests is described in Chapter 14.0.
Figure 6.2.6-1 shows the test arrangement for a Type A test.
For penetrations which are exempt from Type B or C tests, as noted in Figure 6.2.4-1, the leakage testing require-ment of Appendix J is accomplished by the Type A test.
The absolute test method is used to measure containment leakage.
Containment dry bulb temperature, pressure, and dew point tem-perature are periodically monitored during the test.
These data are analyzed as they are taken so that the leakago rate and its Once statistical significance is known as the test progresses.
the leak rate has been found with sufficient accuracy, a known additional leak is imposed and the measurements are continued, i
giving additional verification of the leakage rate.
Further details, including the accuracy analysis and test duration criteria, are in BN-TOP-1 or in Section 6.2.6 of each Site Addendum.
The following aspects of Type A testiing follow 10 CFR 50, Appendix J guidelines without exception:
Pretest requirements including a general inspection a.
b.
Conduct of tests Acceptance criterion c.
d.
Periodic retest schedule l
Inspection and reporting of test e.
Should an inservice ILRT fail, repairs will be made and a success-ful ILRT conducted prior to leaving ccid shutdown conditions, subject to one exception.
The integrated leakage rate retest after repair will not be required provided that 1) the prerepair e
l ILRT was completed and met the acceptance criteria with accept-able accuracy with tne leaking penetration (s) isolated, 2) before and after repair local leak rate data are available on the Rev. 7 i
9/81 6.2.6-3 l
SNUPPS repaired or adjusted components taken at the test pressura equal to the calculated peak containment pressure following a LOCA, Pa and, 3) the adjusted integrated leakage rate (and its statistical uncertainty) meets the acceptance criteria.
The adjusted leakage rate is determined by adding the postrepair Type C leakage rates for the penetration to the upper 95 percent confidence level of the measured containment leakage rate.
The postrepair leakage rate assigned to a penetration is the maximum amount which could leak through both penetration bar-riers during a Type A test.
The penetration leakage rates are determined as follows:
a.
For barriers tested in series - The penetration leak-age rate is the measured leakage rate of the barrier with the lowest leakage rate.
b.
For penetration barriers tested simultaneously - for penetrations which are tested by pressurizing between the barriers, the penetration leakage rate is 1/2 of the measured leakage rate.
c.
For penetrations which have one or both barriers con-sisting of parallel valves - For parallel valves tested individually, the barrier leakage rate is the sum of the leakage rates.
For parallel valves tested together, the barrier leakage rate is the measured leakage.
The penetration leakage rate is that of the barrier with the icwest leakage rate.
6.2.6.2 Containment Penetra; ion Leakage Rate Tests (Type y Tests)
Each of the following containment penetrations will be tested with a ~.ype B test.
a.
Personnel uccess hatches (refer to Section 3.8.2) b.
Equipment natch (refer to Section 3.8.2) c.
Fuel transfer tube (refer to Section 3.8.2) d.
Electrical penetrations (refer to Section 8.3)
These penetrations are provided with double seal closures and connections to allow for pressurization between the seals.
Each penetration is designed to withstand the calculated peak con-tainment pressure while maintaining its scal.
Equipment and personnel hatches have provisions for test clamps to ensure seating of the internal seal during testing.
l Rev. 7 6.2.6-4 9/81
SNUPPS I
The test pressure for Type B tests is the calculated peak pres-sure for the co.ntainment, Pa.
The combined leakage rate for all Type B and C tests must be less than 0.6 LThe individual leakage rat 8s(maxi leakage rate).
and testing per-formed on the Type B penetration are described in Chapte-16.0.
The test equipment utilized to perform the Type B tests is the same equipment used for Type C tests.
The test equipment is described in Section 6.2.6.3.
The test procedure will be the same as the one used for Type C tests.
Type B tests are performed in accordance with Appendix J to 10 CFR 50, with the fo2Jowing addition and exception:
a.
An additional test method may be used.
This method measures the air flow rate to maintain the test volume at a Jonstant pressure.
b.
The equipment and personnel hatches will be tested at 6-month intervals.
However, when containment integrity is regoired, the door seals for the air locks which have been opened are tested after each opening, except when the air lock is being used for multiple entries, then at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
In any event, the air locks will be tested prior to exceeding a cold shutdown condition.
i Rev. 7 6.2.6-4a 9/81
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