JAFP-85-0675, Forwards Primary Containment Integrated Leak Rate Test Schedule,Per 10CFR50 App J.Basis for Improved Leakage Performance of Containment & Isolation Valves Encl.Reasons for Continued Improvement Listed

Forwards Primary Containment Integrated Leak Rate Test Schedule,Per 10CFR50 App J.Basis for Improved Leakage Performance of Containment & Isolation Valves Encl.Reasons for Continued Improvement Listed

ML20212L185
Person / Time
Site:	FitzPatrick
Issue date:	01/21/1987
From:	Radford Converse POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
JAFP-85-0675, JAFP-85-675, NUDOCS 8701290356
Download: ML20212L185 (5)

Text

'

James A. Fit: Patrick Nuclear Power Plant PO. Box 41 Lycormng. New York 13093 315 342.3840 Radford J. Converse

1. > NewYorkPbwer 4# Authority January 21, 1987 JAFP 0075 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION:

DOCUMENT CONTROL DESK

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 PRIMARY CONTAINMENT INTEGRATED LEAK RATE TEST SCHEDULE

Reference:

(1)

NYPA letter, R. J. Converse to Director of Nuclear Reactor Regulation, dated August 21, 1985 (JAFP-85-0675)

Dear Sir:

Reference (1) reported the results of the primary containment integrated leak rate test which was conducted during FitzPatrick's Reload 6/ Cycle 7 refueling outage in 1985.

10CFR50, Appendix J, Paragraph III.A.6.(a) requires identification and reporting of our proposed schedule of future Type A tests.

This schedule is described in Section IV of the enclosure.

Section III of the enclosure provides the basis that containment and isolation valve leakage performance has improved and that further improvement can be expected.

This is the result of 1) improved valve maintenance procedures and training, 2) use of train'ed plant personnel to perform repair activities rather than depending on contractors 3) valve modifications, 4) purchase of maintenance tools for the Main Steam Isolation Valves, and 5) removal and/or replacement of some problem isolation valves.

Further valve improvement modifications are planned.

This provides the basis as to why the Type A retest schedule described, together with the normal Type B and C (LLRT) test schedule, will provide adequate assurance of an essentially leak tight containment system.

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United States Nuclear Regulatory Commission

' January 21 1987-Attention':. Director'of Nuclear '

JAFP 87- 0075 Reactor-Regulation Page 2 of~2

SUBJECT:

PRIMARY CONTAINMENT INTEGRATED LEAK RATE TEST SCHEDULE

' If.you>

ve y questions, please contact Mr. P.-Swinburne of my staff.

1. W RA OWD

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RESIDENT MANAGER

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RJC FGU2maa Enclosure b

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.W. Fernandez-R.HBaker D.-Lindsey H. Keith

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'A. Luptak J. Linville:(NRC Region I)-

J.':Golla (NRC Region I)

J. Gray (WPO)-

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ATTACHMENT I TO JAFP 0075 I.

INTRODUCTION The results of the 1985 primary containment integrated leak rate test (PCILRT), along with the results of the 1983 and 1985 local leak rate testing was submitted to the NRC in Reference 1.

These reports indicate that the FitzPatrick containment may not have met the "as found" criterion as stated in the subsequently issued I.E.

-Information Notice (Reference 2).

This attachment summarizes the 1985 PCILRT program, programatic improvements to the FitzPatrick containment, and proposes a schedule for performing future PCILRT tests.

II.

1985 LEAK RATE TEST

SUMMARY

The report submitted with Reference 1 included a Local Leak Rate Test Summary Analysis as an attachment.

This Summary Analysis evaluated the "as found" containment leakage condition using the Local Leak Rate Test (LLRT) data and the minimum pathway leakage method.

This was provided due to a request of the Regional Inspector (Inspection Report No. 50-333/85-08).

The method used was essentially the same as provided by the subsequently issued I.E. Information Notice No. 85-71.

The results of this analysis indicated that the "as found" leakage may have exceeded the currently used plant test leakage rate limit of 0.5 percent / day.

It should be noted that the original FSAR supplement 25, Question 5.10 indicates a containment leakage limit of La = 1.5%/ day.

This value was used for the FSAR offsite dose analysis to ensure that 10 CFR 100 limits were met.

However, this value has not been used for the preoperational or periodic Type A tests because of more restrictive Technical Specification requirements.

The Type A test "as found" results were inconclusive because of limitations on the range of d e LLRT equipment and the requirement to test between certain cont. ament isolation valves.

In these cases, the measured leak rate was the total for both isolation valves.

During the 1985 refueling outage, in two cases, valves that had leakage which measured "offscale" in this type of combined test were both repaired prior to retesting.

Thus it was impossible to determine the minimum pathway leakage, since it could not be determined if either valve had an acceptable leukage rate.

These tests and subsequent repairs were done prior to Inspection 85-08 and prior to issuance of I. E. Notice 85-71.

The personnel performing LLRT testing were therefore unaware that single valve repair and retesting should have been done in order to more accurately evaluate the "as found" leakage condition.

Future LLRT generated repairs and retesting will be done on a valve-by-valve basis to help in determining the minimum pathway "as found" leakage as best as possible.

Additionally, high range LLRT equipment will be obtained to allow measurement to the 0.5

)

ercent/ day limit (5360 SCFD).

This should reduce the number of p'as found" Type C test leakages beyond the range of the LLRT test equipment.

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III.

PROGRAMMATIC IMPROVEMENTS IN CONTAINMENT ISOLATION VALVE TESTING AND MAINTENANCE Local Leakage Rate Testing (LLRT-Type B & C) of containment penetrations and isolation valves has been performed during each refueling outage and as otherwise required since initial plant operation.

This testing has been performed in accordance with 10 CFR 50 Appendix J and applicable plant Technical Specifications.

Plant management has been concerned with failures discovered during LLRT's and the effectiveness of the resulting repairs.

Several important steps were taken to improve valve maintenance methods.

A special Rockwell Main Steam Isolation Valve (MSIV) seat machining tool was purchased along with the l

associated plant maintenance personnel training.

This has l

improved the plant's ability to maintain the MSIV's as essentially leak tight barriers.

MSIV LLRT failures have been l

reduced from 4 and 6 in 1977 and 1978, respectively, to 2 in 1983 and 1 in 1985.

In addition, an upgraded valve maintenance and repair program for other containment isolation valves was initiated in 1980.

This program included training provided by a j

valve maintenance specialist (Atlantic Valve Co.).

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The NRC has indicated in I. E. Information Notice 85-71 that there l

is increased concern about the "as found" containment leakage i

condition.

Determination of the minimum pathway leakage improvement, as a result of repairs and adjustments made for Type B & C (LLRT) testing, is necessary for determining the "as found" containment leakage condition.

In the past this determination has j

been difficult at FitzPatrick for two reasons: 1) the low range f

of the LLRT equipment (1018 SCFD maximum) and 2) the many j

containment isolation valves that are tested together, with the l

inboard valve tested in the reverse direction.

To improve the l

ability to determine a more accurate "as found" value, FitzPatrick i

is obtaining higher range LLRT equipment so that fewer offscale results will occur.

Additionally, a commitment has been made to J

do individual valve repair and retesting where a Type C test indicates excessive or offscale leakage through multiple isolation valves.

l Several modifications have been performed or are planned for many j

of the containment isolation valves that have had problems with "as found" leakage.

For example, penetration X-36, the CRD return line, was cut and capped, removing valves CRD-113 and CRD-110.

Also, valves 27-SOV-123 A&B were removed from penetration X-59.

Future planned modifications include adding solenoid operated valves (SOV's) for the recirculation pump seal " mini-purge" penetre.tions X-31Ac and X-31Bc and replacement of tbc Atkomatic S0V's used on the containment atmosphere sampling system with more reliable Target Rock SOV's.

The FitzPatrick plant staff has recognized the problems associated with containment isolation valve leakage.

Action has been taken and is currently planned in the areas of maintenance, design and testing of containment penetrations to improve the containment system leakage performance and to provide a better evaluacion of that performance.

- ~

e IV.

PROPOSED TEST SCHEDULE The Authority plans-to perform the next scheduled test prior to the startup from the Reload 8/ Cycle 9 refueling outage, presently scheduled for the fall of 1988.

This test will be the first in the second set of three Type A tests which must be performed during'each ten year service period.

It will be approximately 3 1/2 years from the test conducted at the end of the first 10 years service period and approximately 7~ years prior to the end of the second 10 year service period.

V.

REFERENCES 1)

NYPA Letter, R. J. Converse to Director of Nuclear Regulation, dated August 21, 1985 (JAFP-85-0675).

2)

I.E. Information Notice 85-71, Containment Integrated Leak Rate Tests, dated August 22, 1985.

3)

Code ~of Federal Regulations,.10 CFR part 50, Appendix J, Primary Reactor Containment Leakage Testing ~for Water-Cooled Power Reactors 3

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