ML20197A929

From kanterella
Jump to navigation Jump to search
Commits to Snubber Sampling Plan Discussed in Tech Spec 4.7.9.e.(3) for First Refueling Outage.Snubbers within Surveillance Sample Will Be Functionally Bench Tested
ML20197A929
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 10/17/1986
From: Allen C
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
2268K, NUDOCS 8610270424
Download: ML20197A929 (2)


Text

\\gggggg b

Mb

)

/

/ One First National Plaza. Chicago, Illinois z

g\\

m.

^

\\

j Address Reply to: Post Office Box 767 N# Chicago, Illinois 60690 - 0767

, PRIORITY ROUTING October 17, 1986 f ust sng h

?

r

""C" M 6?

1415 3 OL_

DRMA OL-

-PA0 Mr. James G. Keppler FILEha Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

LaSalle County Station Unit 2 Technical Specification Snubber Surveillance plan NRC Docket No. 50-374

Dear Mr. Keppler:

The LaSalle Technical Specification 4.7.9.e for snubbers offers three sample selection plans for functional surveillance testing'.

It also requires the Station to notify the NRC Regional Administrator of which of the three plans it will use prior to the first refueling outage, and prior to any future surveillances where the choice is to be changed.

LaSalle Station commits to the snubber sampling plan given in Technical Specification 4.7.9.e.(3) for the Unit 2 first refueling nutage.

The plan requires a initial sample of 55 snubbers of each type to be tested, and a total test sample size (N) of 55 (1 + c/2) of each type, where c is the number of snubbers not meeting test acceptance criterion.

The following conditions will be imposed on the snubber functional testing on Unit 2 at the first refuel outage;

1) The Station will consider the snubbers of all sizes on the Residual Heat Removal (RHR) A, B, and C loops as one type of unit for this surveillance, and is committing to test 100% of these snubbers at first refuel. This commitment is based on concerns raised by the results of the Unit 1 first refuel surveillance, where significant numbers of failures were found on the RHR loops.

Test failures on the RHR loops shall not result in an increased test sample size for the second group of snubbers being selected covering the remaining plant systems. Technical justifiction of this group selection is based on the uniqueness of the RHR system with its multiple modes of operation. The operating environment of these snubbers is such that the causes of failure for these snubbers are generally different from those on other systems.

8610270424 861017 DR ADOCK 0500 4

00T 2 01986 fft) 1 Ed/

v Mr. J. G. Keppler October 17, 1986

2) The snubbers on all other systems will initially be considered as a second group for the surveillance at first refuel, and will be tested per the sample plan referenced above. The Station may elect to split the second group of snubbers into two types, consisting of just Pacific Scientific PSA 1/4 and 1/2 sizes in one group, and the remaining larger Pacific Scientific sizes in a second group.

Initial test results will be reviewed to determine if this split is i

necessary and technically justified prior to its implementation.

In the case this option is selected, both resulting groups will meet the 55 (1 + c/2) sample size restriction per T.S. 4.7.9.e.(3).

3) Snubber reduction will be performed in parallel with this surveillance at Unit 2 first refuel. Snubbers removed under the reduction program which are outside of the surveillance test samples will be manually stroked to verify freedom of movement.

Should a snubber fail the stroke test, the Station will either bench test the unit to verify its operability, or declare it inoperable and perform the failure evaluations required in Technical Specification 4.7.9.g.

Snubbers within the surveillance sample, which are removed by snubber reduction will be treated the same as snubbers which remain installed, and will be functionally bench tested Please direct any questions you may have regarding this matter to this office.

Very truly yours, a

C. M. Allen Nuclear Licensing Administrator 1m Attachment cc:

Dr. A. Bournia - NRR Resident Inspector - LSCS 2268K

--