ML20214J212
| ML20214J212 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/13/1986 |
| From: | Gass K, Knightly J, Stewart D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20214H850 | List:
|
| References | |
| SWEC-SQN-17, SWEC-SQN-17-R, SWEC-SQN-17-R00, NUDOCS 8612010208 | |
| Download: ML20214J212 (4) | |
Text
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TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-17 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 TITLE: Containment Leak Rate Test Failure
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REASON FOR REVISION:
SUMMARY
STATEMENT: The item in this report was identified by the Nuclear Regulatory Commission (NRC) and was included in the Stone & Webster Engineering Corporation (SWEC) systematic analysis. The item evaluated within this report was verified to be adequately addressed and was closed by the NRC.
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CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary's signature denotes SRP concurrences are in files.
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Element
Title:
Containment Leak Rate Test Failure i
SWEC Concerns: A02841214003-001 Source Document: NRC Inspection Report 327, 328/84-37 Report Number: SWEC-SQN-17
/6-/0- N Evaluator:
J. J. Knightly '
Date 1 I/=4v to /ro /f 6 Reviewed By:
A. G. Debbige Date' 4/)=fu h
/d [/o[fla Approved By:
R. C. Saue(
Date 1793T
Rsport SWEC-SQN-17 NRC Report 50--327/84-37 and 50-328/84-37 I.
Introduction The Nuclear Regulatory Commission (NRC) conducted a routine inspection November 16-22, 1984 (reference 1), concerning the primary containment integrated leak rate test (type A) on unit 2.
The inspector identified an Inspector Follow-up Item (IFI) which was included in the Stone &
Webster Engineering Corporation (SWEC) systematic analysis:
A02841214003 - Containment Leak Rate Test Failure Information on the background, corrective actions taken, verification methodology and analysis, completion status, and any pertinent references for this item is included in this report.
II.
Verification of Item A02841214003 A.
Background
The NRC stated that evaluation of the leak rate data showed that containment leakage was within acceptable limits. However, to achieve an acceptable test it was necessary for Sequoyah Nuclear plant (SQN) to repair leakago paths during the local leak rate i
testing performed prior to the type A test and after reaching test pressure during the type A test.
Because of this lack of leakage repairs, the test was to be defined as a failed test. The NRC follow-up inspection was under IFI 328/84-37-01 B.
Corrective Actions Taken Ouring the inspection SQN stated that repairs would be accomplished ard a test would be rescheduled.
C.
Verifications Methodology g
The SWEC concern identified for Employee Concerns Task Group (ECTG) verification was stated as follows:
1 RIMS Number Issue RIMS Item i
f A02841214003 Containment leak rate test had failed, RINS-001
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but apparently was not recognized as a 3
failed test by TVA.
NRC identified problem. New test scheduled.
1 ECTG reviewed the SQN Compliance Licensing files for internal and j
external correspondence related to this issue.
Discussions were j
conducted with SQN Compliance and Nuclear Engineering personnel.
D The documentation review and discussions formed the basis for this verification activity.
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D.
~Vnrificrtion Analysis EC1G verified that NRC closed the followup item in their January 1986 inspectioa report (reference 2).
Leakage through the packing of two instrument isolation valves was corrected.
Since the nature of the test failure was minor, SQN and NRC agreed to maintain the normal 40 + 10-month type A test schedule.
It was agreed that it was not necessary to repeat the November 1984 test because the initial leak rate was within the test limits.
E.
Completion Status Based on SQN compliance with requirements and NRC closure of this issue, no further action is required. This SWEC item is closed.
l III.
References
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1.
NRC Report 50-327/328/84-37, dated December 12, 1984, D. M.
Verrelli to H. G. Parris 6
2.
NRC Report 50-327/328/85-44, dated January 14, 1986, D. M. Verrelli to H. G. Parris f
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