ML20214J224

Rev 0 to TVA Employee Concerns Special Program Rept SWEC-SQN-26, Ncr Disposition for Pressure Transmitter

ML20214J224
Person / Time
Site:	Sequoyah
Issue date:	11/13/1986
From:	Gass K, Knightly J, Russell J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214H850	List: ML20214H848 ML20214H865 ML20214H879 ML20214H927 ML20214H956 ML20214H976 ML20214J008 ML20214J040 ML20214J053 ML20214J064 ML20214J083 ML20214J093 ML20214J101 ML20214J126 ML20214J135 ML20214J144 ML20214J161 ML20214J169 ML20214J180 ML20214J199 ML20214J206 ML20214J212 ML20214J220 ML20214J224 ML20214J231 ML20214J243 ML20214J251 ML20214J261
References
SWEC-SQN-26, SWEC-SQN-26-R, SWEC-SQN-26-R00, NUDOCS 8612010214
Download: ML20214J224 (4)

Text

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TVA EMPLOYEE CONCERNS REPORT NUMBER: SWEC-SQN-26 SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant Element REVISION NUMBER: 0 TITLE: NCR Disposition for Pressure Transmitter i

REASON FOR REVISION: N/A i

f SWEC

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 was verified to be adequately 3

addressed and was closed by the NRC.

PREPARATION

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SRP Secretary's signature denotes SRP concurrences are in files 2242T 8612010214 861117 PDR P

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TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OTHER SITES CEG Element

Title:

NCR Disposition for Pressure Transmitter SWEC Concerns: A02850402002-001 Source Document: NRC Memorandum March 26.1985 Report Number: SWEC-SQN-26 l

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Evaluator:  % b ~

18!/f!#8 J. J. Knightly Date Reviewed By: [ [ d f,, a /o-r- 96 K. R. Gass Date 9

Approved By: Me to //(, / f 6 i A.G. Debbag6 Ddte '

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Report SWCC-SQN-26 NRC Memorandum March 26, 1985 I. Introduction During a Nuclear Regulatory Commission'(NRC) staff meeting with TVA hold on March 25, 1985, concerning the topic of NRC and TVA communications, NRC identified (reference A) a concern which was included in the Stone & Webster Engineering Corporation (SWEC) systematic _ analysis:

A02850401002-001 - Disposition of Nuclear Regulatory Commission (NRC) on Pressure Instrument Which Was Unsafe 1 Information on the background, the corrective actions taken, the

, verification methodology and analysis, the completion status, and any i pertinent references for this item is included in the report.

II. Verification of SWEC Issue

A. Background NRC expressed concern that they had not been previously notified of a safety issue concerning disposition of an NCR for units 1 and 2 containment pressure transmitters at Sequoyah Nuclear Plant (SQN).

! The NCR had stated that the plant was unsafe to operate. NRC read of the issue in the newspaper and expressed concern to TVA that NRC j had not been immediately notified. TVA explained at the meeting 4

that the NCR had been withdrawn for revision and that there were still some unanswered questions on the matter which TVA was investigating.

l-R. Corrective Actions Taken The resolution status of the pressure transmitter NCR was summarized in NRC inspection report 327,328/85-10 dated May 31,1985 i' (reference B). This report summarizes the basis for NRC's j determination that no immediate safety concern was involved.

l SQN personnel indicated that NCR SQNNEB 8501 had been received from TVA's Office of Engineering (OE), concerning potential out-of-tolerance conditions when exposed to the containment post-accident environment. The transmitters' ability to provide engineered safety features actuation was not an issue. Site personnel indicated that revision 0 of this NCR l was not considered technically adequate in that the referenced environmental testing document had been misapplied, that the site believed adequate similarity existed between the installed model of the transmitters and the tested model, and -

i that the transmitters were installed in the annulus instead of

) inside the containment. Subsequent discussion with the Manager, Office of Nuclear Power determined that TVA con-

sidered the pressure transmitters fully operable. Based on l

i the information available and Region II's understanding of the t technical data, Technical Specifications for post-accident l

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monitoring operability appeared to be met. The.NRC inspector reviewed NCRSQNNEB 8501 revision 0 and revision 1 issued on March 22. Revision 1 continued to maintain that the transmitters be replaced.but provided justification for continued operation which indicated no immediate safety Concern.

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C. Verification Methodology 1 The SWEC concern identified for Employee Concerns Task Group (ECTG)

{ verification was stated as follows:

1

t t

RIMS NUMBER Issue RIMS ITEM k A02850401002 Disposition of an NCR re- RIMS-001

@ port for a pressure instru-3 ment which stated that Se-

) quoyah Plant was unsafe.

ECTG reviewed the SQN Compliance Licensing Files for correspondence v related to this issue. This review of the pertinent documentation f ;

formed the basis for this verification activity.

) D. Verification Analysis

( ECTG verified that the NCR was revised because of technical inadequacies and that the revision provided adequate justification L for continued operation of the plant. The NRC found the NCR

'{ revision acceptable in their inspection report of May 31, 1985 (reference B). Following correction of the nonconforming conditions, NCR SQNNEB 8501 was closed August 4, 1985.

E. Completion Status l The SQN corrective actions for this issue are complete. The SWEC h concern is closed.

III. Reference y A. NRC Memorandum, " Meeting With Senior NRC Staff," dated 1 March 26, 1985, J. Lieberman to files 1

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B. NRC Inspection Report Nos. 50-327/85-10 and 50-328/05-10, dated May 31, 1985, J. N. Grace to H. G. Parris "l ;

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