ML20245D825

From kanterella
Jump to navigation Jump to search
Responds to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. NDE Completed for 33 Welds on 890314.Two Liquid Penetrant Exams Revealed Indications Exceeding Acceptance Criteria
ML20245D825
Person / Time
Site: Sequoyah 
Issue date: 04/18/1989
From: Fox C
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-008, IEB-88-8, NUDOCS 8905010183
Download: ML20245D825 (3)


Text

_ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _

,e 4 :-

Gr TENNESSEE VALLEY-AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157A' Lookout Place APR 181989 U.S. Nuclear Regulatory Commission

. ATTN:

Document Control Desk

-Hashington, D.C.

20555 Gentlemen:

In the. Matter of

)

Docket No. 50-328 Tennessee Valley Autho-ity

)

SEQUOYAH' NUCLEAR PLANT (SQN) - NRC BULLETIN 88-08, THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS

Reference:

..TVA letter to NRC dated January 10, 1989 As required in item 2 of the reporting requirements section of the subject bulletin, this submittal confirms that action item 2 has been completed for SQN unit 2'.

Nondestructive examination (NDE) was completed for 33 welds, including the normal'and alternate charging path welds, on March 14, 1989.

No indications caused:by thermal stresses were found.

Two liquid penetrant examinations revealed indications exceeding the acceptance criteria: one was due to the fitting forging process, and the other was due to arc strike trail-off.

The two indications have been repaired by light grinding or filing.

The enclosure

. lists a' summary of the NDEs that were performed.

-NDE:was not performed on the base material of the elbows in the normal and alternate charging lines. Although TVA committed to nondestructively exar.ilne these lines, it has been determined that the stresses from temperature stratification or temperature oscillations are insignificant because of the short lengths.of piping involved.

The commitment, therefore, was beyond the requirements of the bulletin.

fglb 8905010183 8904189 I L PDR ADOCK 05000328 G

PNU; An Equal opportunity Employer 2-_

___-_____________________-_-_____________-____________-________-__A

7_

'*j

~;U -

(U.S. NuclearLRegulatory Commission 1

No commitments are contained in this submittal. Please direct questions concerning this issue'to K. S. Whitaker at (615) 843-7748.

Very truly yours, TENNE E

L T

Y l

C.

ox,.Jr., V ce resident and Nuclear Technical trector f '.

Sworn Jfd2subscr ed before me this Id' day of.

, 1989

. Notary Putilic -

MyCommissionExpires/

f-Enclosure cc'(Enclosure):

~Ms. S. C. Black. Assistant Director for' Projects TVA Projects Division-

'U.S.. Nuclear Regulatory Commission

0ne White Flint, North 11555 Rockville Pike
Rockville, Maryland 20852 Ms. L. J. Watson, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear. Regulatory Commission Region II 101 Marietta Street, NH, Suite 2900

Atlanta,l Georgia 30323 Sequoyah Resident Inspector

'Sequoyah Nuclear Plant ~

2600 Igou Ferry Road' Soddy Daisy, Tennessee 37379

____.___________________________m_

ENCLOSURE SQN UNIT 2 NONDESTRUCTIVE EXAMINATIONS COMPLETED MARCH 14, 1989 The following welds were nondestructively examined by liquid penetrant examination using a procedure qualiflad to Sections V and XI of the American Society of Mechanical Engineers (ASME) code, 1977 edition with addenda through the summer of 1978.

CVCH-4 CVC-1746 SI-1816 CVCF-213 CVC-1747 SI-1817 CVCF-214 SIW-01 SI-1818 CVCF-246 SIW-02 SI-1894 l

CVCF-246A SIW-03 SI-1895 CVCF-247 SIW-04 SI-1896 CVCS-414 SI-1123 SI-1897 CVC-1742 SI-1124 SI-1898 CVC-1743 SI-1125 SI-1899 CVC-1744 SI-1126**

SI-1900

.CVC-1745" SI-1815 SI-1901

  • CVC-1745 - Penetrant test (PT) examination revealed an indication determined to be caused by arc strike trail-off.
    • SI-1126 - PT examination revealed an indication caused by the forging process.

The following velds were ultrasonically examined.

These examinations were pcrformed using a procedure qualified to Sections V and XI of the ASME code, 1977 edition with addenda through the summer of 1978.

Enhanced techniques similar to those recommended in NRC Bulletin 38-08, supplement 2, were used.

Weld Scan Limitations CVCF-213 Limited coverage because of valve and intrados of elbow CVCF-214 Limited coverage beceuse of nozzle'and intrados of elbow CVCF-246 Limited coverage because of valve and intrados of elbow CVCF-245A None l

CVCF-247 Limited coverage because of no77.le I

CVCS-414 Limited coverage because of intrados of elbow am*

.