ML20154P872

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Final Deficiency Rept Re Incorrect Response Spectra in Analysis of Reactor Bldg Spray Piping Sys.Initially Reported on 841108.Corrective Actions Not Stated
ML20154P872
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 03/05/1986
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8603200444
Download: ML20154P872 (2)


Text

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place March 5, 1986 C_ _

BLHD-50 438/84-5/

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B L RD-4 3 9 / 84 -- S 3 G

U.S. Nuclear Regulatory Co:nmission Region 11 a

Attn:

Dr.

J. Helson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 CJ.

'A

Dear Dr. Grace:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - INCORRECT RESPONSE SPECTRA Iti ANALYS16 0F REACTOR UUILDING SPHAY P1 PING SYSTEM 3LHD--50-4 3 8 / 8 4 -5 7, BLRD-50-439/84 FINAL RE_ PORT The subject defi.eletiey was initially reported to NRC-01E Irispector S. weise on November 8, 1984 in accordance with 10 CFR 50.5S(e) as NCR BLN CED 8417.

This was f ollowed by our interita reports dated December 7, 1984 and July 9, 1985.

Enclosed is our final report.

If you have any questions, please get in touch with R.

H.

Shell at FTS 858-2688.

Very tr 21y.juurs,

TEIP ES'sEE V ': LEY AUI'HORITY

/

R.

L.

Gridle Manager of I censing Enclosure ee:

Mr. James Taylor, Director (Enclosure)

Office of Inspection and Enforcer:,ent U.S.

Nuclear Regulatory Commission Washington, D.C.

20555 Records Center (hnclosure)

Institute of Nuclear Power Operationn 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 06032004448603Og38 PDR ADO".,K 050 S

An Equal Opportunity Employer I

gry

A.

ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 INCORRECT RESPONSE SPECTRA Ill ANALYSIS OF THE REACTOR BUILDING SPRAY PlPING SYSTEM BLHD-50-438/84-5/ AND BLPD-50-439/84-53 NCR BLN CEB 841/

10 CFR 50.55(e)

FINAL REPO.RT Description of Deficiency Floor response spectra were not generated for the dome of the primary containment structure.

In 1979, amplification factors to apply to the response spectra at the top of the cylinder (elevation 8/5) were informally provided to piping analysis personnel for elevation 886.

Elevation 886 is the maximum elevation at the containment spray piping system, but the supports for this system are attached as high as elevation 890.2 in the dome.

The response spectra at elevation 890.2 is higher than the response spectra at elevation 886.

Theretore, incorrect response spectra were used in the analysis of the containment spray piping system.

Lax supervisory control allowed the information to be requested, provided, and used without proper understanding of and adherence to the QA documentat.lon, review, and control requirements of the following procedures:

EP 1.28, " Control of Documents Affecting QuallLy," issued January 3, 1978 EP 3.02, " Seismic Design, Review, and Control," issued September 3, 1977 EP 3.03, " Design Calculations," issued August 22, 1974 The information was informally provided to Lhe users and was not incorporated into existing Civil Engineering Branch Report CEH-15-24.

This problem is considered to be a random occurrence and applies only to the Bellefonte Nuclear Plant (BLN) spray piping system.

Saf.e ty. Implica t ions, A design of the spray piping system based on the incorrect responso spectra would be unconservative and could result in overstresued conditions in the spray piping system components during a seismic event.

Such a condition could i

i lead to tailure of a component and therefore could have jeopardized the safe operation of the plant had it remained uncorrected.

l

., 7 Corrective Action In order to correct this problem, seismic response spectra for elevation 890.2 of the containment structure have been generated and provided to piping analysis personnel.

These spectra have also been included in a revision to the seismic analysis report. The reactor building spray piping systec.: is being reanalyzed using the correct response spectra.

Supports will be redesigned or added as required by the reanalysis.

The construction work for each uniL will be complete six months before the fuel load date of the applicable unit.

In order to prevent this problem from recurring, training has been provided on QA documentation, review, and control as follows:

CEB-EP 21. 38, " Preparing and Distributing Civil Engineering Branch Reports," issued April 25, 1983, delineates specific supervisory controls to be exercised on information provided in CEB reports.

Training was conducted on this EP on June 6, 1983.

The "Bellefonte Rigorous Analysin Handbook," section BLil-- RAH-2 0 /, issued 14 arch S, 1984, provides guidance in subsection 5.0 in the use of response spectra.

Training on other applicable docu:aents, EP 1.28, EP 3.02, and EP 3.03, was conducted on June 6 and 10, 1983.

Training was conducted on OEP-06, " Design lupu t," OEP- 01,

" Calculations," and OEP-08, " Design output" when these documents replaced the procedures listeti above.

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