ML20085E921

Interim Deficiency Rept Re Possibility of Marginally Adequate Support Structure on Main Steam & Relief Valve Discharge Piping.Initially Reported on 751223.Teledyne Matls Research Supplying TVA W/Analysis on Pipes & Structures

ML20085E921
Person / Time
Site:	Browns Ferry
Issue date:	01/20/1976
From:	Gilleland J TENNESSEE VALLEY AUTHORITY
To:	Knuth D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20085E900	List: ML20085E921 ML20085E925 ML20085E929
References
NUDOCS 8308170119
Download: ML20085E921 (2)

Text

l l . )q.vek g j T ESSEE VALLEY AUTHOR (

j h CH ATTANOOGA. TENNESSEE 37401

$ f -

4 4

%3.n16 January 20, 1976 Dr. Donald P. Knuth, Director Office of Inspection and Enforce:aant U.S. Nuclear. Regulatory Corsaission Washington, DC 20535

Dear Dr. Knuth:

BROWNS FERRY !GCIIAR PLANT UNIT 3 - REPORTA3L2 DEFICIENCY -

POSSIBILITY OF 1!ARGE! ALLY ADEQUATE SU? PORT STPSCTURE ON

!!AIN STEAM AND RELIE7 VALV3 DISCHARGE PIPING Initial report. of the subject reportable daficiancy vaa nada to C. R. Klinglar, URC-13, Region II, on December 23, 1975.

In compliance with paragraph 50.55(e) of 10 CFR Part 50, we submit the following incarin report of the subjact daficiancy.

The possible e:ciatanca of marginnily adequata support structurse on the relief valve discharge piping is now under investigation.

Teladyna !!aterials Research is performing and supplying TVA nn analysis on each nain staam and discharge pipe and its relatad structures. Upon our recaipt and ==4= tion of Toladyne's entira analysis of all piping and structures, va vill provida you with the required final report.

/

Very truly yours, J. E. Gilleland Assistant Manager of Power-CC: Mr. Norman C. Moseley, Director /

. Office of Inspection and Enforesment U.S. Nuclear Regulatory Commission Region II - Suits 813 230 Peachtree Street, NW.

Atlanta, Caorgia 30303 s

O5000 s PDR l 1

An Equal Opportunity Ernployer

gowr% 831 Power Building g

q4 4c 9 NNESSEE VALLEY AUTHO Y EDCDS 9

h CHATTANOOGA. TENNESSEE 374o1 *

"Q j -

1. '76 -1'3# January 20, 1976

' ]').2 /

j -

(.-

Dr. Donald F. Knuth, Director ,

Office of Inspection and Enforcement i b, ,

U.S. Nuclear Regulatory Commission .

l Washington, DC 20555 1

Dear Dr. Knuth:

o 9 BROWNS FERRY NUCLEAR PLANT UNIT 3 - REPORTABLE DEFICIENCY -

, POSSIBILITY OF MARGINALLY ADEQUATE SUPPORT STRUCTURE ON MAIN STEAM AND RELIEF VALVE DISCHARGE PIPING Initial report of the subject reportable deficiency was made to G. R. Klingler, NRC-IE, Region II, on December 23, 1975.

In compliance with paragraph 50.55(e) of 10 CFR Part 50, we submit the following interim report of the subject deficiency.

The possible existence of marginally adequate support structures on the relief valve discharge piping is now under investigation.

Teledyne Materials Research is performing and supplying TVA an analysis on each main steam and discharge pipe and its related structures. Upon our receipt and examination of Teledyne's entire anclysis of all piping and structures, we will provide you with the required final report.

Very truly yours, y vil J. E. G111 eland Assistant Manager of Power CC: Mr. Norman C. Moseley, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 818 ,

230 Peachtree Street, NW.

Atlanta, Georgia 30303 h

^ ' '

jf

/

An Equal Opportunity Employer

p["#% UNITED STATES

{JJUCLEAR REGULATORY COMMisslON y *g WASHINGTON, D. C. 20555 -

" e .

\...../ June 10, 1976 Note to K. Seyfrit PROPOSED TRANSFER OF LEAD RESPONSIBILITY, SERIAL NO. IE-RID-76-08 As discussed in our telephone conversation today, the questions requested by the subject proposed transfer of lead responsibility will be considered and resolved as part of our currently ongoing generic activities on Mark I containment problems. We therefore do not think it necessary or appropriate to complete this transfer of lead responsibility.

Karl R. Goller, Assistant Director for Operating Reactors Division of Operating Reactors cc: J. Guibert L Shao s

'% k,'

2- -

.-  : o e .

Date:

Serial No.,: IE-RID-76-08

_ TRANSFER OF LEAD RESPONSIBILITY To: K. R. Goller, Assistant Director for Operating Reactors, D0R

Subject:

ADEQUACY OF SUPPORTS FOR SAFETY / RELIEF VALVE PIPING SYSTEMS AT BROWNS FERRY Responsible Branch Chief: K. V.Seyfrit

_ Description of Item Requiring Resolution:

On December 23, 1975, in accordance with 10 CFR 50.55(c), TVA reported the possibic existence of marginally adequate supporting systems for the main steam and relief valve piping located in the drywell of Browns Ferry Unit 3.

The uncertain status of the adequacy of these piping system supports was revealed as a result of pl:4ns to replace two Target Rock safety / relief valves with Crosby valves on the Unit 3 facility.

This change of valves led to a reanalysis of the stress loadings on these piping systems and the discovery of possibly inadequate supports for the piping systems of Units 1 and 2 with the present Target Rock valve installation.

This problem appears na have generic implications to BWRs currently in operation.

BWRs in operation prior to 1972 were reassessed as to adequacy of these piping systems following the events at Turkey Point and Surry.

The recent development at Browns Ferry, raises questions as to the capability of piping supports for -the relief valve discharge piping in the drywell to withstand the loads resulting from safety / relief valve operation over the design lifetime of the plant.

Recommendations and Proposed Course of Action:

1. The Office of Nuclear Reactor Regulation (NRR) will review and evaluate the adequacy of the modified piping support systems being installed at Browns Ferry Unfts 1, 2 and 3.

2.. The NRR will determine the adequacy of these support systems at other operating BWRs and establish the acceptance criteria for these piping systems.

3. At the completion of the. review and evaluation NRR will inform Office of Inspection and Enforcement of the results and conclusions which they have developed. If at the completion of the review and evalua-tion there is a need for additional information from or new requirements for the Licensee, both the Licensee and IE will be advised by NP.R.

DM* k[

/ tII> (II>

I -

2-

4. IE will provide information related to this subject as requested and will conduct inspections of any required changes to piping support systems to assure conformance to license, code or other imposed requirements.

Reference:

Memo, F. J. Long, IE:II to K. V. Seyfrit, w/ encl., dd. 3/3/76 Concurrence:

vv  : wh > < l 3 /

B. H. Grier, Director, Division of Reactor Inspection Programs, IE/Date

/

K. R. .Goller, Assistant Director for Operating Reactors, D0R Date cc: E. Volgenau, IE R. S. Boyd, DPM J. G. Davis, IE R. A. Purple, DOR T. V. Wambach, D0R K. V. Seyfrit, IE J. H. Sniczek, IE G. W. Reinmuth, IE C. J. DeBevec, IE D. Thompson, IE G. Roy, IE G. Gower, IE J. P. O'Reilly, IE:I N. C. Moseley, IE:II W. C. Seidle, IE:II C. E. Murphy, IE:II J. G. Keppler, IE:III E. M. Howard, IE:IV R. H. Engelken, IE:V T. Abell, MIPC H. K. Shapar, ELD s

s e

f * *

• m m.- - - - - . , - -

._e- _ _ _ - - , .

$ *% UNITED STATES yg 'a NUCLEAR REGULATORY COMMISSION .

$ ., $ HEGION 11

~g 230 PEACHTREE STR EET, N. W. SUITE 318

• {.

<,  %" ATL ANT A. GEORGI A 30303 March 3, 1976 i

Karl V. Seyfrit, Office of Inspection and Enforcement, IIeadquarters TilRU: N. C. Moseley, Director, Office of Inspection and Enforcement, Region II Afhy' x t TVA, BROWNS FERRY UNITS 1, 2, AND 3, MARGINALLY ADEQUATE SUPPORT STRUCTURES ON RELIEF VALVE DISCHARGE PIPING TVA reported the possibility of marginally adequate support structures on main steam and relief valve piping under 50.55(e) requirements December 23, 1975. An interim report received January 22, 1976, stated that a final report would be sent upon TVA's receipt and analysis of all piping and structures provided by Teledyne. A telecon check with TVA has indicated that the final report will be issued mid-April.

An inspection was performed by the IE:II Construction Branch the week of February 23, 1976, to determine the design and construction status of modifications to the relief valve discharge piping. It appears that the support structure problem could be generic to BWR sites. It is therefore requested that the Lead Responsibility for this problem be s transferred to Licensing to determine the adequacy of the new supports added at the Browns Ferry site and to determine the generic implications for other BWR sites.

_ ND Th F. J. Long Reactor Operations and Nuclear Support Branch cc: G. Gower G. Roy W. C. Seidle C. E. Murphy s

4 kA

cy.G I I 0,*,

NESSEE VALLEY AUTHO n.9a j

5 -

CHATTANOOGA. TENNESSEE 374ol g .

%$s- 4@

'/73.;916 ,

January 20, 197o Dr. Donald P. Knuth, Director Office of Inspection and Enforcenent U.S. Nuclaar. Regulatory Con 21ssion Washington, DC 20555

Dear Dr. Knuth:

BROUNS FERRY NUCLEAR PLANT U' TIT 3 - REPORTA3LE DEFICIENCY -

l POSSIBILITY OF MARGINALLY ADEQUATE SU? PORT STRUCT'JR3 ON j  !!AIN STEAM AND RELIEF VALV3 DISCHARGE PIPING 1

l Initial report of the subject reportable deficiancy vaa nada to C. R. Klinglar, URC-IE, Region II, on Dacember 23, l')75.

In complianca with paragraph 30.55(e) of 10 CFR Part 50, we submit tha following intarin report of the subject daficiancy.

l The possibla c:tistanca of margM11y adequata support structursa on the relief valva discharga piping is now under investigation.

Teladyna Materials Resaarch is performing and supplying TVA nn nnalysia on each cain staam and discharge pipe and its relatad structures. Upon our recaipt and a - h tion of Toladyna's entira milysis of all piping and structures, va vill provida you with the caquired final report.

Very truly yours, l

J. E. 0111 eland Assistant Manager of Power CC: Mr. Norman C. Moseley, Director /

. Office of Inspection and Enforcement U.S. N:2 clear Regulatory Commission Region II - Suits 813 230 Peachtree Street, NW.

Atlanta, Georgia 30303 l

4 LLVA_

An Equal Opportunity Employer

~ ~

~~ - " " ~ ~ ~ ~ ~ ~

- _ _ __ _'_____~__" .