W3P82-4011, Forwards Ebasco Svcs,Inc Rept, Analysis of Pressurizer Safety Valve Discharge Piping in Response to NUREG-0737, Item II.D.1, Performance of PWR Relief & Safety Valves

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Forwards Ebasco Svcs,Inc Rept, Analysis of Pressurizer Safety Valve Discharge Piping in Response to NUREG-0737, Item II.D.1, Performance of PWR Relief & Safety Valves
ML20064D905
Person / Time
Site: Waterford Entergy icon.png
Issue date: 12/29/1982
From: Maurin L
LOUISIANA POWER & LIGHT CO.
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20064D909 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM W3P82-4011, NUDOCS 8301040785
Download: ML20064D905 (3)


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s LOUISIANA f 24a OEtAnONOe S1nur POWE R & L1G HT/ P O box 6008 + NEW OnLEANS. LOUISIANA 70174 * (504) 366 2345

$$EN $s IY L.V. MAURIN Vice President Nuclear Operations W3P82-4011 December 29, 1982 3-A19.09.04.03 Q-3-B31.V2 I.02.02 Mr. Thomas M. Novak L.09 Assistant Director of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Waterford SES 3 Docket No. 50-382 NUREG-0737 SER Confirmatory Issue Performance of PWR Relief and Safety Valves The purpose of this letter is to provide the Louisiana Power & Light response

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to the SER confirmatory issue and the NRC request for a submittal that addressed the functionability of the pressurizer safety valves installed in the Waterford 3 system.

Item II.D.1 of NUREG-0737 required that utilities operating and/or constructing Pressurized Water Reactor (PWR) power plants provide evidence, supported by test, of safety valve functionability.

In response to these requirements, the Electric Power Research Institute (EPRI) implemented a generic test program on behalf of the PWR utilities.

Louisiana Power & Light was a rarticipant in the EPRI program.

The results of the EPRI program were forwarded to the NRC on April 1, l ')8 2.

Louisiana Power & Light, in conjunction with other utilities operating and constructing Combu d on Engineering (CE) designed plants requested, through the CE Owners Group, that CE implement a program to evaluate and apply the EPRI test results.

The results of the CE program, summarized in CEN-227, were for-warded to the NRC on December 20, 1982, in parallel with distribution to the participating utilities. This report, CEN-227, shows that the EPRI tests were directly representative of plant specific safety valve models and valve instal-

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lations. and t. hat ' acceptable valve operation was demonstrated.

Part B Section 3 datails the opproach used in the evaluation of test data.

The safety valv( esed at Waterford 3 is the Dresser Safety Valve Model 31709NA with a "short inlet pipe conffcaration" which is discussed in Part B Section 5 of the Report.

Part C Sectico 5 elves the detailed information specific to Watert < ni 3 and concludes that two combinations of valve adjusting ring settings result nientisfactory operation with blowdowns below the acceptable values identified for Waterford 3 in Appendix C-1.

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In addit _on to the CE study, Louisiana Power & Light had Ebasco perform an evaluation of the ad4 2acy of the pressarizer relief piping and its supports /

restraints as required by NUREG-0737 Item II.D.I.

This report, which is enclosed, presentc the results of the analysis of the Waterford 3 pressurizer safety relief snive discharge piping following SRV actuation. The results of the stress analysis of the piping system using the hydraulic forcing functions 8301040785 021229 PDR ADOCK 05000302 PDR A

Mr. Thomas M. Novak W3P82-40ll Page Two.

generated with the computer code RELAP 5 are also presented in this report.

RELAP 5 has been verified by comparison to experiments in the EPRI safety and relief valve program. The conclusion of the report justifies caat all calculated stresses for the most severe load combination case are below allowable values.

The EPRI program, supplemented by the CE and Ebasco reports, show that the Waterford 3 safety valves and associated piping and supports are adequate and will function as required; furthermore, this information should serve to close-out the SER Confirmatory Item on this issue.

If you have any questions or comments, please advise.

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L. V. Maurin LVM/SFU/pco Enclosure cc:

J. Wilson, E. Blake, W. M. Stevenson

O bec:

F. J. Drummond, R. P. Barkhurst, D. B. Lester, T. F. Gerrets, G. B. Rogers, R. W. Prados, C. J. Decareaux, R. F. Burski, P. V. Prasankumar, J. R. McGaha, S. A. Alleman, G. R. Peeler, T. K. Armington, K. R. Iyengar, M. I. Meyer, L. L. Bass, Richard Hymes, W. A. Cross, Z. A. Sabri, R. W. Kenning, R. A. Savoie, S. M. Jones, J. Hart (Ebasco), Central Records, Nuclear Records (2), Licensing Library

FORn i 3-82 TO:

R. Prados

REFERENCES:

1. Letter IR.3-1306-82 dated 10/8/82 DATE:

December 20, 1982

2. Letter IR3-1595-82 dated 12/16/82 TASK DESCRIPTICN: To perform a study to evaluate the adequacy of the pressurizer relief piping and its supports / restraints as required by UUREG 0737 Item II.D 1 DESCRIPTION S'i:/v.(,7/Mraunfo r,

/7? N DATE:

12/20/82

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(driginatar) y RESPO: SE REQUIRED:

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/ NO DATE RESPOSSE DUE:

To b

__________pSection filled out______________________y Originator "ERIFICATION I certify that 1 Save perforced a review of tha task described, and as a result vf.his review I further certify that: (Choose one a: both.)

/~/ the present caterial status /ccaditions described above presently exist i

and that cari:icatan was made,, direct observation en ny part.

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the report, a n a l y.; i :, infor ati;n, er action taken described above is in i:t trua r.11 eiltl ta the best of my 'n:wledge and belief.

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Date:

/c2 cW 5 d Si. nature:

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(1).erif: cat: n sh ill performed b. a First Line Supervisor, Engineer, j

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Section or Departnent dead, or Mana;;er.

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d) The review is in accordance with i P SI. procedures and is not a nart cf i

.he Quali

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i N act:rns t.t k e n te a::,-' ' sh f. t,n were as f 011cv.3 :

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cro. nen.s a, necessary).

The hydraulic analysis o f the 'Ja ter ford SES Unit ':o. 3 pressurizer cafety relief valve discharge piping

'fellowin" SRV nctuation.wa.s ner_ formed using RELAPS computer code..-The stress analysis w

a of the ni1linn system using the hydraulic forcing functions was donc using PIPESTRESS code.

l Upon connletion of the JERIFICATInN STATEMENT this form is to i

accompan. correspendence throu25 the appr eal process.

Once correspenJe: :e is approved, as applicable, distribution of this h

j fota shall'he as follows:

original to originator, ccpy to ver{ier, copv to file, other copies as necessarv l

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