ML18092A205
| ML18092A205 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/21/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Uderitz R Public Service Enterprise Group |
| References | |
| GL-84-04, GL-84-4, TAC-8731, TAC-8732, NUDOCS 8406210580 | |
| Download: ML18092A205 (7) | |
Text
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Docket Ne. 50-272 1'*
May 2J, 1984 Mr. Richard A. Uderitz, Vice President -
Nuclear Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. Uderitz:
L PDR Gray File DEisenhut OELD EJordan JNGrace ACRS 10 CParrish DFischer
SUBJECT:
ASYMMETRIC LOCA LOADS OPERATING REACTOR LICENSING ACTIONS -
SUMMARY
OF CONCERNS OF INDEPENDENT PLANT SAFETY EVALUATIONS Re:
Salem Unit 1 Generic Letter 84-04, dated February 1, 1984 subject "Safety Evaluation of Westinghouse Topical Reports Dealing With Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops" indicated an acceptable technical basis has been provided for the 16 Westinghouse Owners Group plants so that the asymmetric blowdown loads resulting from double ended pipe breaks in the main coolant loop piping need not be considered as a design basis provided certain specified conditions are met.
However, as you are one of several independently represented nuclear plant facilities currently under review for their ability to withstand asymmetric loadings from postulated loss-of-coolant accident (LOCA), we are transmitting this request for additional information in order to complete our Safety Evaluations which are scheduled for completion in the fourth quarter of fiscal 84.
Under review are the plant-specific LOCA analysis submitted by the independent utilities for the following plants:
Salem Unit 1, Trojan, Beaver Valley Unit 1, Prairie Island Unit 1 and 2, Kewaunee, Maine Yankee and St. Lucie Unit 1.
The asymmetric LOCA load submittals reviewed to date are referenced at the end of the enclosed summary.
All submittals were evaluated with the guidelines set forth by NUREG-0609 and the summary lists the major areas of concern that have not met these established guidelines.
Detailed questions and requests have previously been submitted in the form of initial reviews and additional requests for information.
It is our understanding that a substantial portion of the information which would resolve these concerns is available with the NSSS vendors.
Please respond to the concerns identified in the enclosure in time for the staff to complete the Safety Evaluation as scheduled above, i.e., by July 31, 1984.
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'---84062105808-40521 PDR ADOCK 05000272 p
Mr. Richard May 21, 1984 The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Enclosure:
As stated cc w/enclosure:
See next page
/s/SVarga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
__j
~' '
Mr. R. A. Uderitz Public Service Electric & Gas Company cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Assistant General Solicitor
- Public Service Electric & Gas Company P. 0. Box 570 - Mail Code TSE Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. Jdhn M. Zupko, Jr.
General Manager - Salem Operations Public Service Electric & Gas Company Post Office Box E Hancock Bridge, New Jersey 08038 Mr. Dale Bridenbaugh M.H.B. Technical Associates 1723 Hamilton Avenue San Jose, California 95125
, James Linville, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancock Bridge, New Jersey 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, New Jersey 08625 Richard B. McGlynn, Commission Department of Public Utilities State of New Jersey 101 CoITTnerce Street Newark, New Jersey 07102 Salem Nuclear Generating Station Units 1 and 2 Regional Radiatjon Representative EPA Region II 26 Federal Plaza New York, New York 10007 Mr. R. L. Mittl, General Manager Nuclear Assurance and Regulation Public Ser.vice Electric & Gas Co.
Mail Code Tl6D - P. 0. Box 570 Newark, New Jersey 07101 Regional Administrator, Region U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancock Bridge, NJ 08038 Mr. Alfred C. Coleman, Jr.
Mrs. Eleanor G. Coleman 35 K Drive Pennsville, New Jersey 08070 Carl Val ore, Jr., Esquire Valore, McAllister, Aron and Westmoreland, P.A.
535 Tilton Road Northfield, NJ 08225 June D. MacArtor, Esquire Deputy Attorney General Tatnall Building Post Office Box 1401 Dover, Delaware 19901 Harry M. Coleman, Mayor Lower Alloways Creek Township Muni c i pa l Ha 11 Hancock Bridge, New Jersey 08038
cc:
Mr. Edwin A. Liden, Manager Salem Nuclear Generating Station Units* 1 and 2 Nuclear Licensing & Regulation Public Service Electric & Gas Company Post Office Box 236 Hancock Bridge, New Jersey 08038 Mr. Charles P. Johnson Assistant to Vice President, Nuclear Public Service Electric & Gas Company Post Office Box 570 80 Park Plaza - 15A Newark, New Jersey 07101 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120
SALEM UNIT 1 A.
Cavity Pressurization Analysis
- 1. The TMD input parameters are required, especially those concerning contraction from losses and vena contracta effects.
- 2.
The methodology used in the calculation of the mass and energy release rates utilized in the analysis is required.
B.
Thermal Hydraulics Analysis
- 1.
The MULTIFLEX node-volume spatial schematics for each postulated break analyzed are required *
. 2.
A list of the MULTIFLEX thennal-hydraulic input parameters is required for each MULTIFLEX analysis perfonned.
3~ The resulting absolute and differential pressure ___ transients across the core support barrel are required for each postulated pipe break analyzed.
C.
Structural Analysis
- 1. The applied loads and the use of the design loads in the primary shield wall analysis require clarification.
- 2.
THe structural analysis of the following components requires quanti-tativ~ results, allowable values, and the bases for the allowables.
- a. fuel assemblies (1) assembly component stresses and grid impact forces (2) derivation and value of the minimum grid strength (Pcrit)
- b. reactor vessel internal components other than the core barrel
- c. steam generator and pump supports
- 3.
The structural analyses of the following components require allowable values for the submitted results and the associated acceptance criteria:
- a. core barrel
- b. *contro 1 rod drive mechanism
- c. primary shield wall (acceptance crite~ia only)
- 4. A complete LOCA analysis adhering to the criteria outlined in "NUREG-0609 is required for the ECCS piping and supports
I
~
- l.
- 2.
REFERENCES 110ynamic Analysis of the Reactor Coolant System Accidents:
Salem Nuclear Generating Stations I Westinghouse Electric Corp., December 1, 1978.
Pro*pri eta ry) for Loss-of-Coolant and iI,
11 NS-TMA-19 9 6,
(Westinghouse 11 Evaluation of the Reactor Coolant System Considering Pressurization Following a LOCA for Salem Units No. 1 enclosure to R. L. Mittl to 0. D. Parr letter, Public and Gas Company, March 6, 1979.
Subcompa:*rtment and 2 11 Service Electric
- 3.
11 React~r Vessel Support Analysis for the Trojan Nuclear Plant,"
PGE-1014, Portland General Electric Company, January 1977.
- 4.
"Analysis of the Effects of LOCA on Reactor toclant System Supports, 11 Beaver Valley Power Station Unit 1, January 1976.
- 5.
"Structural Analysis of Reactor Coolant System for Postulated Loss-of-Coolant Accident--Prairie Island/Kewaunee Nuclear Power Plant,'.' P'rel iminary Issue, Westinghouse Electric Corp.,
February 1980.
(P1oprietary)
- 6.
"Evaluat.ion of Asymmetric LOCA-Related Loadings on the Reactor Coolant System at Maine Yankee," Enclosure (A) of letter 83.2.1, WMYS0-75, -
Maine Yankee Atomic Power Company, May 14, 1S80.
- 7.
"Reactor.Coolant-System Asymmetric LOCA Loads Evaluation", Revision 1, Enclosure to letter L-80-263, Florida Power and Light Company, August 8, 1980.
B.
St. Lucie Unit No. 1 Final Safety Analysis Rep~:t, Amendment No. 36, Dock.et No.
50~335, De~ember 20, 1974~
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