ML18086B412

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Approves Use of Rod Exchange Procedure in Safety Evaluation of Pse&G Rod Exchange Methodology, Subj to Confirmatory Testing Per Encl Criteria.Data from Measurements & Meeting W/Representatives to Discuss Procedure Requested
ML18086B412
Person / Time
Site: Salem  
Issue date: 04/09/1982
From: Varga S
Office of Nuclear Reactor Regulation
To: Udaritz R
Public Service Enterprise Group
References
NUDOCS 8204190410
Download: ML18086B412 (3)


Text

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Docket Nos. 50-272 and 50-311 Mr. Richard fJ... Uderitz Vice President - Nuclear Public Service Electric and Mail Code Tl 5A P.0. Box 570 Newark, New Jersey 07101

Dear Mr. IJderitz:

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By 1 etter dated February 2, 1982 you transmitted for our comment a

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entitled "Safety Evaluation of the PSE&G Rod Exchange Methodology."

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intend to use this method ofrmeasuring control rod worth in order to verify shutdown margin at the beginning of each cycle.

In your letter you stated that the implementation of the Rod Exchange Procedure described in the subject document does/inotrnepresent an unreviewed safety questions as defined by 10 CFR 50.99.

You also stated that, subject to our comments, this procedure wi11 be implemented during the current startup of Salem Unit 1.

We are familii.ar with the rod m<change approach for establishing rod worth; however, it is our position that the PSE&G version should be confirmed by testinq before it is fully approved.

Our review of your Rod Exchange Procedure has progressed to the point where we approve its use during the current startup of Cycle 4 if the following criteria are met:

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a.

Reference Bank Dilution Measurement The maximum difference between the ratio of the difference between measured value [M] of integral t'lotth of Bank D at any particular step and the design (PSE&G) value [D] of the integral worth of Bank O at any particular step to the de~ign value should be~ 6%

at each step in the region of inferencing which is approximately from 100 steps to 228 steps.

M-D x l 00% < 6%

-0 (b)

The maximum difference between the meast1red roe! worth for individual banks and that predicted by the RSE methods should be< 15%.

(c)

The maximum difference between the total rod worth and that predicted by the RSE methods should be < 103.

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PDR ADOCK 05000272 I

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suRNAME ~.......................... ************e*********

DATE~ ********* *************** ************************ *****........****.*..**.

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NRC FORM 316 (10-BO) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1961-335-96()

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Mr. R. (d)

The standard deviation between the measured and predicted "exchange mode" rod worths must be < 4%.

If criteria (a) or (c) are not met Banks O, C, B, and A must be measured by the boron dilution method~ If criterion (d) is not met, then the difference between the actual standard deviation and the 4% criterion shall be less than the minimum excess shutdown margin or Banks C~ B, and A shall be measured by boron dilution. If criterion (b) is not met the impact of not meeting criterion ( b) must be assessed by the 1 icensee to his satisfaction Before proceeding.

We request that the data from these measurements be provided to the staff for review as soon as practical.

We also would proposed to discuss this Procedure with your representatives, before the end of Cycle 4, to reach a decision on the acceptance of the PSE&G version for future use.

Please respond by letter committing to the above criteria and restdctions.

CC!

See next page Sincerely, Steven A. Varga, Chief Operating Reactors Branch #1 Division of licensing ORB

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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960

4 Mr. R. A. Uderitz

  • Public Service Electric and Gas Company cc:

Mark J. Wetterhahn, Esquire Conner and Wetterhahn 1747 Pennsylvania Avenue, NW Suite 1050 Washington, D.C.

20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric and Gas Company Mail Code TSE - P.O. Box 570 Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. R. L. Mittl, General Manager -

Corporate Quality Assurance Public Service.Electric and Gas Company Mail Code Tl6D - P.O. Box 570 Newark, New Jersey 07101 Mr. Henry J. Midura, General Manager -

Salem Operations Public Service Electric and Gas Company P.0. Box 168 Hancocks Bridge, New Jersey 08038 Salem Free Library 112 West Broadway Salem, New Jersey 08079 Leif J. Norrholm, Resident Inspector Salem Nuclear Generating Station U. S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038 Mr. Edwin A. Liden, Manager -

Nuclear Licensing Public Service Electric and Gas Company Mail Code Tl6D - P.O. Box 570 Newark, New Jersey 07101 Ronald C. Haynes Regional Administrator - Region I U. S. Nuclear Regulatory Conmission 631 Park Avenue King of Prussia, Pennsylvania 19406