ML20085E871

Change Request 21 to License DPR-4,changing Control Rods

ML20085E871
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	08/02/1965
From:	Kohr M SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
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References
FOIA-91-17 NUDOCS 9110210233
Download: ML20085E871 (2)

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S/.XT0!! !."JCLEAR E' gel'I:!:TAL C0F03ATICII DOCKET NO. 50-146 LICESE DPR '.

Unance Requen r/21 1.

Applicant bereby sate. tits Change Request Mc. 21 in co apliance with paragraph 3 cf License DPR-; as provided for in 10 CFR 50.59.

Sid:TO'i IPJCII.ttR E;G)ERIl3'TAL CORPORisTIQ!!

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h. E. Neidig Fre!iden*,

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R. E. Sypter Secretaty (S E A L)

Sucrn and subecribed tc before ne this 2r - day cf

August, 1965.

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/s/ Martin A. Kohr Netary Public Muhlenberg Township, Berks County

& Cen:missi t Expires Feb. h, 3 966 9110210233 910422 PDR FOIA DEKOK91 -- 1'?

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August 2, 1965 Docket 14o. 50-146 DPR-4 Techrical Specifications Change Request 11o. 21 Page 1 of 1 1.

Dystription of Chance Change cection li.6.d. to read as follows d.

To perforn a change of control rode the coolant water will be borated to a concentration that will insure at least 10Z shutdown when all control rods are fully inserted.

Then all control rods will be

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withdrawn approximately eight inches. The two highest worth control rods will then be withdrawn from the core and an inverse count rate plot maintaiwd dur$ng withdrawal to insure that criticality is not achieved.

If the inverse count rate plot shows that the reactor will be critical before the rods are fully withdrawn, boron will be added to the coolant water.

After the two highest worth control rods are fully withdrawn and cuberiticality is assured, all control rods l

will be inserted to the fully scrammed position and any two control rods may be removed from the core.

2 P rpose of Chance a

To equalize the " burn-up" of the control rods and fuel followers it is desirable periodically to rotate the control rodo from the center of the core to the lower flux areas in the periphery. The present Technical Specifications provide for the releval of only one control rod at a time.

lluelear safety would not be served either by Gilly unloading th core or by using an extensive procedure of coupling and uncoupling the absorber and follower sections of the control rods to complete the intereaange in a manner allowed by the present Technical Specifications. Such a proceb:

although even more conservative from a nuclear standpoint would subject the reactor to additional risk of physical damage during all of the movements and handling required.

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3.

Safety Considerations The procedure outlined will assure that criticality will not be achie.ed upon removal of any two control rods. In our opinion the proposed change does not present any signifit ant safety considerations not described or implicit in the Final Safeguar4 Report.

4.

Health and Safety It is our conclusion that the health and safety of the public wdM not be endangered by this chance.

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