ML20054J552

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PNO-TMI-82-015C:on 820625,axial Power Shaping Rod Testing Completed.Rods 64 & 69 Did Not Move,Rod 68 Inserted to 22.9% from Bottom Position & Rod 67 Inserted to Position 1.1% from Bottom.No Changes in Neutron Population Occurred
ML20054J552
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/28/1982
From: Barrett L, Shanbaky M, Thonus L
Office of Nuclear Reactor Regulation
To:
References
PNO-TMI-82-015C, PNO-TMI-82-15C, NUDOCS 8206290236
Download: ML20054J552 (2)


Text

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June 28, 1982 NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-TMI-82-15C This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verifi-cation or evaluation and is basically all that is known by NRC staff on this date.

Facility: GPU Nuclear Corporation Licensee Emergency Classification:

Three Mile Island, Unit 2 X

Not Applicable Docket Number 50-320

Subject:

AXIAL POWER SHAPING R0D TEST (UPDATE)

Axial Power Shaping Rod (APSR) testing was completed on the 3:00-11:00 PM shift on Friday, June 25, 1982. Two rods, Nos. 64 and 69, did not move; rod No. 68 was inserted to the 22.9% from the bottom position and rod No. 67 was inserted to a position 1.1%

from the bottom.

The following is a summary of "as left" rods / positions and reactor core locations (see attached map).

(Initial rod positions were approximately 25%.)

Rod Core Location As Left Position 62 F-4 5.3%

63 L-4 18.8%

64 N-6 25.0%

65 N-10 0.1%

66 L-12 4.2%

67 F-12 1.1%

68 D-10 22.9%

69 D-6 26.1%

No change in neutron population nor reactor coolant fission product chemistry occurred as a result of the APSR testing. The above indicated positions represent the maximum achievable rod insertion, except rod No. 67.

Rod No. 67 was left at the 1.1% position to avoid the rod becoming stuck at the bottom.

The licensee is evaluating the need for further APSR testing. This PN is issued for information only.

Media interest occurred because the licensee press release updates. The NRC does not plan to issue a press release. The Commonwealth of Pennsylvania was informed.

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. Thonus 590-1128 M. Shanbaky 590-1140 L. Barrett 590-1120 Distribution:

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' II I CORE BARREL 8

.,.I i i i 8 D f F G H K Lh W The eight Axial Power Shaping Rods (A), used to shape power output of the reactor during operation, are the control rods involved in the June,1982 testing.

The remaining control rods were inserted into the core when the Till-2 reactor shut down automatically on !; arch 28, 1979.