ML19332F101
| ML19332F101 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/28/1989 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-89-148 VPNPD-89-620, NUDOCS 8912130406 | |
| Download: ML19332F101 (2) | |
Text
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' POWER COMPANY 231 W Mchoon. PO Bcm 2045, kWoakee. WI $3201 (414)221 2345 VPNPD-89-620 L
NRC-89-148 November 28, 1989
,y U.'S.
NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station.P1-137 Washington, Di C.
20555 Gentlemen:
DOCKET 50-301 USE OF CONTROL ROD R71 IN UNIT 2 CYCLE 16 s
POINT BEACH NUCLEAR PLANT, UNIT 2 The present' core for Point Beach Nuclear Plant, Unit 2, uses a control rod'(R71) that was discussed in an August 18, 1983 L,
letter from Wisconsin Electric to the NRC.
One of the rodlets
.on R71 was noted to have a longitudinal crack, about two inches:long, near the tip of.the rodlet.
At that time,
, Wisconsin Electric implemented a Westinghouse recommendation and did:not use the rod.
This was documented in the above x
correspondence.
'A further evaluation"of R71 by Westinghouse, documented in November-20, 1989 correspondence to Wisconsin Electric, 1
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' concludes that "...RCCA R71 containing hairline tip cracks is L",
expected to continue.to meet functional: requirements of Point Seach 2 for an additional cycle of operation."
In particular, u
this evaluation states:
"1.
No cladding, thimble tube dashpot interference would be expected; therefore, continuous free E kg movement will be satisfied.
- 2.
There is no anticipated adverse impact of (j,s longitudinal cracks, of the limited length u.4, projected for RCCA R71 during one additional L
cycle on the rodlet overall integrity, including the ability of the cladding to contain'the absorber.
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Shutdown margins are not expected to be measurably affected as a result of absorber corrosion effects.
This will be confirmed utilizing already required startup reactivity measurements."
In constueration of the above, RCCA R71 has been used in the Point Beach Unit 2 Cycle 16 core.
If you have any questions L
concerning this matter, please contact us.
i very truly yours, l
/
e kN:
C. W.
Fay L
Vice President Nuclear Power l
Copies to NRC Regional Administrator, Region III NRC Resident Inspector l
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