ML20056H646

Informs That Addl Info Needed Re Licensee Response to GL 92-01,rev 1

ML20056H646
Person / Time
Site:	Point Beach
Issue date:	08/26/1993
From:	Hansen A Office of Nuclear Reactor Regulation
To:	Link R WISCONSIN ELECTRIC POWER CO.
References
GL-92-01, GL-92-1, TAC-M83737, TAC-M83738, NUDOCS 9309100249
Download: ML20056H646 (5)

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UNITED STATES I

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E NUCLEAR REGULATORY COMMISSION i

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l WASMNGTON. D.C. 205500001 gw /

August 26, 1993 I

Docket Hos. 50-266 and 50-301

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Mr. Robert E. Link, Vice President i

Nuclear Power Department Wisconsin Electric Power Company

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i 231 West Michigan Street, Room P379

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Milwaukee, Wisconsin 53201 i

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Dear Mr. Link:

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING NRC REVIEW OF THE POINT l

BEACH RESPONSE TO GENERIC LETTER 92-01, REVISION 1 (TAC NOS. M83737 i

AND M83738) i While conducting its review of your response to Generic Letter (GL) 92-01, which was necessary to obtain information needed to assess compliance with

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requirements set forth in Appendices G and H to Part 50 and commitments made in response to GL 88-11 regarding reactor vessel structural integrity, the l

staff has determined that additional information is required to complete the

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review. The additional information required is as follows-l POINT BEACH I (TAC No. M83737)

Question 2a in GL 92-01 The response to GL 92-01 states that the unirradiated USE of circumferential weld SA-1101 is 70 ft-lb.

In report BAW-1803, which is cited in GL 92-01, the unirradiated value of circumferential weld SA-i 1101 is stated to be 65 ft-lb. Resolve this discrepancy.

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There is no unirradiated USE value provided for nozzle belt forging i

122P23 val in the response to GL 92-01.

Provide an unirradiated USE value for this forging, or provide the neutron fluence specific to this forging and demonstrate that it is not the limiting material.

Ouestion 2b in GL 92-01 The initial RT values provided in the response to GL 92-01 for certainplateslA-9811andC-1423)andwelds(SA-812,SA-847,andSA-1101) differ from the values provided in the Correction to Pressurized Thermal Shock (PTS) Submittal (original submittal dated January 20, 1986) Point Beach, Units 1 and 2 (dated March 14,1986), as shown in the table below.

Resolve these discrepancies.

5 9309100249 930826 PDR ADDCK 05000266 f

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i Mr. Robert E. Link August 26, 1993 l

Description IRT from GL 92-01 IRT., from Correction to PTS...

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Plate A-9811 1

-2 i

Plate C-1423 1

-20 Weld SA-812

-5 0

Weld SA-847

-5 0

Weld SA-1101

-5 0

Provide the unirradiated reference' temperature for all welds (from Point Beach and other reactor vessels) fabricated using SA 1101 or weld wire i

heat number 71249. Assess the effect of this data on the reported -

unirradiated reference temperature and end of license RTthe SA 1101 weld metal in the i

Question 3a in GL 92-01 Provide for each fuel cycle, the cold leg temperatures, the neutron fluence at the limiting weld, and the effective full power time.

For cycles with coastdown periods, provida the requested information during j

the constant power operating period and the coastdown period.

Provide the weighted average cold leg temperature for all cycles of f

power operation until the end of the current cycle and the value projected for end of license. The averages should be weighted based on both time and irradiation embrittlement.

Indicate the cycles when each surveillance capsule was withdrawn from l

the reactor vessel and provide the weighted average cold leg temperature to which it was exposed.

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Based on the information provided above and the Point Beach surveillance

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data, assess the effect of irradiation temperature on the end of license RT,l.value for the SA 1101 weld metal in the Point Beach I reactor-l py vesse POINT BEACH 2 (TAC No. M83738)

Question 2a in GL 92-01 I

There is no unirradiated USE value provided for nozzle belt forging 122P23 val in the response to GL 92-01.

Provide an unirradiated USE value for this forging, or provide the neutron fluence specific to this forging and demonstrate that it is not the limiting material.

1 Ouestion 2b in GL 92-01 j

l The response to GL 92-01 does not provide the following information for i

the nozzle belt / intermediate shell circumferential weld: heat number of wire and flux lot number used in fabrication, and chemical composition in weight percent of phosphorous and sulfur.

Please provide this data j

for the aforementioned weld.

l is Mr. Robert E. Link August 26, 1993 Please provide your response to the enclosed questions within 60 days of receipt of this letter.

Should you have questions please contact me at (301) 504-1390.

This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under Pub. L.96-511.

Sincerely, h

Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc:

See next page l

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i Mr. Robert E. Link Point Beach Nuclear Plant Wisconsin Electric Power Company Unit Nos. I and 2 cc:

Ernest L. Blake, Jr.

Shaw, Pittman, Potts & Trowbridge l

2300 N Street, N.W.

l Washington, DC 20037 Mr. Gregory J. Maxfield, Manager Point Beach Nuclear Plant Wisconsin Electric Power Company l

6610 Nuclear Road Two Rivers, Wisconsin 54241 l

Town Chairman Town of Two Creeks Route 3 Two Rivers, Wisconsin 54241 Chairman l

Public, Service Commission of Wisconsin i

i Hills Farms State Office Building l

Madison, Wisconsin 53702 Regional Administrator, Region III l

U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241

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Mr. Robert E. Link August 26, 1993 l

Please provide your response to the enclosed questions within 60 days of receipt of this letter.

Should you have questions plc..se contact me at (301) 504-1390.

l This request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under Pub. L.96-511.

Sincerely, Original Siged By: R. Laufter/for i

Allen G. Hansen, Project Manager Project Directorate III-3 l

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc:

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