ML19326C396

Responds to Util 760817 Request for 10CFR50,App H Exemption Mod to Conduct Surveillance Program at Davis Besse 1. Requests Addl Info by 761210

ML19326C396
Person / Time
Site:	Arkansas Nuclear, Davis Besse
Issue date:	11/12/1976
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	Phillips J ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8004220942
Download: ML19326C396 (6)

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Horace Jewell, Esquire House, Holms & Jewell 1550 Tower Building

't Little Rock, Arkansas 72201 I

Mr. Donald Rueter Manager, Licensing i

Arkansas Power & Light Company i

Post Office Box 551 Little Rock, Arkansas 72201 Arkansas Polytechnic College Russellville, Arkansas 72801 Phillip K. Lyon,' Esquire House, Hel.as & Jewell 1550 Tower Building Little Rock, Arkansas 72201 4

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s ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO.1 (ANO-1)

REQUEST FOR ADDITIONAL INFORMATION 1.

Provide your contingency plans for assuring that your surveillance

-program will not be jeopardized by an' extended outage of any other reactor (s) f om which you expect to receive data. What time limits will you place on the host

• reactor (s) for a given outage and justify these limits.

2.

Provide your program and schedule for installing the redesigned surveillance capsule holders in your reactor in the event this action becomes necessary.

3.

What is the schedule for withdrawa'l of your capsules from the host reactor (s)? Relate the schedule to predicted trends in adjusted reference temperature and Charpy upper shelf energy. What arrangements

-have been made with the' owners of the host reactor (s) to assure that this withdrawal schedule will be met.

4.

Specify the minimum' and maximum radiation lead times for:

(a) surveillance specimens relative to the vessel beltline inner surface, and (b) surveillance specimens relative to the 1/4T ppsition in the vessel wall, which you will require for guest' specimens exposed in the host reactor (s). Justify the values specified.

• The " host reactor" has Lthe redesigned surveillance specimen capsule holders for irradiation of both the " host capsules" which contain material representative of the host reactor beltline, and " guest capsules" which represent,(for want of a better word) " guest reactors".

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-2 5.

Indicate the corrective action to be undertaken at the guest reactor if the limits specified in response to Question 4, above, cannot be met.

If the corrective action does not involve reactor shutdown, justify the proposed alternative.

1 6.

Describe how the operating staff of the guest reactor will keep informed of the exposure status of the guest specimens at the host reactor (s) relative to the limits specified in response to Question 4, i

above.

7.

Submit amended proposed Technical Specifications that reflect the appropriate portions of your responses to Questions 3, 4, 5 and 6 (bove.

Similarity of Guest and Host Reactors 1

Provide a cumprehensive tabulation for the guest reactor and each host reactor of the values of all parameters, including construction and operating characteristics, that may affect the fracture toughness of the reactor vessel material as it is irradiated.

Discuss how all differences in these parameters are accommodated in the integrated surveillance program.

Fluence Estimates

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1.

Describe analytical techniques that 'you plan to use to estimate the fluence expected at the various welds of the beltline of your vessel.

How much uncertainty do you expect there to be in the fluence estimates?

. 2.

Describe any dosimetry checks that you plan to make on the analytical results.

3.

What differences in neutron energy spectra and dose rate do you predict for your reactor beltline and your surveillance specimens, wherever they are to be irradiated? Describe the corrections, if any, that will be made to the predicted radiation damage at your beltline welds as a result of these differences. Possible corrections include differences in specimen irradiation temperatures, differences in neutron spectra arising from differences in reactor geometry or a different type of fuel (e.g. mixed oxides), and difiarences in dose rate if some test reactor data are used.

Traceability of Welds 1.

Identify the heats of weld wire and flux used in all beltline welds, and give specific locations where each 13used.

2 State which weld or welds is expected to be controllir.g with regard to radiation damage and why, i.e., give expected neutron flux, initial RTNDT, Charpy upper shelf energy, and chemical composition for the controlling welds.:

3.

Which welds are represented in the surveillance capsules irradia:ed in your reactor?

4, Which welds, if any, are represented in surveillance programs for

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- other reactors?

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5.

List any test reactor programs on radiation damage in which your weld metals are represented.

6.

List any test and surveillance programs on radiation sensitivity which include weld metals in the same category as your weld metals.

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