ML19098B304

Response to Request for Refueling Information & Draft Entitled Guidance for Proposed License Amendments Relating to Refueling

ML19098B304
Person / Time
Site:	Surry
Issue date:	08/01/1975
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Goller K Office of Nuclear Reactor Regulation
References
Serial No. 592/070175
Download: ML19098B304 (4)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA. 2 3 2 61 August 1, 1975 Mr. K. R. Goller, Assistant Director for Operating Reactors Division of Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

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Dear Mr. Goller:

Serial No. 592/070175 FR/MLB:clw Docket Nos. ~-~SQ:)

50-281 License Nos. DPR-32 DPR-37 This letter is in reference to your letter of July 1, 1975 in which you requested refueling information and also provided a draft entitled "Guidance for Proposed License Amendments Relating to Refueling.

11 The requested refueling information is provided in Attachments A and E.

You suggested that in the future this information be included in our semi-annual report.

We believe it would be more efficient and timely to submit the information directly to you by separate correspondence rather than in the semiannual report.

The draft guidance on refueling appears to provide a logical and complete framework for supplying the necessary information to satisfy licensing amend-ments for reload fuel.

However, it is not clear as to whether the draft guidance is intended to pertain just to those reload fuel designs which require a change in the Technical Specifications or have an unreviewed safety question, or to all reload fuel designs on a routine basis regardless of whether tech-nical specification changes and/or unreviewed safety questions are involved.

Information is also needed on the proposed effective date of implementation for the draft guidance format.

In addition, there are several technical areas requiring clarification and several information request areas which do not seem to be necessary.

These areas are identified in Attachment C.

We would be most happy to meet with and discuss these areas with the appropriate tech-nical representatives at the Nuclear Regulatory Commission at your earliest convenience, but in any event, prior to September 1, 1975 at which time we plan to submit reload cycle information for Cycle 3 of Surry Unit No. 1.

Attachments Very truly yours,

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C. M. Stallings Vice President-Power Supply and Production Operations 8393

1.

Name of facility:

ATTACHMENT A

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REFUELING INFORMATION REQUEST Surry Power Station Unit No. 1

2.

Scheduled date for next refueling shutdown:

October 15, 1975 (approximate) 3._

Scheduled date for restart following refueling:

December 1, 1975 (approximate)

4.

5.

6.

Technical Specifications change required in allowable control rod insertion limits.

Scheduled date for submitting licensing action:. September 1, 1975 (approximate)

No important licensi~g considerations associated with refueling are anticipated.

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ATTACHMENT B REFUELING INFORMATION REQUEST

1.

Name of facility:

Surry Power Statiori Unit No. 2

2.

Scheduled date for next refueling shutdown:

April 15, 1976 (approximate)

3.

Scheduled date for restart following refueling:

June 1, 1976 (approximate)

4.

No Technical Specification change or other licensing amendment anticipated at this time.

The reload fuel design and core configuration will be reviewed by the Station and System Nuclear Safety and Operating Committees by March 1, 1976 (approximate).

5.

Scheduled date for submitting license action:

March 1, 1976 (approximate)

6.

No important licensing considerations associated with refueling are anticipated.

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ATTACHMENT C

1.

AREAS REQUIRING TECHNICAL CLARIFICATION:

a.

Critical boron concentration startup test.

b.

Ejected rod worth startup test.

c.

Dropped rod worth startup test.

d.

Power Doppler coefficient startup test.

e.

Startup power maps.

2.

AREAS WHICH MAY NOT BE NECESSARY:

a.

Requirement to provide initial fill gas pressure.

Clad collapse time should be sufficient.

b.

)Requirement to provide all physics parameters that change from the reference cycle in lieu of providing just those parameter changes which result in a Technical Specification change or an unreviewed safety question.

c.

Requirement to provide all safety related input parameters in lieu of providing just those parameters, with corresponding

• accident/transient re-analysis, which fall outside of bounds previously analyzed.