ML17037B622

Letter Providing Additional Information Relating to Fuel Loading Sequence and Verification Techniques and Completing Response to the 03/03/1977 Request

ML17037B622
Person / Time
Site:	Nine Mile Point
Issue date:	06/30/1977
From:	Rhode G Niagara Mohawk Power Corp
To:	Lear G Office of Nuclear Reactor Regulation
References
Download: ML17037B622 (8)

Text

U.S. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER IVRC,FORM,19/

FILE NUMBER FROM: NIAGARA MOHAWK POWER CORP SYRACUSE, N.Y.

G.K, RHODE DATE OF DOCUMENT 6 30 77 TO'"

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LEAR DATE RECEIVED 7

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RESPONSE

TO NRC'S 3/3/77 REQUEST;FOR~ADDITI

'AL INFO RELATED TO FUEL LOADING SEQUENCEj'AND~

VERIFICATION TECHNIQUES PRIOR TO STAR]'UP.

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PL'ANT NAME: NINE MILE PT 8.1 SAB l)tl Ml Ri,Ã JECT MANAGER:

FOR ACTION/INFORMATION ASSIGNED AD:

BRANCH CHIEF:

PROJECT MANAGER:

ENVIRHNMENTAL Vo MOORE LTR CENSIiVG ASS3) STANT:

INTERNAL0 STFMS SAFETY HEINEMAN ROEDER LICENSING ASSISTANT:

Bo HARLESS ISTRI BUTION PLANT SYSTEMS TEDESCO BENAROYA SITE SAFETY &

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CZY CHECK AT&I ALTZMAN BERG E TERNAL OISTRIBUTION BAER BUTLER RIME GAMMILL 2

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HAiICHETT 16 CYS ACRS SENT CAT GO NSIC 771870055

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NIAGARA MOHAWK POWER CORPORATION GERAI.D K. RHODE VICE PRESIDENT NIAGARA~

MOHAWK 300 ERIE BOUI.EVARD WEST SYRACUSE, N.Y. I3202 June 30, 1977 Director of Nuclear Reactor Regulation ATTN:

Mr. George Lear, Chief Branch 83 U. S. Nuclear Regulatory Commission Washington, DC 20555

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Fife'y RE:

Nine Mile Point Unit 1

Docket No. 50-220

Dear Mr. Lear:

In response 7 of our March 14, 1977 letter, it was stated that Niagara Mohawk would provide additional information related to fuel loading sequence and verification techniques prior to startup.

This letter provides this additional information and completes our response to your original request dated March 3, 1977.

The fuel loading placement for Cycle 5 is identical to that provided in NEDO 21466.

The fuel loading and shuffling sequence for Cycle 5 is generated by a computer code.

Utilizing the end of Cycle 4 and beginning of Cycle 5 core configurations, the code generates the allowable loading sequence.

A sample of the generated loading sequence is shown on Figure 1.

To reduce the probability of misloading a fuel bundle, in most cases no more than one fuel assembly is removed from a quadrant at any one time.

Proper rotational orientation of fuel assemblies in the reactor core is readily checked by visual observation and assured by verification procedures during core loading.

Five separate visual indications of proper fuel assembly rotational orientation exist:')

The channel fastener assemblies, including the spring and guard used to maintain clearances between

channels, are located at one corner of each fuel assembly adjacent to the center of the

,control rod.

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2) The identification boss on the fuel assembly handle points toward the adjacent control rod.

3) The channel spacing buttons are adjacent to the control rod passage area.

4) The assembly identification numbers which are located on the fuel assembly handles are all readable from the direction of the center of the cell.

5) There is cell-to-cell replication.

A Core Loading Verification Procedure is used to verify that the core is properly loaded and that the fuel loading plan agrees with the core loading.

An underwater TV system is used to videotape the as loaded core and the tape is independently reviewed to assure proper loading.

The videotape of thy core verification process is filed in permanent records for retention.

The use of the fuel shuffling code, visual observations, and verification procedures assures the proper placement and orientation of the fuel assemblies in the reactor core.

Sincerely, NIAGARA MOHAWK POWER CORPORATION aid hode Vice President, gineering SWW:nld

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