2CAN071301, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471

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License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
ML13183A124
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 07/01/2013
From: Jeremy G. Browning
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN071301
Download: ML13183A124 (5)
v • d • e


Text

2CAN071301 July 1, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

REFERENCES:

1.

Entergy letter dated April 4, 2012, License Amendment Request -

Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (2CAN041201) (ML12096A022) (TAC No. ME8348)

2.

NRC email dated May 10, 2012, Proposed License Amendment Request to Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (ML121310562)

3.

Entergy letter dated July 9, 2012, License Amendment Request -

Supplemental - Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (2CAN071201) (ML12192A089) (TAC No. ME8348)

4.

NRC email dated June 12, 2013, Request for Additional Information -

Proposed License Amendment Request to Technical Specification (TS)

Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (TAC No. ME8348)

5.

Entergy letter dated June 18, 2013, License Amendment Request -

Supplemental - Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (2CAN061302) (TAC No. ME8348)

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Vice President - Operations Arkansas Nuclear One

2CAN071301 Page 2 of 3

Dear Sir or Madam:

With regard to Reference 1, Entergy Operations, Inc. (Entergy) submitted a request to amend the Technical Specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2) related to a revised fuel assembly drop analysis and adoption of NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Travelers TSTF-51, TSTF-272, TSTF-286, and TSTF-471. By email dated May 10, 2012 (Reference 2), the NRC accepted the proposed amendment for review and notified Entergy of supplemental information that would be necessary for the NRC to complete the overall review of the Reference 1 submittal. Entergy submitted the requested supplemental information in letter dated July 9, 2012 (Reference 3).

By email dated June 12, 2013 (Reference 4), the NRC identified minor changes needed to complete the review process. The NRC also requested that all of Attachment 1 of the Reference 3 letter be resubmitted and all the TS pages be resubmitted, in order for this final supplement to represent a complete package. Entergy submitted the requested supplemental information in letter dated June 18, 2013 (Reference 5).

During subsequent review of Attachment 2 of the Reference 5 supplemental letter, an error was discovered on the markup of TS page 3/4 3-25 in that the markup page did not exactly match the corresponding clean (revised) TS page (Attachment 3 of the Reference 5 letter), nor did it match the corresponding discussion and illustration included on Pages 23 and 24, respectively, of Attachment 1 of the Reference 5 letter. Specifically, Table 3.3-6 Note 3.b does not contain the TSTF-51 term "recently." This term is appropriately included in the aforementioned attachments of the Reference 5 letter. Therefore, a revised markup page is provided in Attachment to this letter, which includes the missing term. Entergy requests the NRC substitute the respective TS markup page included in this letter in lieu of the corresponding TS markup page contained in Attachment 2 of the Reference 5 letter.

No change in the commitments included in Attachment 4 of the Reference 5 letter is being made. In addition, the changes incorporated by this supplemental letter have no impact on the no significant hazards consideration (NSHC) included in Attachment 1 of the Reference 5 letter.

In accordance with 10 CFR 50.91(b)(1), a copy of this application and the NSHC is being provided to the designated Arkansas state official.

If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on July 1, 2013.

Sincerely, ORIGINAL SIGNED BY JEREMY G. BROWNING JGB/dbb

Attachment:

Markup of Technical Specification Page

2CAN071301 Page 3 of 3 cc:

Mr. Arthur T. Howell Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment to 2CAN071301 Markup of Technical Specification Page

ARKANSAS - UNIT 2 3/4 3-25 Amendment No. 63,130,145,206,231,255, TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABLE MODES ALARM/TRIP SETPOINT MEASUREMENT RANGE ACTION

1.

AREA MONITORS

a.

Spent Fuel Pool Area Monitor 1

Note 1 1.5 x 10-2 R/hr 10 101 R/hr 13

b.

Containment High Range 2

1, 2, 3, & 4 Not Applicable 1 - 107 R/hr 18

2.

PROCESS MONITORS

a.

Containment Purge and Exhaust Isolation 1

5 & 6Note 3 2 x background 10 - 106 cpm 16

b.

Control Room Ventilation Intake Duct Monitors 2

Note 2 2 x background 10 - 106 cpm 17,20,21

c.

Main Steam Line Radiation Monitors 1/Steam Line 1, 2, 3, & 4 Not Applicable 10 104 mR/hr 19 Note 1 - With fuel in the spent fuel pool or building.

Note 2 - MODES 1, 2, 3, 4, and during movementhandling of irradiated fuel assemblies or movement of new fuel assemblies over irradiated fuel assemblies.

Note 3 - Applicable during:

a.

PURGE of the Containment Building or,

b.

Containment Building continuous ventilation operations when moving recently irradiated fuel assemblies or moving new fuel assemblies over recently irradiated fuel assemblies in the Containment Building.

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