2CAN060906, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal

Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal

ML091800331
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/24/2009
From:	Walsh K Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN060906
Download: ML091800331 (5)

Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Kevin T. Walsh Vice President, Operations Arkansas Nuclear One 2CAN060906 June 24, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

License Amendment Request Supplemental Technical Specification Change To Modify the Mode of Applicability for Emergency Feedwater Actuation Signal Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6 REFERENCE 1: Entergy Letter to NRC dated March 2, 2009, License Amendment Request related to Technical Specification Change To Modify the Mode of Applicability for Emergency Feedwater Actuation Signal (2CAN030901)

Dear Sir or Madam:

In letter dated March 2, 2009 (Reference 1), Entergy Operations, Inc. (Entergy) proposed changes to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) associated with various Reactor Protective System (RPS) and Engineered Safeguard Features (ESF) setpoint modes of applicability.

Recently, the NRC notified ANO-2 Licensing that, while discussion of changes to TS Table 3.3-1 (TS Page 3/4 3-2) relating to Logarithmic (Log) Power were included in the aforementioned Entergy letter, there appeared to be no markup of the TS page in this regard.

Therefore, a new markup page is included in attachment to this letter with the appropriate changes illustrated. Note that this page already illustrated changes to the Pressurizer Pressure - Low and Steam Generator Pressure - Low functions and are included in the attachment for consistency with the original letter (Reference 1). Therefore, the attached page may be used to replace the like page in the original letter (Reference 1).

As communicated above, changes to the Log Power function within TS Table 3.3-1 were discussed in the March 2, 2009, Entergy letter. However, to provide ease of review, a short discussion of the changes associated with this function is included below.

2CAN060906 Page 2 of 3 The and

• under the Functional Unit 3.a column is deleted. The

• refers to conditions when the reactor trip circuit breakers are closed and the control rods are, therefore, capable of withdrawal. This is redundant to the

• next to the modes of applicability shown in the Applicable Modes column. Note that Mode 2 does not contain a

• because Mode 2 (reactor critical) cannot be physically achieved with reactor trip circuit breakers open (power source to control rods). Therefore, it is not necessary for the

• to be tied to Mode 2 conditions.

In addition, a

• is added to the modes of applicability shown in the Applicable Modes column for Functional Unit 3.b. When reactor trip circuit breakers are open (control rods inserted),

boron dilution monitors are used to monitor changes in reactivity. In addition, significant shutdown margin is maintained during shutdown operations by the elevated boron concentration of the Reactor Coolant System (RCS) up to the point an approach to criticality is to be initiated. Prior to initiating an approach to criticality, reactor trip circuit breakers are closed and control rod Shutdown Banks A and B are withdrawn (cocked rod protection) as backup to the Boron Dilution Monitors. The proposed change to Functional Unit 3.b will ensure Log Power channels are operable for reactivity monitoring purposes any time cocked rod protection is established.

The proposed change does not result in a change to the current TS Action required to be performed if sufficient Log Power channels are not operable. In addition, the proposed change does not result in an impact to the original No Significant Hazards Determination contained in the March 2, 2009, Entergy letter (Reference 1).

The proposed change does not include any new commitment.

If you have any questions or require additional information, please contact David Bice at 479-858-5338.

I declare under penalty of perjury that the foregoing is true and correct. Executed on June 24, 2009.

Sincerely, Original signed by Brad Berryman for Kevin Walsh KTW/dbb

Attachment:

Proposed Technical Specification Changes (mark-up)

2CAN060906 Page 3 of 3 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 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-8 B1 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 2CAN060906 Proposed Technical Specification Changes (markup)

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1,2 5 2 sets of 2 1 set of 2 2 sets of 2 3*,4*,5* 8

2. Linear Power Level - High 4 2 3 1,2 2,3

3. Logarithmic Power Level - High

a. Startup and

• 4 2(a)(d) 3 2,3*,4*,5* 2,3

b. Shutdown 4 0 2 3*,4*,5* 4

4. Pressurizer Pressure - High 4 2 3 1,2 2,3

5. Pressurizer Pressure - Low 4 2(b) 3 1,2,3*,4*,5* 2,3

6. Containment Pressure - High 4 2 3 1,2 2,3

7. Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1,2,3*,4*,5* 2,3

8. Steam Generator Level - Low 4/SG 2/SG 3/SG 1,2 2,3

9. Local Power Density - High 4 2(c)(d) 3 1,2 2,3 ARKANSAS - UNIT 2 3/4 3-2 Amendment No. 24,134,159,