2CAN121403, License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186).

License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186).

ML14339A406
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/05/2014
From:	Pyle S Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2CAN121403
Download: ML14339A406 (6)

Text

s Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 2CAN121403 December 5, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)

Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

By letter dated March 26, 2013 (Reference 1), Entergy Operations, Inc. (Entergy) submitted a request for an amendment to Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TS) to incorporate the NRC-approved Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186). During subsequent review, Entergy identified the revised (clean) TS page for TS 3.4.1.3 last submitted in letter dated May 12, 2014 (Reference 4), contained an incorrect footer. In addition, one of the amendment numbers in the footer of TS Page 3/4 8-1 from the original submittal (Reference 1) was found to not be lined-through (previous amendment numbers are maintained in the footers, but lined-through when superseded by a future amendment). Therefore, revised (clean) versions of the two affected TS pages are attached to this letter. The submission of the subject pages do not result in any technical changes to the Reference 1 request or any of the supplemental letters listed in References 1, 3, 5, or 6 below. Therefore, this letter has no impact on the no significant hazards consideration included in the Reference 1 request, nor affect the applicability and acceptability of ANO-2 adoption of TSTF-422.

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

No new commitments have been identified in this letter.

If you have any questions or require additional information, please contact me.

2CAN121403 Page 2 of 3 Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE JGB/dbb

REFERENCES:

1. Entergy letter dated March 26, 2013, License Amendment Request -

Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)

(2CAN031303) (ML13085A283)

2. NRC email dated November 22, 2013, Arkansas Nuclear One, Unit 2 -

RAI related to the adoption of TSTF-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)" (TAC No. MF1199)

(ML13326A345)

3. Entergy letter dated December 12, 2013, Response to RAI related to the adoption of TSTF-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)" (2CAN121303) (ML13347B235)

4. Entergy letter dated May 12, 2014, License Amendment Request Supplemental - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)" (2CAN051403) (ML14132A344)

5. NRC letter dated August 4, 2014, Request for Additional Information Regarding License Amendment Requests to Adopt Changes to Technical Specification End States (0CNA081401) (ML14209A627)

6. Entergy letter dated August 19, 2014, Response to Request for Additional Information Regarding License Amendment Requests to Adopt Changes to Technical Specification End States (0CAN081407)

(ML14231A370)

Attachment:

Revised (Clean) Technical Specification Pages

2CAN121403 Page 3 of 3 cc: Mr. Marc L. Dapas 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: Ms. Andrea E. George 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 2CAN121403 Revised (Clean) Technical Specification Pages

REACTOR COOLANT SYSTEM SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the coolant loops listed below shall be OPERABLE:

1. Reactor Coolant Loop (A) and its associated steam generator and at least one associated reactor coolant pump.

2. Reactor Coolant Loop (B) and its associated steam generator and at least one associated reactor coolant pump.

3. Shutdown Cooling Loop (A) #.

4. Shutdown Cooling Loop (B) #.

b. At least one of the above coolant loops shall be in operation.*

APPLICABILITY: Modes 4 and 5.

ACTION:

a. With less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant loops to OPERABLE status as soon as possible and initiate action to make at least one steam generator available for decay heat removal via natural circulation. LCO 3.0.4.a is not applicable when entering HOT SHUTDOWN.

b. With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required shutdown cooling loop(s) shall be determined OPERABLE per the Inservice Testing Program.

4.4.1.3.2 The required reactor coolant pump(s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.3 The required steam generator(s) shall be determined OPERABLE by verifying the secondary side water level to be 23% indicated level at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.4 At least one coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• All reactor coolant pumps and decay heat removal pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) core outlet temperature is maintained at least 10°F below saturation temperature.

1. The normal or emergency power source may be inoperable in Mode 5.

ARKANSAS - UNIT 2 3/4 4-2a Amendment No. 24,29,233,

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system and

b. Two separate and independent diesel generators each with:

1. A day fuel tank containing a minimum volume of 300 gallons of fuel,

2. A separate fuel storage system, and

3. A separate fuel transfer pump.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

NOTE: Specification 3.0.4.b is not applicable to diesel generators.

a. With one offsite A.C. circuit of the above required A.C. electrical power sources inoperable, perform the following:

1. Demonstrate the OPERABILITY of the remaining offsite A.C. circuit by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and

2. Restore the offsite A.C. circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. LCO 3.0.4.a is not applicable when entering HOT SHUTDOWN. Startup Transformer No. 2 may be removed from service for up to 30 days as part of a preplanned preventative maintenance schedule. The 30-day allowance may be applied not more than once in a 10-year period.

ARKANSAS - UNIT 2 3/4 8-1 Amendment No. 141,215,234,249,255, 281,