ML060900430

Revision to License Amendment Request Single Recirculation Loop Operation

ML060900430
Person / Time
Site:	Pilgrim
Issue date:	03/22/2006
From:	Balduzzi M Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC4333
Download: ML060900430 (5)

Text

Entery Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Michael A. Balduzzi March 22, 2006 Ste Vice President U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Revision to License Amendment Request, Single Recirculation Loop Operation (TAC No. MC4333)

Reference:

1. Entergy Letter, 2.04.074, License Amendment Request, Single loop Operation, dated September 2, 2004. (TAC No. MC4333)

LETTER NUMBER: 2.06.024

Dear Sir or Madam:

In Reference 1, Entergy Nuclear Operations, Inc. (Entergy) submitted a proposed license amendment to revise the Pilgrim Station Operating License and Technical Specifications to allow continued plant operation with a single recirculation loop in service.

Discussions with the NRC staff during a teleconference held on March 20, 2006, determined clarification to the technical specifications which address APRM flow biased setpoints would improve future understanding of single loop operating requirements. As discussed, the revised technical specifications are enclosed.

The information contained in this letter does not invalidate the no significant hazard conclusions previously submitted in Reference 1. There are no commitments contained in this letter.

If you have any questions or require additional information, please contact Bryan Ford at (508) 830-8403.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 22nd day of March, 2006.

Sincerely, Michael A. Balduzzi Enclosure (2 pages):

Revised note 15 for TS Table 3.1.1; and Revision to requested change to TS 3.6.F

Entergy Nuclear Operations, Inc. Letter No. 2.06.024 Pilgrim Nuclear Power Station Page 2 CC:

Mr. James Shea, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 0-8C2 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Regional Administrator Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. Robert Walker, Director Radiation Control Program Commonwealth of Massachusetts 90 Washington Street Dorchester, MA 02121 Ms. Cristine McCombs, Director Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702

Enclosure to Letter 02.06.024 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Mark-ups of specific technical specifications:

Note 15 to TS Table 3.1.1 and Revision of proposed change to TS 3.6.F (Total of 2 pages enclosed)

NOTES FOR TABLE 3.1.1 (Cont)

2. Permissible to bypass, with control rod block, for reactor protection system reset Inrefuel and shutdown positions of the reactor mode switch.

3. Permissible to bypass when reactor pressure is c576 psig.

4. Permissible to bypass when turbine frst stage pressure Is less than < 112 psig.

5. IRM's are bypassed when APRM's are onscale and the reactor mode switch Is Inthe run position.

S. The design permits closure of any two lines without a scram being Initiated.

7. When the reactor mode switch Is Inthe Refuel position, the reactor vessel head Is removedK and control rods are Inserted In aD core cogs containing one or more fuel assemblies, these scram functions are not required.

8. Not required to be operable when primary containment Integrity Is not required.

9. Not required while performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).

10. Not required to be operable when the reactor pressure vessel head Is not bolted to the vessel.

11. Deleted

12. Deleted

13. An APRM will be considered Inoperable If there are less than 2 LPRM Inputs per level or there Is less than 50% of the normal complement of LPRM's to an APRM.

14. Deleted

15. The APh gh flux trip level set~nphall be as specified in the CORE OPERATING LIMITS REPAUT P hall In no case exce 120% of rated thermal power.

16. The A-%) high flux sram bypassed when Inthe run mode.

17. The APR ow biased high flux m Is bypassed when Inthe refuel or startuplhot standby

18. Delete De_. . 4 SIP +i 45-4ass unc69 n RAendmen 1 o _1 Amendment N o.( _ _ ,A6 3/4.1-4

. b A,

( Insert for TS 3.6.F - Recirculation Loops Operating F. Recirculation Loops Operatina During operation in the Run and Startup Modes, at least one recirculation pump shall be operating.

1. Whenever both recirculation pumps are in operation, pump speeds shall be maintained within 10% of each other when power level is greater than 80%

and within 15% of each other when power level Is less than or equal to 80%.

2. Whenever a single recirculation loop Is operating, the following limits are applied when the associated LCO is applicable:

a) LCO 3.11 .A, "Average Planar Unear Heat Generation Rate (APLHGR)," single loop operation limits specified in the COLR, b) LCO 3.11.C, "Minimum Critical Power Ratio (MCPR),' single loop operation limits specified in the COLR, and c) LCO 3.1, "Reactor Pro on System,' Average wer Range Monitor High 11 function, trip level settIn s reset for single loop operation per Table 3.1.1.

3. If the requirements of Specification 3.6.F.1 or 3.6.F.2 are not met, restore compliance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If compliance is not restored or with no recirculation pumps in operation the reactor shall be in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.