ML101330455

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Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance
ML101330455
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/13/2010
From: Schwarz C
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101330455 (9)


Text

Palisades "'",.''

27780 Blue Star Memorial Highway Covert, MI 49043 Tel 269 764 2000 Christopher J. Schwarz Site Vice President May 13, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Reference:

1. Entergy Nuclear Operations, Inc. letter dated March 31,2010, License Amendment Request: Control Rod Drive Exercise Surveillance

Dear Sir or Madam:

In Reference 1, Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) to revise the Palisades Nuclear Plant Renewed Facility Operating License. The proposed amendment would add a new license condition 2.C(4). In telephone calls on 3,2010, and May 10,201 the Nuclear Regulatory Commission staff requested the wording proposed license condition and a note be Specifications Surveillance Requirement SR 3.1.4.3.

response the request wording license and adding a note to SR 3.1.4.3, ENO proposes the changes below. These changes do not change the intent of the submitted in Reference 1.

In the proposed license condition 2.C(4), delete the following words at the end of the sentence: "in a maintenance or refueling outage, whichever is earlier."

The modified proposed license condition 2.C(4) would read:

"Performance of Technical Specifications Surveillance Requirement SR 3.1.4.3 is not required for control rod drive CRD-22 during cycle 21 until the next entry into Mode 3."

the following Technical Specifications Surveillance Requirement SR 3.1.4.3:

"Not required to be performed or met for control rod 22 during cycle 21 provided control rod 22 is administratively declared immovable, but trippable and Condition D is entered for control rod 22." provides the marked-up pages to the operating license and Technical Specifications showing the revised proposed changes. Attachment 2 provides the page change instructions and revised pages to the operating license and Technical Specifications for the revised proposed changes.

In the May 10, 2010, telephone call, ENO modified its request for approval of the LAR to May 28, 2010. The amendment would be implemented by June 10, 2010.

A copy of this supplement letter has been provided to the designa.ted representative of the State of Michigan.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

I declare under penalty of perjury that the foregoing is true and accurate. Executed on May 13, 2010.

Sincerely, cjs/jlk Attachments: 1. Proposed Renewed Facility Operating License and Technical Specifications Change (mark-up)

2. Proposed Renewed Facility Operating License and Technical Specifications Change (typed) cc: Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

1 PROPOSED RENEWED FACILITY OPERATING LICENSE and TECHNICAL SPECIFICATIONS CHANGE (mark-up)

Page 4 of Renewed Operating License 1 Technical Specifications Two pages follow

a. ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
b. ENO may alter specific features of the approved fire protection program provided:

- Such changes do not result in failure to complete the fire protection program as approved by the Commission. ENO shall maintain in auditable form, a current record of all such changes, including an analysis of the effects of the change on the fire protection program and shall make such records available to the Commission Inspectors upon request. All changes to the approved program shall be reported along with the FSAR revision as required by 10 CFR 50.71(e); and

- Temporary changes to specific fire protection features which may be necessary to accomplish maintenance or modifications are acceptable provided interim compensatory measures are implemented.

(4)

(5) [deleted]

Renewed License No. DPR-20 Amendment No. 2a4, 235

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify the position of each control rod to be within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 8 inches of all other control rods in its group.

SR 3.1.4.2 Perform a CHANNEL CHECK of the control rod 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> position indication channels.

SR 3.1.4.3 92 days Verify control rod freedom of movement by moving each individual full-length control rod that is not fully inserted into the reactor core:::: 6 inches in either direction.

SR 3.1.4.4 Verify the rod position deviation alarm is 18 months OPERABLE.

SR 3.1 Perform a of the control 18 months rod position indication channels.

SR 3.1.4.6 Verify each full-length control rod drop time is Prior to reactor

s; 2.5 seconds. criticality, after each reinstallation of the reactor head Palisades Nuclear Plant 3.1.4-3 Amendment No. 189

2 PROPOSED RENEWED FACILITY OPERATING LICENSE and TECHNICAL SPECIFICATIONS CHANGE (typed)

Renewed Facility Operating License and Technical Specifications Page Change Instructions, Page 4 Renewed Operating License Page 1.4-3 Technical Specifications Three pages follow

DOCKET NO. 50-255 Remove the following page of the Renewed Facility Operating License and replace it with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

REMOVE INSERT Page 4 Page 4 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

REMOVE INSERT 3.1.4-3 3.1.4-3

a. ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
b. ENO may alter specific features of the approved fire protection program provided:

- Such changes do not result in failure to complete the fire protection program as approved by the Commission. ENO shall maintain in auditable form, a current record of all such changes, including an analysis of the effects of the change on the fire protection program and shall make such records available to the Commission Inspectors upon request. All changes to the approved program shall be reported along with the FSAR revision as required by 10 CFR 50.71 (e); and

- Temporary changes to specific fire protection features which may be necessary to accomplish maintenance or modifications are acceptable provided interim compensatory measures are implemented.

(4) Performance of Technical Specifications Surveillance Requirement SR 3.1.4.3 is not required for control rod drive CRD-22 during cycle 21 until the next entry into Mode 3.

(5) [deleted]

Renewed License No. DPR-20 Amendment No. 224, 235, xxx

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify the position of each control rod to be within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 8 inches of all other control rods in its group.

SR 3.1.4.2 Perform a CHANNEL CHECK of the control rod 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> position indication channels.

SR 3.1.4.3 ------------------------------N()TE---------------------------- 92 days Not required to be performed or met for control -

rod 22 during cycle 21 provided control rod 22 is administratively declared immovable, but trippable and Condition D is entered for control rod 22.

Verify control rod freedom of movement by moving each individual full-length control rod that is not fully inserted into the reactor core::::: 6 inches in either direction.

SR 3.1.4.4 Verify the rod position deviation alarm is 18 months

()PERABLE.

SR 3.1 Perform a CHANNEL CALIBRATI()N of the control 18 months rod position indication channels.

SR 3.1.4.6 Verify each full-length control rod drop time is Prior to reactor S 2.5 seconds. criticality, after each reinstallation of the reactor head Palisades Nuclear Plant 3.1.4-3 Amendment No. +89, xxx