GNRO-2008/00025, Technical Specification Bases Update to the NRC for Period Dated March 5, 2008

Technical Specification Bases Update to the NRC for Period Dated March 5, 2008

ML080650519
Person / Time
Site:	Grand Gulf
Issue date:	03/05/2008
From:	Larson M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2008/00025
Download: ML080650519 (5)

Text

,.

~Entergy Entergy Operations, Inc.

PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800 GNRO-2008/00025 March 05, 2008 u.s. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Technical Specification Bases Update to the NRC for Period Dated March 5, 2008 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29

Dear Sir and Madam:

Pursuant to Grand Gulf Nuclear Station (GGNS) Technical Specification 5.5.11, Entergy Operations, Inc. hereby submits an update of all changes made to GGNS Technical Specification Bases since the last submittal (GNRO-2007/00073 dated December 03,2007 to the NRC from GGNS). This update is consistent with update frequency listed in 10CFR50.71(e).

This letter does not contain any commitments.

Should you have any questions, please contact Michael Larson at (601) 437-6685.

Sincerely, Michael J. Larson Acting-Manager Licensing MJL attachment: GGNS Technical Specification Bases cc: (See Next Page)

GNRO-2008/00025 Page 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ALL LETTERS ATTN: Mr. Elmo E. Collins, Jr. (w/2) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S. Nuclear Regulatory Commission ALL LETTERS -

ATTN: Mr. Jack Donohew, NRRlDORL (w/2) COURIER DELIVERY (FEDEX, ETC.)

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ATTACHMENT to GNRO-2008/00025 Grand Gulf Technical Specification Bases Revised Pages LDC# BASES PAGES AFFECTED TOPIC of CHANGE 08008 83.1-17,83.1-20 CLARIFICATION TO 8ANKED POSITION WITHDRAWAL SEQUENCE (8PWS)

Control Rod OPERABILITy 8 3.1.3 BASES ACTIONS 0.1 and 0.2 (continued)

(BPWS) analysis (Ref. 7) requires inserted control rods not in compliance with BPWS to be separated by at least two OPERABLE control rods in all directions, including the diagonal. Therefore, if two or more inoperable control rods are not in compliance with BPWS and not separated by at least two OPERABLE control rods, action must be taken to restore compliance with BPWS or restore the control rods to OPERABLE status. Required ACTION 0.1 is utilized when inoperable control rods that violate the generic BPWS separation criteria cannot be restored to an OPERABLE condition. In this situation, compliance with either the generic BPWS analysis (Ref. 7) or a specific BPWS analysis for the evolution will satisfy ACTION 0.1 and allow the condition to be exited (Ref. 11).

A Note has been added to the Condition to clarify that the Condition is not applicable when> 10% RTP since the BPWS is not required to be followed under these conditions since analysis has shown that the CRDA is inherently self-limiting for powers> 10% RTP due to the presence of voids in the core (Ref. 8, 9, and 10), as described in the Bases for LCD 3.1.6. The allowed Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is acceptable, considering the low probability of a CRDA occurring.

If any Required Action and associated Completion Time of Condition A, C, or 0 are not met or nine or more inoperable control rods exist, the plant must be brought to a MODE in which the LCD does not apply. To achieve this status, the plant must be brought to MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This ensures all insertable control rods are inserted and places the reactor in a condition that does not require the active function (i.e., scram) of the control rods. The number of control rods permitted to be inoperable when operating above 10% RTP (i .e., no CRDA considerations) could be more than the value specified, but the occurrence of a large number of inoperable control rods could be indicative of a generic problem, and investigation and resolution of the potential problem should be undertaken. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

(continued)

GRAND GULF B 3.1-17 LBDeR 08008

Cant ro 1 Rod OPERAB I LI TY B 3.1.3 BASES SURVEILLANCE SR 3.1.3.5 (continued)

REQUIREMENTS position (notch position 48) or prior to declaring the control rod OPERABLE after work on the control rod or CRD System that could affect coupling. This includes control rods inserted one notch and then returned to the "full out" position during the performance of SR 3.1.3.2. This Frequency is acceptable, considering the low probability that a control rod will become uncoupled when it is not being moved and operating experience related to uncoupling events.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 26, GDC 27, GDC 28, and GDC 29.

2. UFSAR, Section 4.3.2.5.5.

3. UFSAR, Section 4.6.1.1.2.5.3.

4. UFSAR, Section 5.2.2.2.3.

5. UFSAR, Section 15.4.1.

6. UFSAR, Section 15.4.9.

7. NEDO-21231, "Banked Position Withdrawal Sequence,"

Section 7.2, January 1977.

8. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR In."

9. AECM-90/0146, Proposed Amendment to the Operating license (PCOl-90/07, Revision 1), dated August 15, 1990.

10. MAEC-90/0285, Issuance of Amendment No. 73 to Facility Operating license No. NPF Grand Gulf Nuclear Station, Unit 1, Regarding Fuel Cycle 5 Reload (TAC No.

76992), dated November 15, 1990.

11. GNRI-95/00044, Issuance of Amendment No. 120 to Facility Operating license No. NPF Grand Gulf Nuclear Station, Unit 1, Regarding Improved BWR-6 Technical Specifications (rAC No. 88101), dated February 21, 1995, Safety Evaluation Report, Page 63, Item 40.

GRAND GULF B 3.1-20 LBDCR 08008