GNRO-2008/00069, Technical Specification Bases and Technical Requirements Manual Update to the NRC for Period Dated October 22, 2008

Technical Specification Bases and Technical Requirements Manual Update to the NRC for Period Dated October 22, 2008

ML082960728
Person / Time
Site:	Grand Gulf
Issue date:	10/22/2008
From:	Larson M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2008/00069
Download: ML082960728 (8)

Text

,.Entergy

-===- Entergy Operations, Inc.

PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800 GNRO-2008/00069 October 22, 2008 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Technical Specification Bases and Technical Requriements Manual Update to the NR C for Period Dated October 22, 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 and Technical Requirements Manual since the last submittal (GNRO-2008/00025 dated Mar ch 5, 2008 and GNR 0-2008/00005 dated Januar y 10, 2008 to the NRC from GGNS). This update is consistent with update frequency listed in 10CFR50. 71 (e).

This Jetter 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-2008/00069 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. Carl F. Lyon, NRRlDORL (w/2) COURIER DELIVERY (FEDEX, ETC.)

ATTN: ADDRESSEE ONLY ADDRESS ONLY -

ATTN: Courier Delivery Only ****00 NOT USE FOR Mail Stop OWFN/8 81 U.S. POSTAL 11555 Rockville Pike SERVICE Rockville, MD 20852-2378 ADDRESS*****

NOT USED IF EIE USED

ATTACHMENT to GNRO*2008/00069 Grand Gulf Technical Specification Bases Revised Pages LDC# BASES PAGES AFFECTED TOPIC of CHANGE 07044 B 3.4-32a CHANGE TO REFLECT USE OF NEW RCS LEAKAGE DETECTION INSTRUMENTATION Grand Gulf Technical Requirements Manual Revised Pages LDC# TRM PAGES AFFECTED TOPIC of CHANGE 08026 6.3-5 COMPLIANCE WITH 10CFR50.68 CRITICALITY MONITORING REQUIREMENTS 08023 7-8, 7-9, and TRB-7 CHANGE TO SNUBBER PROGRAM TO CHANGE TO COMPLIANCE WITH ASME OM CODE SUBSECTION ISTD

RCS Leakage Detection Instrumentation B 3.4.7 BASES BACKGROUND The Drywell floor drain in-leakage is monitored by the P45 (continued) floor drain sump level transmitters and associated instrumentation. The leakage and change in leakage can be determined by monitoring the associated computer point or recorders which calculate leakage based on the level rate of change.

(continued)

GRAND GULF B 3.4-32a LDC 07044

TABLE 6.3.1-1 RADIATION M:>NITOlUNG INSTRUMENTATION APPLICABLE CONDITION KlDES OR REFERENCED OTHER FBQo!

SPECIFIED REQUIRED REQUIRED ALAIlM SURVEILIANCE FUNCTION CONDITIONs CH.iUlNELS ACTION B.1 SETPOINT MEASUREMENT RANGE REQUIREMZNTS

9. Area Monitors

a. Fuel Handling Area Monitors

1) New Fuel (b) 1 D ~2.5 mR/hr 10- 2 to 10 3 mR/hr SR 6.3.1.1 Storage Vault SR 6.3.1.2 SR 6.3.1.5

2) Spent fuel (c) 1 (f) (h) D :S2.5 mR/hr 10- 2 to 10 3 mR/hr SR 6.3.1.1 Storage Pool SR 6.3.1.2 SR 6.3.1.5

3) Dryer Storage (d) 1 (g) D :S15 mR/hr 10- 2 to 10 3 mR/hr SR 6.3.1.1 Area SR 6.3.1.2 SR 6.3.1.5

b. Control Room At all times 1 D :S0.5 mR/hr 10- 2 to 10 3 mR/hr SR 6.3.1.1 Radiation Monitor SR 6.3.1.2 SR 6.3.1.5

• With RHR heat exchangers in operation.

• • When irradiated fuel is being handled in the primary or secondary containment.

1. When CCW System is in operation.

1. 1. With ADHR heat exchangers in operation.

(a) With irradiated fuel in spent fuel storage pool.

(b) With fuel in the new fuel storage vault.

(c) With fuel in the spent fuel storage pool.

(d) With fuel in the dryer storage area.

(e) The actuation and isolation caused by the Function is covered under other LCOS, except Function 5. Two upscale Hi Hi, one upscale Hi Hi and one downscale, or two downscale signals from the same trip system actuate the trip system and initiate isolation of the associated isolation valves. A channel may be placed in an inope£able status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(f) Two monitors are required to meet the requirements of 10CFR72.124.

(g) Monitors that are credited to comply with 10CFR50.68 are ID2l-K626, K627 and K629.

(h) One monitor is required to comply with 10CFR50.68.

TRM 6.3-5 LDC 08023

b. a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

Shall become effective upon review and acceptance by the OSRC and the approval of the General Manager, Plant Operations.

7.6.3.9 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Licensee initiated changes to the ODCM shall become effective upon review and acceptance by the OSRC.

7 . 6 . 3 . 10 SNUBBER PROGRAM 7.6.3.10.1 Snubber testing and visual examinations will be performed in accordance with the ASME OM Code Subsection ISTD and applicable addenda as required.

7.6.3.10.2 Deleted 7.6.3.10.3 Deleted TRM 7-8 LDC 08026

7.7 REPORTING REOUIREMENTS 7.7.1 ROUTINE REPORTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Nuclear Regulatory Commission pursuant to Section 50.4 of 10 CFR Part 50.

7.7.1.1 STARTUP REPORTS Deleted 7.7.2 SPECIAL REPORTS Special reports shall be submitted to the Nuclear Regulatory Commission pursuant to Section 50.4 of 10 CFR 50 within the time period specified for each report.

7.7.2.1 Eces SYSTEM ACTUATIONS In the event an ECCS system is actuated and injects water into the Reactor Coolant System during Modes 1, 2, or 3, a Special Report shall be prepared and submitted to the Commission within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

7.7.2.2 DIESEL GENERATOR FAILURES Deleted 7.B RECORD RETENTION Deleted T~ 7-9 LDC 08026

TECHNICAL REQUIREMENTS MANUAL BASES GGNS TRM BASES B 7.6.3.10 SNUBBERS The snubber testing and visual inspection program will be performed in accordance with ASME OM Code Subsection ISTD and applicable addenda as required by 10CFR50.55a.

TRM TRB-7 LDC 08026