AECM-86-0238, Forwards Revised Application for Amend to License NPF-29, Allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a Provided Test Performed at Least Every 18 Months

Forwards Revised Application for Amend to License NPF-29, Allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a Provided Test Performed at Least Every 18 Months

ML20212P456
Person / Time
Site:	Grand Gulf
Issue date:	08/26/1986
From:	Kingsley O MISSISSIPPI POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20212P458	List: AECM-86-0238, Forwards Revised Application for Amend to License NPF-29, Allowing Entry Into Operational Conditions 1 & 2 W/O Performing Surveillance Requirement 4.1.3.1.4.a Provided Test Performed at Least Every 18 Months ML20212P464 ML20212P470
References
AECM-86-0238, AECM-86-238, TAC-60587, TAC-60588, TAC-60589, TAC-60590, TAC-60591, TAC-60592, TAC-61782, NUDOCS 8609030142
Download: ML20212P456 (2)

Text

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v MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi EIAHMdMdB P. O. B O X 16 4.0, J A C K S O N. MISSISSIPPI 39215-1640 August 26, 1986 O. D. KINGSLE Y, J R.

VICE PRESIDENT NUCLE AR OPERATIONS U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/0840/L-860.0 Additional Information on (PCOL-86/04) and (PCOL-86/06)

AECM-86/0238 Mississippi Power and Light (MP&L) Company submitted changes to the Grand Gulf Technical Specifications in a letter dated January 29, 1986. Item 5 of that letter requested changes to allow implementation of a design change to add diverse and redundant Scram Discharge Volume (SDV) level instrumentation and redundant vent and drain valves. An additional submittal was made on April 14, 1986 related to the SDV modification. This additional submittal requested deletion of the part of Surve:illance Requirement 4.1.3.1.4.a requiring testing of the SDV from a control rod configuration of less than or equal to 50% rod density. Several discussions with NRR staff followed the April 14, 1986 submittal resulting in modifications which are submitted in Item 1 of this letter. In a telephone conversation between NRR staff and flP&L on August 20, 1986 the proposed exemption to the provisions of Specification 4.0.4 for Surveillance Requirement 4.1.3.1.4.a was discussed in detail. It is MP&L's understanding that when approved, the proposed change will allow entry into Operational Conditions 1 and 2 without having performed Surveillance Requirement 4.1.3.1.4.a provided the test is performed at least once per 18 months. This exemption will apply to the new vent and drain valves being installed at the first refueling outage provided Surveillance Requirement 4.1.3.1.4.a is performed for the initial time at the next scheduled test for the presently installed SDV vent and drain valves. This exemption also applies when future maintenance is performed on the SDV vent and drain valves provided the test is performed a+ least once per 18 months.

By letter dated June 13, 1986, MP&L requested a license amendment to change the Technical Specifications regarding surveillance requirements for the Automatic Depressurization System (ADS) air accumulator system. Following discussions with the NRR staff, MP&L has revised its application, as described in Item 2 of this letter, to include the requirements for the low pressure alarm system channel function test and channel calibration, including the low pressure alarm setpoint. 860903o142 860026 -

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. AECM-86/0238 Page 2 The design changes associated with changes proposed in this letter are scheduled for implementation not later than startup following the first refueling outage. As previously provided to MP&L on several Technical Specification changes involving design changes to the plant, the NRC is requested to issue the amendments with an open effective date and require that MP&L notify the NRC within 30 days of the effective date of implementation of the technical specification change.

In accordance with the provisions of 10 CFR 50.30, three (3) signed originals and forty (40) copies of the requested amendment are enclosed. The attachment provides the complete technical justification and discussion to support the requested amendment. This amendment has been reviewed and accepted by the Plant Safety Review Committee (PSRC) and the Safety Review Committee (SRC).

Based on the guidelines presented in 10CFR50.92, it is the opinion of MP&L that this proposed amendment involves no significant hazards considerations.

If there are any questions, feel free to contact my office.

Yours tr ly, s

ODK:gft Attachment cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a) l Mr. James M. Taylor, Director (w/a)

Office of Inspection & Enforcement i U. S. Nuclear Regulatory Commission

! Washington, D. C. 20555 Dr. J. Nelson Grace, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 i Atlanta, Georgia 30323 Dr. Alton B. Cobb (w/a)

State Health Officer State Board of Health Box 1700 Jackson, Mississippi 39205 J14AECM86072901 - 2

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