ML20063M549

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Application to Amend License NPF-13 for one-time Suspension of Tech Specs 3.7.3,3.4.7 & 3.4.3.1.a to Permit non-nuclear Heatup & Add New Condition 2.C.(12)(C) Re Environ Qualification of Equipment Milestone
ML20063M549
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 09/13/1982
From: Mcgaughy J
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20063M548 List:
References
NUDOCS 8209150197
Download: ML20063M549 (6)
v • d • e


Text

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-13 DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC.

and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, J. P. McGaughy, Jr. , being duly sworn, stated that I am Assistant Vice President - Nuclear Production of Mississippi Power &

Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I an authorized by Mississippi Power & Light Company to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Assistant Vice President - Nuclear Production of Mississippi Power & Light Company; and that the statements made and the matters set forth therein are true and correct to the best of my knowledge, information and belief.

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.' P. Mctaught,' Jr.

STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBED AND SWORN TO before me, a Notary Publ'c, in and for the County ani State above named, this /J Mday of N y,j u , 1982.

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(SEAL) 8209150197 820913 PDR ADOCK 05000416 /d P PDR Nota ry 'Public [

My commission expires:

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T PROPOSED CHANGE TO THE OPERATING LICENSE NPF-13 PCOL-82/08 Mississippi Power & Light (MP&L) requests that the operating license for Grand Gulf Nuclear Station (NPF-13) be amended as indicated below.

One-time exceptions to the Technical Specifications, as listed below, to permit Non-Nuclear Heat Up (NNHU).

Add the following statement to License Condition 2.C(42):

h. The provisions of Specifications 3.7.3, 3.4.7, and 3.4.3.1.a may be suspended.

This proposed change, as discussed below, is provided for NRC review and approval per 10CFR 50.90.

1)

SUBJECT:

Specification 3.7.3, Reactor Core Isolation Cooling System (RCIC).

DISCUSSION:

Non-nuclear heat up will require entry into Operational Condition 3 and invoke 3.7.3.

JUSTIFICATION:

Steam will not be available at this time to the RCIC System. An exception is required from this specification since the non-availability of steam will prevent operability testing of the RCIC System.

2)

SUBJECT:

Specification 3.4.7, Main Steam Isolation Valves (MSIVs).

DISCUSSION:

Non-nuclear heat up will require entry into Operational Condition 3 and invoke 3.4.7.

JUSTIFICATION:

A one-time exception to this specification is appropriate in order to provide consistency with other one-time exceptions related to the main steam isolation valves, already granted in the Operating License, Condition 2.C(42)f.

3)

SUBJECT:

I Specification 3.4.3.1.a, Reactor Coolant System Leakage.

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PROPOSED CHANGE TO THE OPERATING LICENSE NPF-13 PCOL-82/08 (Continued)

DISCUSSION:

Non-nuclear heat up will require entry into Operational Condition 3, which requires that Specification 3.4.3.1.a be met. This specification pertains to the drywell atmosphere particulate radioactivity monitoring system.

JUSTIFICATION:

A one-time exception to Specification 3.4.3.1.a is appropriate c' since there will be no significant buildup of fission product inventory in the core prior to reaching 1.0 percent of rated thermal power.

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T PROPOSED CHANGE TO THE OPERATING LICENSE NPF-13 PCOL-82/09 Mississippi Power & Light (MP&L) requests that the operating license for Grand Gulf Nuclear Station (NPF-13) be amended as follows:

Delete the existing Operating License Condition 2.C.(12)(c) and substitute the following proposed new Operating License Condition 2.C.(12)(c):

(c) MP&L shall complete the following actions on schedules specified with each:

(i) Prior to exceeding 5% thermal power, MP&L shall implement the aging requirements specified in Section 3.7 and Section 4.3 of Appendix H of Supplement No. 2 of the Safety Evaluation Report.

(ii) Corrective actions for equipment identified in Exhibit B (Equipment Requiring Additional Information and/or Corrective Action) of Appendix H to Supplement No. 2 of the Safety Evaluation Report shall be completed in accordance with the time requirements to be specified in the final 10 CFR 50.49 rulemaking on environmental qualification.

(iii) For equipment identified by MP&L in AECM-81/335, dated September 1, 1981, AECM-81/502, dated December 21, 1981, and AECM-82/141, dated April 8, 1982, requiring either replacement or modification to justify interim operation, MP&L shall complete this work prior to exceeding 5%

thermal power as committed and agreed in letter AECM-82/99, dated March 19, 1982.

This proposed change, as discussed below, is provided for NRC review and l approval per 10 CFR 50.90.

SUBJECT:

Environmental qualification of equipment, as discussed in Operating License Condition 2.C.(12)(c) and Appendix H to Supplement No. 2 of the Safety Evaluation Report (SSER 2), NUREG-0831.

DISCUSSION / JUSTIFICATION:

Operating License Condition 2.C.(12)(c) states: s "By September 15, 1982, MP&L shall complete the open items and corrective actions stipulated in Appendix H to Supplement No. 2 of the Safety Evaluation Report."

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PROPOSED CHANGE TO THE OPERATING LICENSE NPF-13 PCOL-82/09 (Continued)

The deletion of the existing Operating License Condition 2.C.(12)(c) and the substitution of the proposed new Operating License Condition in its '

place, will bring the Operating License into agreement with MP&L commitments, listed in letters AECM-81/335, AECM-81/502, and AECM-82/141, to complete certain modifications and replacements in the short term (prior to exceeding 5% thermal power) and in the long term in accordance with the final rulemaking on 10 CFR 50.49.

The proposed new Operating License Condition for 2.C.(12)(c) has been discussed with Jim Kennedy of the NRC Equipment Qualification Branch on l September 7, 1982, and has received his tentative approval.

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I REMITTANCE ADVICE CHECK oats 09-10-82 v'Noo" NUCLEAR _ REGULATORY CObgfN a NuveEa681358 CHECK NO. 09-0039

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