AECM-86-0221, Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid

Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid

ML20207E698
Person / Time
Site:	Grand Gulf
Issue date:	07/15/1986
From:	Kingsley O MISSISSIPPI POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20207E704	List: AECM-86-0221, Application for Amend to License NPF-29,changing Tech Spec Seismic Monitoring Instrumentation Tables to Delete four- Peak Recording Accelerographs on Reactor Piping & Make Measurement Values Consistent.Fee Paid ML20207E726
References
AECM-86-0221, AECM-86-221, TAC-61931, NUDOCS 8607220402
Download: ML20207E698 (7)

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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi Editikhildd5 P. O. B O X 16 4 0, J A C K S O N, MIS SIS SIP PI 39215-1640 July 15, 1986 O. D. KINGSLEY, J R.

YlCE PRESIDENT NUCLEAR 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 Proposed Amendment to the Operating License (PCOL-86/16)

AECM-86/0221 Mississippi Power and Light (MP&L) Company is submitting by this letter proposed changes to the Seismic Monitoring Instrumentation Tables 3.3.7.2-1 and 4.3.7.2-1. The changes will delete the four peak recording accelerographs located on reactor piping from the GGNS Unit 1 Technical Specifications and make the measurement values consistent throughout Table 3.3.7.2-1.

In accordance with the provisions of 10 CFR 50.59 and 50.90, Mississippi Power & Light (MP&L) request an amendment to License NPF-29, for Grand Gulf Nuclear Station (GGNS) Unit 1.

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 10 CFR 50.92, it is the opinion of MP&L that this proposed amendment involves no significant hazards considerations.

8607220402 860715 PDR ADOCK 05000416 goo J19AECM86071401 - 1 Member Middle South Utilities System ll l

AECM-86/0221 Page 2 In accordance with the requirements of 10 CFR 170.21, we have determined that the application fee is $150. A remittance of $150 is attached to this letter.

Yours uly, s

ODK: .

Attachments: GGNS PCOL-86/16 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)

Mr. James M. Taylor, Director (w/a)

Office of Inspection & Enforcement 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 Atlanta, Georgia 30323 Dr. Alton B. Cobb (w/a)

State Health Officer State Board of Health Box 1700 Jackson, Mississippi 39205 J19AECM86071401 - 2

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE N0. NPF-29 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, 0. D. Kingsley, Jr., being duly sworn, stated that I am Vice President, Nuclear Operations of Mississippi Power & Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am 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 Vice President, Nuclear Operations of Mississippi Power & Light Company; and that the statements made and the matters set forth therein are true and correct to th best of my knowledge, information and belief.

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STATE OF MISSISSIPPI COUNTY OF HINDS County and State above named, this g day ofSUBSCRIBED AND SWORN T0 b

, 1986.

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REMITTANCE ADVICE CHECx oATE 06/05/86 VENDOR US NUC REG COMM VENDOR NUMBER 929958 CHE CK NO. 06-0030

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EUus'E R / ESCRIPTION NUMBE R GROSS AMCUNT DISCOUNT NET AMOUNT 060486 10CFR170 APPLICA FEE 06-0646 15000 15000 I I ' I 1 I t g

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P.O. BOX 1640 + JACKSON, MISSISSIPPI 39205 CHECK NO.06-0030 JOINT ACCOUNT CHECK DATE OOLLARS CENTS 06 05 86 $150 iOO ;

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NPE-86/13

SUBJECT:

Technical Specification Tables 3.3.7.2-1 and 4.3.7.2-1 pages 3/4 3-64 and 3/4 3-65.

DISCUSSION: The proposed change will delete the four peak recording accelerographs located on reactor piping from the Grand Gulf Nuclear Station (GGNS) Unit 1 technical specification.

Changes in the measurement range values from 2g to 2.0g in Section 2 of Table 3.3.7.2-1 are strictly administrative to make the listing of these parameters consistent with the others in this table. Mississippi Power & Light (MP&L) is requesting this proposed change be reviewed by the Nuclear Regulatory Commission (NRC) on a schedule that will allow incorporation before startup (scheduled for early November 1986) following the first refueling outage.

JUSTIFICATION: Regulatory Guide 1.12, Rev. 1, requires that a total of three (3) triaxial peak recording accelerographs (PRA) be provided at one location of each of the following:

(1) A selected location on the reactor equipment; (2) A selected location on the reactor piping; (3) The most pertinent location on Seismic Category I equipment or piping outside of the containment structure.

Furthermore, the NRC Staff requested that triaxial peak recording accelerographs be provided on reactor vessel supports and reactor piping for Grand Gulf Nuclear Station, Unit 1.

The NRC staff review is documented in Supplement 2 to the GGNS Safety Evaluation Report, Section 3.7.4.

The operability and effectiveness of PRAs on reactor piping was discussed with the NRC during the GGNS Technical Specification Review Program in the spring of 1984. MP&L -

commitments to review this matter were documented in a letter from Sam H. Hobbs to Mr. Harold R. Denton, dated May 31, 1984.

The NRC review of this issue is found in Supplement 6 to the -

GGNS Safety Evaluation Report (Section 16.3.1).

In a letter from Mr. O. D. Kingsley, Jr. to Mr. Harold R.

Denton dated January 10, 1986, MP&L requested that the NRC approve deletion of the four PRA's on the reactor piping. The NRC responded to this request in a letter dated May 27, 1986.

It was the NRC's conclusion that the four PRAs which are mounted on the reactor piping do not serve any meaningful purpose for post-seismic damage evaluation and therefore can be deleted.

J13 MISC 86062402 - 1

There are eleven triaxial peak recording accelerographs provided in the GGNS unit 1 design. Seven of the eleven PRAs function satisfactorily while four units mounted on the reactor piping are subject to repeated failures. The reactor piping is subjected to various transients during startup and normal plant operation. These operating transients exceed the range of the four PRAs mounted on the reactor piping and render them inoperable, even though the response on the piping system is very small. The vendor (Kinemetrics) has confirmed that a passive device (PRA) is not suitable for installation on a system which is subjected to frequent operational transients.

For the four PRA's mounted on the reactor piping, the peak acceleration response due to a seismic event can not be separated from the response due to the system transients. In some cases the peak predicted seismic response is less than that due to the system transients.

Currently there are five (5) Triaxial Time History Accelerographs (SMAs) installed in GGNS-1. One (1) SMA is installed on the containment foundation, and one (1) on the drywell wall. Two (2) SMAs are installed outside the containment; with one (1) of these two in the SSW pump house, and one (1) on the SGTS filter train. The fifth (5th) SMA is installed on the free field.

These recorders will provide reliable acceleration time history, which can be converted to seismic response spectra. This response spectra can easily be compared with the respective GGNS design seismic spectra for post-seismic damage evaluation. A sixth (6th) SMA will be installed on a reactor piping support t for the high pressure core spray system before restart from the l

first refueling outage (Operating License Condition 2.C.(7)).

This SMA will provide an acceleration time history for a reactor piping location and confirm the post-seismic evaluation for the affected plant equipment. As discussed above, there are also seven (7) PRAs mounted at various locations inside and outside the containment which will provide reliable and meaningful information for post-seismic evaluation.

Based on the justification provided above, MP&L has concluded that the PRAs mounted on the reactor piping can be deleted since they do not serve any meaningful purpose for post-seismic -

evaluation. Additionally, there are sufficient seismic i

instruments which will provide required information for post-seismic evaluation and therefore, meet the intent of Reg. -

Guide 1.12, Rev. 1.

i SIGNIFICANT HAZARDS CONSIDERATIONS:

The proposed change to delete the four PRAs does not involve a significant increase in the probability or consequences of an

! accident previously evaluated. The four PRAs which are mounted l on the reactor piping do not serve a meaningful purpose for post-seismic evaluation.

J13 MISC 86062402 - 2

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. With the sixth SMA which is to be installed and the available PRA's in GGNS-1, there are sufficient seismic instruments which will provide required information for post-seismic evaluation.

The seismic monitoring instrumentation provides information to allow assessment of seismic damage and to allow plant restart following a seismic event. The four PRAs being deleted do not perform a mitigating function or actuate any ESF system. Their deletion does not involve a significant reduction in the margin of safety.

Therefore, the proposed change involves no significant hazards considerations.

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