AECM-82-290, Application to Amend License NPF-13,changing Tech Spec Table 3.6.6.2-1 Re Secondary Containment Ventilation Sys Automatic Isolation Dampers/Valves.W/Class II Amend Fee
| ML20054H932 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 06/23/1982 |
| From: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054H933 | List: |
| References | |
| AECM-82-290, NUDOCS 8206250216 | |
| Download: ML20054H932 (4) | |
Text
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l l
j MISSISSIPPI POWER & LIGHT COMPANY l
Helping Build Mississippi mm654MME P. O. B O X 16 4 0. J A C K S O N, MISSISSIPPI 39205 June 23, 1982 NOARIS L STAMPLEY stNiGR VICE PRf SiDFNT U.S. Nuclear Regulatory Commission Of fice of Nuclear Reactor Regulation Washington, D.C.
20555 Attention:
Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File 0272/0840 Amendment to the Operating License AECM-82/290 In accordance with the provisions of 10 CFR 50.59, we are requesting an amendment to License No. NPF-13 to change the technical specifications of Grand Gulf Nuclear Station Unit 1.
In accordance with provisions of 10 CFR 50.30, 40 copies of the requested amendment are enclosed. The attachment provides the complete technical justification and discussion to support the requested amendment.
In accordance with the requirements of 10 CFR 170.22, we have determined the proposed amendment to be Class II.
A remittance of
$1,200 will be expressed mailed this date as an attachment to this letter.
Yours truly, t
f/
NLS:Im i
Attachment:
GGNS PCOL-82/01 Q !
cc:
(See Next Page)
C 0*
y30 8206250216 820623 DR ADOCK 05000416 PDR AEIA1 Member Middle South Utilities System
AECM-82/290 MISSISSIPPI POWER & LIGHT COMPANY Page 2 cc:
Mr. N. L. Stampley (w/o)
Mr. R. B. McGehee (w/o)
Mr. T. B. Conner (w/o)
Mr. G. B. Taylor (w/o) 2 Mr. Richard C. DeYoung, Director (w/a)
Office of Inspection & Enforcement l
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. J. P. O'Reilly, Regional ^dministrator (w/a)
Office of Inspection & Enforcement l
Region II 101 Marietta Street, N.W.,
Suite 3100 Atlanta, Georgia 30303 AEIA2
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION 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, Norris L. Stampley, being duly sworn, stated that I am Senior Vice President - Nuclear, 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 Senior Vice President - Nuclear, 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.
Aur h
14 V
Norris L.' Stamp 1 STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBED AND SWORN TO before me, a Notary Public, in and for the County and State above named, this 23d day of Tu4a f.
, 1982.
(SEAL) lotary Public
'w My conunission expires:
f rem i s,os s
Attachment to AECM-82/290 Propossd Chinga to Opsrating License (PCOL-82/01)
JUSTIFICATION FOR CllANGE TO TECHNICAL SPECIFICATIONS Table 3.6.6.2-1 Secondary Containment Ventilation System Automatic Isolation Dampers / Valves Page 3/4 6-50 As per the attached page, the maximum isolation time for secondary containment isolation valve P11-F062 (Cond. & Refuel Water Transfer Aux.
Bldg. Isol. Valve) has been increased from 4 seconds to 9 seconds.
The safety evaluation of the secondary containment isolation valves is related to the FSAR Chapter 15 accident analysis assumption that the SGTS reduces secondary containment pressure to -1/8" vg within 120 seconds after an accident. This function is accomplished provided the maximum isolation times do not exceed 12 seconds for P11-F062. Thus, there are no safety or environmental effects associated with the suggested change.
In addition, the specified closing time used in the design of the P11-F062 valve was changed from 4 seconds to 9 seconds in June 1980, but was inadvertently not incorporated into draft Technical Specifications at that time.
4 0
I Didel