ML20137G508
| ML20137G508 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/14/1986 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20137G514 | List: |
| References | |
| ULNRC-1238, NUDOCS 8601210066 | |
| Download: ML20137G508 (5) | |
Text
{
n UNION ELECTRIC COMPANY January 14, 1986 1901 Grotiot Street. St. Louis Donald F. Schnell Vice President Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
ULNRC-12 38 DOCKET NUMBER 50-483 CALLAWAY PLANT LICENSE CONDITION C(11)-STEAM GENERATOR TUBE RUPTURE
Reference:
SLNRC-86-01 dated January 8, 1986 Callaway Facility Operating License NPF-30, License Condition C(11) requires that:
" Prior to restart following the first refueling outage, UE shall submit for NRC review and approval an analysis which demonstrates that the steam generator single-tube rupture (SGTR) analysis presented in the FSAR is the most severe case with respect to the release of fission products and calculated doses.
Consistent with the analytical assumptions, the licensee shall propose all necessary changes to Appendix A to this license."
Union Electric, in conjunction with Kansas Gas and Electric, has completed the required analysis for the SGTR event for the Callaway and Wolf Creek plants and have submitted this for NRC review and approval via Reference 1.
Transmitted herewith are three originals and 40 conformed copies of an application for amendment to Callaway Facility Operating License NPF-30, Appendix A, which proposes an additional Technical Specification ( 3 / 4. 7.1. 6) for the Main Steam Line Atmospheric Relief Valves (ARVs).
At least one ARV is assumed to be operable in the analysis provided by Reference 1.
This proposed change would become effective for Union Electric implementation 30 days following NRC approval.
Enclosed is a check for the $150.00 application fee as required by 10CFR170.12.
Very truly yours, o
D Donald F.
Schnell DS/lw Attachments:
1 - Safety Evaluation and Significant Hazards Considerations 2 - Proposed Technical Specification Changes 3 - Check for Application Fee 00 I
Mailing Address RO Box 149, St Louis, MO 63166
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STATE OF MISSOURI
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SS COUNTY OF CALLAWAY )
Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By
_j s
Donald F.
Schnell Vice President Nuclear SUBSCRIBED and sworn to before me this /h day of.
, 198d.
b BARBARA.PFA NOTARY PUBUC, STATE OF MISSOURt NY COMMISSION EXPIRES APRIL 22, 1989 ST. LOUIS COUNTY.
r cc:
Gerald Charnoff, Esq.
Shaw, Pi t tman, Potts & Trowbridge 1800 M.
- Street, N.W.
Washington, D.C.
20036
. Nicholas A.
Petrick Execu ti ve ' Di rector SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 G. C. Wright Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 i
Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 Tom Alexion Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop.P-316 7920 Norfolk Avenue Bethesda, MD 20014 Ron Kucera, Deputy Director Department of Natural Resources P.O.
Box 176 Jefferson City, Missouri. 65102-l
T ULNRC-1238 SAFETY EVALUATION and SIGNIFICANT HAZARDS CONSIDERATION Callaway License Condition C(ll) requires that an analysis be performed which demonstrates that the steam generator tube rupture (SGTR) analysis presented in the FSAR is the most severe case with respect to the release of fission products and calculated doses.
In addition the license condition requires that technical specification changes be proposed consistent with the analytical assumptions in the analysis.
Union Electric, in conjunction with Kansas Gas and Electric, has completed the SGTR analysis and have submitted this information for NRC review and approval via Reference 1.
This analysis is based in part on the main steam line atmospheric relief valves (ARVs) being operable.
Therefore, the addition of the Technical Specification in Attachment 2 is proposed to ensure operability of sufficient ARVs such that the analysis requirements are met.
The operability of at least 3 of the 4 main steam line atmospheric relief valves (ARVs) ensures that reactor decay heat can be dissipated to the atmosphere in the event of a steam generator tube rupture and loss of offsite power and that the Reactor Coolant System can be cooled down for Residual Heat Removal System operation.
Only one ARV is needed for the heat removal required.
Three operable ARVs are adequate, assuming that one of the operable valves is on the faulted stear generator and that one ARV fails to function.
The proposed Technical Specification is applicable in Modes 1,
2, and 3.
Since the purpose of the ARVs is to provide for removal of reactor decay heat and the RHR system is available in Mode 4, this Technical Specification is not applicable in Mode 4.
Each ARV is equipped with a manual block valve (in the auxiliary building) to provide a positive shutoff capability should an ARV develop leakage.
The AP.V is considered operable if the block valve is closed solely becruce of leakage.
Closure of the block valves of all ARVs because of leakage does not endanger the reactor core; decay heat can be dissipated with the steam line safety valves or a block valve can be opened manually in the auxiliary building and the ARV can be used to control release of steam to the atmosphere consistent with the analysis.
Prims y to secondary leakage can be terminated by depressurizing the Reactor Coolant System with the pressurizer power operated relief valves.
Proposed Action Statement a. provides for one of the required ARVs to be inoperable for up to 30 days.
This is based on an evaluation which shows that the probability of a steam generator tube rupture event occurring coincident with a loss of r
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offsite power during this 30-day time period and an intact steam generator not hgving an operable ARV due to single failure is less than 1x10 Proposed Action Statement b. provides for more than onc of the required ARV's to be inoperable for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This is based on an evaluation which shows the probability of a steam generator tube rupture coincident with a loss of offsite poweg i
during the Action Statement time allowance is less than 1x10 Pursuant to the above information, this amendment request l'
does not adversely affect or endanger the health of the general public and does not involve an unreviewed safety question.
The Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain examples (48FR14870).
This amendment request is similar to the example a change that constitutes an additional limitation, restriction or control not presently included in the Technical Specifications.
This amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated; nor create the possibility of a new or different kind of accident from any accident previously evaluated; nor involve a reduction in the required margin of safety.
Based on the foregoing, the requested amendment does not present a significant hazard.
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