ML20136G399

Application to Amend License NPF-30,revising Listed Tech Specs to Indicate Correct Value of P(A) as Given in Snupps FSAR Section 6.2.1.4.3.3.Safety Evaluation & Significant Hazards Consideration Encl.Fee Paid

ML20136G399
Person / Time
Site:	Callaway
Issue date:	11/15/1985
From:	Schnell D UNION ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20136G404	List: ML20136G399 ML20136G411
References
ULNRC-1208, NUDOCS 8511220338
Download: ML20136G399 (5)

Text

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asu UNION ELECTRIC COMPANY 1901 Grotiot Street St. Louis Donoid F. Schnell Vice President November 15, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor. Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555.

Dear Mr. Denton:

ULNRC-1208 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 REVISIONS TO CONTAINMENT SYSTEMS TECHNICAL SPECIFICATIONS

Reference:

ULNRC-794 dated 4-9-84 Union Electric Company is transmitting three (3) original and forty (40) conformed copies of an application for amendment to Facility Operating License No. NPF-30 for Callaway Plant, Unit 1.

This amendment application requests that the following Technical Specifications be revised to indicate the correct value of P 6.2.1.4.3.3 and Table 6.2.f as2 given(i.e.,in SNUPPS 48.1 psig):FSAR Section

1. 4.6.1.1.c

2. 3.6.1.2.a

3. 3.6.1.2.b

4. 4.6.1.2.a

5. 4.6.1.2.d

6. 3.6.1.3.b

7. 4.6.1.3.b

8. 4.6.1.7.2 The proposed changes would become effective for Union Electric implementation upon NRC approval. Enclosed is a check for the $150.00 application fee as required by 10CFR170.21.

! Very truly yours,

]

f it Do Schnell GGY/lae Attachments: 1-Safety Evaluation 2-Significant Hazards Considerations 1-Proposed Technical Specification Changes l, B511220338 851115 3 DR ADOCK 050 4 /,

Moding Address- RO Box 149. St. Lout MO 63166 ,

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STATE OF MISSOURI )

) SS CITY OF ST. LOUIS )

Robert J. Schukai, of lawful age, being first duly sworn upon oath says that he is General Manager-Engineering (Nuclear) for 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.

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By Rob rt J. Schukai Gene nager-Engineering

' Nuclear SUBSCRIBED and sworn to before me this / day of , 198f i

BARGAR J.FFA NOTARY PUBUC, STME OF Mts?,0Grd NY COMMISSION EXPIRES APRIL 22, IW3)

ST. LOUIS COUNTY t

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cc: Gerald Charnoff, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.

Washington, D.C. 20036 Nicholas A. Petrick Executive Director 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 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

Attachment 1 ULNRC- / Zo#

SAFETY EVALUATION This amendment request revises Technical Specifications 4.6.1.1.c, 3.6.1.2.a, 3.6.1.2.b, 4.6.1.2.a, 4.6.1.2.d, 3.6.1.3.b, 4.6.1.3.b, and 4.6.1.7.2 to indicate that containment leak rate testing (Type A, B, C tests per 10CFP50, Appendix J) is to be performed at the calculated peak containment internal pressure (P of 48.1 psig. This value for P is a result of containment pr8s)sure/ temperature analyses in the"SNUPPS FSAR (refer to r

Section 6.2.1.4.3.3 and Table 6.2.1-2).

This change has no effect on the Integrated Containment Leakage Rate Test results submitted via the referenced letter (ULNRC-794)? This Type A test was performed at 50.05 psig.

!!owever , all Local Leakage Rate Tests (Type B and C) have been perft ned at the current Technical Specification value of P (i.e., 48.0 psig). To reconcile the use of this slightly 18wer test pressure, an evaluation was performed to determine the impact on meeting the acceptance criteria for Type B and C tests.

The results of this evaluation indicated a negligible effect on meeting the acceptance criteria (i.e., a 0.1% increase in the total leakage for Type B and C tests which remains 25% of the allowable value of 0.6L ) . Therefore, the error estimated to result from performing fhe Local Leakage Rate Test at 48.0 psig is within the uncertainty associated with the test method and is considered to be insignificant. The Technical Specification changes cited in Attachment 3 will ensure that future testing is performed at the correct pressure.

Pursuant to the above information, this amendment request does not adversely affect or endanger the health of the general public and does not involve an unreviewed safety question.

L_ ,

Attachment 2 ULNRC- /203 SIGNIFICANT HAZABDS CONSIDERATIONS As discussed in Attachment 1, the Technical Specification changes delineated in Attachment 3 have an insignificant effect on previous test results and will ensure that future tests are performed at the correct pressure as derived from the safety analyses. These changes have no effect on plant design or operation.

The Commission has provided guidance concerning the application of the standards in 10CFR50.92 by providing certain examples (48FR14870). The amendment requests given in Attachment 3 are similar to the example of an action involving no significant hazards consideration which relates to a change that is administrative in nature. These changes ensure consistency between the Technical Specifications and the FSAR.

Based on the foregoing, the requested amendment does not present a significant hazard.

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