ML20034E508
| ML20034E508 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/22/1993 |
| From: | Wharton L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034E509 | List: |
| References | |
| NUDOCS 9302260245 | |
| Download: ML20034E508 (5) | |
Text
/'
No, UNITED STATES
!"3 ('%
NUCLEAR REGULATORY COMMISSION
,i wAsain;r:n, p. c. 20sss v*ess+/
UNION ELECTRIC COMPANY CALLAWAY NANT. UNIT 1 D_0CKET NO. 50-483 AMEND _ MENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, the licensee) dated June 16, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth ii, 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pablic; nd E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-30 is hereby amended to read as follows:
9302260245 930222 PDR ADOCK 05000483 P
PDR (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.77
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporate <1 into the license. UE shall operate the facility in accordance with the Technical Specifications and'the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance. The i
Technical Specifications are to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L. Raynard Wharton, Project Manager i
Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
February 22, 1993
ATTACHMENT T0 LICENSE AMENDMENT NO. 77 OPERATING llCENSE NO. NPF-30 DOCKET NO. 50-483
' Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned anendment number and contain marginal lines indicating the area of change.
Corresponding overleaf pages are provided to maintain document completeness.
i REMOVE INSERT 3/4 6-2 3/4 6-2 B 3/4 6-1 B 3/4 6-1
. CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)
Three Type A tests (Overall Integrated Containment Leakage Rate) a.
shall be conducted at 40 i 10 month intervals
- during shutdown at a l
pressure not less than P,, 48.1 psig, during each 10-year service period.
b.
If any periodic as found Type A test fails to meet L the test schedule for subsequent Type A tests shall be review,,d and approved e
by the Commission.
If two consecutive as found Type A tests fail to meet L, a Type A test shall be performed at least every 18 months until Iwo consecutive as found Type A tests meet L, at which time the above test schedule may be resumed.
Theaslettoverall integrated containment leakage rate shall be less than 0.75 L,;
i
- A one-time extension of the test interval is allowed for the third Type A test of the first 10-year service period, provided unit shutdown occurs no later than March 31, 1995 and performance of the Type A test occurs prior to unit restart following Refuel 7.
CALLAWAY - UNIT 1 3/4 6-2a Amendment No. D//g,77 m
i 3/4.6 CONTAIM ENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage ra.o limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKA01 The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P measured overall integrated leakage rate l. As an added conservatism, the s further limited to less than.or equal to 0.75 L, during performance of the periodic test to account for possible degradaH on of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50.*
l The following exemptions have been granted to the requirements.of Appendix J of 10 CFR Part 50:
1.
Section Ill.A.l(a) - an exem) tion to the requirement to stop the Type A test if excessive lea (age is determined. This exemption allows the satisfactory completion of the Type A test if the leakage can be isolated and appropriately factored into the results.
2.
Section Ill.A.5(b) - an exemption for the acceptance criteria, in lieu of the present single criterion of the total measured containment leakage rate being less than 0.75 of the maximum allowable leakage rate, L, the "as found" allowable leakage rate and the "as left" allowable leakage rate will be less will be L,L,.
than 0.75 3.
Section III.D.l(a) - an exemption that removes the requirement that the third test of each set of three Type A tests be conducted when the plant is shutdown for the 10-year plant inservice inspection.
- A one-time extension of.the test interval.is allowed for the third Type. A:
test of the first 10-year service period, as required by Surveillance Require-ment 4.6.1.2.a and.by Section Ill.D.l.(a) of Appendix J to 10 CFR Part 50,.
provided unit shutdown occurs no later than March 31, 1995 and performance.of-the Type A test occurs prior to unit restart following Refuel 7.
CALLAWAY - UNIT 1 B 3/4 6-1 Amendment No.75,77 ll