ML20126F539
| ML20126F539 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/16/1992 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126F541 | List: |
| References | |
| NUDOCS 9212300375 | |
| Download: ML20126F539 (8) | |
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UNITE D STATES 7,
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NUCLEAR REGULATORY COMMISSION j.
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UNION ELECTRIC' COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 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 March 15, 1991, as supplemented by letters dated December 13, 1991, September 16, 1992 and October 30, 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 in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, t_he 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 public; and 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, Accordingly, the license is amended by changes to the Technical c.
Specifications as indicr.ted in the attachment to this license amendment, and p2.ragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
92123o0375 921216 PDR ADOCK 0500 3
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(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
75, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated 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.
FOR THE NUCLEAR REGULATORY COMMISSION
,s' Af f(,
=x John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation-
Attachment:
Changes to the Technical Specifications Date of issuance:
December 16, 1992
ATTACHMENT TO LICENSE AMENDMENT NO. 75 OPERATING LICENSE 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 amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are provided to maintain document completeness.
REMOVE INSERT 3/4 6-2 3/4 6-2 3/4 6-2a B 3/4 6-1 B 3/4 6-1 8 3/4 6-la
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIKARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION
- 3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINbiENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
i a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by manual valves, blind flanges, or deactivated automatic valves secured in tneir closed positions, except as provided in Table 3.6-1 of Specification 3.6.3; b.
By verifying that each containment air lock is in compliance with the l
requirements of Specificaticn 3.6.1.3; and c.
After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B l
test, by leak rate testing the seal with gas at a pressure not less i
than P, 48.1 psig, and verifying that when the measured leakage rate-l for th$se seals is added to the leakage rates determined pursuant to i
specification 4.6.1.2d. for all other Type B and C penetrations, the coebined' leakage-rate is less than 0.60 L,.
l AExcept valves, blind flanges, and deactivated automatic valves which are Incated inside the containment and are 1ccked, sealed or otherwise secured l
l in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more of ten than once per 92 days.
1 l
l CALLAWAY - UNIT 1 3/4 6-1 Amendment No.
17, 62 l
CONTAINMENT SYSTEMS CONTA'NMENT tEAKAGE 1,lMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or equal to L 1 a.
0.20% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 48.
psig.
b.
A combined leakage rate of less than 0.60 L, for all penetrations andvalvessubjecttoTypeBandCtests,whenpressurizedtoP,,
48.1 psig.
APPLICA6ILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the overall integrated containment leakage rate exceeding 1.0 a.
L,, perform the ACTION of Specification 3.6.1.1.
b.
With the as left overall integrated containment leakage rate exceeding 0.75 L, restore the overall ' integrated leakage rate to less than 0.75 L, prior to increasing the Reactor Coolant System temperature 'above 200*F.
c.
With the combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L,:
1)
Restore the combined leakage rate to less than 0.60 L, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or 2)
Isolate each failed penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or-a deactivated automatic valve secured in the closed position, or 3)
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates-shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using the methods and provision, of ANSI N45.4-1972:
i CALLAWAY - UNIT 1 3/4 6-2 Amendment No. 73, 75
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LONTAINMENT SYSTEMS SURVEltlANCE REQUIREMENTS [ Continued) a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 i 10 month irtervals during shutdown at a pressure not less than P,, 48.1 psig, during each 10-year service period.
I b.
If any periodic as found Type A test fails to meet L, the test schedule for subsequent Type A tests shall be review,ed and approved 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 bo consecutive as found Type A tests meet L, at which time the above test schedule may be resumed.
The as lef t overall integrated containment leakage rate shall be less than 0.75 L,;
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CALLAWAY - UNIT 1 3/4 6-2a Amendment No. 73,75
3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the relesse 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 rate 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.? CONTAINMENT LEAKAGE 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. As an added conservatism, the measured overall integrated leakage rate,is further limited to less than or equal to 0.75 L, during performance of the periodic test to account for possible degradation 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.
The following exemptions have been granted to the requirements of Appendix J of 10 CFR Part 50:
1.
Section llI.A.l(a) - an exemption to the requirement to stop the Type A test if excessive leakage 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 Ill.D.l(a) - an exemption that removes the requirement that the third test of each set of three Type A tests be conducted when i
the plant is shutdown for the 10-year plant inservice inspection.
CALLAWAY - UNIT 1 B 3/4 6-1 Amendment No. 75
CONTAINMENT SYSTEMS BASES CONTAINMENT LEAKAGE (Continued)
Exemption 1 allows the continuance of a Type a test when excessive leakage is found provided that significant leaks are identified and isolated.
After completion of the modified Type A test (i.e., a Type A test with the significant leakage paths isolated during the test), local leakage rates of those paths isolated during the modified Type A test will be measured before and after repairs to those paths. The adjusted "as found" leakage rate for the Type A test can be determined by adding the local leakage rates measured, before any repairs to those previously isolated leakage paths, to the containment integrated leakage determined in the modified Type A test plus any leakage improvements (defined below) made prior to the test.
This adjusted "as found" leakage rate is to be used in determining the scheduling of the periodic Type A test in accordance with Section Ill.A.6 of Appendix J.
The acceptability of the modified Type A test can be determined by calculating the adjusted "as left" containment oserall integrated leakage rate and comparing it to the acceptance criteria of 0.75 L,.
The adjusted "as left" Type A leakage rate is determined by adding the local leakage rates measured, after any repairs and/or adjustments to those previously isolated leakage paths, to the leakage rate determined in the modified Type A test.
It should be noted that additional adjustments for non-standard lineup and changes in containment volume are added to the measured leakage rate for both "as found" and "as left" determinations.
Leakage improvements are defined as the difference between the pre-repair LLRT and post-repair LLRT done on containment penetrations prior to the start of the Type A test.
The only differences between this approach and Appendix J requirements are that:
(1) the potentially excessive leakage paths will be repaired and/or adjusted after the Type A test is completed; and (2) the Type A test leakage rate is partially determined by calculation rather than by direct measurement.
314.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
CALLAWAY - UNIT I B 3/4 6-la Amenda.nt No. 75
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