ML20083B930
| ML20083B930 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/08/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083B931 | List: |
| References | |
| NUDOCS 9505150007 | |
| Download: ML20083B930 (5) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055EL4001
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 NILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDNENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated September 28, 1994, i
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, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can % 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.
P
. i 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-49 is hereby amended to read as follows:
(2)
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 111, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of isscance.
FOR THE NUCLEAR REGULATORY COMMISSION f
Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 8,1995 1
ATTACHMENT TO LICENSE AMENDHENT NO.111 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 6-2 3/4 6-2 8 3/4 6-1 8 3/4 6-1 I
1 i
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- CONAllBIEN SYSTENS i
g CONTAlf9fENT LEAKAGE LINITING ColeITION FOR OPERATION i
3.6.1.2.
Containment leakage rates shall be limited to:
i a.
An overall integrated leakage rate of less than or equal to L.,
0.3% 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.,
l 53.27 psia (38.57 psig);
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A combined leakage rate of less' than 0.60 L, for all penetrations
[
b.
and valves subject to Type B and C tests, when pressurized to P,;
and c.
A combined leakage rate of less than or equal to 0.042' L, for all I
penetrations that are SECONDARY CONTAINNENT BOUNDARY bypass leakage paths when pressurized to P,.
APPLICABILITh N0 DES 1, 2, 3, and 4.
ACTION:
With the measured overall integrated containment leakage rate exceeding 0.75 L., or the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L., or the combined bypass leakage rate exceeding 0.042 L., restore the overall integrated leakage rate to less than 0.75 L., the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L., and the combined bypass leakage rate to less than 0.042 L, prior to increasing the Reactor Coolant System l
temperature above 200*F.
SURVEILLANCE REQUIRENENTS i
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 methods and provisions of ANSI N45.4-1972 (Total Time Method) and/or ANSI /ANS 56.8-1981 (Nass Point Method):
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at a pressure not less than P., 53.27 psia (38.57 psig), during each 10-year service period.*
b.
If any periodic Type A test fails to meet 0.75 L., the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L.,
a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed;
- The third Type A test will be conducted during the sixth refueling outage. As a result, the duration of the first 10-year service period will be extended to the end of the sixth refueling outage.
NILLSTONE - UNIT 3 3/4 6-2 Amendment No. JJ 77, pp.111 use
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 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 restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guidelines of 10 CFR Part 100 during accident conditions and the control room operators dose to within the guidelines of GDC 19.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety 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. A partial exemption has been granted from the requirements of 10CFR50, Appendix J, Section III.D.1(a). The exemption removes the requirement that the third Type A test for each 10-year period be conducted when the plant is shut down for the 10-year plant inservice inspection (Reference License Amendment No.111 ).
The enclosure building bypass leakage paths are listed in Operating Procedure 3273, " Technical Requirements - Supplementary Technical Specifica-tions."
The addition or deletion of the enclosure building bypass leakage paths shall be made in accordance with Section 50.59 of 10CFR50 and approved by the Plant Operation Review Committee.
3/4.6.1.3 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.
3/4.6.1.4 and 3/4.6.1.5 AIR PRESSURE and AIR TEMPERATURE The limitations on containment pressure and average air temperature ensure that:
(1) the containment structure is prevented from exceeding its design negative pressure of 8 psia, and (2) the containment peak pressure does MILLSTONE - UNIT 3 8 3/4 6-1 Amendment No. J7, 77,111 0289 i