ML17059B261
| ML17059B261 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/27/1996 |
| From: | Jeffrey Mitchell NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059B262 | List: |
| References | |
| NUDOCS 9609050021 | |
| Download: ML17059B261 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NIAGARA HOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE HILE POINT NUCLEAR STATION UNIT 2 HENDHENT TO FACILITY OPERATING LICENS Amendment No.
License No. NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Hohawk Power Corporation (the licensee) dated Harch 15,
- 1996, as supplemented July 18,
- 1996, 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 1;
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 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.
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-69 is hereby amended to read as follows:
960905002i 960827 PDR ADOCK 050004i0 P
lf
(2)
Tec 'l S ecif cations and Environmental Protection Pla The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No.
75 are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan
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This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance.
A<&st 27, 1996
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Jocelyn A. Mitchell, Acting Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
0
TTACHMENT TO LICENSE AMENDMENT AM ND T NO.
75 TO F CILITY OPERATING LICENSE NO.
NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa es 3/4 6-17 3/4 6-18 Insert Pa es 3/4 6-17*
3/4 6-18 ver eaf page (for TS with two-side copies text not changed)
0
CONTAINMENT SYSTEMS DEPRESSURIZATION SYSTEMS SUPPRESSION POOL SURVEILLANCE RE UIREMENTS 4.6.2. 1 The suppression pool shall be demonstrated OPERABLE:
a.
By verifying the suppression pool water volume to be within the limits at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in OPERATIONAL CONDITION 1 or'2 by verifying the suppression pool average water temperature to be less than or equal to 90 F, except:
2.
3.
During testing that adds heat to the suppression pool verify the suppression pool average water temperature to be less than or equal to 105 F at least once per 5 minutes.
When suppression pool average water temperature is greater than or equal to 904F, verify at least once per hour that:
a)
Suppression pool average water temperature is less than or equal to 110 F, and b)
THERMAL POWER is less than or equal to 1X of RATED THERMAL POWER after suppression pool average water temperature has exceeded 90'F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Following 'a scram with suppression pool average water, temperature greater than 904F, verify suppression pool average water temperature to be less than or equal to 1204F at least once per 30 minutes.
C.
By verifying at least 20 suppression pool water temperature instrumenta-tion channels" OPERABLE by performance of a:
1.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.
CHANNEL CALIBRATION""at least once per 18 months, with the water high temperature alarm setpoints
< 90 F for 10 of the tem-perature instruments and
< 1104F for 10 of the temperature instruments.
" At least one pair in each of 10 suppression pool sectors with the alarm set-point alternating between adjacent sectors.
"" Calibration excludes sensors; sensors comparisons shall be made in lieu of calibration.
NINE MILE POINT - UNIT 2 3/4 6-17
4.6.2.1 (Continued) d.
At least once per 18 months by conducting a visual inspection of the exposed accessible interior and exterior surfaces of the suppression chamber.*
e.
At least every outage requiring the performance of a Containment Integrated Leak Rate Test, as scheduled in conformance with the criteria specified in the 10CFR50 Appendix J Testing Program Plan described in Section 6.8.4.f, by conducting a drywell-to-suppression chamber bypass leak test at an initial differential pressure of 3 psi and verifying that the A/gK calculated from the measured leakage is within the specified limit of 0.0054 square feet.
1.
If any drywall-'to-suppression chamber bypass leak test fails to meet the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission.
2.
If two consecutive tests fail to meet the specified limit, a test shall be performed at least each refueling outage until two consecutive tests meet the specified limit. at which time the original test schedule may be resumed.
3.
The provisions of Specification 4.0.2 do not apply.
E During each refueling outage for which the drywall-to-suppression chamber bypass leak test in Specification 4.6.2.1.e is not conducted, by conducting a test of the four drywell-to-suppression chamber bypass leak paths containing the suppression chamber vacuum breakers at a differential pressure of at least 3 psi and verifying that the total leakage area A/gK contributed by all four bypass leak paths is less than or equal to 24% of the specified limit, and 2.
the leakage area for any one of the four bypass leak paths is less than 'or equal to 12% of the specified limit.
Includes each vacuum relief valve and associated piping.
NINE MILE POINT - UNIT 2 3/4 6-18 Amendment No. >>