ML17055C837
| ML17055C837 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/10/1987 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055C838 | List: |
| References | |
| NUDOCS 8702190412 | |
| Download: ML17055C837 (10) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
93.
License No.
DPR-63 The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Niagara Mohawk,Power Corporation (the licensee) dated August 22, 1986, 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; E'.
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 Operatina License No. tIPR-63 is hereby amended to read as follows:
8702190412 870210 PDR ADOCK 05000220 P
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Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
91, are hereby incorporated in the license.
The licer see shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CONHISSIOV
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 10, 1987 John A. Zwolinski, Director Bl<R roject Directorate 81 Division of PhR Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
91 FACILITY OPFRATIN6 LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment nUmber and contain marginal lines indicating the area of change.
REMOVE 178a 178b INSERT 178a 178b
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT
~5i i
ti C.
d.
e.
The results of laboratory carbon sample analysis shall show >90K radioactive methyl iodine removai when tested in accordance with ANSI N.510-1980 at 80oC and 95k R.H.
Fans shall be shown to operate within
+10'L design flow.
From and after the date that the control room air treatment system is made or found to be inoperable for any
- reason, reactor operation or refueling operations is permissible only during the succeeding seven days unless the system is sooner made operable.
If these conditions cannot be met, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for reactor operations and refueling operations shall be terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c.
Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural maintenance on the system housing.
d.
Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal absorber bank or after any structural maintenance on the system housing.
e.
The system shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
f.
At least once per operating cycle, not to exceed 24 months, automatic initiation of the control room air treatment system shall be demonstrated.
g.
At least once per operating cycle, not to exceed 24 months, the control room air treatment system shall be shown to maintain a positive pressure within the control room of greater than one sixteenth of an inch (water) relative to areas adjacent to the control room.
Amendment No.
78>>
91 178a
C
BASES FOR 3.4.5 AND 4.4.5 CONTROL ROOM AIR TREATMENT SYSTEM The control room air treatment system is designed to filter the control room atmosphere for intake air.
A roughing filter is used for recirculation flow during normal control room air treatment operation.
The control room air treatment system is designed to automatically start upon receipt of a high radiation signal from one of the two radiation monitors located on the ventilation intake and to maintain the control room pressure to the design positive pressure (one-sixteenth inch water) so that all leakage should be out leakage.
High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorber The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room.
The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a
HEPA efficiency of at least 99 percent removal of DOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident condi tions.
If the efficiencies of the HFPA filter and charcoal adsorbers are as specified, adequate radiation protection will be provided such that resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Po~er
- Plants, Appendix A to 10CFR Part 50.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be operable, there is no immediate threat to the control room and reactor operation or refueling ope. ation may continue for a limited period of time while repairs are being made.
If the makeup system cannot be repaired within seven
- days, the reactor is shutdown and brought to cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or refueling operations are terminated.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
In addition, air intake radiation monitors wi 1 1 be calibrated and functionally tested each operating cycle, not to exceed 24 months, to verify system performance.
The frequency of tests and sample analysis are necessary to show the HEPA filters and charcoal adsorbers can perform as evaluated.
The charcoal adsorber efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the. adsorbent.thoroughly and obtaining at least two samples.
Each sample should be at least two inches in diameter and a length equal to the thickness of the bed.
If test results are unacceptable, all adsorbent in the system shall be repl,aced with an adsorbent qualified according to Table 5-1 of ANSI 509-1980.
The replacement charcoal for the adsorber tray removed for the test should Amendment No. 73, 9I 178b