ML20113H333
| ML20113H333 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/24/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20113H335 | List: |
| References | |
| DPR-65-A-161 NUDOCS 9207290218 | |
| Download: ML20113H333 (4) | |
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UNITED STATES o
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NORTHE.A_ST NUCLEAfUdt RGY COMPA41 f
THE CONNJ_QJlCUT LIGHT AND POWER COMPAN'I THE WESTERN MASSACHUSITTS ELECTRIC COMPANY DOCKET N0 J 0-33G MILLSTONE NUCLEAR POW R STATION. yNIT_t[0ml J.
AMENOMLtlL TO FACILITY OPERATING LICENSE Amendment No. 161 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The cpplication for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated January 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; 8.
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 aunior hed 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 regulattons; 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.
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PCW ALJCK 05000336 p
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e Accordingly, the license is amended by changes to the Technical 2.
Specifications as inrlicated in the attachment to this license amendment, d paragraph 2.C.(2) of Facility Operating License No. OPR-65 is hereby amended to read as follows:
(2)
Technial Sorcificattom The Technical Specifications contained in Appendix A, as revised through Amendment No. 161 are hereby incorporated in the license, The licensee shall operate the facility in accordance with the t
Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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06hnj. Stolz, Director Project Directorate I-4 04 Vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Cate of Issuance: July 24,1992 7
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ATTACHMENT J_0 LICENSE AMENDMENT NO.161 FACILITY OPERATING LICENSE NO. DPR-6E DOCKEI NO. 50-131 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
!!gmove Insert 3/4 5-5 3/4 5-5 s
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EMERGENCY CORE COOLING SYSTEMS' SURVEllLANCE RE0VIREMENTS (Continued)
~10, Verifying _ that the following valves.are in the indicated position with power to the valve operator removed:
Valve Numbar Valve Function Valve Position 2-5I-306 Shutdown Cooling Open Flow Control 2-51-659 SRAS.Recirc.
Open*
- 51-660-SRAS Recire.
Open*
2-CH-434:
Thermal Bypass Closed **
b..
By a visual ir,0ction which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the, pump suctions during LOCA conditions. This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.
c.:
At least once per 18 months by:
1.-
Verifying automatic interlock action of the shutdown cooling system from the resctor coolant system by ensuring that with a simulated. reactor ccolant system pressure signal greater than or. equal to 300 psia the inte lock prevents the shutdown cooling system suction valves from being opened.
2.
A visual inspection of the containment sump and verifying that h
the subsystem suction inlets are not restricted by debris and that'the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
L 13.
Verifying that a minimu:n total of 110 cubic f.:at of trisodium phosphate dodecahydrate-(TSP) is contained within the TSP storage baskets.
4.
Verifying.that when a representative sample of 0.35 0.05'lbs of TSP from a TSP storage-basket'is submerged, without y
agitation, in-50 5 gallons of 180 10*F borated water from L
the RMST, the pH of-the mixed solution is raised to 2 6 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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- To be closed _ prior to recirculation following LOCA.
- **2-CH-434,: a m nual valve, shall be locked closed.
MIL'LSTONE -. UNIT-2 3/4 5-5 Amendment No. 7, JE, A2, /JI oose 161 I
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