ML20111B264
| ML20111B264 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/21/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Vermont Yankee |
| Shared Package | |
| ML20111B266 | List: |
| References | |
| DPR-28-A-086 NUDOCS 8503130047 | |
| Download: ML20111B264 (6) | |
Text
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'g [, c g NUCLEAR REGULATORY COMMISSION 5g ij WASHINGTON, D. C. 20555 Q.ro ] 4 VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-28 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated March 26, 1984, as supplemented .,_ September 7,1984, 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 wii'l operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; i 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 4 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 arrendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-28 is hereby amended to read as follows: M3130 { 850 gg hog p , PDR ~ 4 -ue-
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 86' are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificatinns. 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION m Domenic B. Vassallo, Chief Operating. Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 21, 1985 2 I f d
i ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Revise the Technical Specifications as follows: Remove Insert 41 41 63 63 133 133 1 l e m -
VYNPS TABLE 3.2.2 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION Minimum Number of Operable Instrument Required Action When Minimum Channels per Trip Conditions for Operations are System Trip Function Trip Setting Not Satisfied (Note 2) 2 Low-Low Reactor Vessel 182.5" above the A Water Level top of enriched fuel 2 of 4 in each of IIish Main Steam Line $2120F B 2 channels Area Temperature l 2/ steam line Itigh Main Steam Line Flow $140% of rated flow B 2/(Note 1) Low Main Steam Line Pressure >850 psis B 2/(Note 6) liigh Main Steam Line Flow $40% of rated flow B 2 Low Reactor Vessel Same as Reactor A Water Level Protection System 2 liigh Main Steam Line $3 I background at B Radiation (7) (8) rated power (9) 2 High Drywell Pressure Same as Reactor A Protection System 2/(Note 10) Condenser Low Vacuum 112" IIg absolute A 1 Trip System Logic A 41 Amendment No. 68, 86 ~ 9
~ l ~ VYNPS 3.2 (Cont'd) The low-low reactor water level instrumentation is set to trip when reactor water level is 82.5" H O indicated 2 on the reactor water level instrumentation above the top of the enriched fuel. This trip initiates closure of the Group 1 primary containment isolation valves and also activates the ECCS and starts the standby diesel generator i system. This trip setting level was chosen to be low enough to prevent spurious operation, but high enough to initiate ECCS operation'and primary system isolation so that no melting of the fuel cladding will occur and so that post-accident cooling can be accomplished and the limits of 10CFR100 will not be violated. For the complete circumferential break of a 28-inch recirculation line and with the trip setting given above, ECCS initiation and primary system isolation are initiated in time to meet the above criteria. The instrumentation also covers the full range of specteum of breaks and meets the above criteria. The high drywell pressure instrumentation is a backup to the water level instrumentation and in addition to initiating ECCS it causes isolation of Group 2, 3, and 4 isolation valves. For the complete circumferential break discussed above, this instrumentation will initiate ECCS operation "at about the same time as the low-low water level instrumentation, thus the results given above are applicable here also. Group 2 isolation valves include the drywell vent, purge, and sump isolation valves. High drywell pressure activates only these valves because high drywell pressure could occur as the result of non-safety-related causes such as not purging the drywell air during startup. Total system isolation is not desirable for these conditions and only the valves in Group 2 are required to close. The water level instrumentation initiates protection for the full spectrum of loss-of-coolant accidents and causes a trip of all primary system isolation valves. Venturis are provided in the main steam lines as a means of measuring steam flow and also limiting the loss of mass inventory from the vessel during a steam line break accident. In addition to wonitoring steam flow, instrumentation is provided which causes a trip of Group 1 isolation valves. The primary function of the 1 instrumentation is to detect a break in the main steam line, thus only Group 1 valves are closed. For the worst l case accident, main steam line break outside the drywell, this trip setting of 140 percent of rated steam flow in conjunction with the flow limiters and main steam line valve closure limit the mass inventory loss such that fuel is not uncovered, cladding temperatures remain less than 12950F and release of radioactivity to the environs is well below 10CFR100. Temperature monitoring instrumentation is provided in the main steam line tunnel to detect leaks in this area. l l Trips are provided on this instrumentation and when exceeded cause closure of Group 1 isolation valves. Its setting of ambient plus 95 F is low enough to detect l'eaks of the order of 5 to 10 gpm; thus, it is capable of 0 covering the entire spectrum of breaks. For large breaks, it is a backup to high steam flow instrumentation discussed above, and for small breaks with the resultant small celeace of radioactivity, gives isolation before the limits of 10CFH100 are exceeded. Amendment No. 58,68,86 63 ---s O ^
...m_. 4 VYNPS 3.7 UIMITING CONDITIONS FOR OPERATION 4.7 SURVEILI.ANCE REQUIREMENTS (2) The instrument line flow check valves shall be tested for proper oper tion. b. At least once per quarter: (1) All normally op'en power-operated isolation valves (except for main steam isolation valves) shall be fully closed and reopened. (2) With the reactor power less than 75 percent of rated, trip all main steam isolation valves (one at a time) and verify closure time. c. At least twice per week: (1) The main steam line isolation valves shall be exercised by partial closure and subsequent reoper.ing. 2. In the event any isolation valve specified in 2. Whenever an isolation valve listed in 4.7.2 is Table 4.7.2 becomes inoperable, reactor power inoperable, the position of at least one other operation may continue provided at least one valve valve in each line having an inoperable valvo in each line having an inoperable valve is in the shall be logged daily. mode corresponding to the isolated condition. 3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours. 133 Amendment No. 50, 86 \\g 'N' =0. 04}}